Temporary plug cover for hole or port in steam generator of nuclear power plant

Information

  • Patent Grant
  • 6662759
  • Patent Number
    6,662,759
  • Date Filed
    Monday, August 26, 2002
    22 years ago
  • Date Issued
    Tuesday, December 16, 2003
    21 years ago
  • Inventors
  • Original Assignees
    • (North Huntingdon, PA, US)
  • Examiners
    • Wilson; Gregory
Abstract
A temporary cover is plugged into an open handhole or inspection port in a steam generator or another pressure vessel of a nuclear power plant after bolted covers are removed for maintenance inside the generator or vessel. The temporary cover may be locked to prevent foreign objects from entering the generator or vessel. The cover is vented at inclined angles so that air or gas may pass therethrough but is shielded so that gamma rays, which are the most penetrating type of radiation, are greatly reduced and dispersed away from personnel.
Description




BACKGROUND OF THE INVENTION




1. Field of the Invention




This invention relates to a steam generator of a nuclear power plant and, in particular, to a temporary plug cover for a hole or a port in the steam generator.




2. Description of the Related Art




The prior art references developed as a result of a preliminary patentability search are listed below.






















U.S. Pat. No.




Inventor(s)




Issue Date











5,850,423




Rusnica, Jr. et al.




Dec. 15, 1998







4,948,981




Wallace et al.




Aug. 14, 1990







4,932,553




Reich, Jr. et al.




Jun. 12, 1990







4,860,919




Weisel et al.




Aug. 29, 1989







4,624,824




Dooley




Nov. 25, 1986







4,524,729




Hill, Jr. et al.




Jun. 25, 1985







4,192,053




Blanco et al.




Mar. 11, 1980











Foreign Patent




Inventor




Publ. Date











JP 5-172982




Maekawa




Jul. 13, 1993















We note at the outset that the search had not developed any references which taken alone or in combination might be considered to anticipate or render obvious the combination of features in the invention. So, the above references are considered as being of secondary interest.




Rusnica, Jr. et al., Weisel et al. and Dooley show various types of plugs for sealing holes or openings in reactor-related apparatuses. However, none have any significant teaching of the features of the present invention.




Wallace et al., Reich, Jr., et al. and Blanco et al. show the use of lead shielding in reactor-related covers or doors. In the patent to Wallace et al., see the language of col. 2 at line 53. In the patent to Reich, Jr. et al., see the language of col. 4 at line 8. The patent to Blanco et al. teaches both lead shielding as well as the use of openings in the shield for the insertion of a camera. See the embodiment of FIGS. 12 and 13 along with the description of col. 4 beginning at line 60.




Japanese Kokai No. 5-172982 to Maekawa provides a teaching in FIG. 4 of a scheme for securing a cover 20 to a steam generator opening using a nut screwed onto what could be a captive bolt in a blind hole anchored in a vessel wall.




SUMMARY OF THE INVENTION




The present invention is characterized by three distinct structural features of a cylindrical cover used temporarily to plug an opening in a steam generator. The features are: an integrally formed lead shielding layer; radiation channeling and diffusing ventilation holes; and a mechanical retainer.




The cover is particularly adapted for temporarily closing openings in a steam generator associated with a nuclear power plant. The cover is cylindrically shaped to fit snugly into round openings in the vessel walls, such as man holes, hand holes, inspection ports, and the like, during maintenance.




As disclosed in a first embodiment which is one of three illustrative embodiments, a cylindrical sleeve formed of stainless steel may have a diameter in the range of several inches and include a layer of lead plate shielding on its inner face. The layer of lead plate may have a thickness of two inches or more. An elongated retaining bar is affixed to its outer face. An array of nominally longitudinal vent holes are drilled through the lead plate. Each hole is typically oriented at a 7 to 25 degree angle to the longitudinal axis. This angle depends upon the diameter of the temporary cover used. The angled holes allow ventilation through the lead plate but channel and diffuse radiation that is axial to the plate away from an operator. During maintenance of the steam generator, any handhole or inspection port that is opened is temporarily fitted with a cover of suitable diameter and retained in place by the elongated bar which is anchored to a flange by a lock which engages a slot permanently cut in the elongated bar.




In a second embodiment, the elongated bar is secured directly to a flange of the handhole or the inspection port. In a third embodiment, two of the ventilation holes are enlarged in diameter to allow the insertion of a camera and/or a retrieval tool into the generator.




Other objects and features of the present invention will become apparent from the following detailed description when considered in connection with the accompanying drawings which illustrate preferred embodiments of the present invention.











BRIEF DESCRIPTION OF THE DRAWINGS





FIG. 1

is a cutaway perspective view of a steam generator in a nuclear power plant.





FIG. 2

is a partially cutaway front elevation view of a lower portion of the steam generator.





FIG. 3

is a perspective view of a first embodiment of the present invention.





FIG. 4

is a front elevation view of the first embodiment.





FIG. 5

is a cross-sectional side elevation view taken along line


5





5


in FIG.


4


.





FIG. 6

is an enlarged, detailed, side elevation view of one end of the first embodiment shown in FIG.


3


.





FIG. 6A

is a side elevation view of a pin which can be used instead of the bolt shown in FIG.


6


.





FIG. 7

is a cross-sectional top plan view of a second embodiment.





FIG. 8

is a front elevation view of a third embodiment.





FIG. 9

is a rear perspective view of the third embodiment.











DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS




In a pressurized-water, nuclear-powered, electric generating plant, heat generated by a nuclear reactor is absorbed by a primary coolant that circulates through a reactor core and transfers heat to produce steam inside a steam generator


10


shown in FIG.


1


. The steam generator


10


is typically an upright cylindrical pressure vessel with an upper hemispherical end section


12


and a lower hemispherical end section


14


. The steam generator


10


has an upper external steel shell


16


and a lower external steel shell


18


. Note that the upper shell


16


has a wider diameter than the lower shell


18


and is separated therefrom by a transition cone


20


.




Inside the lower shell


18


and the transition cone


20


, there is a wrapper barrel


22


of thin carbon steel surrounding a tube bundle


24


which is an array of individual tubes extending from an upper portion of the transition cone


20


downwardly to a predetermined space at a bottom of the lower shell


18


.




The tube bundle


24


inside the wrapper barrel


22


is the main source of heat transfer and also is a radiation source emitting most of the doses absorbed by nuclear power plant workers.




The wrapper barrel


22


is supported by wedges


26


and anti-rotation devices (not shown) inside an annular space


28


formed between the wrapper barrel


22


and the lower shell


18


.




The upper shell


16


has its interior space dedicated to separating moisture from wet steam which is generated during an operating cycle. Primary moisture separation is accomplished through angled vanes


30


inside swirl barrels


32


that throw off excess moisture through centrifugal steam action.




Entrance into the interior space of the upper shell


16


is made by a worker through one of two manways


34


of which each has a circular opening with a 16-inch diameter. Because of the distance from each manway


34


to the tube bundle


24


, there is generally a low field of only one to five millirads of gamma rays per hour at the opening such that the radiation dosage is not a cause for concern about the worker's health.




The main concern at this height of the generator


10


is venting for a safe atmosphere, i.e. oxygen. Also, there is a need to document equipment that is introduced and persons who enter through the manway


34


. No lead shielding is necessary at this upper level.




For the sake of completeness, other elements of the upper shell


16


shown in

FIG. 1

are a steam nozzle


36


, positive entrainment steam dryers


38


, and a feed water nozzle


40


. At the lower shell


18


, there is a thick horizontal plate called a tubesheet


42


surrounded by a support ring


44


.




In

FIG. 2

, the lower hemispherical end section


14


and the bottom of the lower shell


18


are shown. Also, the wrapper barrel


22


, the tube bundle


24


, and the annular space


28


are illustrated in two cutaway views.




Along the curvature of the end section


14


, there is a primary water inlet nozzle


46


and a primary water outlet nozzle


48


. At a transition area between the end section


14


and the bottom of the lower shell


18


, there is the support ring


44


.




Access to the area of the tubesheet


42


of

FIG. 1

inside the support ring


44


of

FIG. 2

is made through either two or four six-inch openings in handholes


50


situated at either 180° or 90°, respectively, around the bottom of the lower shell


18


. However, the six-inch diameters of the openings in the handholes


50


may vary, depending upon the model of the steam generator


10


.




The handholes


50


in

FIG. 2

have the same general purpose as the manway


34


shown in

FIG. 1

, i.e. to maintain, service and inspect vital components inside the generator


10


. However, the three embodiments deal primarily with the handholes and the inspection ports due to the higher level of radiation inside the lower shell


18


than inside the upper shell


16


.




Other circular openings, such as visual inspection ports


52


seen in

FIG. 2

, can have the same but generally smaller diameters than the diameters of the handholes


50


. These ports


52


, like the handholes


50


, may be arranged around an outer circumference of the lower shell


18


at either 90° or 180° from each other. In

FIG. 2

, three of the four handholes


50


and their corresponding inspection ports


52


are seen at 90° from each other.




Each handhole


50


have a flange


51


with bolt holes


51


A. Likewise, each inspection port


52


has a flange


53


with bolt holes


53


A.




In

FIG. 3

, a perspective view of a first preferred embodiment of the present invention is shown. A temporary cover


60


has a cylindrical metal sleeve


62


with an outer diameter which is slightly smaller than an inner diameter of the opening. In other words, the handhole


50


or the inspection port


52


in

FIG. 2

is matched with the sleeve


62


in FIG.


3


and the sleeve


62


is inserted in the selected handhole


50


or port


52


.




A solid lead plate shield


64


has a thickness which reduces by absorption the radiation from a source inside the tube bundle


24


of

FIGS. 1 and 2

to approximately one-tenth or less of its initial energy. Depending upon the necessary shielding required and the intensity of the radiation source, the shield


64


with a thickness of two inches of lead is usually sufficient to obtain the desired reduction in harmful gamma rays.




Vent holes


66


are machined by drilling into the shield


64


to provide for adequate circulation of air. The plurality of vent holes


66


typically comprises approximately five cubic inches of volume in the cylindrical shield


64


which has a six-inch diameter and a two-inch thickness. A mesh screen


68


is placed entirely over an external surface of the shield


64


to prevent the accidental or purposeful insertion of foreign objects into one or more of the vent holes


66


.




An elongated bar


70


is fillet-welded to an outer circumferential edge


72


of the sleeve


62


in order to prevent the sleeve


62


from slipping into the opening in either the handhole


50


or the inspection port


52


in FIG.


2


and falling down on top of the tubesheet


42


seen in FIG.


1


.




Returning to

FIG. 3

, the bar


70


has a slot


74


cut into one end through which a D-shaped ring


76


on a head of a bolt


78


is secured by a lock


80


. Although the lock


80


may be opened and closed with a key (not shown), a resettable combination is preferred because it can be changed from time to time.




The temporary cover


60


is now ready to be plugged and secured into the opening of either the handhole


50


or the inspection port


52


of

FIG. 2

by the elongated bar


70


which serves as a handle. Thus, the cover


60


functions as a radiation block via the lead plate shield


64


, a vent through the plurality of holes


66


, a foreign object excluder due to the mesh screen


68


, and a nonremovable device because of the D-shaped ring


76


which is secured in the slot


74


of the bar


70


by the lock


80


.




In

FIG. 4

, there is shown a top plan view of the cover


60


without the mesh screen


68


of FIG.


3


. The elongated bar


70


is fillet-welded onto the outer circumferential edge


72


and extends over two sides of the sleeve


62


. The plurality of vent holes


66


is arranged around an outer periphery of the lead plate shield


64


. In this first embodiment, there are


12


vent holes


66


in an equally spaced array from the center of the lead plate shield


64


. Of course, more or less vent holes


66


of small or larger diameters, respectively, may be drilled as long as the total area of openings for the vent holes


66


and their angles do not impede shielding. The size of the vent holes


66


and their angles will vary with the diameter and the thickness of the shield


64


. The slot


74


is seen in the one end of the elongated bar


70


without the D-shaped ring


76


and the lock of FIG.


3


.




In

FIG. 5

, a cross-sectional, side elevation view taken along line


5





5


in

FIG. 4

shows the elongated bar


70


of the cover


60


to be a hollow square tube. Inside the outer edges


72


of the sleeve


62


, there is the mesh screen


68


fillet-welded in front of the solid lead plate shield


64


. Two of the 12 vent holes


66


drilled through the lead plate shield


64


are shown to be inclined at an angle. This angle may vary from 70 to 25° from the longitudinal axis of the sleeve


62


.




Because gamma rays travel in a linear manner, i.e. in a straight line, from their radiation source and do not bend around corners, the inclined vent holes


66


prevent the majority of the gamma rays from escaping therethrough while simultaneously allowing air to circulate in and out of the openings. Gamma radiation that emerges through the vent holes


66


is channeled away from the operator. In other words, the majority of gamma rays from the radiation source on the right side of the lead shield


64


are absorbed and diffused by the lead in the plate shield


64


at the same time that air is adequately vented through the holes


66


, thus protecting a worker on the left side of the temporary cover


60


.





FIG. 6

shows a close-up detailed view of the one end of the elongated bar


70


. At this one end, the slot


74


receives the D-shaped ring


76


formed integrally on a head


78


A of the threaded bolt


78


. A body


78


B of the bolt


78


is threaded, with reference to

FIG. 2

, into either one of the bolt holes


51


A in the flange


51


or one of the bolt holes


53


A in the flange


53


so that the temporary cover


60


of

FIG. 3

may be secured by the lock


80


into either the handhole


50


or the inspection port


52


, respectively, seen in FIG.


2


.





FIG. 6A

shows an unthreaded pin


71


which may be substituted for the threaded bolt


78


in FIG.


6


. The pin


71


has a head


71


A and a body


71


B. The D-shaped ring


76


is welded to a distal end of the body


71


B instead of to a top of the head


71


A. The lock


80


in

FIG. 3

is secured through the D-shaped ring


76


to prevent the pin


71


from slipping out of the slot


74


in FIG.


6


.





FIG. 7

shows a second embodiment of the temporary cover


60


plugged into the inspection port


52


. Inside the outer edges


72


of the cylindrical sleeve


62


, there is a mesh screen


68


placed over the lead plate shield


64


through which vent holes


66


are inclined at an angle in the range of 7° to 25° from the front outer periphery towards a rear center of the lead plate shield


64


.




However, the cover


60


of the second embodiment differs from the cover


60


of the first embodiment shown in

FIGS. 3-6A

in that the elongated bar


70


in

FIG. 7

extends beyond only one side of the outer circumferential edge


72


of the sleeve


62


.




The slot


74


at the one end of the bar


70


receives a leg


82


of the lock


80


instead of receiving the D-shaped ring


76


of the threaded bolt


78


illustrated in

FIGS. 3 and 6

. In

FIG. 7

, the leg


82


of the lock


80


extends through one of the bolt holes


51


A in the flange


51


of the handhole


50


. Alternatively, the leg


82


may extend through one of the bolt holes


53


A in the flange


53


if the inspection port


52


of

FIG. 2

is being temporarily plugged by the cover


60


.




With reference to

FIGS. 2 and 7

, the reader must realize that usually, during operation of the pressurized steam generator


10


shown in

FIG. 1

, the handholes


50


and the inspection ports


52


are tightly and permanently plugged by a heavy cover (not shown) that is secured over a gasket (not shown) by bolts or studs and nuts (not shown) threaded through the bolt holes


51


A and


53


A of the flanges


51


and


53


, respectively.




However, when the nuclear power plant is shut down periodically for routine maintenance, each steam generator


10


is taken out of service and cleaned. To prevent radiation from escaping through the handholes


50


and the inspection ports


52


seen in

FIG. 2

, a plurality of the temporary covers


60


are plugged therein.




Although the second embodiment of

FIG. 7

is used where the bolt holes


51


A and


53


A of

FIG. 2

are unthreaded bores extending completely through the flanges


51


and


53


, respectively, the first embodiment of

FIGS. 3-6A

can also be used where the bolt holes


51


A and


53


A of

FIG. 2

are unthreaded holes in the flanges


51


and


53


, respectively, because the pin


71


of

FIG. 6A

can be inserted from a rear of the flanges


51


and


53


and still hold the cover


60


of

FIGS. 3-6A

in either the handhole


50


or the inspection port


52


of FIG.


2


.




In

FIG. 8

, there is illustrated a third embodiment of the temporary cover


60


with its elongated bar


70


fillet-welded to the outer circumferential edge


72


of the cylindrical sleeve


62


. Inside the sleeve


62


, there is the lead plate shield


64


.




However, instead of having the plurality of small vent holes


66


as in the first embodiment of

FIGS. 3-6A

and the second embodiment of

FIG. 7

, the third embodiment has only two large vent holes


66


which allow an operator's hand H to insert two guide tubes (not shown). Through these guide tubes, a small camera


84


or a retrieval tool (not shown) are inserted for finding and grasping a dropped tool (not shown) or a foreign object (not shown).




Note that the elongated bar


70


does not have a slot


74


. The reason for this omission is that this third embodiment is intended for immediate use and is not supposed to be left unattended after a foreign object is removed. Unlike the first embodiment of

FIGS. 3-6A

and the second embodiment of

FIG. 7

, the third embodiment of the temporary cover


60


cannot be locked in place and left overnight. Thus, when the operator is finished making a search and a retrieval, he or she must promptly replace the temporary nonlocking cover


60


of

FIGS. 8 and 9

with one of the temporary locking covers


60


of

FIGS. 3-6A

or


7


. The permanent cover (not shown) that is usually bolted to flange


51


or


53


of the handhole


50


or the inspection port


52


, respectively, seen in

FIG. 2

, is then installed after all maintenance is finished.




In

FIG. 9

, there is illustrated a rear perspective view of the third embodiment of the temporary cover


60


. The cylindrical sleeve


62


is seen with the shield


64


having the two slightly inclined vent holes


66


bored therethrough and opened to the outer circumferential edge


72


of the sleeve


62


. The elongated bar


70


, which serves as a handle to put the cover


60


into place and to prevent the cover


60


from falling inside the steam generator


10


of

FIG. 1

, is attached to the outer edge


72


of the sleeve


62


.




The cover


60


is kept in place in the handhole


50


or the inspection port


52


during an inspection being made when the two guide tubes (not shown) are inserted through the large vent holes


66


illustrated with open sides extending to the outer circumferential edge


72


of the cylindrical sleeve


62


in

FIGS. 8 and 9

. The small camera


84


is slipped through one guide tube (not shown) to search for and find the foreign object. When it is located, the retrieval tool (not shown) is slipped through the other guide tube (not shown) to grasp and remove the foreign object (not shown).




The outer circumferential edge


72


of the cylindrical sleeve


62


is smooth so as to allow quick and easy removal of the cover


60


from the handhole


50


or the inspection port


52


. Thus, the foreign object will not be dropped back in and possibly lost again inside the steam generator


10


. Furthermore, when the cover


60


is in place in the handhole


50


or the inspection port


52


, it provides protection by reducing radiation to less than one-tenth of its value before the gamma rays strike the shield


64


.




Because the two vent holes


66


are so large and are inclined at only a slight angle, more radiation escapes through the holes


66


in this third embodiment than the first embodiment of

FIGS. 3-6A

and the second embodiment of FIG.


7


. However, the operator is aware of the increased exposure to the gamma rays. Therefore, he or she will know to stay out of the direct path of the radiation or stay behind lead shielding before undertaking any work using this third embodiment of the cover


60


.




The above-described embodiments are not intended to be the only manner in which the invention is made. Instead, the scope and the spirit of the invention are defined by the appended claims.



Claims
  • 1. A temporary cover for plugging a selected one of a handhole and an inspection port in a steam generator of a nuclear power plant, said cover comprising:a cylindrical sleeve having an outer circumferential edge; a lead plate shield positioned inside the sleeve, said shield having a plurality of vent holes therethrough; and an elongated bar secured to the outer circumferential edge of the sleeve and configured to retain the sleeve with the shield in the selected one of the handhole and the inspection port.
  • 2. A temporary cover according to claim 1, further comprising:a mesh screen fitted over the shield inside the sleeve so that no foreign object may enter or exit through any one of the plurality of vent holes.
  • 3. A temporary cover according to claim 1, wherein:each one of the plurality of vent holes is inclined at an angle in the range of 7° to 25° from a longitudinal axis of the sleeve.
  • 4. A temporary cover according to claim 1, wherein:each one of the plurality of vent holes is inclined at an angle from a longitudinal axis of the sleeve so that approximately no more than 10% of gamma rays approaching the shield from a radiation source are allowed to pass through the vent holes.
  • 5. A temporary cover according to claim 1, wherein:said plurality of vent holes numbers two and each of the plurality of vent holes is open to the outer circumferential edge of the cylindrical sleeve for easy detachment of tools.
  • 6. A temporary cover according to claim 1, wherein:said plurality of vent holes numbers 12.
  • 7. A temporary cover according to claim 1, wherein:a total area of openings for the plurality of vent holes does not exceed 20% of a total surface area of the shield.
  • 8. A temporary cover according to claim 1, wherein:said shield has a thickness of lead plate such that no more than 10% of gamma rays approaching the shield from a radiation source pass through the shield.
  • 9. A temporary cover according to claim 1, wherein:said elongated bar extends beyond two sides of the sleeve.
  • 10. A temporary cover according to claim 1, wherein:said elongated bar extends beyond only one side of the sleeve.
  • 11. A temporary cover according to claim 1, wherein:said elongated bar has a slot being formed in one end extending over a side of the sleeve.
  • 12. A temporary cover according to claim 11, wherein:said slot is configured to receive a leg of a lock.
  • 13. A temporary cover according to claim 11, further comprising:a D-shaped ring formed on a head of a threaded bolt and configured to extend into the slot.
  • 14. A temporary cover according to claim 13, further comprising:a lock configured to retain the D-shaped ring in the slot.
  • 15. A temporary cover according to claim 14, wherein:said lock is a resettable combination type.
  • 16. A temporary cover according to claim 11, further comprising:a D-shaped ring formed on a distal end of an unthreaded pin configured to extend into the slot.
  • 17. A temporary cover according to claim 16, further comprising:a lock configured to retain the unthreaded pin in the slot.
  • 18. A temporary cover according to claim 17, wherein:said lock is a resettable combination type.
CROSS REFERENCE TO RELATED APPLICATION

This application is related to and claims domestic priority from U.S. Provisional Patent Application Ser. No. 60/315,919 filed on Aug. 29, 2001.

US Referenced Citations (10)
Number Name Date Kind
4192053 Blanco et al. Mar 1980 A
4524729 Hill, Jr. et al. Jun 1985 A
4624824 Dooley Nov 1986 A
4860919 Weisel et al. Aug 1989 A
4932553 Reich, Jr. et al. Jun 1990 A
4948981 Wallace et al. Aug 1990 A
5094809 Lenoble et al. Mar 1992 A
5423351 Keating Jun 1995 A
5850423 Rusnica, Jr. et al. Dec 1998 A
6609908 Guilmette et al. Aug 2003 B2
Foreign Referenced Citations (1)
Number Date Country
405172982 Jul 1993 JP
Provisional Applications (1)
Number Date Country
60/315919 Aug 2001 US