ML20058N491
| ML20058N491 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/05/1993 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20058N489 | List: |
| References | |
| PROC-931105, NUDOCS 9312220071 | |
| Download: ML20058N491 (580) | |
Text
{{#Wiki_filter:- ! l f 4- .
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1
.[]. IST PROGRAM, REVISION 7 ) +~ , .
l The following summary describes the changes from Revision 6 to ) Revision 7 of the North Anna Unit 1 Inservice Testing (IST) ; Program Plan. In addition to describing the changes to the l l program, the summary indicates the approval mechanism for each 'j relief request given in Sections 2.2.6 and 2.3.5. The changes in : the IST Program result from a review of the scope of the program ' l and from the NRC Safety Evaluation Report (SER) for Revision 6, l dated September 17, 1993. 1 2.2.5 PUMP INSERVICE TESTING TABLE UNIT 1 PUMP ! HUMBER COMMENT / PROGRAM CHANGE ' i 1-CC-P-1A Program change: Added Relief Request P-16. 1-CC-P-1B ! l 1-CH-P-1A ' 1-CH-P-1B -
+
1-CH-P-1C l 1-CH-P-2A Relief Request P-13, which deals with 1-CH-P-2B instrument accuracy, no longer applies to these pumps. Added Relief Request P-16. L Program change: Deleted reference to Relief Request P-13. ! 1-EG-P-1HA These non-Code diesel fuel oil transfer pumps 1-EG-P-1HB are positive displacement pumps. The ASME OM 1-EG-P-1JA Code-1987, Part 6, with Addenda to OMa-1988, 1-EG-P-1JB i Table 2, requires that only. discharge : pressure need be measured for positive ! displacement pumps. Per the requirements of ; OM Part 6, discharge pressure instead of l inlet and differential pressure will be l measured. Non-Code Alternative Testing i description PNC-1 was added to document this I fact. Relief Request P-4 is being withdrawn { and the contents of P-4 moved to PNC-1. ' Program change: Non-Code Alternative I Testing description PNC-1 was added and { Relief Request P-4 is being withdrawn. " M)
'q 1
DOCKhfohoh38 PDR , l
i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 }J m
}
i 1-FW-P-2 Relief Request P-13, which deals with 1-FW-P-3A instrument accuracy, no longer applies to 1-FW-P-3B these pumps. Also, a full flow test loop was installed that allows these pumps to be tested to the requirements of Section XI on a . quarterly basis. ! Program change: Deleted reference to Relief Request P-13 and deleted Relief Request P-14. Added Relief Request P-16. 1-QS-P-1A Relief Request P-13, which deals with 1-QS-P-1B instrument accuracy, no longer applies to 1-RH-P-1A these pumps. 1-RH-P-1B Program change: Deleted reference to Relief Request P-13. Added Relief Request P-16. 1-RS-P-1A Withdrew Relief Request P-6. .' 1-RS-P-1B
) 1-RS-P-2A Withdrew Relief Request P-7.
1-RS-P-2B 1-RS-P-3A The system resistance description _was changed : 1-RS-P-3B from FIXED to VAR. Relief Request P-13 no ; longer applies to these pumps.
-t Program change: Deleted reference to Relief ;
Request P-13 and replaced FIXED with VAR. ' Added Relief Request P-16. < 1-SI-P-1A The lube oil description was changed from N/A ' 1-SI-P-1B to Q. Relief Request P-13 no longer applies to these pumps. Program change: Deleted reference to Relief ; Request P-13 and added lube oil check. 1-SW-P-1A Relief Request P-13 for flow instrumentation 1-SW-P-1B no longer applies to these pumps. 1-SW-P-4 , Program change: Deleted reference to flow instrumentation in Relief Request P-13. 2 . 1
SUMMARY
OF. CHANGES TO NORTH ANNA UNIT 1 ! . IST PROGRAM, REVISION 7 h 1-HV-P-20A The ASME classification was upgraded from 1-HV-P-20B non-Class to Class 3. 1-HV-P-20C 1-HV-P-22A Program change: Replaced non-Class with 1-HV-P-22B Class 3. Added Relief Request P-16. i 1-HV-P-22C b I k s O : i
~I l
I
.l l
l 1 I l 1 O 3 i l 1
s i l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 L[ \ IST PROGRAM, REVISION 7 i ' \_ : l 2.2.6 PUMP INSERVICE TESTING PROGRAM RELIEF REQUESTS = ; The following summarizes the changes to relief requests since Revision 6. It also contains a description of the approv.al mechanism for each relief request. That is, the - summary indicates whether the approval is: t
- 1) through a position in Generic Letter 89-04,
- 2) through a previously issued NRC SER or .
- 3) obtained using a relief request that will need '
approval by the NRC. Relief requests requiring NRC , approval are marked with an asterisk
- I i
UNIT 1 RELIEF REQUEST COMMENT / STATUS P-1 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September
'O 17, 1993.
P-2 and 3 These relief request numbers are no longer active.
'P-4 This relief recuest is beina withdrawn. The basis !
for relief was'noved to Alternative Testing l description PNC-1 and revised to enhance clarity. ; P-5* The test frequency was changed from cold shutdown to reactor rcrueling. Also, the basis for relief ! was expanded to describe the conditions where the l residual heat removal system is needed during cold 1 shutdowns. The Revision 6 version of P-5 was approved by the NRC in their SER dated September I 17, 1993. P-6 This relief reauest is beina withdrawn. According to the SER for Revision 6 dated September 17, , 1993, the testing described for the inside recirculation spray pumps in Revision 6 is in accordance with the requirements of OM Part 6. Therefore, relief is not necessary as long as all , related requirements in OM Part 6 are met. ' 4 i I
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 _ f,s\ IST PROGRAM, REVISION 7 (_) I t P-7 This_Inliff reouest is beine withdrawn. According to the SER for Revision 6 dated September 17, the i testing described for the outside recirculation spray pumps in Revision 6 is in accordance with the requirements of OM Part 6. Therefore, relief l is not necessary as long as all related l' requirements in OM Part 6 are met. P-8 This relief request number is no longer active. P-9* The discussion dealing with static inlet pressure ' was expanded to explain why just using the discharge pressure for these deep draft pumps is a ; more conservative application of the Section XI i acceptance criteria then using differential i pressure and to describe the burden associated ! with recording the static suction pressure. This revision is in response to concerns raised by the NRC in their SER dated September 17, 1993. P-10* The discussion dealing with static inlet pressure
'~^
was expanded to explain why just using the discharge pressure for these deep draft pumps is a more conservative application of the Section XI , acceptance criteria then using differential pressure and to describe the burden-associated with recording the static suction pressure. This , revision is in response to concerns raised by the { NRC in their SER dated September 17, 1993. , P-11 This relief request number is no longer active. P-12 Reference to the third degree polynomial was _ deleted from the alternate testing section. Also, -l reference to establisning the pump curve using a ' minimum of six points was replaced by reference to using a minimum of five points. The use of five l points to describe the pump curve was taken from guidance provided by the NRC in their SER for the . Surry Units 1 and 2 IST Programs which was -; received in March of 1993. The Revision 6 version : of P-12 was approved by the NRC in their SER dated i September 17, 1993. The approval was granted as ' long as the calculated curve bounds the operational band in which the pump operates. t
~.
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1
/ IST PROGRAM, REVISION 7 L)
_ _ _ i P-13* Reference to the accuracy for the calculated differential pressure was deleted and the number of instruments that exceed the Section XI accuracy requirements was reduced. Also, the flow accuracy for the charging pumps (1-CH-P-1A, B and C) was changed from 2.5% to 2.34%, and the discharge pressure accuracies for the service water pumps (1-SW-P-1A, 1B and 4) were changed from 2.69% to .l 3.18% for pumps 1A and 1B, and to 2.61% for pump l
- 4. The Revision 6 version of P-13 was approved by ,
the NRC in their SER dated September 17, 1993. ! P-14 This relief reauest is beina withdrawn. Full flow test loops were installed for the auxiliary feedwater pumps. Therefore, this relief request is no longer necessary. P-15* Reference to running the boric acid transfer pumps on the recirculation flow path for three minutes was deleted. This relief request was submitted to the NRC by letter dated October 17, 1990. Except r' for the duration of the run period prior to measuring the test quantities, the alternate testing complies with Generic Letter 89-04, , Attachment 1, Position 9. The Revision 6 version , of P-15 was approved by the NRC in their SER dated September.17, 1993. P-16* This relief request is being submitted to-address , the situation of having to measure the static inlet pressure for a pump that is in operation prior to the test. i i k t 6 ; ~ d 4 I
p( .
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 2.2.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS Starting with Revision 7 to the IST Program, non-Code pumps that are included in the IST Program but are not tested to ' the provisions of the Code will be discussed in this new
~
section. Although a request for relief is not required for non-Code components, the reasons for why the Code ' provisions are not met and the-alternative testing description should be documented with the IST Program. NON-CODE i ALTERNATIVE TESTING DESCRIPTION COMMENT PNC-1 The diesel fuel oil transfer pumps are positive l' displacement pumps. One characteristic of positive displacement pumps is that the discharge pressure is independent of inlet pressure. /~' Therefore, to determine pump degradation, only ( discharge pressure need be measured. Also, the basis from Relief Request P-4'was moved into PNC- .
- 1. This basis deals with the Code required five minute run time before the test quantities are measured.
I i I
)
l i l 1 j 7 ; i
I l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ! .)_ IST PROGRAM, REVISION 7 2.3.4 VALVE INSERVICE TESTING TABLE Valves marked with an
- are being added to the IST Program.
UNIT 1 VALVE + EMMEEE COMMENT / PROGRAM CHANGE i 1-AS-FCV-100A These normally open valves are on the ; 1-AS-FCV-100B auxiliary steam supply line to the condenser i air ejectors. They automatically close in the event of a containment isolation signal. : Although they have an automatic trip i function, closing of these valves has no l specific function with respect to accident i recovery or mitigation. ' Program change: The valves were removed from ; the IST Program. 1-CA-026 This non-Code control room bottled air supply discharge check valve is adequately tested as part of the control room bottled air supply-Because the valve is non-Code and test. ! adequately tested outside the IST Program, ! this valve is being removed from the IST ! Program. , Program change: The valve was removed from l the IST Program. ; 1 1-CC-020 These valves open to provide flowpaths for 1-CC-045 constant vents from the CC pump casings to the surge tank to ensure the pumps are maintained full of water. Venting of these pumps is not considered to be critical to their performance. Backflow through this , line to an idle pump is insignificant due to the small size of the line. Program change: The valves were removed from i the IST Program. O 8
?
?
P f 7
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 , ( IST PROGRAM, REVISION 7 k.
~
t , _ . _ i l i 1-CC-RV-102 This valve protects the non-regenerative heat-exchangers from over-pressure in the event.an , isolated heat exchanger is subjected to l heating. Since this valve is a thermal relief valve and performs no specific safety function, testing is not required. Program change: The valve was removed from I the IST Program. . r 1-CC-RV-103 This valve protects the seal water. heat , exchangers from over-pressure in the event an , isolated heat exchanger is subjected to heating. Since this valve is a thermal relief valve and performs no specific safety ' function, testing is not required. , Program change: The valve was removed from the IST Program. 1-CC-RV-126 This relief valve protects the excess letdown heat exchanger (shell side) from over-pressure as a result of thermal expansion : when the heat exchanger is isolated. It is unlikely that CC to the heat exchanger would be isolated and even if it were, damage to i this non-safety-related heat exchanger would l be inconsequential. Note that protection of the header is provided by 1-CC-RV-128A and B. Program change: The valve was removed from the IST Program. l l l 1-CH-215" During normal operation this check valve I opens to provide flow from the VCT's to the i charging pump suction headers. Under. ! accident conditions when the upstream motor- ) operated valves are closed, it provides 'l recirculation pathways from the charging pump . minimum flow lines to the charging pump I suction headers. This valve must close to prevent contaminated water from entering the ; s VCT after recirculation mode transfer. j i 9 ! 1
V~ 7
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 g ) IST PROGRAM, REVISION 7 v Program change: The valve was added'to the i IST Program to be tested to the full open position every three months and closure and leak _ tested every reactor refueling. Refer to Relief Request V-72. , l 1-CH-217 This primary grade water supply to make-up blender manual valve is outside the ISI class boundaries and performs no safety function. , credit for isolation of this line during emergency boration is attributed to the downstream air-operated valve. i Program change: The valve was removed from , the IST Program. 1-CH-252 These charging pump discharge recirculation : 1-CH-264 line check valves open to provide flowpaths l 1-CH-277 from the charging pumps' discharge.to the O seal water return lines in order to protect the charging pumps from overheating during low or minimal flow operations. Since the pump suction headers are common and recirculation is not secured except when in recirculation cooling when the individual pump recirculation valves are closed, backflow through an idle pump via these lines has no safety consequence. Thus, no closure test is required for these valves. Program change: The closure test was deleted. 1-CH-FCV-1114A' This normally-closed (fail closed) valve opens as required to supply water to the VCT or charging pump suctions in order to control the reactor coolant system boric acid concentration during normal boration (dilution) . and plant shutdown. During manual emergency boration it must be closed to prevent diversion of boric acid into the primary water system. Program change: The valve was added to the 10 i
i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 (n) IST PROGRAM, REVISION 7 ; IST Program to be tested to the closed position every three months and to have its remote position indicator verified every 24 i months. . 1-CH-FCV-1160 This normally-closed (administratively , controlled) valve remains closed during plant ; operation and accident recovery to ensure safety injection flow from the charging pumps , is directed to the safety injection he 8ers , and to provide containment isolation. TF s it is categorized as passive and no exercising is required. ! Program change: A remote position indication verification test was added to be ' performed every 24 months and the closure test was deleted. r 1-CH-HCV-1303A These normally open valves may be closed at ' {s_,} 1-CH-HCV-1303B operator discretion during an accident to " 1-CH-HCV-1303C isolate an individual reactor coolant pump in i the event of a pump seal failure. The I abnormal operating procedure requires closure , within 5 minutes of discovering a seal leak. , Under accident conditions this function is - redundant with that of containment isolation valves 1-CH-MOV-1380 and 1381 which isolate all three seals. Thus, these valves are not required to be in the' Program. 2 Program change: The valves were removed from ] the IST Program. i 1-CH-LCV-1460A* These normally open letdown isolation-valves 1-CH-LCV-1460B' are closed in the event of an accident where continued letdown flow is undesirable and , automatically close on low pressurizer level ! to retain reactor water inventory. This would be important in the case of a small-break LOCA where containment isolation does not occur. Also, in the event of an incident l that results in a containment isolation signal, these valves must close to isolate 11
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 t j IST PROGRAM, REVISION 7
\s downstream low-pressure piping and to prevent lifting of downstream relief valve 1-CH-RV- i 1203. They fail closed on loss of. electric power or air header pressure. ;
Program change: The valves were added to the IST Program to be tested to the closed ; position every cold shutdown and to have their remote position indicators verified every 24 months. Refer to Cold Shutdown Justification CSV-5. 1-CH-MOV-1115B After recirculation mode transfer, there 1-CH-MOV-1115D exists a path for contaminated sump water ; through the piping from the suction of the ' charging pumps to the RWST. These valves isolate this piping and should be leak tested. . Program change: Leakage testing was added. () 1-CH-MOV-1267A* These normally-open valves remain open i 1-CH-MOV-1269A* following an accident to provide flowpaths 1-CH-MOV-1270A* from the RWST and LHSI Train "B" to each of the charging pumps during an accident and for post-accident recirculation. Thus, they are considered to be passive. I Program change: The valves were added to the IST Program to have their remote position indicators verified every 24 months. ! 1-CH-MOV-1267B* These normally-open valves would remain open 1-CH-MOV-1269B* following an accident to provide flowpaths 1-CH-MOV-1270B* from the "A" LHSI Pumps to each'of the charging pumps during post-accident ! recirculation. Thus, they are considered to be passive. , Program change: The valves were added to the IST Program to have their remote position i indicators verified every 24 months. ! i i 12 ; 1 i
L
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1
/fs\ IST PROGRAM, REVISION 7 A.)
1-CH-MOV-1373 This valve is normally open to provide a flowpath from the charging pumps common discharge to the seal water return line in order to protect the charging pumps from overheating during low or minimal flow operations. It may be closed by the operator to maximize flow to the RCS during safety-injection; however, this action is not desirable since it affects all three pumps and the individual pump minimum flow isolation valves (1-MOV-1275A-C) provide adequate means of isolation. Since the valve need not be repositioned during an accident it is considered to be passive. Program change: The exercise test was ; deleted. 1-CH-RV-1209 This valve provides over-pressure protection for the low-pressure letdown piping and
, components downstream of the non-regenerative \ heat exchangers but does not have any r specific function with respect to plant shutdown or accident mitigation.
Program change: The valve was removed from the IST Program. 1-CH-RV-1257 This valve protects the volume control tanks j and associated components from over-pressure. ' It performs no specific safety function related to accident mitigation. During and i following an accident, the VCT is typically isolated from the charging pump suction headers. Therefore, this valve need not be included in the test program. Program change: The valve was removed from the IST Program. 1-CH-RV-1382A This valve protects the seal water leakoff piping from over-pressure during an accident j when the associated piping segment is ; isolated and may be subjected to heating or' ; 13 '
~
j d i l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1
/~N IST PROGRAM, REVISION 7 r \s, seal failure. The portion of piping being protected is not critical. Thus, testing of this valve per the IST Program is not required.
Program change: The valve was removed from the IST Program. 1-CV-08* These valves must open to allow the removal 1-CV-14* of hydrogen from the containment atmosphere following an accident. Program change: The valves were added to the IST Program to be tested to the open position every three months. 1-CV-TV-100 This valve is a normally closed (administratively controlled) air-operated valve opened only during operation of the (- containment hogger at plant startup. Thus it is considered to be passive. Program change: The exercise test was deleted. 1-EB-015 Program change: 1-EB-034 Relief' Request V-55 is being withdrawn and replaced by Non-Code 1-EB-065 Alternative Testing Description VNC-4. 1-EB-084 1-EG-SOV-600HA 1-EG-SOV-601HA 1-EG-SOV-600HB 1-EG-SOV-600JA 1-EG-SOV-607JA 1-EG-SOV-600JB 1-EB-041 These non-Code valves open to provide 1-EB-053 flowpaths from the air dryers to the EDG 1-EB-072 1-EB-091 starting air receivers and close to prevent blowdown of the receivers through the l compressors when they shut down. Since } ' receiver pressures are monitored and' alarmed such that at " time zero" in the accident it can be assumed they are charged to the 14
y t i g-
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ($ / IST PROGRAM, REVISION 7 required minimum pressure.at the onset of an accident and the capacity of the tanks allows for the minimum of three engine starts required, compressor operation is not required. Thus, exercising these valves to the open position is likewise not required (Air compressors are not safety-related). However, these valves must close and remain leak tight to preserve the air inventory.in the receivers. Therafore, each of these valves should be leak tested to verify its ; capability to perform its safety-function. Program change: Leakage testing was added to ' be performed very reactor refueling, 1-EG-254 Flow instrumentation has been installed on 1-EG-266 the diesel fuel oil transfer pump discharge 1-EG-278 piping. Therefore, these valves can be full 1-EG-295 flow tested every three months. ' Program change: Relief Request V-49 is being withdrawn. 1-EG-SOV-601HA These hon-Code valves are normally open to 1-EG-SOV-607JA ensure the air start-header (and engine cylinders) remain de-pressurized during idle periods. They close during the starting sequence and reopen to protect the air supply i line. Each line has an orifice which permits pressurizing of the starting air header even if the SOV failed to close. Therefore, no closure testing is required. However, these valves should be tested open. l; Program change: The closure test was replaced by an open test. 1-FP-272 This valve is designated as containment a isolation valve and is leak tested per 10CFR50, Appendix J. ' Program change: Leakage testing was added. O 15 l
ry
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 (j IST PROGRAM, REVISION 7 1-FP-275 This valve is no longer subject to Type C leakage testing. Program change: The valve was removed from > the IST Program. 1-FW-0 6 2
- These valves are manipulated as required by 1-FW-064* the abnormal operating procedures to align 1-FW-094* each of the motor-driven pump headers to the ,
1-FW-0 9 6* steam generators via the desired control 1-FW-126* valve (MOV or HCV) . 1-FW-128' Program change: The valves were added to the IST Program to be exercised to the open and closed positions every cold shutdown. Refer to Cold Shutdown Justification CSV-40. 1-FW-068 These valves open on initiation of auxiliary 1-FW-100 feedwater flow to provide flowpaths from the f~D 1-FW-102 AFW pumps to the steam generators. They N- close in the event of a rupture (passive failure) of the upstream AFW piping . Since this evaluation does not postulate passive failure of ISI-classed components, testing of the closure function is not required. Therefore, Relief Request V-61, which deals with closure testing, is being withdrawn. Progs ange: The closure test was del '.ec. 1-FW-145* These normally locked-closed manual valves 1-FW-162* are opened as required by the abnormal 1-FW-180* operating procedures in the event of an. accident where all of the normal sources of ' steam generator makeup water have been exhausted (or are otherwise unavailable). , The emergency condensate storage tanks are only sized to provide sufficient makeup to allow the AFW system to satisfy its safety function for hot shutdown. The next safety-related backup water supply is the service water system. Thus, these valves should be exercised in the open direction. 16 1
=
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1
.(%) I- IST PROGRAM, REVISION 7.
Program change: The volves were added to the IST Program to be exercised to the.open ' position every cold shutdown. Refer to Cold Shutdown Justification CSV-41. 1-FW-148 These valves open to provide flowpaths from 1-FW-165 their respective AFW pumps to the designated 1-FW-183 steam generator. Since each pump is aligned to a single steam generator, reverse flow > through an idle pump is of no concern. Therefore, Cold Shutdown Justification.CSV-25, which deals with closure testing, is being withdrawn. Program change: The closure test was deleted.
- 1-FW-149* These manual valves are manipulated as 1-FW-155* required by the abnormal operating procedures ,
(~) 1-FW-166* to align each AFW pumps to a desired header
\~/ 1-FW-17 2 * (MOV or HCV) and to isolate the unused line.
1-FW-184* 1-FW-19 0* Program change: The valves were added.to the IST Program to be exercised to the open and , closed positions every cold shutdown. Refer t to Cold Shutdown Justification CSV-40. 1-FW-150 These check valves open to ensure minimum . 1-FW-167 recirculation flow through the auxiliary 1-FW-185 feedwater pumps to prevent pump damage in the event of isolation of an AFW discharge line. Since flow through these lines is limited by inline orifices and the head on these lines is merely that of the. emergency condensate tank, there is no adverse operational consequence if these valves failed to prevent reverse flow. Therefore, Cold Shutdown. Justification CSV-25, which deals with closure testing, is being withdrawn. Program change: The closure test was deleted. .i 17
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 () IST PROGRAM, REVISION 7 1-FW-227* This normally locked-closed manual valve is opened in the event of an accident where all of the normal sources of steam generator makeup water have been exhausted (or are otherwise unavailable). .The emergency condensate storage tanks are only sized to provide sufficient makeup to allow the AFW system to satisfy its safety function for hot shutdown. The next safety-related backup water supply is the service water system. 5hus, this valve should be exercised in the open direction. Program change: The valve was added to the ' IST Program to be exercised to the open position every cold shutdown. Refer to Cold Shutdown Justification CSV-41. 1-FW-526 These valves open to ensure flow through the-1-FW-527 AFW pamps and to provide cooling water flow /'T 1-FW-528 to the respective bearing oil cooler. The (ms/ potential for reverse flow through a cooler is of no consequence to the safety functions of the AFW pumps. Therefore, Cold Shutdown Justification CSV-25, which deals with closure testing, is being withdrawn. Program change: The closure test was deleted. 1-FW-FCV-1479 These feedwater bypass regulating valves do 1-FW-FCV-1489 not have remote position indication. Also, 1-FW-FCV-1499 these valves do not need to be partial stroke exercised as explained in Cold Shutdown Justification CSV-11. Program change: The remote position indicator verification test was deleted. 1-FW-MOV-100A Valves 1-FW-MOV-100A and C are normally , 1-FW-MOV-100C closed during plant operation. During the j course of an accident, the operator may manually position these valves as required to modulate flow to the steam generators, or to 18
g
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 1 ) IST PROGRAM, REVISION 7 isolate the affected steam generator in the. case of a tube rupture or s'eam leak. Thus these valves should be exervised in both directions.- Program change: The closure test was added to be performed every three months. 1-FW-RV-101 This valve was installed to protect the emergency condensate storage tanks from over-pressure in the event of' operator . error or ,- regulator failure while pressurizing from the plant nitrogen system. The piping from the ' plant nitrogon system has been removed and the associated tank penetration permanently opened for a vent. Therefore, pressurization is not possible. Program change: The valve was removed from
- the IST Program. '
a l-GN-RV-108A-1* These relief valves protect the PORV air and 1-GN-RV-108A-2* nitrogen supply piping from over-pressure in 1-GN-RV-108A-3* the event that a pressure control valve 1-GN-RV-10 8 B-1* should malfunction. An over-pressure 1-GN-RV-108B-2* condition could also result from a 1-GN-RV-108B-3* temperature transient in containment. ; Program change: The valves were added to the IST Program to be setpoint tested per OM-1, 1-GN-225* These non-Code valves open to provide 1-GN-451* flowpaths for nitrogen from the safety injection nitrogen header to the nitrogen reserve tanks and the PORVs. Since the- , reserve tanks are normally maintained in a charged condition, there is no requirement for these valves to open upon accident initiation. They close to maintain the nitrogen pressure in the reserve tanks in the event of a loss of pressure in the nitrogen supply piping. l Program change: The valves were added to the 19 j i
' T3
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ( ,) IST PROGRAM, REVISION 7 IST Program to be tested to the closed position and leak tested every reactor refueling. Refer to Non-Code Alternative Testing description VNC-1. 1-HC-014 These valves are opened periodically 1-HC-018 following an accident to sample and process hydrogen from the containment atmosphere and; thus, are considered to be active in the open and closed direction. Program change: The open test was added to the program to be performed every reactor refueling. Refer to Relief Request V-20. 1-HC-64 These non-Code valves open to provide return 1-HC-TV-109A pathways from the High Radiation Sampling 1-HC-TV-109B Subsystem (HRSS) panels and the HRSS waste tank to the return header leading to the containment. They close to prevent recirculation through the idle sample panel should a discharge valve be open. The HRSS function is not considered critical for accident recovery or mitigation. Program change: The-valves were removed from the IST Program. 1-HC-TV-108A These valves open to provide return pathways 1-HC-TV-108B from the High Radiation Sampling Subsystem (HRSS) panels and the HRSS. waste tank to the return header leading to the containment. The HRSS function is not considered critical for accident recovery or mitigation. Program change: The open test was deleted. 1-HV-AOD-160-1 These are non-Code. air operat'ed' dampers that 1-HV-AOD-160-2 close to isolate the control room. Dampers 1-HV-AOD-161-1 are outside the scope of the Section XI ; 1-HV-AOD-161-2 testing program. Also, the dampers are J adequately tested during the control room bottled air system tests. 20 l ___ _j
I n
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ( - j' IST PROGRAM, REVISION 7 Program change: The dampers were removed from the IST Program. 1-HV-MOV-111A Program change: The ASME Class was upgraded 1-HV-MOV-111B from non-Class to Class 3. 1-HV-MOV-111C 1-HV-MOV-113A 1-HV-MOV-113B 1-HV-MOV-113C 1-HV-PCV-1235A1 1-HV-PCV-1235A2 1-HV-PCV-1235B1 1-HV-PCV-1235B2 1-HV-PCV-1235C1 1-HV-PCV-1235C2 ; 1-HV-RV-1200 1-HV-RV-1201 1-HV-RV-1202A 1-HV-RV-1202B 1-HV-RV-1202C . () 1-HV-RV-1205A
\_/ 1-HV-RV-1205B 1-HV-RV-1205C 1-HV-SOV-1200A ,
1-HV-SOV-1200B 1-HV-SOV-1200C 1-HV-MOV-111B These valves have no remote position ! 1-HV-MOV-111C indication. Also, the ASME Class was 1-HV-MOV-113B upgraded from non-Class to Class 3. 1-HV-MOV-113C Program change: The remote position indication verification tested was deleted and the ASME Class changed to Class 3.- ! 1-HV-MOV-115-1 These valves are normally closed and may be 1-HV-MOV-115-2 cycled occasionally to clear a fouled i 1-HV-MOV-116-1 strainer. However, if necessary the 1-HV-MOV-116-2 strainers could be cleared manually. Program change: The valves were removed from the IST Program. i l 21
I rm
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 () IST PROGRAM, REVISION 7 i 1-HV-TV-1306A These trip valves provide flowpaths from the 1-HV-TV-1306B control room bottled air supply tanks to the control room via the ventilation system. These non-Code valves are adequately tested ! during the control room bottled air system-tests and need not be included in the IST ' Program. Program change: The valves were removed from the IST Program. 1-IA-925 These valves open to provide flowpaths for 1-IA-926 air from the normal instrument air supply 1-IA-934 header to the main valve operators and 1-IA-935 controllers of dampers 1-HV-1301A and B. Since the normal air supply is not relied upon to operate the dampers, no exercising in ; the open direction is required. In the event of a loss of pressure in the respective air i' supply header they close to prevent blowdown () (_/ of the reserve air volume tank into the depressurized header. Note that following the loss of pressure in the main header, back-leakage through these valves must be limited to that amount that will ensure the air bottle supply will be available to operate the main valves for a specified period during the accident scenario. Thus, these valves should be verified to be-leak tight. -l Relief Request V-64 is being withdrawn and
- replaced by Non-Code Alternative Testing '
description VNC-2 for these non-Code valves. Also, the leak test method to be used for ! these valves is included in VNC-2. i Program change: The IWV category was changed F from C to AC and a leak test was added to be o performed every reactor refueling. 1-IA-944 These valves open to provide a flowpath for ; 1-IA-948 air frvm the hermal instrument air supply 1-IA-952 header to the main valve operators. Since ; the normal air supply is not relied upon to 22
g5
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 {} operate the main valves, no exercising in the open direction is required. In the event of a loss of pressure in the respective-air supply header, they close to prevent blowdown of the reserve air bottle 3nto the depressurized header. Nota < hat'following the loss of pressure in t6n aain header, back-leakage through these valves must be limited to that amount that will ensure the air bottle supply will be available to operate the main valves for a specified period of timc during the accident scenario. Thus, these valver should be verified to be leak tight. In lieu of a leakage P.est for the isolation check valves, the main valves will be cycled the required number of times over the required period as defined by their design requirements with the normal air supply isolated and vented. g-(~/ Program change: The IWV category was changed
- from C to AC and a leak test was added to be performed every reactor refueling. Non-Code Alternative Testing description VNC-3 documents the alternative leak testing.
1-I A -9 59 These valves open to provide flowpaths for 1-IA-963 air from the normal instrument air supply 1-IA-971 header to the main valve operators and controllers of 1-FW-HCV-100A-C. Since the normal air supply is not relied upon to operate the main valves, no exercising in the open direction is required. In the event of a loss of pressure in the respective air supply header, they close to_ prevent blowdown of the reserve air volume tank into the i depressurized header. . Note that following the loss of pressure in the main header, back-leakage through these valves must be - limited to that amount that will ensure the air bottle supply will be available to operate the main valves for a specified r period during the accident scenario. Thus, these valves should be verified to be leak i 23
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 (r) IST PROGRAM, REV.TSION 7 tight. In lieu of a leakage test for the isolation check valves, the main valves will be cycled the required number of times over the required period as defined by.their design requirements with the normal air supply ; isolated and vented. ^ Program change: The IWV category was changed from C to AC and a leak test was added to be i performed every reactor refueling. .Non-Code { Alternative Testing Description VNC-3 documents the alternative leak testing. 1-IA-967 These. valves open to provide flowpaths for 1-IA-975 air from the normal instrument air surply header to the main valve operators and controllers of 1-FW-PCV-159A and B. Since the normal air supply is not relied upon to (^} (/ operate the main valves, no. exercising in the open direction is required. In the event of a loss of pressure in the respective air supply header, they close to prevent blowdown of the reserve air bottles into the depressurized header. Note that following the loss of pressure in the main header, back-leakage through these valves must be limited to that amount.that will ensure the air bottle supply will be available to operate the main valves for a specified time period during the accident scenario. Thus, these valves should be verified to be leak tight. In lieu of a leakage test for the isolation check valves, the main valves will be cycled the required number of times over the required period as defined by their design requirements with the normal air supply isolated and vented. Program change: The IWV category was changed from C to AC and a leak test was added to be performed every reactor refueling. Non-Code ( Alternative Testing Description VNC-3 24 e
()
,m
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7
- i documents the alternative leak testing.
1-IA-2152* These valves open to provide a flowpath for 1-IA-2153* air from the normal containment air supply 1-IA-2154* header to the.nORV operators. Since the 1-IA-2155* normal air supply is not relied upon to operate the main valves, no exercising in the open direction is required. In the event of a loss of pressure in the respective air supply header, they close to prevent blowdown of the air bottle into the depressurized header. Note that following.the loss of pressure in the main header back-leakage through these valves must be limited to that amount that will ensure the air bottle supply will be available to operate the main valves during the accident scenario. Thus, these valves should be leak tested as well as exercised. ' f Program change: These valves were added to the IST Program to be back seat tested and leakage tested every reactor refueling. Refer to Non-Code Alternative Testing Description VNC-1, 1-IA-TV-102A The Appendix J leakage requirements were deleted for this valve. Program change: The leakage test was deleted. 1-MS-119 These valves can be back seat tested every 1-MS-122 three months. Therefore, Relief Request V-52 1-MS-124 is being withdrawn. Program change: Valves will be closure tested every three months'instead of every reactor refueling. 1-MS-NRV-101A Program change: The test method was changed 1-MS-NRV-101B to use the Valve Operation Test and '(~ 1-MS-NRV-101C Evaluation System (VOTES) to verify disk ( 25 ,
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 . .s(m) IST PROGRAM, REVISION 7 position. Refer to Cold Shutdown Justification CSV-13. 1-MS-NRV-103A These motor-operated stop-check valves are 1-MS-NRV-103B opened only during plant startup to provide 1-MS-NRV-103C flowpaths for steam from each of the steam. generators to equalize ~ pressure across the , main line non-return valves. They remain closed during normal operation, The upstream trip valve-1-MS-TV-113A, B and C will isolate i the line if necessary. Therefore, the stop-
- check valves are passive.
Program change: The valves were removed from the IST Program.
?
1-MS-PCV-101A These valves provide a means of rejecting 1-MS-PCV-101B reactor core heat when the main condenser 1-MS-PCV-101C heat sink is unavailable. In the event of a [~} small break LOCA these valves would be opened
\~- to remove heat and reduce reactor coolant system pressure until RHR system operational limits are achieved. The valves are required to close, if open, to limit release of fission products in the event of a steam generator tube rupture. Although it is unlikely that a tube rupture incident would occur simultaneously with a plant condition where opening of these valves is required, ,
the emergency operating procedure (EOP) identifies the need for closure in such an event and, for that reason, is considered prudent to include a requirement for exercising in the closed direction. Since there are several cases where the EOP's depend on these valves to operate under accident conditions to effect a safe and orderly plant shutdown, it is prudent to include them in the test program. These valves open with air and close on loss of air pressure or electric power. i Program change: The open test was added to be performed every three months and their. e 7]
%)
remote position indicators will be verified 26 i
p
- e.
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ( )(. IST PROGRAM, REVISION 7 every 24 months. The closure test frequency was changed from every cold shutdown to every three months. 1-MS-TV-113A Program change: A fail safe test was added. 1-MS-TV-113B 1-MS-TV-113C 1-MS-TV-115* This normally open (passive) valve provides a flowpath for steam from the steam generators to the steam-driven AFW Pumps. The valve closes to shutdown the AFW pump turbine in the event of turbine overspeed - not a safety function. Program change: The valve was added to the IST Program to have its remote position indicator verified every 24 months.
\ 1-QS-MOV-100A These valves are normally-open to provide 1-QS-MOV-100B flowpaths from the RWST's to the quench spray-pumps. Since they are not normally closed, except for maintenance, they are considered-to be passive and no exercising is required.
Program change: .The exercise test'was deleted. 1-RC-HCV-1556A* Since these valves are normally closed 1-RC-HCV-1556B* (administratively controlled) and remain 1-RC-HCV-1556C' . closed whenever the RCS is pressurized, they are determined to be passive and exercising is not required. However, their remote position indicators need to be verified.' Program change: These valves were added-to the IST Program to have their remote position indicators verified every 24-months. n 27
e
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ( IST PROGRAM, REVISION 7 i 1-RC-PCV-1455C The test frequency was changed from during 1-RC-PCV-1456 cold shutdowns when the RCS is depressurized to every cold shutdown and Relief Request V-27 was withdrawn and replaced with cold Shutdown Justification CSV-42. . Program change: Test frequency was changed to every cold shutdown. 1-RC-SOV-102A-1 These valves are opened as needed to vent '; 1-RC-SOV-102A-2 non-condensible gases trapped in the 1-RC-SOV-102B-1 pressurizer. This is considered to be a 1-RC-SOV-102B-2 backup function to that of the PORV's and i thus are not relied upon in-an accident. Program change: These valves were removed from the IST Program. 1-RH-7 These RHR pump discharge check valves can 1-RH-15 only be tested during the RHR pump tests. Os The pump test frequency has been changed from cold shutdown to reactor refueling. Program change: The test frequency was changed from cold shutdown to reactor refueling. Refer to Relief. Request V-74. 1-RH-MOV-1700 These valves are opened to provide flowpaths ; 1-RH-MOV-1701 for reactor coolant from the RCS to the " suctions of the RHR pumps to effect shutdown ; cooling recirculation from the RCS to the RHR heat exchangers. They are closed and remain so during plant' operation to isolate the low pressure portions of the RHR System from the ,. high pressure of the RCS. Therefore, these valves have no requirement to change position to perform their closed function. Thus, , testing in the closed direction is not ! required. Program change: The closure test was deleted. (, i 28 :
c
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ( IST PROGRAM, REVISION 7 1-RH-MOV-1720A These valves are opened to provide flowpaths 1-RH-MOV-1720B for reactor coolant from the discharge of the RHR heat exchangers to the RCS to effect shutdown cooling recirculation from the RHR heat exchangers back to the RCS. They are normally closed and remain so during plant operation to isolate the low pressure portions of the RHR System from the high pressure of the RCS. There is no requirement = for the valves to change position to perform their closed function, thus they are passive in the closed position. Program change: The closure test was deleted. 1-RM-TV-100D This valve is no longer subject to Type C leakage testing per Appendix J. Program change: The leakage testing was deleted. {) 1-RS-123 These valves open to provide flowpaths from 1-RS-138 the casing cooling pumps to the suctions of the outside recirculation spray pumps. They close to prevent backflow through an idle pump. However, if a pump is idle the casing cooling discharge valve-(1-MOV-RS-101A and B) will automatically close to isolate the line due to the action of the associated casing cooling flow switch. Program change: The closure test was deleted. 1-RS-MOV-155A These valves are normally-open (automatically 1-RS-MOV-155B open if closed) to provide flowpaths from the containment sump and the casing cooling pumps to the outside recirculation spray pumps (passive function). They are considered to be active in the closed direction since they are designated as containment isolation valves (non-leak tested). -They also'would be closed if a leak were to develop in the outside recirculation spray system. In the t 29 l a
n
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 Q IST PROGRAM, REVISION 7 course of an accident there could be intermittent operation of the recirculation spray system that would require closing and opening these valves. Program change: The closure test was added to be performed every three months. 1-SI-004 These valves open to provide flowpaths from 1-SI-021 the RWST's to the LHSI pump seal. The RWST , head provides sealing pressure during idle periods to prevent seal leakage when a pump is not in operation. When the related LHSI pump is running, the seal pressure is supplied from the pump discharge and these -! valves must close to prevent recirculation to the respective RWST. This function is primarily related to operations while in the recirculation mode. Seal leakage from an idle pump is not considered a critical [\s/'l function. Thus, exercising.in the open direction is not required. After recirculation mode transfer, these valves isolate the RWST from contaminated sump water. Therefore, they should be leak tested. Program change: The open test was deleted and the leak test was added. P 1-SI-012 These valves open to provide flowpaths for l l-SI-029 the LHSI pump. minimum flow to ensure adequate- ' pump cooling during low-flow conditions. , They have no function to close that is ~ related to accident recovery or mitigation. Program change: The closure test was deleted. 1-SI-47 After recirculation mode transfer, there exists a path for contaminated sump water through the piping from the suction of the charging pumps to the RKST. This valve V(N 30
I
)
1
~i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 O IST PROGRAM, REVISION 7 l l isolates the piping and should be leak l tested. Program change: Leakage testing was added~ { and the closure test frequency.was changed- l from cold shutdown to. reactor refueling. Refer to Relief Request V-39.' j
'f 1-SI-125 These valves are normally closed and upon [
1-SI-142 depressurization'of the RCS during a LOCA i 1-SI-159 open to provide flowpaths from each of:the SI' 't Accumulators to the RCS cold-legs. There-is ; no specific safety function for these valves 1 to close following discharge from the f associated accumulator. Thus, they need not i be tested in the closed direction. Program change: deleted. The closure test'was ) - O f i 1-SI-HCV-1853A These valves are normally closed.(fail ~ 1-SI-HCV-1853B closed) and are only required to open from , 1-SI-HCV-1853C time to time to adjust the pressure within I the respective accumulators to assure'
- compliance withit he Technical Specification. l requirements for SI accumulator pressure and- '!
level. Following an accident where. gross blowdown of the RCS does.not occur and there j ' is insufficient. inventory:of water.in'the- ! containment sump for. recirculation, thel ; accumulator discharge motor-operated valves- ! (1-SI-MOV-1865A,fB- and C) will be closed : prior to depressurization to preclude. injecting large' quantities of nitrogen into; the RCS that couldTultimately'cause the RHR
~
r pumps to become air bound. The alternate ,i method of-preventing nitrogen injection into the RCS requires using these valves to vent: ;! the accumulators; however, since these1 vent 1 valves' require instrument air to open, it is- '; assumed that this option is. unavailable. 7 Thus, during emergency cooldown operations, no credit is taken for venting the-accumulators since thetair supply to the-j operators is not-considered to be reliable 31 i i
l i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 )
- (o) IST PROGRAM, REVISION:7 l and the outlet motor-operated valves would be closed. During post-accident conditions,.
these valves will remain closed until plant' l conditions are stable and long-term recovery valve lineups are established. Program change: These valves were removed from the IST Program. 1-SI-HCV-1336 This valve is normally closed (fail closed) and is only required to be opened infrequently to reduce the pressure (vent) - within the accumulators. Since the valve is opened intermittently during operation and receive a Phase A signal to close, it is considered an active valve and should be tested in the closed direction. During l emergency cooldown operations no credit is taken for venting the accumulators and this valve will remain closed until plant conditions are stable and long-term recovery s valve lineups are established. I Program change: The open test was deleted. I 1-SI-MOV-1863A These normally-closed valves automatically 1-SI-MOV-1863B open when SI is initiated and the respective . RWST reaches its Low-Low level setpoint to ! provide a pathway from the LHSI pumps to the i HHSI pumps while in the recirculation mode. As an alternative, they may be closed to direct LHSI pump recirculation flow directly to the RCS instead of the HHSI-pumps. Program change: The closure test was added. 1-SI-MOV-1865A During plant operation at power these valves , 1-SI-MOV-1865B remain open with the power to their motor ' 1-SI-MOV-1865C controller removed; however, during startup they could be closed at RCS pressures of 1000 psig or less per Technical Specification Section 3.5.1 thus they are considered to be active in the open direction. Following an ( ( accident where gross blowdown of the RCS does 32
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ( IST PROGRAM, REVISION 7 not occur and there is insufficient inventory of water in the containment sump for recirculation, these valves will be closed prior to depressurization to preclude injecting large quantities of nitrogen into the RCS that could ultimately cause the RHR ' pumps to become air bound. There is no case where these valves would be reopened after closure during an accident. The alternate method of preventing nitrogen injection into ; the RCS requires venting of the accumulators;. however, since the valves associated with the venting process require instrument air to open, it is assumed that this option is unavailable. Program change: The closure test was added. 1-SI-MOV-1885A After recirculation mode transfer, there 1-SI-MOV-1885B exists a path for contaminated sump water
/^)
(_/ 1-SI-MOV-1885C 1-SI-MOV-1885D through the piping from the discharge of the low head safety injection pumps to the RWST. These valves isolate the piping and should be leak tested. Program change: Leakage testing was added. 1-SI-RV-1857 These valves protect the high head safety injection line downstream of the boron injection tank from over-pressure. This is ! primarily a thermal relief to protect from pressure developed by the heat tracing in the I isolated portion of the piping and BIT. Therefore, they do not require testing per the IST Program. Program change: The valve was removed from the IST Program. 1-SI-RV-1858A These valves protect the SI accumulators and 1-SI-RV-1858B associated piping and components from ' 1-SI-RV-185BC overpressure. Since the accumulator system is a passive system and not subject to r' operational pressure transients, the on.'f ' ( 33 e
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 I) N-IST PROGRAM, REVISION 7 potential source of over-pressure of an accumulator is overfilling with nitrogen. Specifically, in-leakage from the RCS does not present a significant potential for over-pressurization since the volume in the tanks allows sufficient time for operator action by draining or isolating the affected. tank (s) to prevent exceeding design limits should significant in-leakage develop during plant operation. If in-leakage were so great as to preclude operator action, then the plant would be shutdown as required to satisfy the requirements of Technical Specification 3.4.6.2. Program change: The valves were removed from the IST Program. 1-SI-TV-101 This valve is normally closed. It is opened infrequently to reduce the pressure in_the SI (~'} accumulators. During emergency cooldown (_- operations no credit is taken for venting the accumulators. Therefore, this valve need not be tested in the open direction. Program change: The open test was deleted. 1-SS-TV-103A These valves are opened to draw samples from 1-SS-TV-103B the RHR system when in operation. Since the RHR system would only be operating at or near . cold shutdown, it is not likely'that they would be opened during an accident resulting in containment isolation. Therefore, they are considered to be passive valves for their , function of containment isolation. Program change: The exercise test was deleted. SV-TV-102-1 This normally closed valve is' opened following a steam generator tube leak or rupture or on receipt of a high radiation signal from the vent stack monitoring ("m instrumentation when it is desirable to have (-) '
p
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 Q IST PROGRAM, REVISION 7 the main condenser air ejectors lined up to discharge into containment. Although this is identified as a step in the emergency procedure, such action is considered to be , precautionary and preferable but not mandatory for accident mitigation. Also, this valve is no longer subject to Appendix J leak testing. Program change: The open test and leak test ~ were deleted. 1-SV-TV-102-2 This normally open valve is closed following a steam generator tube leak or rudture or on receipt of a high radiation signal from the vent stack monitoring instrumentation when it is desirable to have the main condenser air ejectors lined up to discharge into containment and receive a Phase A signal to close. Although this is identified as a step [s in the emergency procedure, closure of this valve is precautionary and not required to meet 10CFR100 limits during prescribed accidents. Program change: The valve was removed from the IST Program. 1-SV-TV-103 This normally closed valve is cpened following a steam generator tube leak or rupture when it is desirable to have the main condenser air ejectors lined up to discharge ' into containment. Although this is identified as a step in the emergency , procedure, such action is considered to be precautionary and preferable but not mandatory for accident mitigation. Program change: The open test was deleted. 1-SW-3 Observation'of the non-running pump's 1-SW-10 discharge pressure gauge every three months was added to Relief Request V-63 to enhance the verification of check valve closure. 35 s
i
}
r'
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 Program change: Added quarterly closure - test. 1-SW-22 Program change: The valve was moved from ! Relief Request V-63 to V-73. 1-SW-681 Program change: The valve number was changed from 1-SW-695 to 1-SW-681. 1-SW-MOV-102A During normal plant operation these valves- l 1-SW-MOV-102B are normally open and they would be closed to ! isolate a ruptured header. Since passive failure is not considered for this evaluation i and operationally they can be in any position, no exercising of these valves is required. Program change: The exercise test was () deleted. 1-SW-MOV-106A During normal plant operation these valves 1-SW-MOV-106B are open. They would be closed to isolate a ruptured header. Since passive failure is not considered for this evaluation and ' operationally they can be in any position, no exercising of these valves is required. , t Program change: The exercise test was-deleted. , s 1-SW-MOV-110A* During plant operation these valves are 1-SW-MOV-110B* normally closed with their breakers locked , open. If open when a CDA signal is received, 2 they will automatically close'for containment isolation and service water conservation. Since they are normally-closed they are ! considered to be passive and no exercising is required. j Program change: These valves were added to ! the IST Program to have their remote position indicators verified every 24 months. 36 f
c
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 - IST PROGRAM, REVISION 7 1-SW-MOV-113A During plant operation these valvos are 1-SW-MOV-113B normally locked closed and are only opened as a emergency backup supply of cooling water to the fuel pit coolers.- Since component cooling is a safety grade system and considered to be highly reliable, this backup capability is considered to be a convenient I operational backup and not required for accident mitigation. Therefore, exercising of these valves is not required. If open when a CDA signal is received, they would be closed for service water conservation and to minimize non-essential heat loads. Since they are normally closed they are considered to be passive and no exercising is required. , Program change: The exercise test was deleted. /~] N/ 1-SW-MOV-114A* 1-SW-MOV-114B* During plant operation these valves are normally closed with their breakers locked open. If open when a CDA signal is received, they will automatically close for containment isolation and service water conservation. Since they are normally closed they are considered to be passive and no exercising is ' required. Program change: _These valves were added to the IST Program to have their remote position indicators verified every 24 months. 1-SW-MOV-118* This valve is normally closed and is'used to provide operational flexibility. Therefore, no exercising is required. , Program change: This valve was added to the IST Program to have its remote position indicators verified every 24 months. 1-SW-MOV-119* This valve opens to provide a flowpath for i makeup to the reservoirs via the screen wash pumps. Since this mode of makeup is not 37 l
4 q
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 I 's _ /
/ IST PROGRAM, REVISION 7 relied upon during an accident, exercising in the open direction is not required. In the event an accident occurs while this valve is open, it would be closed to isolate the non-classed portions of the system from the safety-related portions.
Program change: This valve was added to the IST Program to be tested to the closed position every three months and to have its remote position indicator verified every 24 months. 1-SW-MOV-120A* During plant operation these valves are 1-SW-MOV-120B' normally closed except when in the lake-to-lake cooling mode. Since the plant is seldom, if ever, in this mode, these valves are passive in the closed position. Since each line must remain closed to retain-the water in the service water reservoir, it is (~ prudent to verify the accuracy of.the remote \ s)/
% position indication of these valves.
Program change: These valves were added to the IST Program to have their remote position indicators verified every 24 months. 1-SW-RV-101A These valves open to provide over-pressure 1-SW-RV-101B protection for an isolated heat exchanger. Since the only time a heat exchanger would be isolated is when it is out of service and unavailable, protection of the heat exchanger is not significant. Therefore, testing of - these valves is not required. Program change: The valves were removed from ! the IST Program. i I w 38
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 2.3.5 VALVE INSERVICE TESTING PROGRAM RELIEF REQUESTS The following summarizes the changes to relief requests since Revision 6. It also contains a description of the approval mechanism for each relief request. That is, the summary indicates whether the approval is:
- 1) through a position in Generic Letter 89-04,
- 2) through a previously issued NRC SER or
- 3) obtained using a relief request that will need approval by the NRC. Relief requests requiring NRC approval are marked with an asterisk *.
UNIT 1 RELIEF REOUEST COMMENT / STATUS V-1 and These relief request numbers are no longer active. V-3 The basis for going from a cold shutdown test frequency to a reactor refueling frequency was expanded. Also, reference to a partial stroke test was deleted. The only safety function for valves 1-CC-84, 119 and 154 is to close. An open test is not required in conjunction with a closed test for valves that only need to close. The Revision 6 version of V-3 was approved by the NRC in their SER dated September 17, 1993. The minor changes made to V-3 should not affect the conclusion reached by the NRC in their SER. V-4 to V -8 These relief request numbers are no longer active. V-9 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-10 The basis was expanded for valve 1-CH-330. Also, reference to a partial stroke test was deleted. The only safety function for valves 1-CH-322, 330,
-336, 358, 380 and 402 is to close. An open test is not required in conjunction with a closed test 39 q l
l
1 p
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ( IST PROGRAM, REVISION 7 i for valves that only need to close. The Revision 6 version of V-10 was approved by the NRC in their SER dated September 17, 1993. The minor changes- , made to V-10 should not affect the conclusion reached by the NRC in their SER. V-11 to These relief request numbers are no longer active. V-13 V-14 This relief reauest is beina withdrawn. It was determined that valve 1-CV-TV-100 is a passive ; valve and is not subject to an exercise test. ' Therefore, Relief Request V-14, which dealt with the exercise test, is not necessary. V-15 This relief request number is.no longer active. I V-16 Reference to a partial stroke test was deleted. The only safety function for the normally closed i valve 1-FP-272 is to close. An open test is not ' required in conjunction with a closed test for
, valves that only need to close.- The Revision 6 version of V-16 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-16 should not affect the conclusion reached by the NRC in their SER.
V-17 to These relief request numbers are no longer active. V-19 i V-20* This relief request was revised to addressed the open test for valves 1-HC-14 and 18. The open 4 test was added in Revision 7 to the IST Program. The alternative testing methods meet the requirements of Generic Letter 89-04, Attachment ; 1, Positions 1 and 3. The test frequency for the new open test needs approval from the NRC. The Revision 6 version of V-20 was approved by the NRC in their SER dated September 17, 1993. V-21 Reference to a partial stroke test was deleted. The only safety function for these normally closed instrument air valves is to close. An open test ' is not required in conjunction with a closed test for valves that only need to close. The Revision i 6 version of V-21 was approved by the NRC in their i (" SER dated September 17, 1993. The minor change 40 : I l
n
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 Q IST PROGRAM, REVISION 7 made to V-21 should not affect the conclusion reached by the NRC in their SER. V-22 to These relief request numbers are no longer active. V-26 V-27 This relief renuest is beine withdrawn. This relief request is being replaced by cold Shutdown Justification CSV-42 and the test frequency-for , the PORV's 1-RC-PCV-1455C and 1456 changed to - every cold shutdown. This change is in response to NRC concerns described in their SER dated September 17, 1993. V-28 Reference to a partial stroke test was deleted. The only safety function for the normally closed valve 1-RC-149 is to close. An open test is not , required in conjunction with a closed test for valves that only need to close. The Revision 6 version of V-28 was approved by the NRC in their SER dated September 17, 1993. The minor change O, made to V-28 should not affect the conclusion reached by the NRC in their SER. V-29 to These relief request numbers are no longer active. V-32 V-33 Reference to back seat testing valves 1-RS-123 and 138 was deleted. The Revision 6 version of V-33 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-33 ~! should not affect the conclusion reached by the NRC in their SER. The alternative testing conforms to NRC Generic Letter 89-04, Attachment 1, Position 2. V-34 to These relief request numbers are no longer active. V-36 l V-37 No change. This relief request was approved by. ' the NRC in the SER for Revision 6 dated September 17, 1993. The alternative testing conforms to NRC l Generic. Letter 89-04, Attachment 1, Position 2. V-38 No change. This. relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. 41 i
() , m
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 V-39' Reference to leakage testing was added for valve 1-SI-47. Also, the frequency for closure testing was changed from every cold shutdown to every reactor refueling to coincide with the leakage test frequency. The test frequency for the closure test needs approval.from the NRC. The Revision 6 version of V-39 was approved by the NRC in their SER dated September 17, 1993. ' V-40 Reference to a partial stroke test was deleted. The only safety function for_ valves 1-SI-106 and 110 is to close. .An open test is not required in conjunction with a closed test for valves that only need to close. The Revision 6 version of V-40 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-40 , should not affect the conclusion reached by the NRC in their SER. V-41 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September
~'\ 17, 1993.
[V V-42 Reference to using a sampling program for non-intrusive testing for the SI accumulator discharge check valves was added. The sampling program is , similar to the one given in Generic Letter 89-04, Attachment 1, Position 2 for check va3ve disassembly and inspection. This change is in response to NRC qualifications for approval of the relief request that are described in their SER dated September 17, 1993. Also, reference to closure testing for valves 1-SI-125, 142 and 159 was deleted because the closure test for these valves was deleted from the program. The minor change of deleting the closure tests should not affect the conclusion reached by the NRC in their SER. V-43 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-44 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. J~s 42 4
.e c
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 l IST PROGRAM, REVISION 7 V-45 Reference to FSAR Section 6.2.2.2.5 was added in Revision 7. The Revision 6 version of V-45 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-45 should not affect the conclusion reached by the NRC in their SER. V-46 Reference to a partial stroke test was deleted. The only safety function for valve 1-VP-12 is to close. An open test is not required in conjunction with a closed test fer valves that only need to close. The Revision 6 version of V-46 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-46 i should not affect the conclusion reached by the NRC in their SER. ' V-47 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September , 17, 1993. ( V-48 This relief request number is no longer active. L V-49 This relief reauest is beine withdrawn. Flow instrumentation has been installed. Therefore, the diesel fuel oil pump discharge check valves can be full flow tested every three months. V-50 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-51 This relief request number is no longer active. V-52 This relief reauest is beina withdrawn. The sainsteam to the turbine driven auxiliary feedwater pump check valves (1-MS-119, 122 and - 124) can be exercised closed every three months. V-53* The method of closure testing was changed from disassembly and inspection to back seat / leak testing for valves 1-SI-4 and 21 every reactor refueling. Also, the basis was expanded to justify the reactor refueling test frequency. The
... Revision 6 version of V-53 was approved by.the NRC in their SER dated September 17, 1993.
)
43
l fs
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 l {) IST PROGRAM, REVISION 7 V-54 The list of rapid acting valves was deleted. This list is maintained by the site ISI engineer. The Revision 6 version of V-54 was approved by the NRC ' in their SER dated September 17, 1993. The minor , change made to V-54 should not affect the i conclusion reached by the NRC in their SER. V-55 The relief reauest is beine withdrawn and replaced by Non-Code Alternative Testing Description VNC-4. The basis for relief was revised slightly to enhance clarity. Because the diesel air start valves are non-Code components, approval is not required from the NRC to deviate from Code provisions. V-56 This relief request number is no longer active. , V-57' The basis was expanded to describe the risks associated with stroking the vessel head vent > valves while the RCS is pressurized. This change is in response to NRC concerns described in their (^\
\--
SER dated September 17, 1993. Also, valves 1-RC-SOV-102A-1, 102A-2, 102B-1 and 102B-2 were deleted from the IST Program and are being deleted from , this relief request. V-58 This relief request number is no longer active. V-59 Valves 1-HV-MOV-100A and C were deleted from the relief request. The Revision 6 version of V-59 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-59 should not affect the conclusion reached by the NRC in their SER. V-60 No change. This relief request was approved by the NRC in the SER for Revision 6' dated September 17, 1993. V-61 The relief reauest is beina withdrawn. The closure test was deleted for valves 1-FW-68, 100 and 132. Therefore, the request for relief is no longer necessary. V-62 No change. This relief request was approved by 1 the NRC in the SER for Revision 6 dated September l 17, 1993. ) 44 ) 1 I l
p
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1
) IST PROGRAM, REVISION 7 l
V-63 The alternative testing was expanded to include observation of the discharge pressure gauge on the non-running pump every three months. This test was added in response to.NRC concerns described-in their SER dated September 17, 1993. .Even without this change, the NRC. approved the relief request in their SER for Revision 6 dated September 17, 1993. Valve 1-SW-22 was deleted from this relief request and put into Relief request V-73. This minor change should not affect the-bonclusion reached by the NRC in tht'.r SER. V-64 The relief reauest is beina withdrawn and replaced . by Non-Code Alternative Testing Description VNC-2. Reference to back seat / leak testing the non-Code instrument air valves 1-IA-925, 926, 934 and 935 every reactor refueling was added. Also~, the method for performing the leak test was added. V-65 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September [~) U 17, 1993. V-66 No change. This relief request was approved by . the NRC in the SER for Revision 6 dated September 17, 1993. V-67 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-68 This relief request number is no longer active. V-69 This relief request deals with using an evaluation instead of repair as corrective action for Appendix J valves that exceed their maximum leakage but do not allow the overall leakage to ' exceed 0.6La. V-69 was originally submitted on June 14, 1990. Following a meeting with the NRC held on September 6, 1990, V-69 was withdrawn per guidance from the NRC. The SER dated September-17, 1993, approved the originni version of V-69 with certain restrictions. V-69 is being resubmitted with the restrictions included and is considered approved for use by the SER. 45 i
- l
gy
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 ,
!u) IST PROGRAM, REVISION 7 i
V-70 No change. The basis was expanded to indicate that the vessel is defueled every reactor refueling. This change is in response to NRC concerns described in their SER dated September . ; 17, 1993. With the clarification included, V-70 ; is considered approved for use by the SER. V-71 The relief reauest is beine withdrawn. Valves 1-CA-26, 1-HV-TV-1306A and 1-HV-TV-1306B were deleted from the IST Program. Therefore, Relief Request V-71 is no longer necessary. . V-72* This relief request is being added to the program. Due to.the plant configuration, the VCT discharge check valve 1-CH-215 cannot be verified closed using flow. The only method to verify closure other than disassembly and inspection is to perform a leak rate /back pressure test. During normal operation, this valve cannot be isolated to perform a back pressure' test because
'N
[d normal letdown and reactor coolant flow would be interrupted. This valve is also subject to leak testing, which is performed every reactor refueling. Verification of closure will be performed during the leak test every reactor refueling instead of
- every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify draining the lines and performing a leak rate test. j V-73 This relief request is being added to the program.
Full accident flow cannot be. established through i the auxiliary service water pump discharge check valve 1-SW-22 using the normal system lineup because the accident heat loads and corresponding demand on the service water system cannot be duplicated. The accident flow can be established using a lake-to-lake configuration. However, the lake-to-lake lineup could contaminate Lake Anna with chemicals used in treating the service water ' system. Therefore, the lake-to-lake lineup is never used.
. (s This check valve can be disassembled while the +
d 46
l' E i
.?~
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 L( IST PROGRAM, REVISION 7- { plant is operating. . UN) allow for flexibility in i planning for refueling outages and still meet the intent of Generic Letter 89-04,~ Attachment 1, l Position 2, the valve will be disassembled on a reactor refueling frequency but not necessarily. during refueling outages. Because V-73 meets the , requirements of Generic Letter 89-04, Attachment 1, Position 2, no approval by the'NRC.is necessary prior to implementation. V-74* This relief request replaces cold Shutdown-Justification CSV-19 for valves 1-RHR-7 and 15. These.RHR pump discharge' check valves =can only be I tested during the RHR pump tests. During cold { shutdowns of short duration or if the reactor coolant pumps are left running during the cold shutdown, both trains of RER may be required for decay heat removal and to maintain RCS i temperature. Tak.ing one train.of RHR.out of , service for testing purposes even for a short' -! period could allow the RCS temperature to increase- r
/~}
(> to the. point that the pressurizer power operated relief valve would be challenged. Therefore, these pumps and the discharge check valves should- -; only be tested during reactor refuelings.- I l 47
t
-~
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 , IST PROGRAM, REVISION 7 2.3.6 VALVE INSERVICE TESTING PROGRAM COLD SHUTDOWN JUSTIFICATIONS > UNIT 1
'i COLD SHUTDOWN JUSTIFICATION COMMENT / STATUS CSV-1 No change.
CSV-2 This CSV number is no longer active. CSV-3 No change. CSV-4 Reference to valva 1-CH-217 was deleted. CSV-5 Valves 1-CH-TV-1204A and B were added. Also, more technical bases were added to the justification. , CSV-6 and 7 No change. t CSV-8 Justification is being withdrawn because the __ exercise test for valve 1-CH-MOV-1373 was deleted from the IST program. F CSV-9 This CSV number is no longer active. CSV-10 Justification is being withdrawn because the exercise test for valve 1-CH-FCV-1160 was deleted. 1 CSV-11 The justification was expanded to say that the feedwater bypass valves 1-FW-FCV-1479, 1489 and 1499 do not have to be partial stroke exercised , every three months and the motor operated valves 1-FW-MOV-154A, B and C cannot be partial stroke exercised. CSV-12 Reference to a partial stroke test was deleted. The only safety function for valves 1-FW-47, 79 and 111 is to close. An open test is not required-in conjunction with a closed test for valves that only need to close. CSV-13 The justification was revised to describe the.use of VOTES to determine the position of the disk on , the main stOom non-return valves. ~CE) 48 ;
?
- t
()
SUMMARY
OF' CHANGES TO NORTH ANNA UNIT l' IST" PROGRAM, REVISION 7 , l CSV-14 No change.- 'I CSV-15 This CSV number is no longer active.- ; CSV-16 No change. !
-1 CSV-17 This CSV number is no longer active.-
I CSV-18 No change. ; f CSV-19 Replaced by Relief Request V-74. ' CSV-20 No change. CSV-21 and 22 These CSV' numbers are no longer active. l CSV-23 and 24 No change. j l CSV-25 Justification is being withdrawn because-the ! closure test for the auxiliary feedwater-check' ! valves was deleted. j 7
. O-- CSV-26 This CSV number is-no longer active. !
CSV-27 Justification is being withdrawn because'the l main steam PCVs 1-MS-PCV-101A, B and C can be - isolated and. tested ~every~three months.
- t CSV-28 This CSV number is no' longer active. I CSV-29 to 32 No change.
1 CSV-33 References-to valves 1-MS-NRV-103A, B, C and D- .j were deleted because these valves were deleted ; from the IST Program, i CSV-34 to 35 No change. ,
'i
.CSV-36 . Justification is being withdrawn-because valves {
CH-HCV-1303A, B and C were deleted from the'IST j Program. ; i CSV-37 Justification is being withdrawn because valves 1- -j CC-20 and 45 were deleted from.the IST Program. l, CSV-38 The cold shutdown justification was revised to Li
. delete the partial flow' testing requirement for.
49 j q
gN .
, .j di" !
~:
- n.
SUMMARY
OF CHANGES TO NORTH ANNA UNIT.1. l [ . IST PROGRAM, REVISION-7
]
the charging recirculation check valves 1-CH-252,. j 264 and 277. _i CSV-39 Reference to using' ultrasonic flow transducers for- i measuring flow through the' service water header ! check valves-1-SW-252 and 255 was. replaced by a-
~
reference to using installed flow instrumentation. 1 i CSV-40 This coldishutdown justification was added to the l program to describe why the auxiliary feedwater _j manual. lineup valves.should not be exercised a during normal operation. I CSV-41 This cold shutdown justification was added to the-program. The normally locked closed auxiliary , feedwater manual valves discussed in.this' relief ; request are opened as required-by the abnormal operating procedures to provide. service water to' ; the auxiliary feedwater pumps in the~eventiof-an j accident where all normal auxiliary feedwater pump' ; supplies have been exhausted. Opening these ~ l O valves every three months to' fulfill quarterly' testing requirements.would accelerate-the buildup of sludge"in the supply lines from the service. l water system. The supply lines are flushed.once every 18fmonths to-reduce the buildup of sludge and to identify if { there is any accumulation of asiatic clams or shell debris in the lines. Because these manualf ; valves remain in the closed. position during normal ; operation'and are not subject to wear, exercising l these valves on a cold shutdown test frequency is ; adequate to demonstrate that the valves can~be ! opened in the case where service water is. required' .; as a. supply for the auxiliary feedwater' pumps. j CSV-42 This cold shutdown justification for the power i operated relief valves ~1-RC-PCV-1455C and 1456 is. i being added to' replace' Relief request V-27.- -l ll , 50
I t
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 '( ) IST PROGRAM,-REVISION 7 2.3.7 ALTERNATIVE TESTING FOR NON-CODE VALVES l Starting with Revision 7 to the IST Program, non-Code valves that are included in the IST Program but are not tested to the provisions of the Code will be discussed in this new section. Although a request for relief is not required for non-Code components, the reasons for why the Code provisions are not met and the alternative testing description should be documented with the IST Program. NON-CODE ALTERNATIVE TESTING DESCRIPTION COMMENT , VNC-1 Due to the plant configuration, the PORV service air valves cannot be verified closed using flow. The only method to verify closure other than disassembly and inspection is to perform a local
,O; \_,
leak rate /back pressure test. To perform the leak rate /back pressure test, the normal instrument air and nitrogen supplies to the PORVs must be isolated. The PORVs are required to be operable during normal operation. Also, these valves are located inside containment and are inaccessible during normal operation. These valves are also subject to leak testing, which is performed every reactor refueling. Verification of closure will be performed during the leak test every reactor refueling instead of every cold shutdown because the small increase in safety gained by testing during cold. shutdown does not justify the burden of performing a back pressure test. Valves 1-IA-2152 and 2153 are in series and valves 1-IA-2154 and 2155 are in series. There are no vents in between the two sets of valves; therefore, these valves cannot be individually back pressure tested or leak tested. VNC-2 Relief Request V-64 was replaced by this non-Code alternative testing description because the valves
~) in V-64 (1-IA-925, 926, 934 and 935) are non-Code.
J 51
f
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 iv) IST PROGRAM, REVISION 7 Also, the following leak test method description was added. The leak test will consist of pressurizing the volume upstream of the two valves in series and venting downstream of the valves. Then the upstream test volume will be isolated. If a given differential pressure across the two valves in series can be maintained for a predetermined period of time, the test.will be satisfactory. The actual leak rate will not be
- measured.
VNC-3 In lieu of a leakage test for the non-Code isolation check valves 1-IA-944, 948, 952, 959, 963, 967, 971 and 975, the main valves will be cycled the required number of times over the required period as defined by their design requirements with the normal air supply isolated and vented. VNC-4 Relief Request V-55 was replaced by this non-Code alternative testing description because the diesel (~) air start system valves in V-55 are non-Code.
'O v 52
9 (~ ' . s , i VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES '; SECOND INSPECTION INTERVAL ' DECEMBER 14, 1990 - DECEMBER 14, 2000 REVISION 7 0 t l r t b i,s s ,
ABSTRACT ('- ) VIRGINIA ELECTRIC AND POWER COMPANY i NORTH ANNA POWER STATION UNIT 1 INSERVICE TESTING PROGRAM PIAN FOR PUMPS AND_ VALVES SECOND INSPECTION INTERVAL DECEMBER 14, 1990 TO DECEMBER 14, 2000 The interval for which the North Anna Unit 1 Inservice. Testing Program (IST) program is applicable commenced on December 14, 1990, and will end on December 14, 2000. The Inservice Testing Program was developed employing 10CFR50 ' which references ASME Section XI, 1986 Edition, and Reg. Guide - 1.26. Quality Groups A, B, and C are the same as ASME Classes 1, 2, and 3 respectively. , Section 1: Introduces the Inservice Testing Program. Section 2: Describes the Class 1, 2, and 3 pump and valve - Inservice Testing Program developed in accordance with Subsections IWP and IWV of ASME Section XI. Certain pumps and valves within the boundaries defined by the ISI classification { m-Boundary Drawings are subject to testing except.where relief from examination is noted in Section 2. A Component listing is also provided in Section 2.
+
Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10CFR50, Section 50.55a(g), except where specific written relief has been granted-by the Commission pursuant to 10CFR50, Section 50.55a(g) (6) (i) ." 4 10CFR50, Section 50.55a(g) (4) (iv) states that, , inservice examinations of components, tests of pumps and valves, and system pressure tests, may meet the requirements set forth in subsequent editions and [T addenda of ASME Section XI that have been' approved by \ the NRC, subject to Commission approval. North Anna Unit 1 will. test those pumps that fall under the scope of ASME Section XI using Subsection IWP of the 1986 Edition. The scope of the program includes ASME Section XI Class 1, 2 and 3, and certain non-Code class pumps that are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident. A review has identified those pumps whose function is safety, (Section 2.2.4, Pump. Testing List). These ; pumps will be tested in accordance with the 1986 Edition of ASME Section XI to the extent practical. It must be recognized that due to design differences among - plants, some code testing requirements are impractical. Where such impracticalities exist, relief has been ' requested and alternate testing requirements have been ' proposed when warranted. 2-4 i N1PVR7 Revision 7 ) November 5, 1993 l l
c es. 2.2.2 PROGRAM IMPLEMENTATION I\ ') The Pump Inservice Testing Program will be executed as part of the normal plant surveillance program which is L implemented by periodic-tests. o Reference values were established using original surveillance test data or data from later tests when the pump was operating acceptably in accordance with-IWP-3110. Acceptance criteria'for the periodic tests
- are based on the reference values and the allowable ranges specified in IWP-3210 or technical specifications, whichever is more restrictive.
Following pump corrective maintenance, the previous reference values will be reconfirmed or a new set of i reference values will be determined in accordance with i IWP-3111. This post maintenance testing will be i performed in accordance with the applicable pump periodic test. > 2.2.3 PROGRAM ADMINISTRATION The Engineering staff at North Anna is responsible for
- the administration of the Pump Inservice Testing L Program. The Operations staff is responsible for performing the periodic tests as required by this program. The Pump Inservice Test Program is
-(~}
(_- implemented by Station ISI Administrative Procedure 2.0 "ASME Section XI Pump Program" and Periodic Test Procedures. 2.2.4 PUMP TESTING LIST This list gives a brief description of each pump identified in the Pump Inservice Test Program. 1-CC-P-1A Component Cooling Water Pumps ' 1-CC-P-1B Drawing: 11715-CBM-79A, Sh 1 of 3 Function: Supply cooling water to transfer heat from heat exchangers containing reactor coolant or other radioactive fluids. Qk_/ 2-5 N1PVR7 Revision 7 November 5, 1993 -
'l; i
,g-1-CH-P-1A High Head Safety Injection / Charging Pumps 1-CH-P-1B Drawing: 11715-CBM-95B, Sh 2 of 2 ('-} 1-CH-P-1C Function: Supply high pressure' borated water to the Reactor Coolant System following a Safety Injection , Signal, and to provide normal charging to the Reactor Coolant System. t 1-CH-P-2A Boric Acid Transfer Pumps 1-CH-P-2B Drawing: 11715-CBM-95A, Sh 1 of 4 Function: Supply boric acid to-the suction of the charging pumps for emergency boration. Recirculate the contents of the Boron Injection Tank. , 1-EG-P-1HA Emergency Diesel Generator Fuel Oil 1-EG-P-1HB Transfer Pumps 1-EG-P-1JA Drawing: 11715-CBB-35A, Sh 2 of 2 1-EG-P-1JB Function: Supply fuel oil to the Emergency Diesel Generator Fuel Oil Day Tank which directly supplies the Emergency Diesel Generator. O 1-FW-P-2 Auxiliary Feedwater Pumps 1-FW-P-3A Drawing: 11715-CBM-74A, Sh 3 of 3 1-FW-P-3B Function: Supply feedwater to the steam generators following a loss of normal feedwater flow.
- 1-QS-P-1A Quench Spray Pumps 1-QS-P-1B Drawing: 11715-CBM-91A, Sh 2 of 4 Function: Supply a borated, chemically treated spray to cool, remove iodine from, and depressurize the containment atmosphere following a Containment Depressurization Actuation signal.
2-6 N1PVR7 Revision 7 November 5, 1993
E 1-RH-P-1A Residual Heat Removal Pumps ~l,-) 1-RH-P-1B Drawing: 11715-CBM-94A, Sh 1 of 2 v Function: Remove decay heat from the reactor core and , the Reactor Coolant System during plant cooldown. 1-RS-P-1A Inside Recirculation Spray Pumps 1-RS-P-1B Drawing: 11715-CBM-91A, Sh 3 of 4 Function: Supply a borated spray to cool and depressurize the containment atmosphere following a containment Depressurization Actuation signal and , maintain containment subatmospheric following en accident. , 1-RS-P-2A Outside Recirculation Spray Pumps 1-RS-P-2B Drawing: 11715-CBM-91A, Sh 4 of 4 . Function: Supply borated spray to cool and depressurize the containment atmosphere following a. Containment Depressurization Actuation signal and maintain containment subatmospheric following an accident. f 5 1-RS-P-3A Casing Cooling Pumps 1-RS-P-3B Drawing: 11715-CBM-91B, Sh 1 of 1 Function: Supply cool borated water to the outside Recirculation Spray Pumps to increase the net positive suction head of these pumps. 1-SI-P-1A Low Head Safety Injection Pumps 1-SI-P-1B Drawing: 11715-CBM-96A, Sh 1 of 3 ; Function: Supply low pressure borated water to the Reactor Coolant System following a Safety Injection signal. 1-SW-P-1A Service Water Pumps 1-SW-P-1B Drawing: 11715-CBM-78A, Sh 3 of 4 Function: Supply cooling water to the Component Cooling and Recirculation Spray heat exchangers as well as other safety related components. O 2-7
- N1PVR7 Revision 7 November 5, 1993
,_ 1-SW-P-4 Auxiliary Service Water Pump J( g j - Drawing: 11715-CBM-78A, Sh 1 of 4 ' ~+
Function: Provide make up to the Service Water l Reservoir and can be used as the normal supply to the Service Water system. , 1-HV-P-20A Control and Relay Room Chilled Water ! 1-HV-P-20B Pumps . 1-HV-P-20C Drawing: 11715-CBB-40C, _Sh 1 of 3 ' Function: Circulate chilled water for the Control and Relay Room Cooling Coils. t 1-HV-P-22A Ccntrol and Relay Room Condenser 1-HV-P-22B Water Pumps 1-HV-P-22C Drawing: 11715-CBB-40D, Sh 1 of 3 Function: Supply service water to the Control and Relay Room air conditioning condenser water system. 2.2.5 PUMP INSERVICE TESTING TABLE (~' The Pump Inservice Testing Table identifies the pumps A to be tested in accordance with ASME Section XI. .The following information is provided for each pump; ASME Code Class, test quantities to be measured, test frequency, and relief requests if required. The following is a brief explanation of the abbreviations used in the Pump Inservicu Test Table. NC - Non-class Var. - Variable Resistance System Fixed - Fixed Resistance System , Q - Quarterly Test Frequency CS - Cold Shutdown Test Frequency (not more .i frequently than quarterly) RR - Reactor Refueling (nominally 18 months, not to exceed 24 months) 2Y - 24 Months i N/A - Not applicable or impractical, relief requests ! will explain in detail 2-8 N1PVR7 Revision 7 November 5, 1993
i
,3 Under Speed, N/A applies to constant speed pumps which ! ) do not require the measurement of speed. Therefore, no relief is necessary.
Under Lube Oil,- N/A applies to pumps that have a lubrication system with no level or pressure , indication. Therefore, no relief is necessary. O 2-9 N1PVR7 Revision 7 November 5, 1993
d
, ,~,
n
/ ( ')
['v) 'N (/ PUMP INSERVICE TESTING TABLE Relief Pump ASME System (1) Inlet Differential Flow Lube Dear Request Ident Class Resist Speed Pressure Pressure Rate Vibration Oil Temp. (P- 1 1-CC-P-1A 3 VAR. N/A O O O O O N/A 1.12.13.16 1-CC-P-1B 3 VAR. N/A O O O O O N/A 1.12.13.16 1-CH-P-1A 2 VAR. N/A O O O O O N/A 1.13.16 1-CH-P-1B 2 VAR. N/A O O O O O N/A 1.13.16 1-CH-P-1C 2 VAR. N/A O O O O O N/A 1.13.16 1-CH-P-2A 3 FIXED N/A* O O RR O O N/A 1.15.16 1-CH-P-2B 3 FIXED N/A* O O RR O O N/A 1.15.16 i l 1-EG-P-111A NC VAR. N/A N/A N/A O O N/A N/A 1.PCN-1 1-EG-P-1HB NC VAR. N/A N/A N/A O O N/A N/A 1.PCN-1 1-EG-P-1JA NC VAR. N/A N/A N/A O O N/A N/A 1.PCN-1 1-EG-P-1JB NC VAR. N/A N/A N/A O O N/A N/A 1.PCN-1 2-10 N1PVR7 Revision 7 November 5, 1993 __ i
O O O PLHP INSERVICE TESTING TABLE Relief Pump ASME System (1) Inlet Differential Flow Lube Bear Request Ident Class Resist Speed Pressure Pressure Rate Vibration Oil Temo. (P- ) 1-FW-P-2 3 VAR. O O O O O O N/A 1.16 1-FW-P-3A 3 VAR. N/A O O O O O N/A 1.16 1-FW-P-3B 3 VAR. N/A O O O O O N/A 1.16 1-OS-P-1A 2 FIXED N/A O O O O O N/A 1.16 1-OS-P-1B 2 FIXED N/4 O O O O O N/A 1,16 1-Ril-P-1A 2 VAR. N/A RR RR RR RR RR N/A 1.d.16 1-Ril-P-1B 2 VAR. N/A RR RR RR RR RR N/A 1.5.16 i 1-RS-P-1A 2 VAR. N/A RR RR RR RR N/A N/A 1 1-RS-P-1B 2 VAR. N/A RR RR RR RR N/A N/A 1 1-RS-P-2A 2 VAR. N/A 2Y 2Y 2Y 2Y N/A N/A 1 1-RS-P-2B 2 VAR. N/A 2Y 2Y 2Y 2Y N/A N/A 1 . 1-RS-P-3A 3 VAR. N/A O O O O O N/A 1.16 1-RS-P-3B 3 VAR. N/A O O O O O N/A 1.16 2-11 N1PVR7 Revision 7 November 5, 1993
, t
,, , .. v _m . . . , , . , 4 .- . _..,,e , _ . - _ , , . , , . , . ..._,,.-4 - . , . -
PUMP INSERVICE TESTING TABLE Relief Pump ASME System (1) Inlet Differential Flow Lube Bear Request Ident Class Resist Speed Pressure Pressure Rate Vibration Oil Temo. (P- 1 1-SI-P-1A 2 FIXED N/A O O O O O N/A 1 1-SI-P-1B 2 FIXED N/A O O O O O N/A 1 1-SW-P-1A 3 VAR. N/A N/A N/A O O O N/A 1.9.12 1-SW-P-1B 3 VAR. N/A N/A N/A O O O N/A 1.9.12 1-SW-P-4 3 VAR. N/A N/A N/A O O O N/A 1.10.12 1-HV-P-20A 3 VAR. N/A O O O O N/A N/A l'.16 1-HV-P-20B 3 VAR. N/A O O O O N/A N/A 1.16 4 1-HV-P-20C 3 VAR. N/A O O O O N/A N/A 1.16 2-12 N1PVR7 Revision 7 November 5, 1993
~ ~ . .. - - .
n O .O, U PUMP INSERVICE TESTING TABLE Relief Pump ASME System (1) Inlet Differential Flow Lube Bear Request Ident Class Resist Speed Pressure Pressure Rate Vibration Oil Temp. (P- 1 1-HV-P-22A 3 VAR. N/A O O O O N/A N/A 1.16 1-HV-P-22B 3 VAR. N/A O O O O N/A N/A 1.16 1-HV-P-22C 3 VAR. N/A O O O O N/A N/A 1.16 i (1) Speed is measured for variable speed pumps. 1-FW-P-2 is the only variable speed' pump in this program. (2) Pumps 1-CH-P-2A and B have two speeds; however, they are tested at the high speed and are considered constant speed pumps per this program. 2-13 N1PVR7 _ Revision 7 November 5, 1993 - a n..wm ..m*wuwa- % --w- , w i -r..w-* .-r m , 'ir w d u- d=vr w' w w- et we-- *e 'w r a wwwo w 4 r,- * -- a- a --m.-_.m..-...m - ._ms- _ .u-am_ .
J j: A IN sj n 2.2.6 PUMP INSERVICE TESTING PROGRAM RELIEF REQUESTS
\ Relief requests identify those ASME Section XI Code requirements considered to be impractical. The basis for the- relief-request -and the alternate testing to be performed is given.
1 L I 1 l.-
. j l
l l m I 2-14 1M7 Revision 7-November 5, 1993 5
.. _ _____________________.____.____._______m_._ . . . _ _ _ _ _ _ __.___.._________.___._.__.._____________m. ..__._..__.___..._._____._______J
7-~ RELIEF REQUEST P-1 I. IDENTIFICATION OF COMPONENTS Systems: Various Pump (s): IWP Program Pumps See PUMP INSERVICE TEST TABLE. Class : II. IMPRACTICAL CODE REQUIREMENTS Measure pump bearing temperatures and vibration in mils. III. BASIS FOR RELIEF Pump vibration and bearing temperature measurements are used to detect changes in the mechanical characteristics of a pump. Regular testing should detect developing problems, thus repairs can be initiated prior to a pump becoming inoperable. The ASME Section XI minimum standards require measurements of the vibration amplitude (displacement) in mils every three months and bearing temperatures once per. year. (O~') our proposed program is based on vibration readings in velocity units rather than vibration amplitude _in mils displacement. This technique is an industry accepted method which is more sensitive to small changes that are indicative of developing mechanical problems and hence more meaningful. Velocity measurements detect not only high amplitude vibrations that indicate a major mechanical problem, but also the equally harmful low amplitude high frequency vibrations due to misalignment in balance, or bearing wear that usually go undetected by simple displacement measurements. In addition, these readings go far beyond the capabilities of a bearing temperature monitoring program. A bearing will be seriously degraded prior to the detection of increased heat at'the bearing housing. Quarterly vibration velocity readings should achieve a i .. much higher probability 2-15 N1PVR7 Revision 7 November 5, 1993 s
- 7. RELIEF REQUEST P-1 (Cont.)
t N- ) of detecting developing problems than the once per year reading of bearing temperatures. Bearing temperature l tests present problems -which include the following:
- 1. Certain systems have no recirculation test loops and j a limited source of water. An enforced thirty minute run time would deplete the source.
- 2. The lubrication fluid for some pumps is taken from the process water, which can change temperature depending on ambient conditions. Data trending for these cases is not meaningful.
The small probability of detection of a bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the measurements. In addition, it is impractical to measure bearing temperatures on many pumps. Therefore, the detection of possible bearing failure by a yearly temperature measurement is extremely unlikely. IV. ALTERNATE TESTING Pump vibration measurements will be taken in vibration
/' velocity (in/sec). The evaluation of the readings will
(_,)/ be per the attached table. The ranges of test parameters given in the attached table were taken from ANSI /ASME OM (Part 6), An American National Standard i In-Service Testing of Pumps. l i i O) R-2-16 N1PVR7 Revision 7 November 5, 1993
q fh. U RELIEF REQUEST P-1 (cont.) RANGES OF TEST PARAMETERS (1) PUMP PUMP TEST ACCEPTABLE ALERT REQUIRED TYPE SPEED PARAMETER RANGE RANGE ACTION RANGE Centrifugal, 0600 rpm m V, $2. 5 V,") > 2 . 5 V, to 6V, >6 V, I Vertical Line l Shaft and positive displacement but not >0.325 in/sec but not >0.70 in/sec screw pumps * ' Note: (1) V, is the vibration reference value in the selected units V, is vibration velocity measured peak, unfiltered . I (2) There are no pumps in this program that operate below 600 rpm (3) OM-6 does not address positive displacement screw pumps. The Emergency Diesel Generator Fuel Oil pumps are of this type and will be subject to the OM-6 Criteria.
-(4) Small values for V, will produce small acceptable ranges for pump operation. Based on a'small acceptance range, an adequately and smoothly running pump could be subject to corrective action. To avoid this situation, a minimum value for V, of 0.05 in/sec has been established for velocity measurements. Pumps with a measured 1
reference value below 0.05 in/sec shall have subsequent test results compared to an acceptable range based on 0.05 in/sec. 2-17 N1PVR7 Revision 7 November 5, 1993
b fx RELIEF REQUEST P-2 N -s. Relief Request Withdrawn RELIEF REQUEST P-3 , Relief Request withdrawn. RELIEF REQUEST P-4 Relief Request withdrawn. l l 3 r N
'h t
I i r t O 2-18
- N1PVR7 Revision 7 November 5, 1993 '
[. 1 7- RELIEF REQUEST P-5
'uJ I. IDENTIFICATION OF COMPONENTS System : Residual Heat Removal Pump (s): 1-RH-P-1A 1-RH-P-1B Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Frequency of Pump Test.
III. BASIS FOR RELIEF The low pressure pumps take suction from and discharge to the Reactor Coolant System (RCS)which operates at l 2235 psig. This pressure is well above the operating L pressure of the pumps; therefore, testing during normal operation is not possible. During cold shutdowns of short duration or if the reactor coolant pumps are left running during the cold [ shutdown, both trains of RHR may be required for. decay
\ heat removal and to maintain RCS temperature. Taking 3 one train of RHR out of service for testing purposes even for a short period could allow the RCS temperature to increase to the point that the pressurizer power operated relief valve would be challenged. Therefore, these pumps should only be tested during reactor refuelings.
IV. ALTERNATE TESTING These pumps will be tested every. reactor refueling. 2-19 N1PVR7 Revision 7 November 5, 1993
- -_._---.__--a- - _ - , - - - - - - _ - - _ - . _ . - - - - . _ _ _ _ - - - - - - - - - - - , - - - - _ - - , , - _ . . , - - - - - - _ - - - - - - - . - - - - , - - - - - - - . - - - - - - _ _ - - - - , - - , - - , _ - - , - - - - , , - - - , , - - - - _ . _ :.
- r~g RELIEF REQUEST P-6 J Relief Request Withdrawn RELIEF REQUEST P-7 - Relief Request Withdrawn RELIEF REQUEST P-8 Relief Request withdrawn. ' O
?
i
?
1 f
%m 2-20 ,
N1PVR7 Revision 7 November 5, 1993 :
,_ RELIEF REQUEST P-9 i
. L.- I. IDENTIFICATION OF COMPONENTS ' System : Service Water Pump (s): 1-SW-P-1A 1-SW-P-1B Class : 3 II. IMPRACTICAL CODE REQUIREMENTS Measure inlet pressure and differential pressure. III. BASIS FOR RELIEF These pumps take suction from the Service Water Reservoir. No inlet pressure instrumentation is installed. The secvice water reservoir level indicator is located outside and several feet away from the observation point. Also, the measuring stick tends to collect residue from the surface of the reservoir, thus obscuring the markers. Therefore, measuring the reservoir level can be difficult during periods of inclement weather or low light conditions. ( However, the reservoir level fluctuates very little and ; can be considered to be constant. The Service Water Reservoir has a minimum level of 313 feet elevation as required by Technical Specifications and a maximum recorded level during past testing of 314.9 feet. l Therefore, the expected maximum variation in reservoir level is less than 2 feet, which is less than 1 psi. The discharge pressure gauge has a full scale reading of 100 psig and typical discharge pressures range from 50 to 65 psig. Even the maximum variation, which in all probability will not occur between successive i tests, is a small-percentage of the total head developed by the pump. Therefore, the repeatability of the tests and the ability to detect degradation will not be significantly affected if only discharge , pressure is measured. Applying the Code acceptance criteria to discharge 'l pressure instead of differential pressure is a 1 conservative application of the acceptance criteria for , deep draft pumps. For these pumps, the total developed l head is calculated by adding the measured discharge pressure to the height from the discharge pressure I 2-21 ' N1PVR7 Revision 7 i November 5, 1993
_ 7 ~s RELIEF REQUEST P-9 (Cont.) ' gauge to the pump impeller, and subtracting the height from the reservoir surfac - to the pump impeller. Therefore, the measured .scharge pressure will always be a smaller number tha'. Jie actual total head developed by the pump. Applying the Section XI acceptance criteria to just the discharge pressure instead of the total developed head for a deep draft pump is a conservative application of the acceptance criteria because the operability band is smaller. IV. ALTERNATE TESTING t Discharge pressure will be measured in place of differential pressure.
?
e t C) 2-22 N1PVR7 Revision 7 ' November 5, 1993
RELIEF REQUEST P-10 [v_D I. IDENTIFICATION OF COMPONENTS System : Service Water Pump (s): 1-SW-P-4 Class : 3 i II. IMPRACTICAL CODE REQUIREMENTS Measure inlet pressure and differential pressure. III. BASIS FOR RELIEF
.1 This pump takes suction from Lake Anna. No inlet pressure instrumentation is installed. The North Anna lake level indicator is located outside and several ;
feet away from the observation point. Also, the measuring stick tends to collect residue from the > surface of the lake, thus obscuring the markers. Therefore, measuring the lake level can be difficult , during periods of inclement weather or low light conditions. ('% ' (_) However, the lake level fluctuates very little from test to test and can be considered to be constant. .The ! lake has a minimum level of 244 feet elevation as f required by Technical Specifications, and maximum and minimum recorded levels during past testing of 250.24 ! feet and 248.16 feet, respectively. Therefore,-the expected maximum variation in lake level is about 2 feet, which is less-than.1 psi. The discharge pressure gauge has a full scale reading of.100 psig.and the discharge pressures range from 50 to 65 psig. Even the maximum variation, which in all probability will not occur between successive tests, is a small percentage of.the total head developed by the pump. Therefore, , the repeatability of the tests and the ability to detect degradation will not be significantly affected if only discharge pressure is measured. : Applying the Code acceptance criteria to discharge pressure instead of differential pressure is a conservative application of the acceptance criteria for the deep draft pump. For this pump, the total developed head is calculated by adding the measured. discharge pressure to the height from the discharge j pressure gauge to the pump impeller, and subtracting 1
~~ .
.1 2-23 N1PVR7 Revision 7 j November 5, 1993 j I
7.~ RELIEF REQUEST P-10 (Cont.)
]
the height from the lake surface to the pump impeller. Therefore, the measured discharge pressure will always be a smaller number than the actual total head ' developed by the pump. Applying the Section XI acceptance criteria to'just the discharge pressure instead of the total developed head for a deep draft pump is a conservative application of the acceptance , criteria because the operability hand is smaller. IV. ALTERNATE TESTING Discharge pressure will be measured in place of differential pressure. t, s/ 1 i O 2-24 N1PVR7 Revision 7 November 5, 1993 i
t i RELIEF REQUEST P-11 .i Relief Request withdrawn. k i 5 1
-i I
i r
.I i
-1 2-25 {
N1PVR7 Revision 7 i November.5, 1993 l
RELIEF REQUEST P-12 O,_s I. IDENTIFICATION OF COMPONENTS System : Component Cooling and Service Water Pump (s): . 1-CC-P-1A 1-SW-P-1A 1-CC-P-1B 1-SW-P-1B 1-SW-P-4 ! Class : 3 L II. IMPRACTICAL CODE REQUIREMENTS 7 ASME XI, Subarticle IWP-3110 requires reference values to be one or more fixed set of measured values. .All subsequent test results shall be compared to these reference values. III. BASIS FOR RELIEF Plant conditions may not be the same as when the reference values were established. Many reference points must be established to anticipate future plant conditions. In the Component Cooling and Service Water Systems, reproducing one of these reference flow points s is difficult with the large butterfly valves installed and it may not be desirable to alter cooling because of other plant operating parameters. Past vibration data for the subject pumps has been reviewed and it has been determined that pump vibration does not vary significantly with flow rate over the , range of the test flow rates. ; IV. ALTERNATE TESTING ; All subsequent test results will be compared to' calculated reference values which are determined using the following method. A set of at least five pressure / flow points will be recorded. From these points an equation for the line will be calculated by a- , computer using polynomial regression. The resulting ; polynomial equation describes the reference curve. P% 2-26 I N1PVR7 Revision 7 November 5, 1993 u
1 RELIEF REQUEST P-12 (Cont.) (' '- Flow points will be taken between the limits of the original data points. The resulting pressure is then compared to the' ASME XI, Table IWP-3100-2 limits. Pumps may then be tested during normal operation without any valve throttling. An example of acceptance criteria based on a reference curve is shown in Figure 1. O> g O 2-27 N1PVR7 Revision 7 November 5, 1993 r
i
,/~,
is 100
-,.s.*s
_- s ,'y,,' - - - 95 s _- 's.,'s, s ,
$*N., ' Alert Rage M s :s_ /
AcceptaWe s, '- Rangt g%.%. s s, s i
*, s ,.. (Required Acton Range) 85 ..^**^ ' .**
*... / 's s . 's s
s s..s e _ . 6, s %* , 80 ,
.... . s _% >
Aler1 Range ,**< .' -" !
,s E*%. '
s s
...*..%, s ss*.s'
's s ;..
m.. i i 75
- g. _
s, ,. , s, .
- s <, s,. .
a s' i
- ,... s +
e s 5 srs's..*
- +
70 . . * . * '4
.,s .. -,s s s
.. . s s .s % ,
_2 e
' s s.%- ,
.....'s, g ss.
- g. p
/
-m j
s o E5
'*,.'s s s .
s s.. - ( (Required Acton Range) **N., s s*; , so
.. ., s .
s s s
- s. s s
a _- s s i 55 ." .
~
~.,
's s s >
,.s .
50 ,,;, 33i, 3ii, i,,3 jiji igi;i 3,,3 i
; i ati i33 33 : i$
6,000 6.500 7.000 7,500 8,000 8,500 9,000 9,500 10.000 10.500 11,000 - 11,500 12,000 Total Flow Rate (gpm) " * * " " "
- t Figure 1. Pump Acceptance Criteria Based on a Reference Curve -t i
r \ 2-28 i N1PVR7 Revision 7 ! November 5, 1993 1
RELIEF REQUEST P-13 ~' v . I. IDENTIFICATION OF COMPONENTS e System : Component Cooling i Chemical and Volume Control Pump (s): 1-CH-P-1A 1-CC-P-1A 1-SW-P-1A 1-CH-P-1B 1-CC-P-1B 1-SW-P-1B 1-CH-P-1C 1-SW-P-4 Class : Class 2 for CH and Class 3 for CC and SW II. IMPRACTICAL CODE REQUIREMENTS Instrument Error III. BASIS FOR REQUEST Instruments used to measure certain pump parameters receive their signal at the equipment, which is transmitted to a process rack and then to a control room indicator. The sensor and rack accuracy can be affected by drift, temperature, and calibration accuracy. The indicator has a limit of accuracy. The (~ total loop accuracy is found by the root sum of the N. squares. The only variables in this formula are the sensor calibration accuracy and the indicator accuracy. Installing new sensors and indicators to reduce the accuracy by one percent is not warranted by the increase in safety obtained. The following instrument loops exceed the' 2% tolerance listed in Table IWP 4110-1. Instrument Component Parameter Accuracy FI-1122 1-CH-P-1A,B,C Flow 2.34% FI-CC-100A 1-CC-P-1A Flow 2.69% FI-CC-100B 1-CC-P-1B Flow 2.69% PI-SW-101A 1-SW-P-1A Discharge Pressure 3.18%' PI-SW-101B 1-SW-P-1B Discharge, Pressure 3.18% PI-SW-110 1-SW-P-4 Discharge Pressure 2.61% IV. ALTERNATE TESTING None 2-29 N1PVR7 Revision 7 November 5, 1993 s
RELIEF REQUEST P-14 Relief Request withdrawn. t r i t L e f 5 L : P
^t i
V t t i
.t P
2-30 ; N1PVR7 Revision 7 November 5, 1993
.' i
RELIEF REQUEST P-15 I. IDENTIFICATION OF. COMPONENTS
' System : Boric Acid Transfer Pump (s): 1-CH-P-2A 1-CH-P-2B Class- : 3 3
II. IMPRACTICAL CODE REQUIREMENTS Frequency of pump testing. i III. BASIS FOR RELIEF ; I Permanent flow instrumentation is not installed'on the j recirculation piping, which:is the only test loop- i available for: quarterly testing. To measure flow,. flow , must be established-to the emergency ^and alternate l : boration paths and then to the charging pump' suctions. -l This flow would increase the reactor coolant system i (RCS) boron inventory and cause a reactivity transient '! during normal operation. l
) During cold shutdown, the emergency and alternate boration path valves are tested with flow. However, . .
this test is short in duration-to minimize the amount ; of boric acid injected into the RCS. The pump test' -! requires an extended period of boric acid injection, ; which would upset the RCS boron balance and possibly impact the ability of the plant to restart.' Therefore, this test should~only be performed during~ cold shutdowns on the.way to reactor refueling while the RCS is being borated or during reactor refuelings. , During RCS boration or during reactor refuelings,. extended periods of pump operation on high' speed can either interfere with the boration process or adversely affect the boron balance in~the RCS. Therefore, to: ' limit the amount of boric acid injected into the KCS during the pump tests,_the pumps will be run for two minutes with flow to the'RCS before the test quantities are measured. 2-31 N1PVR7 Revision 7-November 5, 1993
F' l RELIEF REQUEST P-15 (Cont.) x m, IV. ALTERNATE TESTING These pumps will be tested every quarter on the recirculation loop. Inlet pressure, differential pressure and vibration will be measured. Every reactor refueling, inlet pressure, differential pressure, flow and vibration will be measured after the pumps have been run for two minutes with flow to the RCS. C
.. n 2-32 N1PVR7 Revision 7 November 5, 1993
i I ,
,. RELIEF REQUEST P-16 L,
I. IDENTIFICATION OF COMPONENTS System : Various Pump (s): IWP Program Pumps i See PUMP INSERVICE TEST TABLE. Class : II. IMPRACTICAL CODE REQUIREMENTS Pump inlet pressure shall be measured before starting a pump and during the test (Table IWP-3100-1) III. BASIS FOR REQUEST ' If the pump being tested is in operation as a result of normal plant or system needs, it is unreasonable to , reconfigure system lineups just to provide for the i measurement of static inlet pressure. Inlet pressure prior to pump startup is not a significant parameter ' needed for evaluating pump performance or condition.
, IV. ALTERNATE TESTING \ i ~ '
When performing a test on a pump that is already in operation, inlet pressure will only be measured during 4 pump operation. i [ I l ('~\ \
's /
2-33 N1PVR7 Revision 7 l November 5, 1993 l l
2.2.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS N. - According to the Minutes of the Public Meeting on Generic Letter.89-04, " Paragraph (g) of 10CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a
' request for relief' to be submitted to the staff.
Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety, but are not in systems or , portions of systems that are classified ASME Class 1, 2 or 3. , North Anna Power Station has elected to include certain (%) non-Code components in the ASME IST program. Where the s
"' Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability. The alternate testing is '
described in this section. There may be other deviations from Code provisions that are not described in this section. For these cases, documentation is' available at the plant site. As indicated in the Minutes of the Public Meeting on Generic Letter 89-04, a ' request for relief' need not be submitted for non-Code components. Therefore, the alternative tests described in-this section are not
' requests for relief' but are provided for information.
(3 2-34 N1PVR7 Revision 7 November 5, 1993
'l
, NON-CODE ALTERNATIVE TESTING PNC-1 N._, I I. IDENTIFICATION OF COMPONENTS l
)
System : Fuel Oil Pump (s): 1-EG-P-1HA 1-EG-P-1JA i 1-EG-P-1HB 1-EG-P-1JB - Class : NC II. IMPRACTICAL CODE REQUIREMENTS , i Measure test quantities after the pump has been running for five minutes. Measure pump bearing temperatures and vibration in mils. 1 Measure Inlet and differential pressure. III. BASIS FOR ALTERNATIVE TESTING The pump operating time is limited due to operational restraints. These pumps start automatically when fuel oil level in the day tank reaches the low level switch, (,) (~% and stop when the level reaches the high level switch. If the pumps are allowed to run for five minutes prior to measuring the test quantities, the day tank may fill past the high level switch and cause the pump to stop. Therefore, the day tank will fill and the pump will stop prior to the gathering of all of the required Section XI test data. The basis for alternative testing for vibration and temperature is described in Relief Request P-1. The diesel fuel oil transfer pumps are positive displacement pumps. One characteristic of positive displacement pumps is that the discharge pressure is independent of inlet pressure. Therefore, to determine pump degradation, only discharge pressure need be measured. The ASME OM Part 6, Code-1987, with Addenda to OMa-1988, Table 2, which is replacing Section XI, Subsection IWP, requires that only discharge pressure need be measured for positive displacement. pumps. 2-35 N1PVR7 Revision 7 November 5, 1993
,, NON-CODE ALTERNATIVE TESTING PNC-1 (Cont.)
i ) v IV. ALTERNATE TESTING The measurement of Section XI quantities will begin when the flow indication stabilizes after the pump is started (i.e., less than five minutes after the pump is started). The alternative testing for vibration and temperature , is described in Relief Request P-1.- Inlet pressure will not be measured. Discharge pressure, flow and vibration will be measured at least once every three months in accordance with Section XI requirements. The acceptance criteria for flow and discharge pressure will be based on the criteria given in ASME OM Part 6, Code-1987, with Addenda to OMa-1988, Table 2. The acceptance criteria for vibration is addressed in Relief Request P-1. O 2-36 N1PVR7 Revision 7 i November 5, 1993 i
2.3 VALVE INSERVICE TESTING PROGRAM DESCRIPTION V) 2.3.1 PROGRAM DEVELOPMENT PHILOSOPHY The North Anna Unit 1 Valve Inservice Testing (IST) Program has been established to meet the requirements of the 10CFR50, Section XI of the ASME Boiler and Pressure Vessel Code, Subsection IWV and Technical Specifications. North Anna Unit 1 Technical Specification 4.0.5 states l that Inservice Testing of ASME Code Class 1, 2 and 3 ' valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10CFR50, Section ' 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10CFR50, Section 50. 55a(g) (6) (i) . , i 10CFR50, Section 50.55a(g) (4) (iv) states that inservice examinations of components, test of pumps and valves, and system pressure tests, may meet the requirements set forth in subsequent editions and addenda of ASME ; Section XI that have been approved by the NRC, subject [ to Commission approval. North Anna Unit 1 will test those valves that fall under the scope of ASME Section XI using Subsection IWV of the 1986 Edition of ASME (- ') Section XI. The scope of the program includes ASME Section XI Class 1, 2 and 3, and certain non-Code class valves that are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident. Subsection IWV of ASME Section XI defines the rules and requirements of inservice testing of Code Class 1 ,2, and 3 valves and states that each specific valve to be tested by the rules of this subsection shall be identified by the owner and listed in the plant records. , The purpose of the IST program is to identify the valves that are considered by Virginia Electric and Power Company as having a safety function and are therefore subject to the testing requirements of-Section XI, Subsection IWV. The intent of the Code is to assess operational readiness and detect potentially adverse changes in the mechanical condition of these valves. The relief requests for the Valve Inservice Test Program identify Code requirements considered to i be impractical, provide technical basis for the request l and propose alternate testing when warranted. I i 2-37 N1PVR7 Revision 7 , November 5, 1993 ' i I
,, One reason for requesting relief from the ASME Section /)
k_/ XI testing requirenents for exercising check valves to the closed position is that the small increase in safety gained by performing these tests does not justify the complications arising from performing such tests. In some cases, to verify.a check valve closes, a leak rate test must be performed. To perform a leak rate test, systems must be removed from service. Many systems are still required during cold shutdowns and cannot be removed from service. Lines must also be drained or vented. The contents of the lines are often radioactive and require processing prior to release. Draining and venting lines significantly increases the amount of radioactive waste produced by the plant. An extended containment entry is required to perform leak rate tests. During short cold shutdowns, the concentrations of radioactive isotopes (Iodine-131, Xenon-133, etc.) are high because the isotopes do not have sufficient time to decay. Entering containment under these conditions requires respirators or air packs to be worn. Working under these conditions is difficult and-significantly increases the chances of internal contamination. For the above reasons, all check valves inside containment with the exception of those check valves ( v-') listed in T.S. 4.4.6.2.2 shall be exercised to the closed position each refueling shutdown. Leak rate testing for containment isolation valves is performed in accordance with 10CFR50, Appendix J, which irposes specific requirements, and in accordance with IWV--3426 and 3427. Appendix J satisfies the testing requirements of Section XI, Paragraphs IWV-3421 to 3425. 2.3.2 PROGRAM IMPLEMENTATION The Valve Inservice Testing Program will be executed as part of the normal plant surveillance program which is implemented by periodic tests. 2-38 N1PVR7 Revision 7 November 5, 1993 i-
l The operability Tests will verify: /_ ks- 1)- The valve responds to control commands. I
- 2) The valve stroke time is within specific '
limits.
- 3) Remote valve position indication accurately "
reflects the valve position. Failsafe valves will be tested by observing valve operation upon loss of actuating power. In most cases, this can be accomplished using normal control circuits.. Safety and relief valve setpoints are tested in accordance with ANSI /ASME OM-1-1981 as directed by IWV-3510. Valve exercising during cold shutdown shall commence within 48 hours of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hours provided all valves required to be tested during cold shutdown will be tested prior to startup. Certain valves cannot be full stroke exercised during g-~) ( normal operation following maintenance. These valves are described in the relief requests and cold shutdown justifications. If maintenance cannot be deferred to a shutdown condition, then an engineering evaluation must be performed prior to the maintenance to determine the effect of the maintenance on valve operability. If the evaluation shows that operability will not be affected, then no post maintenance testing will be required. A partial stroke test will be performed if possible. p 2-39 N1PVR7 Revision 7 i November 5, 1993
i ,\ 2.3.3 PROGRAM ADMINISTRATION _) The Engineering staff at North Anna is responsible for the administration of.the Valve Inservice Testing-Program. The Operations staff is responsible for performing the periodic tests as required by this program. The Valve Inservice Testing Program is implemented.by Station ISI Administrative Procedure 2.1 "ASME Section XI Valve program" and Periodic Test Procedures. 2.3.4 VALVE INSERVICE TESTING TABLE The Valve Inservice Testing Table provides a. list of North Anna Unit 1 ASME Section XI valves and their testing requirements. The following is a brief explanation of the table headings and abbreviations. Valve Number - Each valve has a unique identification number. Drawina Number - Classification Boundary Drawing ; Number. Sheet Number - Classification Boundary Drawing Sheet Number.
~
Dwa Coor - Drawing Coordinate of valve. Valve Tyne - The type of valve. Some abbreviations are used for valve type which are explained below. AO - air operated SO - solenoid operated DIA - diaphragm MO - motor operated MAN - manual BFLY - butterfly Valve Size - Valve size. Valve Function - A brief description of the_ function of-the valve. ASME Class - ASME Code Class of each valve. Note: NC is for non-class valves. (~ 2-40 N1PVR7 Revision 7 November 5, 1993
/',si ASME XI IWV Catecorv - Categories as defined by ASME Section XI. Categories. determine test requirements. Aw l Valves marked with an "E" are passive valves. Test Position - The following abbreviations are used to describe normal valve positions to which the valves are tested (including'the valve safety position): 0 - open i C - closed OC - open and closed Isolation Valve Type - Valves that are assigned a maximam leakage. The following abbreviations are used to describe the isolation valve types: CIV - Containment Isolation Valve subject to. Appendix J leakage testing PIV - Pressure Isolation Valve which protects low pressure safety related piping from RCS pressure C&P - Valves that serve both CIV and PIV functions Test Recuired - Testing requirements identified for the valves are identified here. ST - Stroke times shall be measured per Section XI, Subsubarticle IWV-3410 or as modified by a specific relief request. , EV - Exercise Valve for operability at least once every 3 months per Section XI, Subsubarticle IWV-3410 or as modified by a specific relief request or cold shutdown justification. LT - Leak Test shall be performed per Section XI, Subsubarticle IWV-3420 or as modified by specific relief request. CV - Check Valves shall be exercised at least once every 3 months per Section XI, subsubarticle IWV-3520 orJas modified by a specific relief request or cold shutdown justification. VP - Valve Position Indication Verification shall be verified per Section XI, Subsubarticle IWV-3300 or as modified by a specific relief request. SP, - Set points of safety and relief valves shall be tested per Section XI, Subsubarticle IWV-3510 or as 7- modified by a specific relief request. 2-41 N1PVR7 Revision 7 November 5, 1993
~
FS - Valves with fai'.-safe actuators shall be tested by (V
'\_)
observing the operation of the valves upon loss of the actuator power at least once every 3 months per Section
~
XI, Subsubarticle IWV-3415 or as modified by a specific relief request or cold shutdown justification. Relief Recuest - The relief requests corresponding to the numbers in the table are in Section 2.3.5. Cold Shutdown Justification - The cold shutdown justifications corresponding to the numbers in the table are in Section 2.3.6. Non-Code Alternative Testino Descriotion - The non-Code-alternative testing descriptions corresponding to the numbers in the table are in Section 2.3.7. ) l O V l
-1 1
l I I l l 2-42 i N1PVR7 Revision 7 November 5, 1993 I u______ ._ _ __ __-_ __ ________ _ _____- ___- _______ _ _ _
ei l t VIRGINIA POWER COMPANY PAGE: 1 0F 78 - ll NORTH ANNA UNIT 1 REVISION: 07 ! SECOND INSPECTION INTERVAL DATE: 11/05/93 :
. INSERVICE TESTING PROGRAM - VALVE TABLE -l NC 150 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REG JUST TEST ,
NUMBER NUMBER WUMBER COOR TYPE $1ZE CLASS CAT TYPE TYPE POS V- CSV- VCN-' !
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... l 1-BD-TV-100A 11715-CBM-098A 2 OF 5 C5 A0 GLOBE 3.000 2 ACIV EV C ;
FS C LT - C t ST .C VP OC $
"A" STEAM GENERATOR BLOWDOWN, OUTSIDE CON-TAINMENT ISOLATION VALVE -
............................................................. ..... ..... ... ..... ..... .... ... .... .... 3 1-BD-TV-100B 11715-CBM-098A 2 of 5 C6 A0 CLOBE 3.000 2 A CIV - EV C f FS C LT C ST C W K ,
"A" STEAM GENERATOR BLo@0WN, INSIDE CON- [
TAINMENT ISOLATION VALVE
'l .
t 1-BD-TV-100C 11715-CBM-098A 3 0F 5 C5 A0 CLOBE 3.000 2 A CIV EV C t FS C LT C ST C VP OC 4 "B" STEAM GENERATOR BLOWDOWN, OUTSIDE CON-TAINMENT ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... . . . . . . . . .... .... }
1-BD-TV 100D 11715-CBM-09BA 3 0F 5 C6 A0 GLOBE 3.000 2 A CIV EV C -' FS C -i LT C ST C t VP OC .[
"B" STEAM CENERATOR BLOWDOWN, INSIDE CON-TAINMENT ISOLATION VALVE i
............................................................. ..... ..... ... ..... ..... ....' ... .... .... t 1 BD-TV 100E 11715 CBM-098A 4 0F 5 C5 A0 GLOBE 3.000 2 A CIV EV C FS C 4 LT C f ST C !
VP- OC
............................................. i.
"C" STEAM CENERATOR BLO W OWN, OUTSIDE CON- {
TAINMENT ISOLATION VALVE j 1-BD TV-100F 11715-CBM-098A 4 0F 5 C6 A0 CLOBE 3.000 2 A Civ EV C , FS C 1 LT C ! f ST C VP OC "C" STEAM CENERATOR BLOWDOWN, INSIDE CON-TAINMENT !$0LAT]DN VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... l L
i 9 t i T i I i e 4
VIRGIN!A POE R COMPANY PAGE: 2 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE gg ( ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REO JUST TEST NUMBER -NLMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1-CC-024 11715 CBM-079A 1 OF 3 c5 CHECK VALVE 18.000 3 C CV C 0
"A" COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 1-CC 047 11715-cam-079A 10F 3 B5 CHECK VALVE 18.000 3 C CV C 0
"B" COMPONENT COOLING PLMP DISCHARGE CHECK VALVE 1-CC-084 11715-CBM 0798 2 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 3 LT C CC SUPPLY TO "A" RC PUMP LO, STATOR SHROLD &
THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV 1-CC-111 11715-lam-0798 2 0F 5 C7 CHECK VALVE 3.000 3 C CV C 65 CC SUPPLY TO "A" RC PUMP THERMAL BARRIER COOLER CHECK VALVE 1-CC-119 11715-CBM-0798 3 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 3 LT C CC SUPPLY TO "B" RC PUMP LO, STATOR SHROLD & THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV A ............................................................. ..... ..... ... ..... ..... .... ... .... .... I 11715-CBM-0798 3 0F 5 C7 CHECK VALVE 1-CC-146 3.000 3 C CV C 65 CC SUPPLY TO "B" RC PUMP THERMAL BARRIER COOLER CHECK VALVE 1-CC-154 11715-cam-0798 4 or 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 3 LT C CC SUPPLY TO "C" RC PUMP LO, STATOR SHROLD & THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV 1-CC-181 11715 CBM-079B 4 0F 5 C7 CHECK VALVE 3.000 3 C CV C 65 CC SUPPLY TO "C" RC PLMP THERMAL BARRIER COOLER CHECK VALVE 1 CC-193 11715-CBM-0798 1 0F 5 FT CHECK VALVE 18.000 2 AC CIV CV C 70 0 70 i LT C ) 1 CC SUPPLY TD "A" RHR HEAT EXCHANGER l 1-CC-198 11715-CBN-0798 10F 5 F7 CHECK VALVE 18.000 2 AC Civ CV C 70 0 70 LT C CC SUPPLY TO "B" RHR HEAT EXCHANGER 1-CC 546 11715 CSM 079D 4 0F 5 E8 CHECK VALVE 6.000 2 AC CIV CV C 62 LT C
l
'l i
l 1 VIRGINIA POWER COMPANT. PAGE: 3 or 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS . ALT d VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST l NUMBER NUMBER WUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- i CC SUPPLY TO "A" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CC-559 11715-CBM-079D 4 or 5 D8 CHECK VALVE 6.000 2 AC CIV CV C 62 LT C-CC SUPPLY T0 "B" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CC-572 11715 CBM-0790 4 0F 5 C8 CHECK VALVE 6.000 2 AC CIV CV C 62 LT C CC SUPPLY TO "C" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... 1 1-CC-MOV-100A 11715-CBM-0798 1 0F 5 A3 Mo BFLY 18.000 3 8 liv 0 ST 0 VP OC q
COMPONENT COOLING WATER RETURN THROTTLING l VALVE FROM "A" RHR HEAT EXCHANGER 1-CC-Mov-1008 11715-CBM-0798 1 0F 5 B3 Mo BFLY 18.000 3 B EV 0 ST 0 VP OC COMPONENT COOLING WATER RETURN THROTTLING VALVE FROM B RHR HEAT EXCHANGER 1-CC-RV-124A 11715-CBM 0798 2 0F 5 F6 RELIEF VALVE 3.000 3 C SP o COMPONENT COOLING WATER TO REACTOR SHROLD HEAT EXCHANGER RELIEF VALVE 1-CC-RV-1248 11715-CBM-0798 3 0F 5 F6 RELIEF VALVE 3.000 3 C SP o COMPONENT COOLING WATER TO REACTOR SHROUD HEAT EXCHANGER RELIEF VALVE 1-CC-RV-124C 11715-CBM 0798 4 0F 5 F6 RELIEF VALVE 3.000 3 C SP 0 COMPONENT COOLING WATER TO REACTOR SHROUD HEAT EXCHANGER RELIEF VALVE 1-CC-RV 125A 11715-CBM-0798 2 0F 5 C6 RELIEF VALVE .750 3 C SP 0 CC SUPPLY TO "A" RC PUMP THERMAL BARRIER RELIEF VALVE 1-CC-TV-1258 11715-CBM-0798 3 0F 5 C6 RELIEF VALVE .750 i C SP 0 CC SUPPLY To "B" RC PLMP THERMAL BARRIER RELIEF VALVE 1-CC-RV-125C 11715-CBM-0798 4 or 5 C6 RELIEF VALVE .750 3 C SP D CC SUPPLY TO "C" RC PUMP THERMAL BARRIER RELIEF VALVE 1-CC-RV-128A 11715-CBM 079B 1 0F 5 E3 kELIEF VALVE .750 3 C SP O p
f VIRGINIA MRER COMPANY PAGE: 4 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERV!CE TESTlWG PROGRAM - VALVE TABLE NC s - 150 REL CS ALT VALVE ORAWING SHEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REQ JUST TEST NUMBER NtmBER IAMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS. V- CSV- VCN-mA" kHR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 1-CC-RV-1288 11715-CBM-079B 10F 5 D3 RELIEF VALVE .750 3 C SP 0 "B" RHR HEAT EXCHANGER CCMPONENT COOLING
' RELIEF VALVE 1 CC-TV 100A 11715 CBM-079D 4 0F 5 E4 A0 SFLY 6.000 2 A CIV EV C FS C LT C ST C VP OC CC RETURN FROM "A" RECIRC AIR COOLING C0!LS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CC-TV-1008 11715-CBM-079D 4 0F 5 D4 A0 BFLY 6.000 2 A CIV EV C FS C LT C ST C VP OC CC RETURN FROM *B" RECIRC AIR COOLING ColLS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CC-TV-100C 11715-CBM-0790 4 0F 5 C4 A0 BFLY 6.000 2 A CIV EV C f
i FS LT C C ST C VP OC CC RETURN FROM "C" RECIRC AIR COOLING ColLS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CC-TV-101A 11715-CBM-079B 10F 5 D7 A0 GLOBE 4.000 2 A CIV EV C 1 FS C 1 LT C ST C 1 VP OC CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CC-TV-1018 11715-CBM-0799 1 0F 5 D6 A0 CLOBE 4.000 2 A CIV EV C 1 FS C 1 LT C ST C 1 VP OC CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIERS, INSIDE CONTAINMENT ISOLATION VALVE 1 CC-TV-102A 11715-CBM 079B 4 or 5 A5 . A0 BFLY 8.000 2 A CIV EV C 1 FS C .1 LT C ST C 1 VP OC CC RETURN FROM "C" RC PUMP LO,5fATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1 CC-TV-1028 11715 CBM-079B 4 0F 5 A3 AO BFLY 8.000 2 A CIV EV C 1 i i
?
l i d 9 9 ,, _
i VIRGINIA paler COMPANT - PAGE: 5 0F 78 NORTN ANNA UNIT 1 REVISION: 07 SEC000 INSPECTION INTERVAL DATE: 11/05/93' INSERVICE TESTING PROGRAM a VALVE TABLE NC 150 REL CS ALT-VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE 1EST TEST REQ JUST TEST NUMBER NLMBER WUMBER C004 TYPE SIZE CLASS CAT TYPE TYPE- POS V- CSV- VCN-1-CC-TV 102B 11715-cam-079s 4 0F 5 A3 A0 BFLY 8.000 2 A CIV FS C 1 ) LT C ST C 1 i YP OC. i CC RETURN FROM "C" RC PUMP LO, STATOR & SHROUD l COOLERS, INSIDE CONTAINMENT ISOLATI0tl VALVE i 1-CC TV-102C 11715-CBM-0798 3 0F 5 A5 A0 BFLY 8.000 2 A CIV -EV C 1 FS C 1 LT C i ST C 1 I i VP OC >
............................................. l CC RETURN FRON *B" RC PUMP LO, STATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1 CC-TV-102D 11715-CBM-0798 3 0F 5 A3 A0 8 FLY 8.000 2 A CIV EV C 1 FS C 1 l LT C j ST C 1 j
vP OC CC RETURN FROM "B" RC PUMP LO, STATOR & SHROLD COOLERS, INSIDE CONTAINMENT ISOLATION VALVE s 1-CC-TV-102E 11715-CBM-0798 2 0F 5 A5 Ao sFLY * .000 2 A CIV EV C 1 FS C 1 LT C ST C 1 VP DC CC RETURN FROM "A" RC PLMP LO, STATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CC-TV 102F 11715-CBM-0798 2 0F 5 A3 A0 BFLY 8.000 2 A CIV EV C 1 FS C 1 LT C ST C 1 VP OC CC RETURN FROM *A" RC PUMP LO, STATOR & SHROLD COOLERS, INSIDE CONTAINMENT ISOLATION VALVE 1 CC-TV-103A 11715-tsM-079B 1 0F 5 A7 A0 BFLY 18.000 2' A CIV EV C 0 FS C LT C ST C 0-VP OC CC RETURN FROM "A" RHR HEAT EXCHANGER, OUT-SIDE CONTAINMENT ISOLATION VALVE 1-Cr tv-1038 11715-C9M-0798 1 of 5 BT A0 BFLY 18.000 2 A CIV EV C 0 FS C LT C ST C 0 YP OC l
i i 6 VIRGINIA P0bER COMPANY PAGE: 6 0F 78 NORTH ANNA UNIT 1 REVisl0N: 07 SECOND INSPECTION INTERVAL - DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE. DRAWING $NEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST l NUMBER iN.MBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-l CC RETURN FROM "B" RNR NEAT EXCKANGER, OUT-l SIDE CONTAIMMENT ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... t 1-CC-TV-104A 11715-CBM-079s 2 0F 5 E8 A0 DFLY 8.000 2 A CIV EV C T-FS C 1 LT C t ST C .1 i
W K j CC SUPPLY TO "A" RC PUMP LO, STATOR, SHROUD & ! THERN BARRIER COOLERS, OUTSIDE CONT ISOL VLV ! 1-CC-TV-104B 11715-CBM-079s 3 0F 5 E8 A0 BFLY 8.000 2 A CIV EV C 1 ! FS C' 1 ! LT C I ST C 1 [ VP OC t 5 CC SUPPLY TO "B" RC PUMP LO, STATOR, SHROUD & t THERM BARRIER COOLERS, OUTSIDE CONT ISOL VLV l 1-CC-TV-104C 11715-CBM-079s 4 0F 5 E8 A0 BFLY 8.000 2 A CIV EV C 1 FS C l' LT C. ' ST .C 1 '! W K j CC SUPPLY TO "C" RC PUMP LO, STATOR, SHROUD & THERM EARRIER COOLERS, OUTSIDE CONT ISOL VLV [ i
............... ............................................. ..... ..... ... ..... ..... .... ... .... .... [
1-CC-TV-105A 11715-CBM-079D 4 of 5 E4 A0 SFLY 6.000 2 A CIV EV C ' FS C - LT C i ST .C 't i W K ! [> CC RETURN FROM "A" RECIRC AIR COOLING COILS, i INSIDE CONTAIMMENT ISOLATION VALVE t 1-CC TV-1058 11715-CBM-079D 4 0F 5 D4 A0 SFLY 6.000 2 A CIV EV C a FS C LT C - ST C VP DC CC RETURN FRON *B" RECIRC AIR COOLING COILS, INSIDE CONIAINMENT ISOLATION VALVE . 1-CC-TV-105C 11715-CBM 0790 4 0F 5 C4 A0 BFLY 6.000 2 A CIV EV C FS .C 'l LT C i ST C .I VP OC I CC RETURN FROM *C" RECIRC AIR COOLING COILS, INSIDE CONTAINMENT !$0LATION VALVE .-*
............................................................. ..... ..... ... ..... ..... .... ... .... .... a f
I 1 i \ i
r 4 J i i l VIRGINIA POER CCSPANY PAGE: 7 0F 78 - i NORTH ANNA UNIT 1 REVISION: 07 l SECONO INSPECTIDW INTERVAL . DATE: 11/05/93 ! INSERVICE TESTING PROGRAM - VALVE TABLE :!; NC ! i 150 REL CS ALT .! VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST I NUMBER WLMBER NUMBER COOR TYPE $1ZE CLASS CAT TYPE TYPE POS V- CSV- VCN- 'I CD-161 1171S-CBB-040C 1 0F 3 E6 CHECK VALVE 3.000 3 C' CV 0 i
-t CONTROL ROOM CNILLED WATER SYSTEM PUMP f
DISCHARGE CHECK VALVE 1 CD-182 11715-CBB '40C 1 0F 3 D6 . CHECK VALVE 3.000 3 C CV 0
............................................. i CONTROL ROOM CHILLED WATER SYSTEM PUMP l DISCHARGE CHECK VALVE '
i, 1-CD-209 11715-CBS-040C 1 0F 3 C6 CHECK VALVE 3.000 3 C CV 0 .
............................................. i CONTROL ROOM CHILLED WATER SYSTEM PUMP DISCHARGE CHECK VALVE I f
4 t ii e f 9 a n B P r 4 1 i i i t I b
-+
f i 5 t a
?
,h i.
5
)
h r T v h s
+
7 i
r VIRGINIA P0bER COMPANY PAGE: . 8 0F 78 WORTH ANNA UNIT 1 REVIS!DN: 07 e SECOND INSPECTION INTERVAL DATE: 11/05/93' '! INSERVICE TESTING PROGRAM - VALVE TAALE i fr~'g
\ l NC h ISO REL CS ALT !
VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST 1 NUMBER NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- !
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... l 1-CH-084 11715-CBM-095A 1 0F 4 C4 CHECK VALVE 2.000 3 C CV 0 3 i "A" BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE
- 1-CN-102 11715 CBM-D95A 1 0F 4 C5 CHECK VALVE 2.000 3 C CV 0 3 i "B" BORIC ACID TRANSFER PUMP DISCHARGE CHECK ;
VALVE I 1-CH-215 11715-CBM-0958 1 0F 2 B6 CHECK VALVE 4.000 2 AC CV C 72 : O LT C CHARGING PLMP SUPPLY FROM VOLUME CONTROL TANK 5 ISOLATION VALVE 1-CH-238 11715-CBM-095B 1 0F 2 BS CHECK VALVE 2.000 2 C CV 0 4. MAIN EMERGENCY BORATION LINE TO CHARGING PUMP SUCTION CHECK VALVE 1-CH-240 11715-CBM-095B 1 0F 2 C3 CHECK VALVE 1.000 3 C CV 0 4 l ALTERNATE EMERGENCY BORATION LINE CHECK VALVE e-'s 1 CH-241 11715-CBM-0958 1 OF 2 B4 MAWuAL GATE 1.000 3 B EV 0 4' g ............................................. ( ALTERNA1E EMERGENCY SORATION LINE i MANUAL VALVE $ 1-CH-242 11715-CBM 0958 1 OF 2 B5 -CHECK VALVE 1.000 2 C CV 0 4 ALTERNATE EMERGENCY BORATION LINE TO - CHARGING PUMP SUCTION CHECK VALVE f 1-CH-252 11715-CBM-0958 2 0F 2 D7 CHECK VALVE 3.000 2 C CV 0 38 "A" CHARGING PUMP DISCHARGE REC!RC LINE CHECK i VALVE ! t 1 CH-254 11715-CBM-0958 2 0F 2 D7 CHECK VALVE 3.000 2 C CV 'C 47
- O 47 ,
"A" CHARGING PUMP DISCHARGE CHECK VALVE t
~
1 CH-264 11715-CBM-0958 2 0F 2 D6 CHECK VALVE 3.000 2 C CV 0 38 l l
............................................. I "B" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE ,
............................................................. ..... ..... ... ..... ..... .... ... .... . . . . - r 1-CH-267 11715-CBM-0958 2 0F 2 D6 CHECK VALVE 3.000 C CV C 47 0 47 "B" CHARGING PUMP DISCHARGE CHECK VALVE 1-CH-277 11715-CBM-D95B 2 0F 2 D4 CHECK VALVE 3.000 2 C CV O 38
............................................. 1 1
*C" CHARGING PUMP DISCHARGE RECIRC LINE CHECK -
VALVE
VIRG!k!A PO KR COMPANY PACE: 9 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE .p. ). .
- - yc .
V 150 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER N(MBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN* 1 CH-279 11715-CBM-095B 2 0F 2 D6 CHECK VALVE 3.000 2 C CV C 47 0 47 "C" CHARGIhG PUMP DISCHARGE CHECK VALVE 1-CH-322 11715-CBM-095C 1 0F 2 D4 CHECK YALVE 3.000 2 AC CIV CV C 10 LT C MAIN CHARGING SUPPLY HEADER, INSIDE CONTAIN-MENT ISOLATION CHECK VALVE 1-CH-330 11715-CBM-095C 1 0F 2 A6 CHECK VALVE 2.000 1 AC CIV CV C 10 LT C CHARGING SUPPLY To LOOP FILL HEADER, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CH-336 11715-CBM-095C 2 0F 2 B8 CHECK VALVE 2.000 1 C CV C 10 "A" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT ISOLAfl0N CHECK VALVE 1-CH-358 11715-CBM-095C 2 0F 2 B7 CHECK YALVE 2.000 1 C CV C 10 "B" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT ISOLATION CHECK VALVE / 1-CN-380 11715-CBM-095C 2 0F 2 B5 CHECK YALVE 2.000 1 C CV C 10 \' .............................................
"C" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CH-402 11715-CBM-09%C 2 0F 2 F4 CHECK VALVE .750 2 AC CIV CV C 10 LT C 59 RC PUMP SEAL WATER RETURN, INSIDE CONTAINMENT ISOLATION CHECK VALVE
.............................................s............... ..... ..... ... ..... ..... .... ... .... ....
1-CH-FCV-1113A 11715-CBM-0958 1 0F 2 C3 A0 GATE 1.000 3 8 EV 0 FS 0 ST 0 VP OC ALTERNATE EMERGENCY BORAT10N LINE FLOW CONTROL VALVE 1 CH FCV-1114A 11715-CBM-0958 1 OF 2 D4 A0 GLOBE 1.000 3 8 EV C FS C ST C VP OC PRIMARY GRADE WATER FLOW CONTROL VALVE 1-CH-FCV 1160 11715-CBM-095C 1 0F 2 A4 A0 GLOBE 2.000 2 AE CIV LT C t VP OC 1 CHARGING FLOW CONTROL TO LOOP FILL HEADER, OUTSIDE CONTAINMENT ISOLAlluN VALVE 1-CH-LCV-1460A 11715-CBM-095C 1 0F 2 F7 A0 CLDEE 2.000 1 B EV C 5 (m 1 FS C 5 l \ ST C
VIRGINIA poler CCWANY . PAGE: 10 0F 78 - NORTH ANNA UNIT 1 REVIS!DN: 07 L SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE p
'( . NC-
!$0 REL CS ALT VALVE DRAWING SHEEF DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMnEii itlun TYPE - SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN*
1-CH-LCV-1460A 11715-CSM-095C 1 0F 2 F7 A0 GLC4E 2.000 1 8 VP OC LETDOWN ISOLATION VALVE 1-CH LCV-1460B 11715-CsM-095C 1 CF 2 F7 A0 GLOBE 2.000 1 5 - EV C 5 FS C 5 ST C VP OC LETDOWN ISOLAT!DN VALVE 1 CH-MOV-11158 11715-cam-095B 2 0F 2 88 M0 GATE 8.000 2 A EV C 6 0 6 LT C ST C 6 h 0 6 VP OC CHARGING PLMP SUPPLY 180LAT10W VALVE FROM , REFUELING WATER STORAGE TANK 'j 1-CH-MOV-1115C 11715-CBM-095B 1 0F 2 C6 MO GATE 4.000 2 8 EV C 6 1 I ST C 6 i VP OC
'1 CHARGING PUMP SUPPLY ISOLATION FROM VOLUME .l CONTROL TANK 1-CH MOV-1115D 11715-CBN-0958 2 0F 2 88 No GATE 8.000 2 A EV C 6 0 6 LT C ST C 6 0 6 VP OC CHARGlhG PUMP SUPPLY !$0LAT10N VALVE FROM 1
REFUELING WATER STORAGE TANK I
............................................................. ..... ..... ... ..... ..... . . . . - ~ . . . .... ....
1 CH Mov-1115E 11715-CBM-0958 1 of 2 C6 M0 GATE 4.000 2 B EV 'C 6 ST C- 6 VP OC CHARGING PLMP SUPPLY ISOLATIDW VALVE FROM VOLUME CONTROL TANK l ............................................................. ..... ..... ... ..... ..... .... ... .... .... l 1-CH MOV-1267A 11715-CBM 0958 2 0F 2 C7 M3 GATE 6.000 2 E VP OC "A" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 1 CH-M0v 1267B 11715-CBM-0958 2 of 2 C7 MO GATE 6.000 2 E VP OC "A" CHARGING PLMP SUCTION ISOLATION FROM LHSI 1-CH-Mov-12694 11715-CBM-0958 2 0F 2 C5 M0 GATE 6.000 2 E VP' OC "B" CHARGING PUMP SUCTION ISOLATIDW FROM RWST AND VCT 1-CM Mov 1269B 11715-CSM 0958 2 0F 2 C5 MO GATE 6.000 2 E VP OC i t .
r
- , VIRGINIA POER COMPANY PAGE
- 11 0F 78 NORTH A MA UNIT 1 REVISIONS 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE I NC
\ . !$0 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASE IW VALVE TEST TEST REQ JUST' TEST I NUMBER -NtmBER NLBGER COOR TYPE SIZE CLASS CAT T"7E TYPE PDS V- CSV- VCN- -;
"B" CHARGING PUMP SUCTION ISOLATION FROM LHSI ~ ,
1-CH-MOV-1270A 11715-CBM-0958 2 0F 2 C3 MO GATE 6.000 2 F. VP OC l "C" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 1
............................................................. ..... ..... ... ..... ..... .... ... .... ....J }
1-CN-MOV-12708 '11715-CBM 0958 2 0F 2 C3 M0 GATE 6.000 2 E VP OC "C" CHARGING PUMP SUCTION ISOLATION FROM LHSI :i 1-CH-MOV 1275A 11715-CBM-0958 2 0F 2 07 M0 GATE 2.000 2 B EV C ! O ST C , 0 i VP OC .
............................................. j "A" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE
[ j 1-CH-MOV-12758 11715-CBM-095B 2 0F 2 D5 Mo CATE 2.000 2 B EV C .l 0 ! ST C l 0 , W K !
"B" CHARGING PUMP MINIMUM RECIRCULATION 150-LATION VALVE 1-CH MOV 1275C ' w CBM-0958 2 0F 2 D4 MO GATE 2.000 2 B EV C I O ,
ST .C i 0 VP OC +
"C" CHARGING PUMP MINIMUM RECIRCULATION ISO- l LATION VALVE 1-CH-MOV-1286A 11715-CBM-095B 2 0F 2 E7 MO GATE 3.000 2 B EV 'C 0
ST C + 0 i VP OC l!
"A" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE
- 1-CH-MOV-12868 11715-CBM 0958 2 of 2 E6 MO GATE 3.000 2 B EV C 0
ST C 0 . VP OC .
"B" (
CHARGING PUMP MAIN DISCHARGE ISOLATION j VALVE ; 1-CH-MOV-1286C 11715-CBM-0958 2 0F 2 E4 Mo CATE 3.000 2 B EV C i 0 l ST C O i VP OC l J d
-l
(, ! l
c , I i 1 I VIRGINIA POWER COMPANY PAGE: 12 0F 78 1 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93
^ INSERVICE TESTING PROGRAM - VALVE TABLE f \
l ) V ISO NC REL CS ALT VALVE DRAVING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER WlMBER NUMBER COOR TTPE SIZE CLASS CAT TYPE TYPE POS V-CSV- VCN-
"C" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH->0V.1287A 11715-CBM-095B 2 0F 2 07 Mo GATE 3.000 2 8 EV C 0
ST C 0 VP OC "A" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 1-CH MOV-1287B 11715-CBM-0958 2 0F 2 D6 M0 CATE 3.000 2 8 EV C 0 ST C 0 VP OC "B" CHARGING PUMP ALTERkATE AND LOOP FILL DISCHARGE ISOLATION VALVE 1 CH-MOV-1287C 11715-CBM-0958 2 0F 2 D4 M0 CATE 3.000 2 8 EV C 0 ST C 0 VP OC
] "C" CHARGING PUMP ALTERNATE AND LOOP FILL Cf DISCHARGE ISOLATION VALVE 1-CH-MOV-1289A 11715-CEM-095C 1 0F 2 D4 M0 CATE 3.000 2 A CIV EV C 7 LT C ST C 7 VP OC MAlW CHARGtkG HEADER ISOLATION VALVE, OUTS!DE CONTAINMENT ISOLATION VALVE 1-CH-MOV-12898 11715-CBM-095C 1 or 2 B3 Mo GATE 3.000 2 B EV C 7 ST C 7 VP OC MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT 1-CH MOV-1350 11715-CBM-0958 1 0F 2 B5 M0 GATE 2.000 2 B EV 0 4 ST 0 4 VP OC EMERGENCY BORAT10N TO CHARGING PUMP SUCTION 1-CH*MOV-1373 11715-CBM-0958 1 OF 2 A8 MO G*.~t 3.000 2 E VP OC CHARGING PUMP RECIRCULATION HEADER ISf1AT!DN VALVE 1-CH Mov-1380 11715-CBM-095C 2 0F 2 F4 MO GATE 3.000 2 A CIV EV C 9 LT C 59 ST C 9 n VP OC
( s
VIRGINIA P0hER CODFANY PAGE: 13 0F 78. NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE yu '. k _ NC
!$0 REL CS' ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASBE IW VALVE TEST TEST REQ .JUST TEST NLMBER NUMBER WUMBER COOR TTPE S!ZE CLASS CAT TYPE TTPE POS V- CSV- VCN-REACTOR COOLANT PUMP SEAL WATER RETURN, INSIDE CONTAINMENT ISOLATION VALVE 1-CH-MOV-1381 11715-CBM 095B 1 of 2 C8 MO GATE 3.000 2 A ClY EV C 9 LT C ST C 9
. VP OC REACTOR COOLANT PUMP SEAL WATER RETURN, OUT-SIDE CONTAINMENT ISOLATION VALVE 1-CH4V-1203 11715-CBM-095C 1 0F 2 F4 RELIEF VALVE 2.000 2 C $P O LETDOWN RELIEF VLV DOWNSTREAM OF REGEN HX, RV DISCHARGE To PRESSURIZER RELIEF TANC 1-CH-RV-13828 11715-CBM-095B 1 0F 2 C7 RELIEF VALVE 2.000 2 C SP O SEAL WATER HEAT EXCHANGER RELIEF VALVE, RV DISCHARGE TO VOLUME CONTROL TANC 1-CH-TV-1204A 61715-CBM-095C 1 0F 2 E3 AO GLOBE 2.000 2 A CIV EV C 5 FS C 5 LT C ST C 5 VP OC
\
LETDOWN CONTROL FROM REGEN HX, INSIDE g . CONTAINMENT ISOLATION VALVE 1-CH TV-1204B 11715-CBM-095A- 4 0F 4 C3 A0 CLOBE 3.000 2 A CIV EV C 5 f5 C 5 LT C ST C 5 VP OC LETDOWN CONTROL TROM REGEN HX, OUTSIDE CONTAINMENT ISOLATION VALVE
i i 1 I VIRGIN!A P0bER C00FANY PAGE: 14 0F 78 - NORTH ANNA UNIT 1 REVISION: 07 ). SECOND INSPECT 10N INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE i \ NC ISO REL CS ALT s VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REG JUST TEST : WUMBER SIZE CLASS CAT TYPE TYPE POS V- ' NUMBER WUMBER COOR TYPE CSV- VCN-1 CV-004 11715-CBM-092A 2 0F 2 A5 MANUAL GATE 8.000 2 AE CIV. LT C CONTAINMENT VACUUM EJECTOR SUPPLY, OUTSIDE ' CONTAINMENT ISOLATION VALVE ? 1-CV-08 11715-CSM-092A 2 OF 2 B3 CHECK VALVE 2.000 2 C CV- 0 CONTAINMENT VACUUM SYSTEM ISOLATION CHECK VALVE - 1-CV 14 11715-CBM-092A 2 0F 2 C3 CHECK VALVE 2.000 2 C CV D ; CONTAINMENT VActAM SYSTEM !$0LATION CHECK VALVE "
............................................................. ..... ..... ... ..... ..... .... ... .... .... I 1-CV-TV-100 11715-CsM-092A 2 0F 2 A3 A0 BFLY 8.000 2 AE CIV LT C l VP OC CONTAINMENT VACUUM EJECTOR, INSIDE CONTAIN- .
MENT ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... L 1-CV-TV-150A 11715 CBM-092A 2 0F 2 B4 A0 CLOBE 2.000 2 A CIV EV C l FS C t LT C i ST C 54 5 VP OC t
*A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CV-TV-150B 11715-CBM 092A 2 0F 2 E5 A0 GLOBE 2.000 2 A CIV EV C FS C LT C ST C 54 ,-
VP OC r "A" CONTAINMENT VACULM PtMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE ' 1-CV-TV 150C 11715-CBM-092A 2 OF 2 C4 A0 GLOBE 2.000 2 A CIV EV C r FS C i LT C ST C 54 VP OC > r "B" CONTAINMENT VACUUM PUMP SUCTION ISOLATION' ; VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CV-TV-150D 11715-CBM-092A 2 0F 2 C5 A0 GLOBE 2.000 2 A CIV EV C l f FS C LT C ST C 54 VP OC >
............................................. e "B" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE m
a 4 4 i
I r i t VIRGINIA POWER COMPANY PAGE: 15 0F 78 t NORTH ANNA UNIT 1 REVISIDW: 07- [ SECOND INSPECTION INTERVAL DATE: 11/05/93 .t INSERVICE TESTING PROGRAM - VALVE TABLE f-%s , ( - NC l ISO REL CS ALT ! VALVE DRAWING SHEET DRWG VALVE VALVE ADME IWV VALVE TEST TEST REQ JUST TEST i NUMBER NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-P 1 DA-039 '11715-CBM-090C 3 0F 3 D3 MAN DIAPHRAM 2.000 2 AE CIV LT C v VENT LINE FROM PRIMARY VENT POT, INGIDE ; CONTAINMENT ISOLATIDW VALVE ; 1-DA-041 11715-CSM-D90C 3 0F 3 E3 MAN DI APHRAM 2.000 2 AE CIV LT C : VENT LINE FROM PRIMARY YENT POT, OUTSIDE CONTAINMENT ISOLATION VALVE l
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 1-DA-TV-100A 11715 CBM-D90A 1 0F 2 E7 AC CLOBE 2.000 2 A Civ EV C {
FS C LT C l ST C 54 i VP OC
............................................. t REACTOR CONTAINMENT SUMP PUMPS DISCHARGE,
- OUTSIDE CONTAINMENT ISOLATION VALVE 1-DA-TV-1008 11715-CBM-090C 3 0F 3 C3 'A0 GLOBE 2.000 2 A CIV EV C
{ FS C , LT C ' ST C 54 VP OC
............................................. l REACTOR CONTAINNENT SUMP PUMPS DISCHARGE, !
INSIDE CONTAIN4ENT ISOLATION VALVE 1-DA-TV-103A 11715-CBM-D90C 3 0F 3 B7 A0 GLOBE 2.000 2 A CIV EV ~ C > FS C 'l LT C ST C 54 l VP OC I POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT ISOLATION VALVE I 1-DA-TV 1038 11715-CBM-090C 3 0F 3 88 A0 CLOBE 2.000 2 A CIV EV C i FS C : LT C ST C 54 VP OC POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT TRIP VALVE 5
3_ f 1 I P VIRGINIA P0lER CGEPANY PAGE: 16 0F 78 WORTN ANNA UNIT 1 REVISION: 07 ; E SECOND INSPECTION INTERVAL DATE: 11/05/V3 i
. INSERVICE TESTING PROGRAM - VALVE TABLE /"S !
NC (-- 150 REL CS ALT
. VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST l NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- .
1-DG-TV-100A 11715-CBM-090C 10F 3 88 A0 GLOBE 2.000 2 A CIV EV C - FS C l LT C ; ST C ! VP OC j
............................................. l PRIMARY DRAIN TRANSFER PLRIPS DISCHARGE, OUT- I SIDE CONTAINMENT !$0LAT10N VALVE ,
1-DG TV 100B 11715 CBN-090C 1 or 3 $7 A0 GLOBE 2.000 2 A CIV EV C ! FS C -> LT C ! ST C 54 W % PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, j INSIDE CONTAINMENT ISOLATION VALVE .t t e i i i t I h
?
i
?
i i
,I i
e b
-.{
r n i
'f 1
}
t 1 i Y
1 l VIRGINIA POWER COMPANY PAGE: 17 OF 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93
/%. INSERVICE TESTING PROGRAM - VALVE TABLE
\' NC ISO REL CS ALT VALVE DRAVING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST WlMBER NtMBER NUMBER COOR TYPE $1ZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1-EB-015 11715-FM -107A 1 0F 4 E6 CHECK VALVE 1.500 NC C cv 0 4 l 1H DIESEL "KA" AIR RECEIVER TANK DISCHARGE VALVE 1-EB-034 11715-FM -107A 3 0F 4 E6 CHECK VALVE 1.500 NC C CV O 4 l 1J DIESEL "JA' AIR RECE!VER TANK DISCKARGE
- VALVE ,
1-EB-041 11715-FM -107A 1 0F 4 06 CHECK VALVE 750 NC AC CV C LT C
............................................. l 1H DIESEL "MA" AIR RECEIVER TANK ISOLATION VALVE 1-EB-D53 11715-FM -107A 3 0F 4 06 CHECK VALVE 750 NC AC CV C LT C 1J DIESEL "JA" AIR RECEIVER TANK ISOLATION VALVE 1-EB-065 11715-FM 107A 2 0F 4 E6 CHECK VALVE 1.500 NC C CV 0 4 i
l 1H DIESEL "B" AIR RECEIVER TANK DISCHARGE l VALVE l 1-EB-072 { 11715-FM -107A 2 0F 4 D6 CHECK VALVE .750 NC AC CV C e'~ LT C ( ............................................. l 1H DIESEL "B" AIR RECEIVER TANK ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... g 1-EB-084 11715-FM -107A 4 0F 4 E6 CHECK VALVE 1.500 NC C CV O 4 I 1J DIESEL "B" AIR RECEIVER TANK DISCHARGE !
1 VALVE l 1 EB-091 11715-FM .107A 4 0F 4 D6 CHECK VALVE .750 NC AC CV C 1J DIESEL "B" AIR RECEIVER TANK ISOLATION VALVE i b s,
1 t VIRGINIA POWER COMPANf PAGE: 18 0F 78 l NORTM ANNA UNIT 1 REVISION: 07 SECONO INSPECT 10M INTERVAL INSEEVICE TESTING PROGRAM - VALVE TABLE
'DATE: 11/05/93
]
~ , NC ISO REL CS ALT .
-VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REO JUST TEST l NUMBER -NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE ' TYPE POS V- CSV- VCN-~ i 1 EG 254 11715-FB -035A 2 or 2 B7 CHECK VALVE 1.500 NC C CV O l 1H DIESEL "A" EMERGENCY GENERATOR PUMP
- DISCHARGE CHECK VALVE-
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 1-EG-266 11715-FB -035A - 2 0F 2 B6' CHECK VALVE 1.500 NC C CV' o 1J DIESEL "A" EMERGENCY GENERATOR PUMP e
DISCHARGE CHECK VALVE i
............................................................. ..... ..... ... ..... ..... .... ... .... .... l 1 EG-278 11715-FB -035A 2 0F 2 B6 CHECK VALVE 1.500 NC C CV 0 1H DIESEL "B" EMERGENCY GENERATOR PUMP ~j DISCHARGE CHECK VALVE .!
1-EG-295 11715-FB -035A 2 OF 2 D6 CHECK VALVE 1.500 NC C CV 0 !
............................................. .t 1J DIESEL "B" EMERGENCY GENERATOR PUMP I DISCHARGE CHECK VALVE ~l
............................................................. ..... ..... ... ..... ..... .... ... .... .... I i
1-EG-RV-103A 11715-FB -035A 2 0F 2 B7 RELIEF VALVE 1.000 NC C SP 0 4 1H DIESEL "A" EMER GENERATOR PUMP DISCHARGE {* RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION <
............................................................. ..... ..... ... ..... ..... .... ... .... .... .j 1 EG-RV-1038 11715-FB -035A 2 OF 2 E6 RELIEF VALVE 1.000 NC C SP O :j
.....................,....................... c 1H DIESEL "B" EMER GENERATOR PUMP DISCHARGE :i RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION
............................................................. ..... ..... ... ..... ..... .... ... .... .... {,
1-EG-RV.105A 11715-FB -035A 2 0F 2 E7 RELIEF VALVE 1.000 NC. C SP O
............................................ i e
1J DIESEL "A" EMER GENERATOR PUMP DISCHARGE i RELIEF VALVE, RV DISCHARGE TO PLMP SUCTION 1-EG RV-105B 11715-FB 035A 2 0F 2 E6 RELIEF VALVE 1.000 NC C SP O- .
............................................. i 1J DIESEL "B" EMER GENERATOR PUMP DISCHARGE !
6 RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION j 1-EG RV 602HA 11715 FM -107A 1 0F 4 E4 RELIEF VALVE 2.000 NC C $P O .i
............................................. 5 1H DIESEL "A" AIR RECE!VER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE ,
1-EG-RV-602HB 11715-FM 107A 2 0F 4 E4 RELIEF VALVE 2.000 NC C SP O + 1H DIESEL "B" AIR RECEIVER TAWK RELIEF VALVE, i RV DISCHARGE TO ATMOSFHERE t
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 1-EG-RV-602JA 11715 FM .107A 3 0F 4 E4 RELIEF VALVE 2.000 NC C SP O l 1J DIESEL "A" AIR RECEIVER TANK RELIEF VALVE, l
RV DISCHARGE TO ATMOSPHERE 1-EG-RV 602JB 11715-FM -107A 4 0F 4 E4 RELIEF VA1VE 2.000 NC C SP O
............................................. f 1J DIESEL "B" AIR RECEIVER TANK RELIEF VALVE, 4 RV DISCHARGE TO ATMOSPHERE
............................................................. ..... ..... ... ..... ..... .... ... .... .... g 1-EG- SOV-600HA 11715 FM -107A 10F 4 E6 So GATE 1.500 NC B EV 0 ;
- /*"+ ST 0 4 I s
% 1 i
.I
?
l t' e.
. i
t i I p VIRGINIA poler CGIPANY PAGE: 19 0F 78 l NORTH ANNA UNIT 1 REVISION: 07 , SECOND INSPECTION INTERVAL DATE: 11/05/93- ! INSERVICE TESTING PROGRAM - VALVE TABLE NC s ISO REL CS ALT [ VALVE DRAWING $NEET DRWG VALVE VALVE ASME ~ IWV VALVE TEST TEST REQ JUST TEST ! NUMBER NLMBER . NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV-' VCN- ! t
............................................. p DIESEL AIR START SOLEN 0!D VALVE i r
.1 1-EG-50V-600HB 11715-FM -107A 2 0F 4 E6 SO GATE 1.500 NC s- EV 0 i ST 0 '4 -!
DIESEL AIR START SOLEWO!D VALVE l 1-EG-50V-600JA - 11715-FM .107A 3 0F 4 E6 50 GATE 1.500 NC B EV O .' > ST - 0 4 ! DIESEL AIR START SOLEN 0!D VALVE l
. ............................................................. ..... ..... ... ..... ..... .... ... .... .... e i
1-EG-$0V 600JB 11715-FM ~107A 4 0F 4 E6 SO GATE 1.500 NC 8 EV 0 t ST 0 4 DIESEL AIR START SOLENOID VALVE t i
............................................................. ..... ..... ... ..... ..... .... ... .... .... I 1-EG-SOV-60lHA 11715-FM -107A 1 0F 4 E6 S0 GATE -1.500 NC B EV 0 j
. ST 0 4 DIESEL AIR START SOLENOID VALVE 5 i
............................................................. ..... ..... ... ..... ..... .... ... .... .... 'j 1-EG-50V-607JA 11715-FM +107A 3 of 4 E6 SO GATE 1.500 NC 8 EV O ST 0 4 [
............................................. t DIESEL AIR START SOLENDID VALVE .! .
............................................................. ..... ..... ... ..... ..... .... ... .... .... [
.L r
i l I 1
.i
?
I e I 6 6 6 1 m -,
1 1 VIRGINIA PthER C(NPANY PAGE: 20 0F'78 l N0kTH ANNA UNIT 1- REVISTON: 07 . ' SECOND INSPECTION INTERVAL DATE: 11/05/93 { INSERVICE TESTING PROGRAM - VALVE TABLE
- . t l
NC I
' \ 130 REL CS- ALT $
VALVE ~ DRAWING. $NEET DRWr, VALVE VALVE ASME IW VALVE TEST - ~ TEST REG JUST TEST
. NL81BER {
NLDIBER NLSIBER COOR TYPE SIZE CLASS CAT TYPE TTPE POS V- CSV- VCN- - 6 1 FP-272 11715-CBB 102B 1 0F 1 C6 CHECK VALVE 4.000 2 AC CIV CV C 16 i LT C FIRE PROTECTION SUPPLY TO CONTAINMENT, INSIDE CONTAleNIENT ISOLATION CHECC VALVE [: 1-FP-274
)
11715-CBB 1028 1 0F 1 C7 MANUAL GATE 4.000 2 AE CIV LT_ C ; FIRE PROTECTION SUPPLY TO CONTAINMENT, i OUTSIDE CONTAINNENT ISOLATION VALVE . f l h l t t t i i n t f i b 1 a i i
?
i h i- - j 4
. 1
,1 I
. , .c . _ _ _ --
b
VIRGINIA POWER COMPANY PAGE: 21 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE im\ (Lj ISO REL CS NC ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER WLMBER NLMSER COOR TYPE $!ZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1- F'J-047 11715-CBM-074A 1 0F 4 E6 CHECK VALVE 16.000 2 C cv c 12 "A" MAIN FEEDWATER SUPPLY, CONTAINMENT PENETRATION CHECK VALVE 1-FW-061 11715-CBN-074A 1 0F 4 B5 CHECK VALVE 3.000 3 C CV 0 29 STANDBY "A" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 1 FW-062 11715-CBM-074A 1 0F 4 B5 MANUAL GATE 3.000 3 B EV C 40 0 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE F20M MOTOR-DRIVEN PUMP HEADERS 1 FW-063 11715-CBM-074A 1 0F 4 B6 CHECK VALVE 3.000 3 C CV 0 29 STANDBY "A" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 1-FW-064 11715-CBM-074A 1 0F 4 B5 MANUAL CATE 3.000 3 B EV C 40 0 40 AUXILIARY FEEDWATER HEADER MAEUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1-FW-068 11715-CBM-074A 1 OF 4 D6 CHECK VALVE 3.000 2 o I p ij "A" AUXILIARY FEEDWATER HEADER CHECK VALVE AT C CV
' MAIN FEEDWATER HEADER 14W-079 11715-CBM-074A 1 0F 4 D6 CHECK VALVE 16.000 2 C cv c 12 "B" MAIN FEEDWATER HEADER SUPPLY, CONTAINMENT PENETRATION CHECK VALVE 1-FW-093 11715-CBM-074A 1 0F 4 B6 CHECK YALVE 3.000 3 C CV O "B" AUXILIARY FEEDWATER HEADER CHECK VALVE, UUTSIDE OF CONTAINMENT 1-FW 094 11715-CBM 074A 1 0F 4 B6 MANUAL GATE 3.000 3 B EV C 40 0 40 AUXILI ARY TEEDWATER HEADER MANUAL ISOLAT]DN VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1-FW-095 11715 CBM-074A 10F 4 $6 CHECK VALVE 3.000 3 C CV O 29 STANDBY "B" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 1-FW 096 11715-CBM-074A 1 0F 4 B6 MANUAL GATE 3.000 3 B EV C 40 0 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION ,
VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1-FW-100 11715-CBM-074A 1 0F 4 C6 CHECK VALVE 3.000 2 C CV O
............................................. l j "B" AUXILIARY FEEDWATER HEADER CHECK VALVE AT
[~ MAIN FEEDWATER HEADER l I ( ............................................................. ..... ..... ... ..... ..... .... ... .... .... 1 4 1 1
.J
i VIRGINIA POWER CCMPANY PAGE: 22 OF 78 NORTH ANNA UNIT 1 REV!$10N: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE O '\ ""<! uC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1-FW-111 11715-CBM-074A 1 0F 4 B6 CHECK VALVE 16.000 2 C CV C 12 "C" MAIN FEEDWATER SUPPLY, CONTAINMENT PENETRATION CHECK VALVE 1-FW-125 11715-CBM-074A 1 0F 4 B7 CHECK VALVE 3.000 3 C CV o 29 STANDBY "C" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 1-FW-126 11715-CBM-074A 10F 4 B7 MANUAL GATE 3.000 3 B EV C 40 0 40 AUX!LIARY FEEDWATER HEADER E MUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1-FW-127 11715-CBM-074A 1 0F 4 B7 CHECK VALVE 3.000 3 C CV 0 "C" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 1-FW-128 11715-CBM-074A 1 0F 4 B7 MANUAL CATE 3.000 3 B EV C 40 0 40 l AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1-FW-132 11715 CBM-074A 1 0F 4 B7 CHECK VALVE 3.000 2 C CV 0 r l k" "C" AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 1 FW-145 11715-CBM-074A 3 0F 4 B7 MANUAL CATE 6.000 3 B EV O 41 ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS 1 FW-1&E 11715-CBM-074A 3 OF 4 DB CHECK VALVE 6.000 3 C CV o
...c......................................... l TURBINE DRIVEN AUXILIARY FEEDWATER PUMP DISCKARGE CHECK VALVE 1-FW-149 11715-CBM-074A 3 0F 4 E8 MANUAL CATE 6.000 3 B EV C 40 0 40 AFW PLMP DISCHARGE HEADER ALIGEMiki/ Cross CONNECT VALVE 1-FW-150 11715-CBM-074A 3 0F 4 D7 CHECK YALVE 1.000 3 C CV O
................................. ........... l TURBINE DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LikE CHECK VALVE 1-FW-155 11715-CBM-074A 3 DF 4 E7 MANUAL GATE 6.000 3 8 EV C 40 0 40 AFW PUMP DISCHARGE HEADER ALIGkMENT/ CROSS CONNECT VALVE 1-FW-162 11715-CBM-074A 3 0F 4 B6 MANUAL CATE 6.000 3 8 EV O 41 f ~s ALTERNATE WATER SUPPLY TO AFW P(MP SUCTIONS ks ............................................................. ..... ..... ... ..... ..... .... ... .... .... ,
I i. 4 VIRGINIA POWER COMPANY PAGE: 23 0F 78 ' WORTH ANNA UNIT 1 REVISION: 07 i SECOND INSPECTION INTERVAL ' DATE: 11/05/93 l INSERVICE TESTING PROGRAM - VALVE TABLE l
~/"~'g \, ,) .
~ ,
"C .i ISO REL CS ALT ;
VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST- TEST REQ JUST TEST . NUMBER WUMBER NUMBER CDOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- i
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... t 1-FW-165 11715 CBM-074A 3 OF 4 D6 CHECK VALVE 4.000 3 C CV O l l I
*A" MOTOR DRIVEN AUXILI ARY FEEDWATER PUMP -
DISCHARGE CHECK VALVE 1 FW-166 11715-CBM-074A 3 0F 4 E6 MANUAL GATE 6.000 3 B EV C 40 i 0 40 f AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS . CONNECT VALVE ! 1-FW-167 11715-CBM-074A 3 0F 4 06 CHECK VALVE 1.000 3 C CV 0 ] !
*A" MOTOR DRIVEN AUXILI ARY FEEDWATER PUMP '
RECIRC LINE CHECK VALVE f 1-FW-172 11715-CBM-074A 3 0F 4 E6 MANUAL GATE 6.000 3 8 EV C 40 '! O 40 , AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS CONNECT VALVE 1-FW-180 11715-CBM-074A 3 0F 4 B5 MANUAL GATE 6.000 3 8 EV O 41 ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS f 1-FW-153 11715-CBM-074A 3 OF 4 D5 CHECK VALVE 4.000 3 C CV 0 l -t
*B" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP '
DISCHARGE CHECK VALVE 1 FW 184 11715-CBM-074A 3 0F 4 E5 KANUAL GATE 6.000 3 B EV C 40 i O 40 AFW PUMP DISCHARGE HEADER ALIGNMENT / Cross i, CONNECT VALVE 1 FW 185 11715-CBM-074A 3 0F 4 D5 CHECK VALVE 1.000 3 C CV 0 l
*B" MOTOR DRIVEN AUXILI ARY FEEDWATER PUMP y RECIRC LINE CHECK VALVE !
1-FW-190 11715-CBM 074A 3 0F 4 E5 MANUAL GATE 6.000 3 8 EV C 40 l 0 40
............................................. i f
AFW PUMP DISCHARCE HEADER ALIGNMEhT/ CROSS COWhECT VALVE , 1-FW-227 11715-CBM 074A 3 0F 4 A7 KANUAL GATE 6.000 3 B EV O 41 ,
............................................. r SERVICE WATER SUPPLY TO AFW PUMP SUCTIONS t
1 - FW-279 11715 CBM-074A 3 0F 4 D8 CHECK VALVE 4.000 3 C CV O "
"A" AUX 1LI ARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAlWMENT
............................................................. ..... ..... ... ..... ..... .... .... .... .... g ;
1 FW 526 11715-CBM-074A 3 0F 4 D7 CHECK VALVE 1.000 3 C CV 0 i }
?
PUMP LUBE CIL COOLER CHECK VALVE f f
I 1
^
J 4 l VIRGINIA PohER COMPANT PAGE: 24 0F 78 1 NORTH ANNA UNIT.1. REVISION: 07 . 'i SECOND INSPECTION INTERVAL DATE: 11/D5/93 } INSERVICE TESTING PROGRAM - VALVE TABLE l ([ - ../"%. wC l 2 ISO REL. CS ALT- } VALVE DRAWING SHEET DRWG VALVE VALVE ABME IWV VALVE TEST . TEST REQ JUST TEST i NtatBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-- CSV- VCN-
'l 1 FW-527 : 11715-cam-074A ' 3 0F 4 E6 CHECK VALVE .1.000 3 C- CV o l l
............................................. =
PLMP LUBE DIL COOLER CHECK VALVE '! 1-FW-528 11715-cam-074A 3 0F 4 E4 CHECK VALVE 1.000 3 C CV 0
............................................. l J
PUMP LUBE DIL Co0LER CHECK VALVE f 1-FW-FCV-1478 11715-CBM-074A 1 0F 4 E3 A0 GLOBE 16.000 NC B EV C ' 11 FS ' C 11 ST C 11 : VP OC c "A" MAIN FEEDWATER REG VALVE ! 1-FW-FCV-1479 11715-CBM-074A 1 0F 4 F4 A0 GLOBE 6.000 NC B EV C 11 i FS C 11 ! ST C 11 i "A" BYPASS FEEDWATER REG VALVE l t 1 FW-FCV-1488 11715-CBM-074A 1 0F 4 D4 A0 GLOBE 16.000 NC B EV C 11 j FS C 11 ! ST C 11 l VP OC -l 7 .............................................
"B" MAIN FEEDWATER REG VALVE t 1 FW-FCV-1489 11715-CBM-074A 1 0F 4 D4 A0 GLOBE 6.000 NC B EV C 11 FS C 11 l ST C 11 l "B" BYPASS FEEDWATER REG VALVE
.l j 1
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 1 FW FCV 1498 11715 CBM-074A 1 0F 4 B4 A0 GLOBE 16.000 NC B EV C- 11 FS C 11 {
ST C 11 ! W K !
............................................. i I
"C" MAIN FEEDWATER REG VALVE -
1-FW-FCV 14P9 11715-CBM-074A 1 0F 4 C4 A0 GLOBE i 6.000 NC B EV C 11 .! FS C 11 , ST .C 11 ;
.{
"C" BYPASS TEEDWATER REG VALVE 1.FW-HCV-100A 11715-CBM DN4A 1 OF 4 B5 A0 GLOBE 3.000 3 B EV 0' 31 i FS 0 31 ST 0 31 ;
VP OC ' STANDBT 4UXILI ARY FEEDWATIR SUPPLY TO "A" I STEAM GiNERATOR l 1-FW-NCV-1008 ; 11715 CBM-074A 1 0F 4 B6 A0 GLOBE 3.000 3 8 EV 0 31. I 4 1
~ , , .
VIRGINIA POWER COMPANY PAGE: 25 0F 78 l NORTH ANNA TWIT 1- REVISION: 07 SECOND INSPECTION INTERVAL. { DATE: 11/05/93 ; INSERVICE TESTING PROGRAM - VALVE TABLE- ! 5 ( ISO REL CS
' NC
'{
-ALT j
. VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST . TEST REQ JUST TEST NUMBER NUMBER WUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV- VCN-1-FW-HCV-1008 11715-CBM-074A 1 0F 4 B6 A0 GLOBE 3.000 3 I FS - -0 31 'i ST C 31 I W E l STANDBY AUXILIARY FEEDWATER SUPPLY TO *B" e STEAM GENERATOR
............................................................. ..... ..... ... ..... ..... .... '?
1-FW-NCV-100C 11715 CBM-074A 10F 4 A7 A0 GLOBE 3.000 3 8 EV 0 31 : FS 'O 31 l ST 0 31
-r VP OC i NORMAL AUXILIARY FEEDWATER SUPPLY TD "C" i STEAM GENERATOR I
............................................................. ..... ..... ... ..... ..... i 1 FW-MOV-100A 11715-CBM-074A 1 0F 4 B5 M0 GLOBE 3.000 3 8 EV C i 6
0 ' ST C i
'O }
W E
...... ...................................... [
STANDBY ADA RIARY FEEDWATER SUPPLY TO "A" - i STEAM GENERATok " t
............................................................. ..... ..... ... ..... ..... .... ... .... .... 6 e
1-FW-MOV-1008 11715-CBM-074A 1 0F 4 A6 MO CLOBE 3.000 3 B EV C { 0 > ST C ! 0 j j VP OC !
............................................. i NORMAL AUXILIARY FEEDWATER SUPPLY 70 "B" STEAM GENERATOR 'i 1-FW-MOV-100C 11715-CBM-074A 1 0F 4 BT MO GLOBE 3.000 3 B. EV C 0
ST C
-t 0 i W E ! ~: ;
STANDBY AUXILIARY FEEDWATER SUPPLY 10 "C" ? i STEAM GENERATOR
- r 1-FW-MOV 1000 11715-CBM-074A 3 0F 4 E8 MO GLOBE 3.000 3 8 EV C L 0
ST C ; O f VP OC NORMAL AUXILIARY FEEDWATER SUPPLY TO *A" STEAM GENERATOR ' i-FW-Mov-154A 11715-CBN-074A 1 0F 4 E3 M0 GATE 16.000 NC B EV C 11 ' ST C 11 i VP OC 6 "A" MAIN FEEDWATER SUPPLY ISOLATIDW VALVE 3
............................................................. ...... ..... ... ..... ..... .... ... .... .... j 1-FW-MOV 1548 11715-CBM-074A 10F 4 D3 M0 CATE 16.000 NC B EV C 11 '
ST C 11 W E l Y f. I T t a 4 f
~r
y VIRGINIA poler COMPANY - 'PAGE: 26 0F 78 - NORTN ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93-A INSERVICE TESTING PROGRAM - VALVE TABLE f NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER IAMBER C00R TYPE SIZE CLASS M T TTPE TYPE POS V-CSV- VCN-
"B" MAIN FEEDWATER SUPPLY ISOLATION VALVE 1-FW-MOV-154C 11715 CBM-074A 1 0F 4 B3 M0 GATE 16.000 NC B EV C 11 ST C 11 VP OC "C" MAIN FEEDWATER SUPPLY ISOLATION VALVE 1 FW-PCV-159A 11715.CBM-074A 3 0F 4 F8 -A0 CLOBE 4.000 3 8 EV 0 32 FS 0 32 ST 0 32 VP OC AUXILIARY FEEDWATER PRESSURE CONTROL VALVE 1-FW-PCV-159B 11715-CBM-074A 3 0F 4 E8 A0 GLOBE 4.000 3 B EV '0 32 FS 0 32 ST 0 32 VP OC-AUXILIARY FEEDWATER PRESSURE CONTROL VALVE 1-FW RV 100 11715-CBM 074A- 3 0F 4 D8 RELIEF VALVE 3.000 3 C SP 0 TURBINE DRIVEN AUXILIARY FEED PUMP FEEDWATER DISCHARGE RELIEF VALVE
-. .. . _ , - ~_ .- ..- __ . ..
').
L VIRGINIA P0bER COMPANY PAGE: 27 0Fz78 l NORTH ANNA UNIT 1 REVISION: 07 SECONO INSPECTION INTERVAL ;
'DATE: 11/D5/93<
s~~ ' INSERVICE TEST!NG PROGRAM - VALVE TABLE I NC : ISO REL CS ALT j
- VALVE DLAWING- SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST. i NLMBER . m MBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1-GN-225 11715 FM -105A 10F 3 E4 CHECK VALVE .750 NC AC CV C 1. 4 LT C .;
i BOTTLED WITROGEN SUPPLY TO PORY ISOLATION CHECK VALVE- l
............................................................. ..... ..... ... ..... ..... .... ... .... ..... i 1-GN-451 11715-FM -105A 1 0F 3 E6 CHECK VALVE .750 NC AC CV C 1 LT C BOTTLED NITROGEN SUPPLY TO PORY ISOLA 110N CHECK YALVE e
............................................................. ..... ..... ... ..... ..... ..... ... .... .... j 1-GN-RV- 1 Dat -1 11715-FM -105A 1 0F 3 E7 RELIEF VALVE .750 NC C SP O t I
BOTTLED WITROGEN SUPPLY TO PORV RELIEF VALVE ' 4 I 1-GN-RV-10BA-2 11715-FM 105A 10F 3 F6 RELIEF VALVE- .750 NC C SP O ; BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE !
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 1-GN-RV 1D8A-3 11715-FM -105A 10F 3 E6 RELIEF VALVE .750 NC - C SP 0 ,
BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE l i
............................................................. ..... ..... ... ..... ..... .... ... .... ..... i GN-RV-1 D88-1 11715-FM -105A 1 0F 3 E3 RELIEF VALVE .750 NC C SP 0- i . f""' ............................................. ,
BOTTLED WITROGEN SUPPLY TO PORV RELIEF VALVE 1-GN RV-1D88 2 11715-FM -105A 1 0F 3 F5 RELIEF VALVE .750 NC C SP O
............................................. l BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE t
i 1-GN-RV-1088-3 11715-FM -105A 1 0F 3 E5 RELIEF VALVE .750 NC C SP O I
............................................. t 3
BOTTLED NITROGEN SUPPLY TO PORV REL1EF VALVE *
............................................................. ..... ..... ... ..... ..... .... ... .... .... .l l
i i 4 l l
i VIRGINIA POWER COMPANY PAGE: 28 0F 78 NORTH ANNA UWIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM . VALVE TABLE I r 1 . NC 150 REL CS ALT < VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER l NUMBER NUMBER COOR TTPE $12E CLASS CAT TYPE TYPE POS V- CSV- VCN- i 1 HC-005 11715-CBM-106A 4 0F 4 C7 CHECK VALVE 2.000 NC C CV 0 50 , CONTf!NNENT ATMOSPHERE PURGE BLOWER DISCHARGE CHECK VALVE 1-NC-014 11715-CBM-106A 10F 4 E8 CHECK VALVE 2.000 2 AC CIV CV C 20 0 20 LT C UNIT 1 RETURN LINE FROM UNIT 1 NYDROGEM ANA. LYZERS & RECOMB, INSIDE CONT ISOL CHECK VALVE 1 HC-018 11715-CBM-106A 2 0F 4 E6 CHECK VALVE 2.000 2 AC CIV CV C 20 0 20 LT C UNIT 1 RETURN LINE FROM UNIT 2 HYDROGEN ANA-LYZERS & RECOMB, IWsIDE CONT ISOL CHECK VALVE 1-HC-062 11715 CBM-106A 1 0F 4 C7 CHECK VALVE .375 NC C CV 0 HYDROGEN ANALYZER DISCHARGE CHECK VALVE 1-NC-063 11715-CBM-106A 1 0F 4 C7 CHECK VALVE .375 kc c CV O HYDROGEN ANALYZER DISCHARGE CHECK VALVE ' 1 HC-TV-100A 11715-CBM 106A 1 0F 4 E8 SO GLOBE .375 2 A CIV EV C 0 ES C LT C ST C 54
.0 54 ,
VP OC I UNIT 1 SAMPLE LINE TO UNIT 1 HYDROGEN ANA-LYZERS, INSIDE CONTAINMENT ISOLATION VALVE 1-HC-TV-1008 11715-CBM-106A 1 0F 4 E7 SO GLOSE .375 2 A CIV EV C 0 FS C LT C ST C 54 0 54 VP OC UNIT 1 SAMPLE LINE TO UNIT 1 HYDROGEN ANA-LYZERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-NC-TV-101A 11715-CBM-106A 1 0F 4 D7 SO GLOBE .375 2 A CIV EV C 0 FS C LT C ST C 54 0 54 VP OC ' RETURN ISOLATION FRCM UNIT 1 HYDROGEN ANA-LYZERS To UNIT 1 CONT,00TSIDE CONT ISOL VALVE / 1-HC-TV-1018 11715-CBM-106A 10F 4 D7 50 GLOBE .375 2 A CIV EV C 3 s O
w- - t VIRGIN!A P0hER CCMPANY PAGE: 29 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL- DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE I NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ.JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE ' POS V- CSV- VCN-1-HC TV-101B 11715-CeM 106A 1 0F 4 07 SO GLOSE .375 2 A- CIV FE C LT C ST C 54 0 54 VP OC ( .. RETURN ISOLATION FROM UNIT 1 HYDROGEN ANA-LYZERS TO UNIT 1 CONT,0UTS!DE CONT ISOL VALVE 1 HC-TV-102A 11715-CBM-1D6A 2 0F 4 E6 50 GLOBE .375 2 A CIV EV C 0 FS C LT C ST C 54 o 54 VP OC UNIT 1 SAMPLE LINE TO UNIT 2 HYDROGEN ANA+ , LYZERS, INSIDE CONTAINMENT ISOLATION VALVE 1-HC-TV-1028 11715-CBM-106A 2 0F 4 ET SO GLOBE .375 2 A CIV EV C 0 FS C LT C ST C 54 0 54 VP OC UNIT 1 SAMPLE LINE TO UNIT 2 HYDROGEN AEA- ,
/ LYZERS, OUTSIDE CONTAINMENT ISOLATION VALVE
- 1-HC-TV 103A 11715-CBM 106A 2 0F 4 D7 SC CLOBE .375 2 A CIV EV C '
0 FS C .[ LT C j' ST C 54 O 54 VP OC RETURN ISOLATION FROM UNIT 2 HYDROGEN AkA-LYZERS TO UNIT 1 CONT,0UTSIDE CONT ISOL VALVE j
............................................................. ..... ..... ... ..... ..... .... ... .... .... 3 1-HC TV-1C3B 11715-CBM-106A 2 0F 4 DT $0 CLOSE .375 2 A Civ ~ EV C 0 ;
FS C I LT C ST C 54 r 0 54 l VP OC ! RETURN ISOLATION FROM UNIT 2 HYDROGEN ANA-LYZERS TO UNIT 1 CONT,0UTSIDE CONT ISOL VALVE .l l
............................................................. ..... ..... ... ..... ..... .... ... ..... .... j 1 HC-TV 1D4A 11715-CBM 1D6A 4 0F 4 F6 A0 GLOBE 2.500 2 A- CIV EV C j
0 FS C LT C ST C 54 ! O 54 i VP OC i
............................................. I SUPPLY ISOL FROM UNif 1 CONT TO N1 HYDRO RE-COM8 & N2 CONT BLOWER,0UTSIDE CONT ISOL VALVE
0
)
VIRGIN!A POE R COMPANY PAGE: 30 0F 78 - , NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 l INSERVICE TESTlWG PROGRAM - VALVE TABLE ! i NC i ISO REL CS ALT ,
' VALVE DRAWING- SHEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REQ JUST TEST i NLMBER NUMBER NLMBER COOR TYPE V-SIZE CLASS CAT TYPE TYPE POS CSV- VCN-1-NC-TV-104B 11715-CBM-106A 4 0F 4 F6 A0 GLOBE 2.500 2 A ' CIV EV C l 0 ,
FS C - LT C ' ST C 54 O 54 VP OC >
$UPPLY ISOL FROM UNIT 1 CONT TO W1 NYDRO RE- 3 COMB & M2 CONT BLOWER,0UTSIDE CONT ISOL VALVF ............................................................. ..... ..... ... ..... ..... .... ... .... .... I 1 HC-TV 105A 11715-CBM-106A 1 0F 4 E6 A0 GLOBE 2.500 2 A CIV EV C 0
- FS C I LT C e ST C 54 j 0 54 t W K -4 1
RETURN ISOLATION FROM UNIT 1 NYDROGEN RECOMB t
& ANAL TO UNIT 1 CONT, OUTSIDE CONT ISOL VALVE !
1-HC-TV-105B 11715-CsM-106A 1 OF 4 E6 A0 GLOBE 2.500 2 A CIV EV C i 0 i FS C LT C ST C 54 ? O 54 W E RETURN ISOLATION FROM UNIT 1 NYDROGEN RECOMB
& ANAL TO UNIT 1 CONT, OUTSIDE CONT ISOL VALVE ............................................................. ..... ..... ... ..... ..... .... ... .... .... j 1-NC TV-106A 11715-CBM-106A 4 0F 4 F8 A0 GLOBE 2.500 2 A- CIV EV C i 0
FS C LT C '! ST C 54 t 0 54 - 'l UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE
- C j
BLOW & N2 NYDRO RECOMB, OUTSIDE CONT ISOL VLV 1-HC-TV-106B 11715 CBM-106A 4 0F 4 F8 A0 GLOBE 2.500 2 A CIV EV C I 0 t FS C l LT. C ST C 54 0 54 VP OC ! l UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE < BLOW & N2 NYDRO RECOMB, OUTSIDE CONT ISOL VLv I 1 HC-TV-107A 11715-CBM 106A 2 0F 4 E7 A0 GLOBE 2.500 2 A CIV EV C j 0 i FS C , LT C ST C 54 'I O 54 ! VP OC .I l
. 1
- I a
i VIRGINIA PohER COMPANY PAGE: 31 0F 78 NORTH ANNA WIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE WC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ -JUST TEST WLMBER - NLMBER NUMBER C00R TTPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-RETURN ISOLATION FROM UNIT 2 NYDROGEN RECOMB
& ANAL TO UNITI CONT, OUTSIDE CONT ISOL VALVE 1-NC TV-107B 11715 CBM 106A 2 0F 4 E8 AD GLOSE 2.500 2 A CIV EV C 0
FS C LT C ST C 54' O 54 VP OC RETURN ISOLATION FROM UNIT 2 HYDROGEN RECOMB
& ANAL TO UNIT 1 CONT, OUTSIDE CONT ISOL VALVE 1-NC-TV-108A 11715-CBM-106A 3 0F 4 E8 $0 GLOBE .375 2 A CIV EV C FS C LT C ST C 54 VP OC UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, INSIDE CONTAINMENT ISOLATION VALVE 1-HC-TV-1088 11715+CSM-106A 3 0F 4 ET So GLOSE .375 2 A CIV EV C FS C l LT C ST C 54 VP OC UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, OUTSIDE CONTAINMENT ISOLATION VALVE J
G
~
i k i r
)
i i I 1 b ( 4 4
+
6 i l
'l <
VIRGIN!A POWER COMPANY PAGE: 32 OF 78 NORTH ANNA UNIT 1 REvls10N: 07 , SECOND INSPECTION INTERVAL DATE: 11/05/93 l INSERVICE TESTING PROGRAM - VALVE TABLE ( i i NC ! b ISO REL CS ALT ' VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NWBER NLMBER NUMBER COOR TYPE $!ZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1 HV-MOV-100A 11715-CBB-006A 1 OF 3 D7 M3 BFLY 36.000 2 AE CIV LT C l VP OC CONTAlWMENT PURGE SUPPLY, INSIDE CONTAINMENT l ISOLATION VALVE 1-HV-MOV-1008 11715-CBB-006A 1 0F 3 07 M3 BFLY 36.000 2 AE CIV LT C 59 VP OC
........u...................................
CONTAINMENT PURGE SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1-HV-MOV 100C 11715-CBB 006A 1 0F 3 C7 M0 BFLY 36.000 2 AE CIV LT C VP OC CONTAINMENT PURGE EXHAUST, INSIDE CONTAINMENT , ISOLATION VALVE 1 HV-Mov-1000 11715-CEB 006A 10F 3 C7 M0 BFLY 36.000 2 AE CIV LT C 59 i VP OC i CONTAINMENT PURGE EXHAUST, CUTSIDE CONTAIN-MENT ISOLATION VALVE 1-HV-MOV-101 11715-CBB-006A 1 0F 3 C7 M0 BFLY 8.000 2 AE CIV LT C 59 i VP OC CONTAINMENT PURGE BfPASS, OUTSIDE CONTAINMENT ISOLAT10N VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 1-HV-Mov-102 11715 CBB-006A 1 0F 3 D7 M0 BFLY 18.000 2 AE CIV LT C 59 VP OC .
............................................. i CONTAINMENT PURGE ALTERNATE SUPPLY, OUTSIDE
'i '
CONTAINKENT ISOLATION VALVE t 1-HV-M?V 111A 11715 CBB-40C 1 0F 3 E8 M3 GATE 4.000 3 B EV 0 ST 0 I VP OC CONTROL ROCM CHILLER ISOLATION VALVE 1-HV-MOV 111B 11715-CBB-40C 1 0F 3 C8 No GATE 4.000 3 8 [V 0 ST 0 l CONTROL RC04 CHILLER ISOLATION VALVE 1-HV-MOV-111C 11715-CBB-40C 1 0F 3 D8 M0 GATE 4.000 3 8 EV 0 < ST 0 CONTROL ROOM CHILLER ISOLATION VALVE 1
............................... ............................ ..... ..... ... ..... ..... .... ... .... .... 3 1 HV MOV 1134 11715-CBB-0400 1 0F 3 E3 No GATE 4.000 3 8 EV 0 l ST 0 VP OC ,
............................................. I CONTROL ROOM CONDENSER WATER SYSTEM ISOLAT!DN VALVE 1 HV-MOV-113B 11715 CsB-0400 1 0F 3 E3 M3 GATE 4.000 3 0 B EV l ST 0 l
l
t' L VIRGINIA PohER COMPANY PAGE: 33 0F 78 NORTH Amh4 UNIT 1 REVIS10N: 07: l SECOND INSPECTION INTERVAL DATE: 11/05/93 ;
, INSERVICE TESTING PROGRAM - VALVE TABLE -i NC ISO REL CS ALT VALVE DRAWING SHEET 3RWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST l WlMBER - NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- !
CONTROL R00M CONDENSER WATER SYSTEM 6 ISOLATION VALVE ,
............................................................. ..... ..... ... ..... ..... .... ... .... .... z 1-HV-MOV-113C 11715-CBS-0400 1 0F 3 C3 MO GATE 4.000 3 B EV 0 l ST C' .
V r CONTROL ROOM CONDENSER WATER SYSTEM i ISOLATION VALVE t 1 HV-PCV 1235A1 11715 CBB-0400 1 0F 3 06 A0 GLOBE 3.000 3 B EV C I' ' FS C ST C -p CONTROL ROOM CONDENSER WATER BYPASS LINE PRESSURE CONTROL VALVE i
............................................................. ..... ..... ... ..... ..... .... ... .... .... )
1-HV PCV 1235A2 11715 CBB 040D 1 0F 3 E3 A0 GLOBE 3.000 3 B EV 0 l . FS 0 l ST 0 -I 3' CONTROL ROOM CONDENSER WATER < . PRES $URE CONTROL VALVE j 1-HV-PCV 1235B1 11715-CBB D40D 1 0F 3 A6 A0 GLOBE 3.000 3 B EV C l . FS C ! ST C ! CONTROL ROOM CONDENSER WATER BYPASS LINE ; PRESSURE CONTROL VALVE 1-HV-PCV 1235R211715-CBB-04DD 1 0F 3 C3 A0 GLOBE 3.000 3 B EV 0 l '! FS 0 3 ST 0 [
............................................. j CONTROL ROOM CONDENSER WATER i PRESSURE CONTROL VALVE '
l 1 HV PCV-1235C1 11715 CBB D400 1 0F 3 C6 A0 GLOBE 3.000 3 B EV C l ! FS - C l ST C CONTROL ROOM CONDEkhii WATER BYPASS LINE PRESSURE CONTROL VALVE 1 HV PCV-1235C2 11715-CBB 0400 1 0F 3 B3 A0 GLOBE 3.000 3 8 EV 0 ' FS - 0 ! t ST 0 ' CONTROL ROOM CONDENSER WATER
- PRESSURE CONTROL VALVE l
................................................ ............ ..... ..... ... ..... ..... .... ... .... .... ,1 1 HV-RV 1200 11715-CBB 40C 1 or 3 04 RELIEF VALVE 3 C SP O ';
J
............................................. I CONTROL ROOM CHILLER SYSTEM RELIEF VALVE 1 HV RV 1201 11715 CBB 40C 1 0F 3 C5 RELIEF VALVE' 3 C SP O -i
............................................. i CONTROL ROOM CHILLER SYSTEM RELIEF VALVE -l
/' 1 HV RV-1202A
.t 11715-CBs 4DC 1 0F 3 E8 RELIEF VALVE .750 3 C SP O l'
I
'j
-l 1
5 i
. VikGINIA P0hER COWANY PAGE:' . 34 0F 78 NCRTN ANNA UNIT 1 REVISION: 07 SECOND INSPECTIDW INTERVAL DATE: 11/05/93 :
INSERVICE TESTING PROGRAM - VALVE TABLE ! t s t WC ! 150 REL CS ' ALT ! VALVE DRAWING SWEET DRWG VALVE VALVE A94E IWV VALVE TEST TEST REQ 'JUST TEST NUMBER NUMBER NLMBER C00R TYPE - SIZE-CLASS CAT TYPE TYPE POS V. CSV. VCN- *
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... l l'
CONTROL ROOM CHILLER STSTEM RELIEF VALVE 1*NV-RV-12028 11715-CBB-40C 1 0F 3 C8 RELIEF VALVE .750 3 C SP O =
............................................. 1 CONTROL ROOM CHILLER SYSTEM RELIEF VALVE I t'
l 1-HV-RV-1202C 11715-Cat-40C 10F 3 D8 RELIEF VALVE .750 3 C SP 0 I i i CONTdOL ROOM CHILLER SYSTEM RELIEF VALVE
-l 1-HV-RV-12D5A 11715-CBS-f400 1 0F 3 E3 RELIEF VALVE 3 C SP 0 ~ '
t
............................................. t CONTROL ADOM CONDENGER WATER SYSTEM
~
RELIEF /ALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... l>
1-HV-RV-12058 11715 CS.1-0400 1 0F 3 B3 RELIEF VALVE 3 C SP O (
.J 00NTROL R031 CONDENSER WATER SYSTEM i RELIEF VALV2 i 1-HV-RV-1205C 11715-CBB-040D 1 0F 3 D3 RELIEF VALVE 3 C SP O l- ^I t
a CONTROL ROOM CONDENSER WATER SYSTEM RELIEF VALVE l 1-HV-RV-1302A 11715-FM 082M 1 0F 1 F7 RELIEF VALVE .750 NC C SP 0 F SAFEGUARD AREA FANS AIR RECEIVER ! RELIEF VALVE ' 1-HV RV 13028 11715-FM -082M 1 0F 1 F6 RELIEF VALVE .750 NC C SP .0 ; SAFEGUARD AREA FANS AIR RECEIVER ! RELIEF VALVE ! 1-HV-SOV-1200A 11715-C88 0400 10F 3 F7 So GATE .500 3 b EV 0 . ST 0 1 6
............................................. +
t CONTROL ROOM CONDENSER PUMP SEAL C00 LING ' WATER LINE ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... .f 1-HV-$0V-12008 11715 CBB 0400 10F 3 87 50 GATE .500 3 8 EV O l ST 0- =
l
............................................. .4 CONTROL ROOM CONDENSER PUMP SEAL COOLING i WsiCR LINE ISOLATION VALVE I 1-HV-SOV 12fs 11715-CBB-0400 10F 3 D7 SO GATE .500 3 8 EV 0 4 0
ST ! CONTROL ROOM CONDENSER PUMP SEAL COOLING WATER LINE ISOLATION VALVE {
............................................................. ..... ..... ... ..... ..... . . . . . ... .... .... i i
.5 4
.i
.} 4 a
I W
' ,b i
m __
l 1 VIRGINIA POWER COMPANY PAGE: 35 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 , m INSERVICE TESTING PROGRAM - VALVE TABLE i (
- l NC '
150 REL CW ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUS 1 TEST i NUMBER WUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- ' CSV- VCN-1-IA-055 11715-CBM-082A 10F 3 f5 CHECK VALVE 2.000 2 AC CIV CV C 21 LT C INSTRUMENT AIR SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1-IA 149 11715-CBM-082N 3 0F 3 C4 CHECK VALVE 1.000 2 AC CIV CV C 21 LT C 6 RETURN TO CONTAINMENT FROM RADIATION MONITOR-ING CABINET, INSIDE CONT ISOL CHECK VALVE 1-IA-2152 11715 FM-082A 2 0F 3 F7 CHECK VALVE .750 NC AC CV C 1 LT C 1
............................................. P
-4 BOTTLED NITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 1-IA-2153 11715-FM-082A 2 or 3 F8 CHECK VALVE .750 NC AC CV C 1 LT C 1 BOTTLED WITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 1-IA-2154 11715 FM-082A 2 0F 3 F7 CHECK VALVE .750 NC AC CV C 1 LT C 1 ,
BOTTLED NITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE [s ............................................................. ..... ..... ... ..... ..... .... ... .... .... 1 IA 2155 11715 FM-082A 2 of 3 F8 CHECK VALVE .750 NC AC CV C 1 LT C 1
............................................. 6 BOTTLED WITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE -
1 IA 925 11715-FM -082M 10F 1 E7 CHECK VALVE .250 NC- AC CV C f LT C Z ; SAFEGUARD AREA FANS AIR RECEIVER ISOLATION CHECK VALVE
' * * ~ ' * * ***
Uji 9)f """jifi$"if.0gjA'"j 6fi [}"*6A[66 Qi[y[ "'* jj6 56"' 16' ""~ hy 6" " " * " " ~ "* LT C 2 SAFEGUARD AREA FANS Alt RECEIVER r ISOLA 110N CHECK VALVE f 1 IA-934 11715 FM -082M 1 0F 1 E6 CHECK VALVE .250 NC AC CV C I LT C 2
- SAFEGUARD AREA FANS AIR RECEIVER i
ISOLATION CHECK VALVE 1 IA-935 11715-FM -082M 1 OF 1 E6 CHECK VALVE .250 NC AC CV C r LT C 2 r
............................................. e SAFECUARD AREA FANS AIR RECEIVER ISOLATION CHECK VALVE j
1-IA 944 11715-FM -082M 1 0F 1 F5 CHECK VALVE .750 NC AC CV C 30 I LT C 3 , r L t I t
i;
. VIRGINIA POWER COMPANY i DAGE: - 36 0F 78 :
NORTH ANNA UNIT 1- REVISION: 07 - SECOND INSPECTION INTERVAL DATE: 11/05/93. : INSERVICE TESTING PROGRAM - VALVE TASLE ' NC
\ ISO REL CS ALT- !
VALVE. DRAWING SHEET DRWG VALVE ' VALVE ASME IW VALVE TEST TEST REQ JUST TEST ; Nims [R NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN* i
.j MAIN STEAM PCV VALVE AIR ACCUMULATOR t s
ISOLATION CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... l 1-IA 948 11715+FM -082M 1 0F 1 F4 CHECK VALVE .750 NC AC CV C 30 >
LT C 3 MAIN STEAM PCV VALVE AIR ACCLMULATOR ISOLAfl0N CHECK VALVE ' 1 IA-952 11715 FM -082M 1 0F 1 F3 CHECK VALVE .750 NC AC cv C 30 l LT C '3J ; MAIN STEAM PCV VALVE AIR ACCLMULATOR ', ISOLATION CHECK VALVE
!A 959 11715-FM -082M 1 OF 1 C4 CHECK VALVE .750 NC AC CV C 30 ,
LT C 3 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR
!$0LATION CHECit VALVE 1 IA 963 11715-FM -082M 1 0F 1 C5 CHECK VALVE .750 NC AC CV C 30 LT C 3
............................................. 6 AUXILIARY FEEDWATER VALVE AIR ACCUElLATOR
!$0LATIDW CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... -l 1-IA 967 11715-FM -082M 1 0F 1 C6 CHECK VALVE .750 NC AC CV C 30 .
t' LT C 3 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE . 1 IA 971 11715 FM 082M 1 0F 1 C6 CHECK VALVE .750 NC AC CV C 30 ;j LT C 3 AUXILIARY TEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE 1 IA 975 11715-FM 082M 1 0F 1 C7 CHECK VALVE .750 NC AC CV C 30 LT C 3 AUXIL1ARY FEEDWATER VALVE AIR ACCUMULATOR
!$0LATION CHECK VALVE 1-!A-SV-105A 11715-FM -082M 1 0F 1 E5 REllEF YALVE NC C SP O MAIN STEAM PCV VALVE AIR ACCUMULATOR '
RELIEF VALVE 1-]A SV-105B 11715 FM -082M 1 OF 1 E4 RELIEF VALVE NC C SP O MAIN STEAM PCV VALVE AIR ACCURJLATOR RELIEF VALVE 1 IA SV-105C 11715-f M -082M 1 0F 1 E3 RELIEF VALVE NC C SP - 0 MAIN STEAM PCV VALVE AIR ACCLMULATOR RELIEF VALVE l 1-IA SV-105D 11715-FM -082M 10F 1 A4 RELIEF VALVE NC C SP O 1 l l
. 1
-
- 1
I VIRGINIA poler COMPANY PAGE: 37 0F 75 NORTH ANNA UNIT 1- REVISION: 07 SECOND INSPECTION INTERVAL
')
DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST - TEST REG JUST TEST , MLMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV- VCN-AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE i 1 IA-SV 105E 11715 FM -082M 1 0F 1 A4 RELIEF VALVE NC C SP O + AUXILIARY FEEDWATER VALVE AIR ACCUR1LATOR 6 RELIEF VALVE I
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 1-IA-SV-105F 11715-FM -082M 1 0F 1 A6 RELIEF VALVE NC C SP O f AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ;
RELIEF VALVE 1 IA-SV-105G 11715-FM -082M 10F 1 A7 RELIEF VALVE NC C SP 0 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE p 1 IA-SV-105H 11715-FM 082M 1 0F 1 AS RELIEF VALVE NC C SP 0 ' AUXILIARY WEEDWATER VALVE A!R ACCUMULATOR - RELIEF VALVE ' 1-IA-TV-102A 11715 CBM-082W 1 0F 3 D3 Ao CLDBE 2.000 2' B EV C. , FS C f ST C i VP OC t INSTRUMENT AIR SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 1 IA TV-102B 11715-CBN 082N 1 0F 3 D3 AO GLOBE 2.000 2 A CIV EV C i FS C ; LT .C ST C : VP OC ! INSTRUMENT AIR SUPPLY TO CONTAINMENT, OUTSIDE ; CONTAINMENT ISOLATION VALVE e t s b ( l i i y ._. 1
d
. i, VIRGINIA POWER COMPANY 38 or 78
~
PAGE: - NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE ,
.g NC l
ISO- REL CS ALT i' VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMSER NLMBE R NLMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV VCN-1-LM TV-100A 11715 CBM 092A- 1 0F 2 E7 A0 GLOSE .375 2 AE CIV LT C i VP OC
............................................. =
CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE ' 1-LM-TV-1008 11715-CoM-0924 1 0F 2 E6 A0 GLOBE .375 2 AE CIV LT C l W E l CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM
$UPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE ;
i 1 LM TV-100C 11715-CsM-092A 1 0F 2 E6 A0 GLOBE .375 2 AE CIV LT C W E I
............................................. i t
CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE
]
1-LM TV-1000 11715-CBM-092A 1 0F 2 E5 A0 GLOBE .375 2 AE CIV LT C ! VP OC CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM i SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1-LM-TV-100E 11715-CBM-092A 1 0F 2 f6 A0 GLOBE .375 2 AE Civ LT C l VP OC CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1 LM TV-100F 11715-CSM-092A 1 OF 2 F5 A0 GLOBE .375 2 AE CIV LT C . VP OC CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT !$0LATION VALVE - e 1 LM-TV 100G 11715-CBM-092A 10F 2 E7 A0 GLOBE .375 2 AE CIV LT C W E ;
............................................. +
CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM j SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE - , 1-LM-TV-100N 11715-CBM-092A 10F 2 E6 A0 GLOBE .375 2 AE Civ LT C W OC .
............................................. Li CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM i s
SUPPLY, DJTSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... ... I 1 LM-TV-101A i 11715-CeM 092A- 1 0F 2 05 A0 GLOBE .375 2 AE CIV LT C.
- VP OC ll i CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM -
SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE !
............................................................. ..... ..... ... ..... ..... .... ........ .... i 1-LM-TV-1018- 11715-cam-092A 1 0F 2 DS- A0 GLOBE .375 2 AE CIV.. LT- C l VP OC 's
............................................. e CONTAlWNENT LEAKAGE MONITORING SEALED STSTEM ,
SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1-LM-TV-10fC 11715-CBM-092A 1 0F 2 D5 A0 CLOBE .375 2 AE CIV - LT- C W OC q i l
}
,~
l
VIRGINIA POE R COIFANY PAGEs: 39 CF 78 WORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE p: NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER WUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE PDS V- CSV - VCN-f CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM i SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE ' 1 LM-TV-101D 11715-CBM-092A 1 OF 2 D4 A0 GLOSE .375 2 AE CIV LT C VP OC CONTAINMENT LEAKAGE MONITORING SEALED STSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE , a I I r F t 5 i i e t i t
?
M i
VIRGINIA POWER COMPANY- PAGEs- 40 0F 78 ' NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTIDN INTERVAL DATE: 11/05/93 , w INSERVICE TESTING PROGRAN - VALVE TABLE , NC ISO REL CE ALT
. VALVE DRAWING SHEET - DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST '
NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1-MS 018 11715-CBM-0708 1 0F 3 C6 MANUAL GATE 3.000 2 B EV C MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 1 MS-019 11715-CBM 0708 1 0F 3 C5 MAN CHECK VLV 3.000 2 C CV C .
............................................. i "A" MAIN STEAM HEADER SUPPLY CHECK VALVE TO DECAY HEAT RELEASE '
1-MS-057 11715-CBM-07DB 2 0F 3 C6 MANUAL GATE 3.000 2 B EV C MAIN STEAM TO AUXILIARY FEEDWATER TURBINE L1NE ISOLATION VALVE 1-MS-058 11715-CBM-0708 2 0F 3 D5 MAN CHECK VLV 3.000 2 C CV C i, "B" MAIN STEAM HEADER SUPPLY CHECK VALVE TO DECAY HEAT RELEASE l-1-MS-D95 11715-CBM 0708 3 0F 3 C6 MANUAL GATE 3.000 2 B EV C 7 MAIN STEAM TO AUXILIARY FEEDWATER TURBINE ' LINE ISOLATION VALVE 1 MS-D96 11715-CBM-0708 3 0F 3 D5 MAN CHECK VLV 3.000 2 C CV C "C" MAIN STEAM HEADER SUPPLY CHECK VALVE TO DECAY HEAT RELEASE I ............................................................. ..... ..... ... ..... ..... .... ... .... .... 1-MS-119 11715-CBM 07DA 3 0F 3 E7 CHECK VALVE 3.000 2 C CV C ! " 0 .
"A" MAIN STEAM HEADER SUPPLT CHECK VALVE TO ?
TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1-MS-122 11715-CBM 070A 3 0F 3 F7 CHECK VALVE 3.000 2 C CV C 0
"B" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP '
1-MS-124 11715-CBM 070A 3 0F 3 F7 CHECK VALVE 3.000 2 C CV C 0 '
~
"C" MAIN STEAM HEADER SUPPLY CHECK VALVE To i TURBINE DRIVEN AUXILIARY FEEDWATER PUMP
-1 MS NRV-101A 11715-CSM 0708 1 0F.3 D3 CHECK VALVE 32.000 2 C CV C 13 L
VP OC (
............................................. 3 "A" MAIN STEAM HEADER NON-RETURN VALVE '
............................................................. ..... ..... ... ..... ..... .... ... ..... .... i 1-ks NRV 101B 11715 CBM 0708 2 0F 3 D3 CHECK VALVE 32.000 2 C CV C 13 :(
VP OC >
*B" MAIN STEAM HEADER NON RETURN VALVE >
?
P 1 MS-NRV-101C 11715-CBM 0709 3 0F 3 D3 CHECK VALVE 32.000 2 C CV C 13 I r VP OC j ( l 1 i l 1 l i
VIRGINIA POWER COMPANT PAGE: 41 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE D t WC r ISO REL CS ALT VALVE DRAWING' SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER WUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- .CSV-~ VCN-
"C" MAIN STEAM HEADER WON-RETURN VALVE 1-MS PCV-101A 11715 CBM-070B 1 0F 3 E5 AD ANGLE 6.000 2 B EV. C 0
FS C ST C 0 VP OC "A" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE 1-MS-PCV-1018 11715 CBM-0708 2 0F 3 E6 A0 ANGLE 6.000 2 8 EV C 0 FS C ST C 0 VP OC "B" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE 1-MS-PCV-101C 11715-CBM-070B 3 0F 3 D3 AD ANGLE 6.000 2 B EV C 0 FS C ST C 0 VP OC "C" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE 1-MS-SV-101A 11715-CBM-0708 1 0F 3 E6 SAFETY VALVE 6.000 2 C SP 0 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS SV-101B 11715-CBM-0708 2 0F 3 E6 SAFETY VALVE 6.000 2 C SP 0 "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS SV 101C 11715-CBM-0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP O "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS-SV 102A 11715-CSM-0708 1 0F 3 E5 SAFETY VALVE 6.000 2 C SP O "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS-SV-1028 11715-CBM-0708 2 0F 3 E5 SAFETY VALVE 6.000 2 C SP O "B" MAIN STEAM HEADER SAFETY YALVE, SV DISCHARGE TO ATMOS 1-MS SV-102C 11715-CBM-0708 3 or 3 D6 SAFETY VALVE 6.000 2 C SP O "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS.
VIRGICIA P0hER CWANY PAGE: 42 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 : INSERVICE TEST!NG PROGRAM - VALVE TABLE l NC ISO REL CS ALT
. VALYE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- ,
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... g 1-MS-SV-103A 11715 CBM-0708 1 0F 3 E6 SAFETY VALVE 6.000 2 C SP O "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS l 1-MS-SV-1038 11715-CBM-0708 2 0F 3 E5 SAFETY VALVE 6.000 2 C SP 0 "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS
............................................................. ..... ..... ... ..... ..... .... ... .... .... MS-SV-103C 11715-CBM-0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C $P 0 ,
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS l
............................................................. ..... ..... ... ..... ..... i 1-MS-SV 104A 11715-CBM-0708 1 0F 3 E6 SAFETY VALVE 6.000 2 C SP O
............................................. I "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS-SV-1048 11715-CBM-0708 2 0F 3 E6 SAFETY VALVE 6.000 2 C SP O .
............................................. i "B" M/IN STEAM HEADER SAFETY VALVE, SV DISCH/RGE TO ATMOS
- 1-MS-SV-104C 11715-CJM-0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP 0 "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS-SV 105A 11715-CBM-0708 10F 3 E5 SAFETY VALVE 6.000 2 C SP 0
............................................. ,i "A" MAIN STEAM HEADER SAFETY VALVE, SV -
DISCHARGE TO ATMOS 1-MS-SV-1058 11715 CBM-0708 2 0F 3 E5 SAFETY VALVE 6.000 2 C SP 0 "B" MAIN STEAM HEADER SAFETY VALVE, SV ' DISCHARGE TO ATMOS '
............................................................. ..... ..... ... ..... ..... .... ... .... .... .1 1 MS-SV 105C 11715-CBM-0708 3 0F 3 D5 SAFETY VALVE 6.000 2 C SP 0 r
~
"C" MAIN STEAM HEADER SAFETY VALVE, SV l DISCHARGE TO ATMOS '
1-MS TV-101A 11715-CBM-0708 1 0F 3 D4' A0 DISC 32.000 2 8 EV C 16 I FS C 16 ST C 16 W E i "A" MAIN STEAM HEADER TRIP VALVE
............................................................. ..... ..... ... ...........- .... ... .... .... I 1-MS-Tv+ 1018 11715-CBM-0708 2 0F 3 C4 A0 DISC 32.000 2 8 EV C 16 ,
FS C 16 . ST C' 16 i VP OC - - 6 "B" MAIN STEAM HEADER TRIP VALVE 1-MS-TV 101C 11715-C8M-0708 3 0F 3 C4 A0 DISC 32.000 2 8 EV C 16 FS C 16 ST C 16 i
VIRGINIA POWER COMPANY PAGE: 43 0F 78 NORTH ANEA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE r ( NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER C00R TYPE $1ZE CLASS CAT TTPE TYPE POS V- CSV- VCN-1-MS-TV 101C 11715-CBM-07DB 3 0F 3 C4 A0 DISC 32.000 2 B VP OC "C" MAIN STEAM HEADER TRIP VALVE 1 MS-TV-109 11715-CBM-070A 1 0F 3 A8 A0 GLOBE 3.000 2 8 EV C 14 FS C 14 ST C 14 VP DC MAIN STEAM HIGH PRESSURE DRAIN ISOLATION TO COWDENSER
....s........................................................ ..... ..... ... ..... ..... .... ... .... ....
1-MS TV-110 11715-CBM-0708 3 0F 3 A4 A0 CLOBE 1.500 2 8 EV C FS C ST C VP OC MAIN STEAM HIGH PRESSURE DRAIN HEADER ISO-LATION TO STEAM GENERATOR BLO@0WN STSTEM 1-MS-TV-111A 11715-CBM-070A 3 0F 3 ES A0 GLOBE 3.000 2 B EV C 0 FS O ST C 0 VP DC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE k DRIVEN AUXILI ARY FEEDWATER PUMP 1-MS-TV-1118 11715-CBM 07DA 3 0F 3 E4 A0 GLO6E 3.000 2 8 EV C 0 ' FS 0 ST C 0 VP OC MAlW STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1 MS-TV-113A 11715-CBM-0708 10F 3 D4 A0 GLOBE 3.000 2 B EV C 33 FS C 33 l ST C 33 VP DC "A" MAIN STEAM TRIP BTPASS VALVE 1-Ms-TV 1138 11715-tBM-070B 2 0F 3 04 A0 GLOBE 3.000 2 8 EV C 33 FS C 33 l 2 ST C 33 ' W M l "B" MAIN STEAM TRIP BYPASS VALVE a 1 1-MS-TV 113C 11715 CBM-0708 3 0F 3 D4 A0 GLOBE 3.000 2 i EV C 33 FS C 33 l ST C 33 VP OC I 1 I 1 I l
VIRGINIA POWER COMPANT PAGE: 44 0F 78 NORTH ANNA UNIT 1 REVIS10N: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 . ,% INSERVICE TESTING PROGRAM - VALVE TABLE f \
\ "- _,1 NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER ' NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV- VCN-
"C" kAIN STEAM TRIP BYPASS VALVE 1-MS-TV 115 11715-CBM-070A 3 OF 3 C4 MECM TRIP VLV 3.000 3 E VP OC i MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AFW PUMP 9
l I i l
)
s/ l l l
.I i
i VIRGINIA poler COMPANY PAGE: 45 0F 78~ l f NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECT 10W INTERVAL DATE: 11/05/93 I INSERVICE TESTING PROGRAM - VALVE TABLE -I, 1' NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST'
. NUMBER NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TfPE ' POS V- CSV- VCW- !
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... v 1-08-011 11715-CBM-091A -2 0F 4 D6 WL CHECK VLV 8.D00 2 AC CIV CV C 67 0 67 LT C i
............................................. t "A" DUENCH SPRAY PUMP INSIDE CONTAINMENT !
t' ISOLATIDW CHECK VALVE t 1-05-019 11715-CBM-091A 2 0F 4 E6 WL CHECK VLV 8.000 2 AC CIV CV C 67 l 0 67 I LT C "B" OUENCH SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... ~ !
1-QS-MOV 100A 11715-CBM-091A 2 0F 4 A3 M0 GATE 10.000 2 E VP OC - i +
............................................. t "A" QUENCH SPRAY PUMP SUCTION ISOLATION VALVE FROM REFUELING WATER STORAGE TANK !
1-QS-MOV-1008 11715-CBM-091A, 2 0F 4 A3 MO GATE 10.000 2 E VP DC b I
.............................................. I- )
"B" QUENCH $PAAY PUMP SUCTION ISOLATION VALVE !
s FROM REFUELING WATER STORAGE TANK i 1-QS MOV-101A 11715-CBM-D91A 2 0F 4 D5 M0 GATE 8.000 2 A CIV EV C 0 ! LT C ST C I g r"'s\/ o W ............................................. VP OC "A" QUENCH SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-QS-MOV-1018 11715-CBM-091A 2 0F 4 ES Mo GATE 8.000 2 A CIV EV C 0 LT C ST C 0 VP OC "B" QUENCH SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLAT10h VALVE 1-QS MOV-102A 11715-CBM-091A 1 0F 4 05 MO GATE 6.000 2 8 EV O ST 0 VP OC CHEMICAL ADDITION TANK DISCHARGE !$0LAT10N VALVE 1+05 MOV-102B 11715 CBM-091A 10F 4 D6 MO GATE 6.000 2 8 EV 0 ST 0 VP OC CHEMICAL ADDITION TANK DISCHARGE ISOLATION VALVE.
VIRGINIA POWER COMPANY PAGE: 46 0F 78 NORTN ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/03/93 e INSERVICE TESTING PROGRAM - VALVE TABLE (' 150 REL CS NC ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REO JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV- VCN-1-RC-149 11715-CBM-0938 2 0F 3 D7 CHECK VALVE 3.000 2 AC CIV CV C 28 LT C PRIMARY GRADE WATER SUPPLY TO PRT-#2 RCP SEAL STANDPIPES / FLUSH CONNECT, INSIDE CONT ISO VLV 1 RC-176 11715-CBM-0938 1 0F 3 A4 MANUAL NEEDLE .125 1 AE CIV LT C PRESSURIZER PRES $URE DEAD WEIGHT TESTER ISOLATION, OUTSIDE CONT ISOLATION VALVE 1 RC-178 11715-CBM 093B 1 0F 3 A3 MANUAL NEEDLE .125 1 AE CIV LT C , PRESSURIZER PRESSURE DEAD WEIGHT TESTER ' ISOLATION, OUTSIDE CONT ISOLATION VALVE 1-RC WCV-1556A 11715-CBM 093A 1 0F 3 D7 A0 GLOBE 2.000 1 E VP OC RCS LOOP FILL BOUNDARY VALVE . 1-RC-HCV-15568 11715-CBM-093A 2 0F 3 08 AO GLOBE 2.000 1 E VP OC RCS LOOP FILL BOUNDARY VALVE 1-RC-HCV-1556C 11715-CBM-093A 3 or 3 D3 A0 GLOBE 2.000 1 E VP OC RCS LOOP FILL BOUNDARY VALVE s 1 RC-MOV-1535 11715-CBM-093B 1 0F 3 E4 M0 CATE 3.000 1 B EV C 0 ST C 0 VP OC BLOCK VALVE FOR PRESSURIZER POWER OPERATED RELIEF VALVE 1-RC MOV-1536 11715-CBM 093B 1 0F 3 D4 Mo CATE 3.000 1 B EV C 0 ST C 0 VP OC BLOCK VALVE FOR PRES $URIZER POWER OPERATED RELIEF VALVE 1-RC PCV-1455C- 11715 CSM 0938 1 0F 3 D3 A0 CLOBE 3.000 1 BC EV C 42 0 42 FS C 42 SP O ST C 54 42 ' O 42 VP OC PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK 1-RC-PCV-1456 11715-CBM 0938 1 0F 3 E3 A0 GLOBE 3.000 1 BC EV C 42 0
) FS C 42 42 'Q SP O
VIRGINIA PO E R COMPANY PAGE: 47 0F 78 NORTN ANNA UNIT 1 REVISION: 07- - SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE
\ NC ISO REL CS ALT VALVE DRAWING - $NEET DRWG VALVE VALVE ASME IW VALVE TEST TEST RE0 JUST TEST r- NUMBER' NimBER NUMBER COOR TYPE $!ZE CLASS CAT TYPE TYPE POS . V- CSV- VCN-
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... ....? ....
1 RC-PCV-1456 11715-cam 0938 1 0F 3 E3 A0 GLOBE 3.000 1 BC ST C 54 42 0 42 VP OC PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK 1-RC-SOV-101A-1 11715-CBM-093A 3 OF 3 A5 SO GLOSE 1.000 1 5 EV C 57 0' 57 FS C 57 ST C 54 0' 54-VP OC REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 1 RC $0V-101A-2 11715-CSM-093A 3 0F 3 B5 50 GLOBE 1.000 1 B EV C 57 0 57 FS C 57 ST C 54 0 54 VP OC . REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUEL!kG CAVITY N 1-RC-50V-1018-1 11715-C8M-093A 3 0F 3 AS SO GLOBE 1.000 1 B EV C. 57 O 57 FS C 57 ST - C 54 0 54 VP OC REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITf 1 RC-SOV-1018-2 11715-tBM 093A 3 0F 3 SS SO GLOBE 1.000 1 B EV C 57 0 57 FS C 57-ST C 54 0 54 VP OC REACTOR VESSEL VENT LINE ISOLATION VALVE 10' REFUELING CAVITY 1-RC-SV 1551A 11715-CBM-0938 1 0F 3 E5 SAFETY VALVE 6.000 1 C SP 0 PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 1-RC SV-1551B 11715-com-0938 1 0F 3 E5 SAFETY VALVE 6.000 1 C SP . 0 PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 1 RC-SV-1551C 11715 CBM 0938 1 0F 3 E6 SAFETY VALVE 6.000 1 C SP 0. PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER REL!EF TANK 1 RC-TV-1519A 11715-CBM-0938 2 0F 3 DB A0 GLOSE 3.000 2 A CIV EV C 4 FS' C 9-,r a .-.A y . +, ,,-,..,.,m 1, .,,-4-, g ,, m % . . , , , . , m .,.m..
VIRGINIA POWER COMPANY PAGE: 48 0F 78 NORTH ANNA UNIT 1 REVISION: 07 l SECOND INSPECTIOC INTERVAL DATE: 11/05/93 n INSERVICE TESTING PROGRAM - VALVE TABLE i NC
!$0 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER WUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1-RC TV-1519A 11715-CBN-0938 2 0F 3 D8 A0 GLOBE 3.000 2 A CIV LT C ST C VP OC PRIMARY GRADE WATER SUPPLY TO PRT-#2 RCP SEAL STANDPIPES & FLUSH CONNECT, OUT CONT ISO YLV Wh b
t b i F t I w I i 1 i i
i VIRGINIA POE R COMPANY PAGE: 49 0F 78 NORTN ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 m INSERVICE TESilWG PROGRAM - VALVE TABLE I NC \- ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMEER NUMBER COOR TYPE SIZE CLASS CAT TYPE TTPE PDS V- CSV- VCN-1-RM-007 11715-CBM-0944 1 0F 2 E5 CHECK VALVE 10.000 2 C CV C 74 0 74 "B" RHR PUMP DISCHARGE CHECK VALVE 1-RN-015 11715 CBM-094A 1 0F 2 E7 CHECK VALVE 10.000 2 C CV C 74 0 74 "A" RHR PUMP DISCHARGE CHECK VALVE 1-RM-036 11715-CBM 094A 2 OF 2 C4 MANUAL GATE 6.000 2 AE CIV LT C RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE , TANK, INSIDE CONTAINMENT ISOLATION VALVE 1-RH-037 11715-CBM-094A 2 0F 2 E3 MANUAL GATE 6.000 2 AE CIV LT C RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE , TANK, OUTSIDE CONTAINMENT ISOLATION VALVE 1-RH FCV-1605 11715-CBM-094A 2 0F 2 C7 A0 BFLY 12.000 2 B EV C 20 FS C 20 ST C 20 RHR HEAT EXCHANGERS BYPASS FLOW CONTROL VALVE
\ ............................................................. ..... ..... ... ..... ..... .... ... .... ....
g 1 RH-HCV-1758 11715-CBM-094A 2 0F 2 C5 A0 BFLY 12.000 2 B EV 0 20 FS 0 20 ST C 20 RHR HEAT EXCHANGERS DISCHARGE FLOW CONTROL VALVE 1-RH-MOV-1700 11715-CBM-094A 1 0F 2 A5 MO GATE 14.000 1 B EV 0 18 ST 0 18 VP OC RHR PUMP SUPPLY ISOLATION FR(N "A" HOT LEG, INSIDE M1551LE BARRIER 1-RH MOV-1701 11715-CBM-094A 1 0F 2 A4 MO GATE 14.000 1 B EV 0 18 ST 0 18 VP OC RHR PUNP SUPPLY ISOLATION FROM "A" HOT LEG, OUTSIDE MIS $1LE BARRIER 1-RM-MOV-172DA 11715-CBM-D944 2 0F 2 C3 MO GATE 10.000 1 B EV O 18 ST 0 18 YP OC RHR RETURN ISOLATION 10 "B" ACCUMJLATOR DISCHARGE LINE 1-RM MOV-17208 11715-CBM-094A 2 or 2 B3 MO GATE 10.000 1 B EV O 18 ST C 18 VP OC
% RHR RETURN ISOLATION 10 "C" ACCLMJLATOR DISCHARGE LINE N ............................................................. ..... ..... ... ..... ..... .... ... .... ....
e VIRGINIA POWER COMPANY PAGE: 50 0F 78 WORTH AN#A UNIT 1 REVISION: 07 , SECOND INSPECTION INTERVAL DATE: 11/05/93 i
- INSERVICE TESTING PROGRAM - VALVE TABLE -
.1 r
\ NC f ISO REL CS ALT.
- VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST. REQ JUST TEST ;
NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... i 1 RM RV 1721A 11715-tBM 094A 10F2E6 RELIEF VALVE 3.000 2 C SP 0
............................................. f RHR SYSTEM RELIEF VALVE AT "A" RNR PUMP SUC- I TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK '
1 RM-RV-17218 11715-CBM D94A. 1 0F 2 E4 RELIEF VALVE 3.000 2 C SP O
~{
t RHR SYSTEM RELIEF VALVE AT "B" RHR PUMP SUC- ? TION, RV DISCRARGE TO PRESSURIZER RELIEF TANK ; t i n 9
-I :
't i
1 h t i 6 r (# 5 J l f r i I
'i I
.1 I
i
. l.
E i' VIRGINIA poler COMPANT PAGE: -51 0F 78 NORTH ANNA UNIT 1 REVISION: 07
'" SECOND INSPECTION INTERVAL DATE: 11/05/93
- m INSERVICE TESTING PROGRAM . VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET. DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST-NUMBER NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- i i 1 RM-TV-100A 11715-cam-082N 3 0F 3 C5 A0 CLOBE 1.000 2 A CIV EV C i FS C ! LT C ; ST C 54 f VP OC f' RETURN ISOLATION FROM AIR RADIAT10W MONITOR TO CONTAINMENT, OUTSIDE CONT ISOLATION VALVE
- i
............................................................. ..... ..... ... ..... ..... .... ... .... .... ?
RM-TV 100s 11715-CeM-082N 3 0F 3 D5 A0 CLOBE 1.000 2 A CIV EV C FS C ! LT C ST C 54 ' VP OC 'i SUPPLY ISOL TO AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, OUTSIDE CONT ISOLATION VALVE 1-RM-TV 100C 11715-csM-082N 3 0F 3 D4 A0 CLOBE 1.000 2 A CIV - EV C FS C LT C i ST C 54 '? VP OC SUPPLY 1$0L TO AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, INSIDE CONT ISOLATION VALVE ..
~ '~
"" " ~ " " ~
ikkIE"-ibbb""INi5Ibb5Ibb2i~ "5'6F 5 65' " 6'6L655' " " " ~ I$666 2 T B ih'" $ " "~ "" ~"' FS C i ST C 54 VP OC RETURN ISOL FROM AIR RADIATION MONITOR To f CONTAINMENT, OUTSIDE CONT ISOLATION VALVE : s 4 f i i h i 0
.[
i i h I
.i h
l 1
- i i
J i VIRGINIA POWER CGIPANT PAGE: 52 0F 78 ! NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93. i INSERVICE TESTING PROGRAM - VALVE TABLE - M l (- ISO REL CE NC ALT i VALVE DRAWING FMEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1 RP-006 11715 COM-088A 2 0F 4 C6 MANUAL DIA 6.000 2 AE CIV LT C r REFUELING PURIFICATION FROM REACTOR CAVITT TO RP PUMPS, INSIDE CONT ISOLATION VALVE i 1 RP 008 11715-CBM-088A 2 0F 4 C4 MANUAL DIA 6.000 2 AE CIV LT C REFUELING PURIFICATION FRO *,4 REACTOR CAVITT TO RP PUMPS, OUTSIDE CONT ISOLATION VALVE 1
.1 RP-026 11715-CBM-088A - 2 DF 4 C4 MANUAL DIA 6.000 2 AE CIV LT C REFUELING PURIFICATION FROM RP PUMPS TO >
REACTOR CAVITY, OUTSIDE CONT ISOLATION VALVE 1-RP-028 11715-CsM-088A 2 0F 4 05 MANUAL DIA 6.000 2 AE CIV LT C REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, INSIDE CONT ISOLATION VALVE - r v i f f t t
?
-9 k
b
.I t
l t
-f I
l
.t r
T f i l l
.t
?
4 VIRGINIA POWER COMPANY PAGE: 53 OF 78 NORTH ANNA UNIT 1 REV1SION: 07 j SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE L NC ISO REL CS ALT VALVE DRAWING SMEET DRWG VALVE VALVE ASME IW VALVE TEST TEST' REO JUST TEST NUMBER NLMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- ; 1-RS 018 11715-CBM-091A 4 0F 4 D6 WL CHECK VLV 10.000 2 AC CIV CV C 67 0' 67 j LT C I
............................................. I 1
"A" OUTSIDE RECIRC SPRAY PUMP INSIDE l
CONTAINMENT ISOLATION CHECK VALVE I 1-RS-027 11715 CBM-091A 4 0F 4 D6 WL CHECK VLV 10.000 2 AC CIV CV C 67 0 67 l LT C l L l "B" OUTSIDE RECIRC SPRAY PUMP INSIDE j CONTAINMENT ISOLATION CHECK VALVE 4 1 RS-123 11715-CBM-0918 10F 1 E7 CHECK VALVE 8.000 2 C CV o 33 "A" CASING COOLING PUMP DISCHARGE CHECK VALVE 70 "A" OUTSIDE RECIRC SPRAY PUMP SUCT 1-RS-138 11715-CBM-091B 1 0F 1 F7 CHECK VALVE 8.000 2 C CV 0 33
............................................. f "B" CASING COOLING PUMP DISCHARGE CHECK VALVE TO "B" OUTSIDE RECIRC SPRAY PUMP SUCT 1-RS-MOV-100A 11715-CBM-0918 10F 1 E7 MO GATE 8.000 2 A CIV EV C 0
LT C ST C 0 VP OC "A" CASING COOLING PtMP DISCHARGE ISOLATION TO A OUTSIDE RECIRC SPRAY PUMP SUCTION 1-RS-MOV-1008 11715-CBM-0918 1 0F 1 F7 MO GATE 6.000 2 A CIV EV C 0 LT C ST C 0 VP OC "B" CASING COOLING PUMP DISCHARGE ISOLATION To "B" OUTSIDE RECIRC SPRAY PUMP SUCTION 1 RS MOV-101A 11715-CBM-0918 1 0F 1 E7 M0 GATE 6.000 3 A CIV EV C 0 LT C ST C 0 VP OC "A" CASING COOLING PUMP DISCHARGE ISOLATION To OUTSIDE RECIRC SPRAY PUMP SUCTION
...................."A" .......................................... ..... ..... ... ..... ..... .... ... .... ....
1-RS MOV 101B 11715-CBM-0918 1 0F 1 F7 M0 CATE 6.000 3 A Civ EV C 0 LT C ST C 0 VP OC "B" CASING COOLING PUMP DISCHARGE ISOLATION TO B CUTSIDE RECIRC SPRAY PUMP SUCTION
. .. ___- ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ _ _ -_ _ _ . _ _ -h
, . ~ .- - ~ ._ - - _ . - .- -
l VIRGINIA poler C0erANT PAGE: 54 0F 75 NORTN ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT-VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V. CSV- VCN-1-RS-MOV-155A 11715-CeM 091A 4 0F 4 86 MO GATE 12.000 2 8 EV C i 0 i ST C ' 0 VP OC ,
............................................. i "A" OUTSIDE RECIRC SPRAY PLMP SUCTION ISOLAT '
VALVE FROM CONTAINMENT SLMP & CASING COOLING 1-RS-MOV 155B 11715-CBM-091A 4 0F 4 A6 MO GATE 12.000 2 8 EV C 0 i ST C 0 VP OC J t
"B" OUTSIDE RECIRC SPRAY PUMP SUCTION ISOLAT ,
VALVE FROM CONTAINMENT SUMP & CASING COOLING
............................................................. ..... ..... ... ..... ..... .... ... .... . . . . - )
1-RS-Mov-156A 11715-CSM-091A 4 0F 4 D5 M0 GATE 10.000 2 A CIV EV C , O LT C i ST C 0 i VP OC "A" OUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO- ' LATION, OUTSIDE CONTAIN4ENT ISOLATION VALVE ' 1-RS-MOV-1568 11715-CBM-091A 4 0F 4 D5 MO GATE 10.000 2 A CIV EV C 0 - LT C ' ST C 0 ! VP OC t
*B" OUTSIDE RECIRC SPRAY PLMP DISCHARGE ISO-LATION, OUTSIDE CONTAINMENT ISOLATION VALVE I
c b 9 L r i
? \
i s p + rr - . ---.
1 VIRGINIA POWER COMPANY PAGE: 55 0F 78 NORTH ANNA UNIT 1 REVISION: 07 EECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE ('s f,
' NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR 1TDE SIZE CLASS CAT TTPE TYPE POS V. CSV. VCN.
1.SA-002 11715-CBM-082F 10F 1 C7 MANUR. GATE 2.000 2 AE CIV LT C SERVICE AIR SUPPLY TO UNIT 100/4TAINMENT, INSIDE CONTAINMENT ISOLATION VALVE 1-SA-029 11715-CBM-082F 1 0F 1 87 MANUAL GLOBE 2.000 2 AE CIV LT C SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, OUTSIDE CONTAINMENT ISOLRTION VALVE t t
VIRGINIA POWER COMPANY PAGE: 56 0F 78 NORTH ANNA UNIT 1 REVISION: 07 . l SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE
.b i
( NC ISO REL CS ' . ALT
- YALVE DRAWING $NEET DRWG YALVE VALVE ASIEE IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER WUMBER COOR TYPE $1ZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1 51 001 11715-COM-096A 10F 3 B7 CHECK VALVE 12.000 2 C CV O 37 "A" LOW HEAD $1 PLMP SUCTION CHECK VALVE FROM CONTAIMMENT CUMP
...................................~.......,,................ ..... ..... ... ..... ..... .... ... .... .... .
i 1-51-004 11715 CBM-096A 1 0F 3 C7 CHECK VALVE .750 2 AC CV C 53 LT C "A" LOW HEAD S1 PLMP SEAL WATER SUPPLY CHECK VALVE FROM RWST 1 SI 009 11715-cam-096A 2 of 3 B6 CHECK VALVE 10.000 2 C CV C 38 0 38 .
"A" LOW HEAD St PUMP DISCHARGE CHECK VALVE ,
1
............................................................. ..... ..... ... ..... ..... .... ... .... .... , s 1 51-012 11715-cam 096A 2 of 3 B5 CHECK VALVE 2.000 2 C CV 0 l ,
"A" LOW HEAD $1 PLMP MIN! MUM FLOW / TEST LINE DISCHARGE CHECK VALVF
~ ~ ~ "~ "~ ~
I i$hi!b55""""$5EiSCaidb9dk"$bE585 bHkhk VkbE ~"" 5$b06 1 5"" b" '"" Cit b " 3f' ~"~ """
"B" LOW HEAD $1 PUMP SUCTION CHECK VALVE FROM CONTA!IMENT SUMP '
1-SI.018 11715-CBM-096A 1 0F 3 B3 CHECK VALVE 12.000 2 C CV 0 38 RWST SUPPLY CHECK VALVE TO "B" LOW HEAD Si i PUMP SUCTION 1-$1-021 11715-cam 096A 10F 3 C5 CHECK VALVE .750 2 AC CV C 53 LT C "B" LOW HEAD $1 PUMP SEAL WATER SUPPLY CHECK VALVE 1-51-026 11715-CBM-096A 2 0F 3 B4 CHECK VALVE 10.000 2 C CV C 38 I O 38 t
"D" LCW HEAD St PUMP DISCHARGE CHFCK VALVE
................................................................o ..... ... ..... ..... .... ... .... .... g 1 51-029 11715-CsM-096A 2 0F 3 B4 CHECK VALVE 2,000 2 C CV O I "B" LOW HEAD St PLMP MINIMLM FLOW / TEST LIFE !
0!$ CHARGE CHECK VALVE 1 51-047 11715 cam-096A 1 0F 3 E5 CHECK VALVE 8.000 2 AC CV C 39 0 39 LT C
............................................. j RWST SUPPLY CHECK VALVE TO CHARGlkG PUMP SUCTION HEADER 1-51-058 11715-CSM-096A 1 0F 3 ET MANUAL GLOBE 1.000 2 AE CIV LT C
............................................. j ACCUMULATOR MAKEUP LINE, OUTSIDE CONTAINMENT ISOLAT10N VALVE -
1 51 066 11715-CBM-0964 3 Of 3 04 CHECK VALVE 1.000 2 C CV C i l
-l
y .-. . . - . . l A> l_ VIRGINIA POWER COMPANY PAGE:. 57 0F 78
. WORTH ANNA UNIT 1' . REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 .I INSERVICE TESTING PROGRAM - VALVE TABLE :
g
. ('~~N i j
' %~ ,1 . NC. i
'IBO REL CS ALT l r - VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST.REO 'JUST TEST 'J NUMBER WUMBER NUMBER COOR TYPE $1ZE CLASS CAT TTPE TYPE ' POS V-CSV-~VCN . ;
BORON INJECTION TANK SUPPLY CHECK VALVE FROM BORIC ACID TRANSFER PUMPS 1 51 077 i 11715 CeM-096A 3 0F 3 F7 MANUAL GLOBE 1.000 2 Ad CIV LT C ; BORON INJECTION TANK BYPASS LINE ISOLATION { VALVE - TO RCS COLD LEG ;* 1-31-079 11715-CBM 0968 4 0F 4 E3 CHECK VALVE 3.000 2 AC CIV CV C 43 t 0 43 - LT C [ HIGH HEAD SI FROM CHARGING Punr. 'O RCS COLD LEGS, INSIDE CONT ISOLATION CHECK JALVE .[ 1-51 083 11715-CBM-0968 4 0F 4 F8 CHECK VALVE 6.000 1 AC PIV CV C 41 ~! O 41 i LT C i "A" RCS COLD LEG SI ADMICS]DN CHECK VALVE
-)
1 SI-086 11715-CBM 0968 4 or 4 E8 CHECK VALVE 6.000 1 AC PIV CV C 41 0 41 LT C "B" RCS COLD LEG SI ADMISSION CHECK VALVE 1-51-D89- 11715-CBM-D968 4 0F 4 D8 CHECK VALVE 6.000 1 AC P!V CV C 41
.0 41 LT C "C" RCS COLD LEG SI ADMIS$1DN CHECK VALVE 1-51-D90 11715-CBM 0968 4 OF 4 C3 CHECK VALVE 3.000 1 AC CIV CV C 43 0 43 LT C HIGH HEAD $1 FROM CHARGING PUMPS TO RCS HOT LEGS, IkSIDE CnNT ISOLATION CHECK VALVE 1 51-095 11715-CBM-0968 4 0F 4 D8 CHECK VALVE 6.000 1 C CV C 43 0 43 "B" RCS HOT LEG SI ADMIS$10N CHECK VA!YC
..................................................m . . . . . . . . . . . . . . .... ... ..... ..... .... ... .... ....
1-51-099 11715-CBM-D968 4 CF 4 C8 CHECK VALVE 6.000 1 C CV C 43 0 43 "A" RCS NOT LEG SI ADMISSION CHECK VALVE 1-51 103 11715 CBM-0968 4 0F 4 B8 CHECK VALVE 6.000 1 C CV C - 43 0 43 "C" RCS NOT LEG SI ADMIS$!DN CHECK VALVE 1 E!-106 11715 CBM 0968 1 0F 4 F4 CHECK VALVE 1.000 2 AC CIV CV C 40 LT . C
1
-l ,
L l
'l
- VIRGINIA POWER COMPANY PAGE: $8 0F 78 - !
NORTH ANNA UNIT 1 REVISION: 07 ') SECOND INSPECTION INTERVAL' .DATE: 11/05/93 > INSERVICE TESTING PROGRAM - VALVE TABLE i I"' NC^
- - - ISO REL CS ALT !
- VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REO JUST TEST-
-NUMBER NUMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-
-[
NITROGEN SUPPLY TO ACCUMULATORS, INSIDE - CONTAINMENT !$0LATION CHECK VALVE ! 1-51 110 11715-CBM-D968 1 0F 4 D4 CHECK VALVE 1.000 2 AC CIV CV C 40 LT C i ACCUMULATOR MAKE UP LINE, INSIDE CONTAINMENT v ISOLATION CHECK VALVE ! 1 SI-125 11715-CBM-0968 10F 4 B7 CHECK VALVE 12.000 1 C O 42 CV h !
"A" ACCUMULATOR DISCHARGE CHECK VALVE ,
b 1 SI-127 11715-CBM 0968 1 0F 4 B8 CHECK VALVE 12.000 1 C CV C 42 i 0 42 ~l [
"A" ACCUMULATOR COLD LEG ADMISSION CHECK ' [
VALVE 1-51-142 11715-CBM-0968 2 0F 4 85 CHECK VALVE 12.000 1 C CV 0 42
............................................. {
"B" ACCUMULATOR DISCHARGE CHECK VALVE I t,
1 SI-144 11715-CBM-0968 2 0F 4 ST CHECK VALVE 12.000 1 C CV C 42 I O 42 ! =I "B" ACCUMULATOR COLD LEG ADMISSION CHECK
\ VALVE 1 51 159 11715-CBM-D968 3 0F 4 85 CHECK VALVE 12.000 1 C CV- 0 42
............................................. l i "C" ACCUMULATDR DISCKARGE CHECK VALVE j i
t 1-$1-161 11715-CBM-0968 3 0F 4 87 CHECK VALVE 12.000 1 C CV C 42 : 0 42 "C" ACCUMULATOR COLD LEG ADMIS$10N CHECK VALVE . 1-$1 185 11715-CBM 0968 4 0F 4 F3 CHECK VALVE 3.000 2 AC CIV CV C 43 0 43 p LT C .; HIGH HEAD SI FROM CH W ING PUMPS TO RCS COLD LEGS, INSIDE CONT !>0LATION CHECK VALVE 1-51-190 11715-CBM-0968 4 0F 4 F7 CHECK VALVE 2.000 1 C CV C. 44 1 0 44 !
............................................. y I
HIGH HEAD SI TO *A" RCS COLD LEG, INSIDE ; MIJslLE BARRIER CHECK VALVE 1-51-192 11715-CBM-0968 4 0F 4 E7 CHECK VALVE - 2.000 1 C CV C 44 I O 44 HIGH HEAD St TO "B" RCS COLD LEC, INSIDE ' MISSILE BARRIER CHECK VALVE 'L 1-51+194- 11715 CBM-0964 4 0F 4 D7 CHECK VALVE 2.0D0 1 C CV C 44 u 0 l l 9
VIRGINIA POWER COMPANY PAGE: 59 0F 75 NORTH ANNA UNIT 1 REVISION: 07 , SECOND INSPECTIDW INTERVAL DATE: 11/05/93
- INSERVICE TESTING PROGRAM - VALVE TABLE i 1 kC *
\._ / ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER WUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-HIGH HEAD S1 T0 "C" RCS COLD LEG, INSIDE ,
MISSILE BARRIER CHECK VALVE 1-St 195 11715-CBM-0968 4 0F 4 F6 CHECK VALVE 6.D00 1 AC C&P CV C 41 > 0 41 LT C LOW HEAD SI TO "A" RCS COLD LEG, INSIDE CON-TAINMENT ISOLATION CHECK VALVE 1-51-197 11715-CBM-096B 4 0F 4 E6 CHECK VALVE 6.000 1 AC C&P CV C 41 0 41 LT C LOW HEAD SI TO B RCS COLD LEG, INSIDE CON- , TAINMENT ISOLATIDW CHECK VALVE 1-51-199 11715-CBM-0968 4 0F 4 D6 CHECK VALVE 6.000 1 AC CLP CV C 41 0 41 LT C LOW HEAD SI To "C" RCS COLD LEG, INSIDE CON-TAlkMENT ISOLATION CHECK VALVE ' 1-51-201 11715-CBM-0968 4 0F 4 D3 CHECK VALVE 3.000 1 AC CIV CV C 43 i 0 43 LT C g-- .............................................
- s. HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT ISOLATION CHECK VALVE 1-51-206 11715 CBM-096B 4 of 4 B3 CHECK VALVE 6.000 2 AC CIV CV C 43 0 43 LT C LOW HEAD SI FROM "A" LHS! PUMP TO RCS HDT LEGS, INSIDE CONT ISOLATION CHECK VALVE 1-51-207 11715 CBM-0968 4 0F 4 B3 CHECK VALVE 6.000 2 AC CIV CV C 43 0 43 LT C LOW HEAD St FROM "S" LHS! PUMP TO RCS HDT LEGS, INSIDE CONT ISOLATION CHECK VALVE 1-SI-209 11715-CBM-0968 4 0F 4 C7 CHECK VALVE 6.000 1 C CV C 43 0 43 )
............................................. i LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE 10 A RCS HOT LEG 1 SI-211 11715-CBM- D968 4 0F 4 C7 CHECK VALVE 6.000 1 C CV C 43 1 0 43 r
LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE To B RCS HOT LEG 1 51-213 11715 CBM-0968 4 0F 4 B7 CHECK VALVE 6.000 1 C CV C 43 0 43 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE / TO C RCS HOT LEG 5 k ....................".."...................................... ..... ..... ... ..... .....
VIRGIN!A PO ER COMPANY PAGE: 60 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL -DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC
% 180 REL CS ALT VALVE DRAWING -SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST RE0 JUST TEST NUMBER NUMBER NUMBER COOR TYPE E!ZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1 Sl*HCV 1936 11715-CBM-096B 1 0F 4 E5 A0 GATE 1.000 2 'A CIV EV C FS C LT C ST C VP DC WASTE GAS FROM ACCUMULATORS TO CHARCOAL FILTERS 1 SI-MOV-1836 11715-CBM-096A 3 0F 3 C8 M0 CATE 3.000 2 A CIV EV C 23 0 23 LT- C ST C 23 0 23 VP OC HIGH HEAD SI FROM CHARGING HEADER TO RCS COLD LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI MOV-1860A 11715 CSM-096A 1 0F 3 B7 M0 GATE 12.000 2 B EV C 0-ST C 0
VP OC "A" LOW HEAD St PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP
\
1.SI MOV-1860B 11715-CBM-096A 1 of 3 B5 M0 CATE 12.000 2 B EV C ST 0 VP OC "B" LOW HEAD S1 PUMP SUCTION ISOLATION FROM CONTAINMENT SLMP 1 SI-Mov-1862A 11715-cam 096A 1 0F 3 A3 No GATE 12.000 2 B EV C ST C VP OC "A" LOW HEAD $1 PUMP SUCTIOl FROM RWST 1-SI Mov 1862s 11715-CBM-096A 1 of 3 B3 .*is CATE 12.000 2 B' EV C ST C VP OC
*B" LOW HEAD $1 PUMP SUCTION FROM RWST 1 SI-Mov-1863A 11715-CBM-096A 2 0F 3 C5 MO GATE 8.000 2 B EV C-0 ST C 0
W E "A" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 1 SI-MOV-1863B 11715-CBM-0958 2 0F 2 BS N0 GATE 8.000 2 B EV C 0 ST C
% 0 e
/;
'I VIRGINIA P0hER C(BIPANY PAGE: 61 0F 78 i NORTH ANNA UNIT 1 .
REVISION: 07 l SECOND INSPECTION INTERVAL DATE: 11/05/93
' -(
INSERVICE TESTING PROGRAM - VALVE TABLE NC i ISO REL CS ~ ALT - VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REO JUST TEST l NUMBER NUMBER. NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV ' VCN- , 1 SI-MOV-18638 11715-CBM-0955 2 0F 2 B8 M0 GATE 8.000 2 B VP . OC I "B" LOW HEAD SAFETT INJECTION PUMP SUPPLY '! ISOLATION TO CHARGING PLDIPS 3 1 SI MOV-1864A 11715-CBM-0964 2 0F 3 C7 M0 GATE 10.000 2, 5 EV C j 0 j ST C ' O
. VP ' OC 4 s
[
"A" LOW HEAD S1 PUMP COLD LEG DISCHARGE STOP VALVE
+
1 SI MOV 1864B 11715-CBM-096A 2 0F 3 C6 Mo CATE 10.000 2 B EV C L 0 - ST C l 0 l W K t
............................................. i "B" LOW HEAD ST PLMP COLD LEG DISCHARGE STOP 'E VALVE f 1 SI MOV 1865A 11715-CBM-0968 1 0F 4 C7 No GATE 12.000 2 B EV C : 24 l 0 24 .
ST C 24 .; o 24 VP OC ;
"A" ACCUMULATOR DISCHARGE ISOLATION VALVE TO ;
RCS COLD LEG '
............................................................. ..... ..... ... ..... ..... .... .'.. .... ..... i 1 SI-MOV 18658 11715-CBM-0968 2 0F 4 C5 M0 GATE 12.000 2 B EV C 24 '!
0 24 , ST C 24 ! 0 24 --3 VP OC . ' j "B" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 1 1 51-MOV-1865C 11715-CBM 0968 3 0F 4 C5 M0 GATE 12.000 2 8- EV C 24 l 0 24 [ ST C , 24 l 0 24 - ; W E ;
"C" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG
1 1-SI-MUV 1867A 11715 CBM 096A 3 or 3 D4 No GATE 3.000 2 B EV C l 0 ! ST C .' l 0 , VP OC
~ I BORON INJECTION TANK HIGH HEAD $1 INLET VALVE
-{
............................................................. ..... ..... ... ..... .. .. ..... ... .... .... j 1-SI-MOV 1867B 11715-CBM-096A 3 or 3 04 ' Mo GATE 3.000 2 B EV C' 1 0 .
ST C } O ! VP OC ' t l
)
i i
'I a
1 a e
F. i VIRGINIA POWER CCMPANY PAGE: 62 0F 75- l NORTH ANNA UNIT 1 REVill0N: 07 ! SECOND INSPECTION INTERVAL DATE: 11/05/93 ! INSERVICE TESTING PROGRAM - VALVE TABLE .I lf ^
~' gg
!$0 REL CS ALT ;
VALVE. DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST- '! NUMBER NUMBER- NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-i BORON INJECTION TANK HIGH HEAD $1 INLET VALVE 1.SI-MOV.1867C 11715-cam-096A 3 0F 3 ET M0 GATE 3.000 2 A CIV EV C .; O LT C 59 i ST C . O !
~
VP OC
............................................. i SORON INJECTION TANK OUTLET 70 RCS C3LD LEG, 't CUTSIDE CONTAINMENT ISOLATION VALVE l
1 SI-Mov 1867D 11715-C8M-096A 3 0F 3 07 MO GATE 3.000 2 A CIV EV C 1 0 - LT C 59 f ST C 0 t W K i SORON INJECTION TANK OUTLET TO RCS COLD LEG, ' OUTSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... l 1-SI-MOV 1869A .11715-CBM-096A 3 0F 3 C8 ~ Mo GATE 3.000 2 A CIV. EV C 23 0 23 LT C i ST C 23 0 5 r VP OC
~
HIGN HEAD SI FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT. ISOLATION VALVE 1 SI-Mov-18698 11715-CBM-096A 3 OF 3 B8 MO GATE 3.000 2 A CIV EV' C 23 0 23 LT C ~ t ST 23 C O 23 - , VP OC ' HIGH HEAD St FROM CHARGING HEADER 70 RCS HOT LEGS, OUISIDE CONTAINMENT ISOLATION VALVE l; 1 SI MOV 1885A 11715-CBM-096A 2 or 3 C3 MO GLOBE 2.000 2 A EV' C .j LT C ST C , VP OC "A" LOW HEAD St PUMP MINIMUM FLOW / TEST LINE ISOLATION 1-SI-MOV 15858 11715 C8M 096A 2 OF 3 B3 MO GLOBE 2.000 2 A EV C , LT C ' ST C W K i
}
"8" LOW HEAD SI PUMP MINIMUM FLOW /1EST LINE ISOLATION '5
]
1-SI-MOV-1885C 11715-CBM-0964 2 0F 3 03 M0 GLOSE 2.000 2 A EV C J 1 LT C ST C VP OC
VIRGINIA POWER COMPANY FAGE: 63 0F 78 WORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE (3 i I V ISO REL CS NC ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER WUMBER C00R TYPE SIZ2 CLASS CAT TYPE TYPE POS V- CSV- VCN-
............................................. +
"A" LOW HEAD St PLMP MINIMUM FLOW / TEST LINE ISOLATION 1-SI MOV 18850 11715-CBM 096A 2 0F 3 IL3 MO GLOBE 2.000 2 A EV C LT C ST C VP OC "B" LOW HEAD $! PUMP MINIMUM FLOW / TEST LINE ISOLATION 1-SI-MOV-1890A 11715-CBM-096A 2 0F 3 D7 M0 CATE 10.000 2 A CIV EV C 23 0 23 LT C ST C 23 0 23 VP OC "A" LOW HEAD S! PUMP HOT LEC DISCHARGE STOP I VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-MOV-1890B 11715-CBM 0964 2 0F 3 D7 MO GATE 10.000 2 A CIV EV C 23 0 23 LT C ST C 23 0 23 VP OC (D '
"B" LOW HEAD S1 PUMP HOT LEG DISCHARGE STOP VALVE, CXJTSIDE CONTAINMENT ISOLATION VALVE i
1-SI-MOV 1890C 11715-CBM-096A 2 OF 3Q MO GATE 10.000 2 A CIV EV C
- O LT C 59 l ST C 0
VP OC LOW HEAD SI PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-MOV-18900 11715-CBM-096A 2 0F 3 C7 MO GATE 10.000 2 A CIV EV C 0 LT C 59 ST C D VP OC LOW HIAD $1 PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI RV-1845A 11715-CBM-0964 2 0F 3 06 RELIEF VALVE .750 2 C SP O "A" LOW HEAD SI PLMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SLMP
~ ~ "
$IEiIhvI58155"'IlfiS I bii4 696I"'Ebf'Ebf"~RiLIEF VILV5"" Sf56 5"" b" ~"" iE" 6~ "" ~"~ ~~~~
LOW HEAD SI HEADER TO COLD LEG RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP s
.................. .......................................... ..... ..... ... ..... ..... .... ... e... .... I 3, 1-SI RV-1845C 11715-CBM 096A 2 0F 3 C6 RELIEF VALVE .750 2 C SP O .v/ ,
I
1 i i VIRGINIA PohER COMPANY .PAGE: 64 DF 78 4 NORTH ANNA UNIT 1 REVISIDW: 07 - - d SECOND INSPECTION INTERVAL DATE: 11/05/93 4 INSERVICE TESTING PROGRAM - VALVE TABLE '
. f. * \ NC -
150 REL CS ALT-VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST 1 NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS ' V- CSV- VCN-
"B" LOW HEAD St PUMP DISCHARGE RELIEF VALVE, ,
RV DISCHARGE TO SAFEGUARDS AREA SUMP ' 1 SI TV-1DO 11715-CSM-0968 1 0F 4 F3 A0 GLOBE 1.000 2 -A CIV EV C i FS C ! LT C - i ST C VP DC NITROGEN SUPPLY TO ACCUMULATORS, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI-TV 101 11715-CBM-0968 1 0F 4 E4' A0 GLOBE 1.000 2 A CIV EV C FS C : LT . C t ST C 54 . W M ! ACCUMULATORS TO WASTE CAS CHARCOAL FILTERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-St-TV-1842 11715-CSM-0968 10F 4 D4 A0 GLOSE .750 2 A CIV EV C FS C LT C ST. I C 54 VP OC ACCUMULATOR TEST LINE, INSIDE CONTAINMENT ISOLATION VALVE 1-SI.TV-1859 11715-CBM-096A 2 0F 3 F7 A0 CLOBE .750 2 A CIV EV C .> FS C' LT ' C ST C VP DC ACCUMULATOR TEST LINE, OUTSIDE CONTAINMENT ISOLATION VALVE i 1 SI TV-1BS4A 11715-CBM-096A 3 0F 3 E4 A0 GLOBE 1.000 2 8 EV C FS C ST C 54 i VP DC
............................................. s BORON INJECTION TANK RETURN !$0LAT10N TO BORIC ACID STORAGE TANK 1 51-TV-1S848 11715 CBM-D96A 3 0F 3 E4 A0 GLOBE 1.000 2 8 EV C I FS C ,
ST C 54 ,
- VP DC BORON INJECTIDW TANK RETURN ISOLATION TD t BORIC ACID STORAGE TANK
....e.............................e.......................... ..... ..... .e. ...e. ..... .... ... .... e..e 1 SI TV-1S&4C 11715-CBM 096A 3 0F 3 04 A0 CLOSE 1.000 3 B EV- C FS C .
-l ST C 54 .
' VP OC BORON INJECTION TANK SUPPLY ISOLATION FROM BORIC ACID TRANSFER PU4PS
............................................................. ..... ..... ... ..... ..... .... ... .... .... 6
p VIRGINIA poler COMPANY 'PAGE: . .65 of 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE-NC ISO REL CS ALT VALVE- DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REG -JUST' TEST NUMBER NUMBER . NUMBER COOR TYPE - SIZE CLASS CAT TYPE POS' V- CSV- VCN-
...... ........ ...... .... ..... ..... ..... ... ..... TYPE .... .... ... .... . . . . -
1 55-TV 100A 11715-CRM-089D 10F 1 F6 A0 CLOBE .375 1 A CIV EV C FS C LT - C ST C 54 VP Cc PRESSURIZER LIQUID SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 1 SS-TV-100B 11715 CBM 089D 1 0F 1 F5 A0 GLOBE .375 1 A CIV EV C FS C LT C ST C VP OC PRESSURIZER LIQUID SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SS-TV-101A 11715-CBM-089D 10F 1 E6 A0 CLOBE .375 1 A CIV EV C FS C-LT C ST C 54 VP OC PRESSURIZER VAPOR SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 1-SS-TV-101B 11715-CBM-089D 1 0F 1 E5 A0 GLOBE .375 1 A CIV EV C [ -FS LT C C ST C VP OC PRESSURIZER VAPOR SPACE SAMPLE t!NE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SS-TV-102A 11715-CBM 089D 1 0F 1 DC $0 CLOBE .375 1 A CIV EV - C FS C LT C ST C 54 VP OC' REACTOR COOLANT COLD LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATION VALVE 1 55-TV-102B 11715 CBM-089D 1 0F 1 D5 SD CLOBE .375 1 A CIV EV C FS C LT C ST C 54 VP OC REACTOR COOLANT COLD LECS SAMPLE HEADER, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SS TV-103A 11715-CBM-0890 1 0F 1 F6 SD CLOBE .375 2 AE CIV LT C VP OC RNR SAMPLE HEADER, INSIDE CONTAINMENT ISOLA-TION VALVE 1 SS-TV-1038 11715 C9M-089D 1 0F 1 F5 S0 CLODE .375 2 AE CIV LT C VP OC 1 i i
p t VIRGINIA POWER C(MPANT PAGE: 66 0F 78 h0RTH ANNA UNIT 1 REVIS!DW: 07 L; SECOND INSPECTION INTERVAL-' DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE
\
NC ISO REL CS -ALT VALVE DRAWING- SHEET DRWG VALVE VALVE ASME IW VALVE TEST -TEST REQ .JUST. TEST NUMBER NUMBER NUMBER COOR TTPE $1ZE CLASS CAT TTPE ~TTPE POS ' V- CSV- VCN - RNR SAMPLE HEADER, OUTS!DE CONTAINMENT ISOLA-T!ON VALVE 1 SS TV 104A 11715-CBM 089D 1 0F 1 C6 A0 GLOSE .375 2 A CIV EV C FS C LT C ST C 54 VP OC PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE j 1 SS-TV-1D4B 11715-CSM D890 1 0F 1 C5 A0 GLOBE .375 2 A CIV EV C FS C LT C ST C VP OC PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SS-TV-106A 11715-CBM-0890 1 of 1 E6 SO GLOBE .375 1 A CIV EV C FS C LT C ST C 54 VP OC
'# .- REACTOR C00LA3lT NOT LEGS SAMPLE HZADER, INSIDE ' 'TAINMENT ISOLATION VALVE 1 SS-TV 1D68 11715-CBM- 't 9 0F 1 E5 So GLD8E .375 1 A CIV EV- C FS C LT -C ST C 54 VP OC ,
REACTOR COOLANT HOT LEGS SAMPLE HEADER, OUT- ,
$1DE CONTAINMENT ISOLATION VALVE !
1-SS-TV-112A 11715-CBM-D898 3 0F 4 D3 A0 CLost .375 2 A CIV EV C
- FS C LT C ,
ST C 54 VP OC 1 STEAM GENERATORS SAMPLE HEADER, INSIDE CON- ; TAINENT ISOLATION VALVE 1 53 TV 1128 11715-CBM 089B 3 0F 4 C3 A0 GLOBE .375 2 A CIV EV C i FS C 'i LT C -j ST C i W E ! STEAM GENERATORS SAMPLE HEADER, OUTSIDE CON
- l TAINMENT ISOLATION VALVE
'i
.)
i i
-VIRGINIA POWER COMPANY PAGE: 67 0F 78 NORTN ANNA UNIT 1 _ REVISION: 07 ,
SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE Yt4LE-4 ISO REL CS T . VALVE DRAWING SHEET DRWG VALVE TEST NUMBER NUMBER NUMBER C00R TTPE VALVE SIZE CLASS ASME CAT TYPE IWTTPE VALVE POS TEST V- - TEST REQ JUS CSV- 'i 1-SV-TV-102 11715-CBM-072A 2 0F 3 C3 ' A0 GLOBE 6.000 2 5 EV C FS C ST C ' W K ' CONDENSER AIR REMOVAL DISCHARG TO CONTAIN* ' MENT, OUTSIDE CONTAIN ISOLATION VALVE i
............................................................. ..... ..... ... ..... ..... '.... ... .... .... i 1-SV TV-103 11715-CBM-072A 2 0F 3 D3 - A0 GLOBE 6.000 2 A. CIV EV C FE C l LT C ,
ST C' VP OC CONDENSER AIR REMOVAL DISCHARGE TO CONTAIN-MENT, OUTSIDE CONTAINMENT ISOLATION VALVE '
.................. .......................................... ..... ..... ... ..... ..... .... ... .... .... j
-t i i
I s e E
.' h h
v b 9 t i e f i e L t f
+
L k e f i
-I i
e _ 'W s b
.~ ,. , - . .. . - - , , .
g, s 1 1 VIRGICIA P0bER CGFANY PAGE: 68 0F 78 , NORTH ANNA UNIT 1 REVIS!0N: 07 : SECOND INSPECTION INTERVAL DATE: 11/D5/93 ! INSERVICE TESTING PROGRAN - VALVE TABLE - !
. s-~s ._ ;
hi NC k Rf ISO REL CS - ALT l VALVE DRAWING SHEET DRWG VALVE VALVE ABME IWV VALVE TEST . TEST REG JUST TEST ; NUMBER - NUMBER WUMBER COOR Tys* SI2E CLASS CAT TYPE TYPE POS V-t CSV - VCN- l
...... .... ..... ..... ..... ... ..... .... ..... ... .... .... i 1 SW-003 11715-CBM-078A 3 0F 4 D~ CHECK VALVE 20.000 3 l C CV C ' 63 i 0 O l
............................................. +
.i UNIT l'"A" SERVICE WA TER PUMP DISCHARGE CHECK ~
VALVE !
}
1-SW-010 11715 CBM-078A 3 0F 4 D6 CHECK VALVE 20.000 3 C CV C 63 -! O 63 UNIT 1 "B" SERVICE WATER PUMP DISCRARGE CHECK VALVE {' I 1 SW 022 11715 CBM-078A 1 0F 4 C3 CHECK VALVE 24.000 3 C CV C 0 D 1
............................................. 1 UNIT 1 AUXILIARY SERVICE WATER PUMP DISCHARGE .
CHECK VALVE f 1 SW-114 11715-CBM-075B 1 0F 4 F8 CHECK VALVE 24.000 3 C CV 0 45 ' f
*A" SERVICE WATR HEADER SUPPLY CHECK VALVE TO !
RECIRC $ PRAY MX UPSTREAM OF CROSS CONNECT 'l
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 1 SW-116 11715-CBM 078B 10F 4 F8 CHECK VALVE 24.000 3 C CV o 45 ;
"B" SERVICE WATR HEADER SUPPLY CHECK VALVE 70 RECIRC SPRAY HX UPSTREAM OF CROSS CONNECT
)
1-SW 120 11715 cam 078s 1 0F 4 E3 CHECK VALVE 16.000 2 C CV O 45
............................................. -l "A" REClRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE -
1-SW-130 11715-CSM-0788 1 0F 4 E4 CHECK VALVE 16.000 2 C CV 0 45 "B" RECIRC SPRAY HEAT EXCKANGER SERVICE WATER SUPPLY CHECK VALVE 1-SW 140 11715 CDM 0788 1 0F 4 E6 CHECK 7ALVE 16.000 2 C CV O 45 I i
"C" RECIRC SPRAY HEAT EXCHANGER SERVICE WATER -
SUPPLY CHECK VALVE ' 1-SW 150 11715 CBM 0788 1 0F 4 ET CHECK VALVE 16.000 2 C CV O 45 l "D" REC 1RC SPRAY HEAT EXCHANGER SERVICE WATER - e SUPPLY CHECK VALVE j
............................................................. ..... ..... ... ..... ..... .... ... .... .... c 1 SW 251 11715 CBM 078C 2 0F 2 88 MANUAL GATE 4.000 3 8 EV C ~
1 SERVICE WATER SUPPLY MAUNAL ISOLATIDN i VALVE ' 1 SW 252 11715 CBM 078C 2 OF 2 B8 CHECK VALVE 4.000 3 C CV 0 39 SERV!CE WATER SUPPLY CHECK VALVE *
............................................................. ..... ..... ... ..... ..... .... ... .... .... s 1 SW-254 11715-CBM 078C 2 0F 2 B8 MANUAL GATE 4.000 3 B EV C t
1 7 SERVICE WATER SUPPLY MAUNAL ISOLAfl0N ' VALVE ' i'
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 1 SW-255 11715-CBM-078C 2 0F 2 88 CHECT VALVE 4.000 3 C CV O 39 r t
h I
i E -I' VIRGIN!A POE R COMPANY PAGE: 69 OF 78
- t. NORTN ANNA UNIT 1 . REVISION: 07 .!
[ SECOND INSPECTIDH INTERVAL LATE: 11/05/93 't
< ~.s- INSERVICE TESTING PROGRAM - VALVE TABLE r .~
a h'--
~
NC-ISO REL CS ALT. I VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REO JUST TEST- .i NUMBER NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE- POS V- CSV- VCN- l s r SERVICE WATER SUPPLY CHECK VALVE ; 1 SW-285 11715-CBM-078C 2 0F 2 B8 MANUAL GATE 4.000 3 B. EV C SERVICE WATER RETURN MAUNAL ISOLATION ! VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... ....- ~l 1-SW-286 11715 CBM-078C 2 0F 2 B8 NANUAL GATE 4.000 3 8 EV C .
............................................. i SERVICE WATER RETURN MAUNAL ISOLATION VALVE 1-SW-364 11715-CBB-04DD 1 0F 3 E7 CHECK VALVE 4.000 NC C CV O
-l SERVICE WATER SUPPLY TO CONTROL ROOM CONDENSER WATER PUMPS i
...........,................................................. ..... ..... ... ..... ..... .... ... .... .... i 1-SW 386 11715 CB8 04DD 10F 3 C7 CHECK VALVE 4.000 NC C CV 0 SERVICE WATER SUPPLY TO CONTROL ROOM CONDENSER WATER PUMPS 1-SW-420 11715-CBs D4DD 1 0F 3 A7 CHECK VALVE 4.000 NC C CV 0
............................................. l t
SERVICE WATER SUPPLY TO CONTROL ROOM
' CONDENSER WATER PUMPS
............................................................. ..... ..... ... ........... .... ... .... .... 5 1-SW 630 11715-CBM-078G 1 or 2 E8 CHECK VALVE 2.000 3 C CV 0 35 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE CIL COOLER CHECK VALVE l 1-SW-631 11715-CSM-078G 1 0F 2 E7 CHECK VALVE 2.000 3 C CV -0 35 -!
SERVICE WATER SUPPLY TO CHARGING PUMP LUBE O!L COOLER CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... t 1-Sw 641 11715-CBM-078G 1 0F 2 E6 CHECK VALVE 2.000 3 C CV 0 35 ,
SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 1 SW-644 11715-CBM-078G ' 10F 2 E7 CHECK VALVE 2.000 3 C CV o 35 SERVICE WATER SUPPLY TO CHARGING PUMP i SEAL COOLER CHECK VALVE
~~ ' ""' "'
i:iG: sit' " "iitis:Eii:5iii "6riisEiiEisitii i i:555i"" E^ ~ ~ ~ "' Ev 6"' ~~ - ii SERVICE WATER SUPPLY TO CHARGING PUMP LUBE DIL COOLER CHECK VALVE i 1-SW-648 11715-CBM 078G 10F 2 E6 CHECK VALVE 2.000 3 C- CV 0 35 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE O!L COOLER CHECK VALVE '
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 1-SW-658 ,11715-CBM-078G 1 0F 2 E5 CHECK VALVE 2.000 3 0 C CV 35 tERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE
(, .................... ........................................ ..... ..... ... ..... ..... .... ... .... .... ( I a
L ! t-VIRGINIA P0bER CCBIPANY PAGE: 70 0F 78 I NORTN ANNA UNIT 1. . REVISION: 07
- p. SECOND INSPECTION INTERVAL DATE: 11/D5/93 'i INSERVICE TESTING PROGRAM . VALVE TABLE l L
p-ISO . REL CS ALT - VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST ' NUMBER NtmBER NUMBER COOR TYPE $1ZE CLASS CAT TYPE TYPE POS V- CSV- YCN. l 1-SW-661 11715-CBM-078G 1 0F 2 E5 CHECK VALVE 2.000 3 C CV o 35 l SERVICE WATER SUPPLY TO CHARGING PUMP SEAL C00LER CHECK VALVE ! I 1-SW-664 11715 CBM-078G 1 OF 2 E4 CHECK VALVE 2.000 3 C CV 0 35 SER(ICE WATER SUPPLY TO CHARGING PUMP LUBE CIL COOLER CHECK VALVE 1-SW-665 11715-CBM-078G 1 OF 2 E4 CHECK VALVE 2.000 3 C CV O 35 I SERVICE WATER SUPPLY TO CHARGING PUMP l LUBE CIL COOLER CHECK VALVE , 1-SW-678 11715-CBM-078G 1 0F'2 A3 MANUAL GATE 4.000 3 8 EV C l 1 SERVICE WATER RETURN MAUNAL ISOLAT!DN VALVE .I
............................................................. ..... ..... ... ..... ..... .... ... .... .... k 1-SW-679 11715-CBM 078G -1 0F 2 B3 MANUAL GATE 4.000 3 B EV C i SERVICE WATER RETURN MAUNAL ISOLATION I VALVE i
............................................................. ..... ..... ... ..... ..... .... ... .... .... h 1-SW-681 11715-CBM 078G 1 of 2 F3 MANUAL GATE 4.000 3 B EV C SERVICE WATER SUPPLY MAUNAL ISOLATION VALVE r
N 1 SW 686 11715-CBM-078G 1 0F 2 E3 CHECK VALVE 2.000 3 C CV O 35 SERVICE WATER SUPPLY To CHARGING PUMP SEAL COOLER CHECK VALVE 1 SW 689 11715 CBM-078G 1 0F 2 E3 CHECK VALVE 2.000 3 C CV 0 35 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... e 1 Sw-694 11715-CBM-078G 1 0F 2 F3 MANUAL GATE 4.000 3 8 EV C !
SERVICE WATER SUSPLT MAUNAL ISOLATION VALVE 1-SW-MOV-101A 11715-CBM-07BA 4 0F 4 B3 M0 BFLY ' 24.000 3 8 EV O 34 ST 0 34 i VP OC 3
"A" SERVICE WATER HEADER SUPPLY ISOLATION To RECIRC SPRAY HEAT EXCHANGERS
............................................................. ..... ..... ... ..... ..... .... ... .... .... .ry 1 SW-MOV 1018 11715 CEN-07BA- 4 0F 4 B3 M0 BFLY 24.000 3 B EV 0- 34 )
ST 0 34 : VP ' OC "A" SERVICE WATER HEADER SUPPLY ISOLATIDN TO I RECIRC SPRAY HEAT EXCKANGERS 'i 1-SW MOV-101C 11715 CBM-078A 4 0F 4 B3 No SFLY 24.D00 3 8 EV 0 34 ST 0 34 VP OC l
)
i
,. , .. ~_. . -. .- - , - . - ~
1l
-l 1
1 VIRGINIA POWER COMPANY PAGE:- '71 OF 78 i NORTH ANNA UNIT 1 REVISION: 07 1
-SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTIN*,P!mGRAM - VALVE TABLE
.i t i
NC . ISO REL CS ALT ! VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST. ! NUMBER NUMBER NUMBER COOR TYPE $!ZE CLASS CAT TYPE TYPE PDS V- CSV- VCN- ?
............................................. +
"B" SERVICE WATER HEADER SUPPLY ISOLATION TO -
RECIRC SPRAY HEAT EXCHANGERS f
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 1-SW-MOV 1010 11715-CBM-078A 4 0F 4 C3 Mo BFLY 24.000 3 B EV O 34 i ST 0 34 '!
W E' l t
"B" SERVICE WATER HEADER SUPPLY ISOLATION TD RECIRC SPRAY HEAT EXCHANGERS 1 SW-MOV-102A 11715-CBM-078B' 1 0F 4 F8 M0 BFLY 24.000 3 E VP OC '. l SERVICE WATER SUPPLY CROSS CONNECTS TO RECIRC I r
SPRAY HEAT EXCHANGERS *
............................................m................ ..... ..... ... ..... ..... .... ... .... .... l 1-SV-MOV 1028 11715-CBM-078B 1 0F 4 F8 Mo BFLY 24.000 3 E VP OC '
............................................. j SERVICE WATER SUPPLY CROSS CONNECTS TO RECIRC SPRAY HEAT EXCHANGERS .;.
1-SW MOV 103A 11715-CBM-0788 1 0F 4 E3 M0 BFLY 16.000 2 A CIV EV C l 4 0 ' LT C ST C 5 0 =I VP OC' I SERVICE WATER SUPPLY TD "A" RECIRC SPRAY HEAT ' EXCHANGER, OUTSIDE CONT ISOLATION VALVE ) 1-SW-MOV-1038 11715-CBM-078B 1 OF 4 E4 MO BFLY 16.000 2 A CIV EV C l 0 LT .C . ST -C ! O W K l SERVICE WATER SUPPLY TO "B" RECIRC SPRAY HEAT ! EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1 SW MOV-103C 11715-CBM 078B 10F 4 E6 MO BFLY '16.000 2 A CIV EV C 0 i LT C ST C 0
- W K ,
SERVICE WATER SUPPLY TO "C" RECIRC SPRAY HEAT i EXCHANGER, OUTSIDE CONT ISOLATION VALVE l 1 SW-MOV 103D 11715 CBM-0788 1 0F 4 E7 M0 BFLY 16.000 2 A CIV EV C I O LT C , ST C ; O 1 VP OC SERVICE WATER SUPPLY TO "D" RECIRC SPRAY HEAT
- EXCHANGER, OUTSIDE CONT ISOLATION VALVE
}
1 SW-MOV 104A 11715-CBM-078B 1 0F 4 C3 Mo BFLY 16.000 2 A CIV ' EV C i 0 LT C m v
VIRGINIA POWER COMPANY PAGE: 72 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE (Av). ISO REL CS NC ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE $!ZE CLASS CAT TYPE TYPE POS V- CSV- VCN-1 SW-MOV-1044 11715-CBM-0780 1 0F 4 C3 M0 BFLY 16.000 2 A CIV ST C 0 VP OC SERVICE WATER RETURN FROM "A" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLAfl0N VALVE 1 SW-MOV-104B 11715 CBM-0788 1 0F 4 C5 M0 BFLY 16.000 2 A CIV EV C 0 LT C ST C 0 VP OC SERVICE WATER RETURN FROM "B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-Mov 104C 11715 CBM-0788 1 OF 4 C6 M0 SFLY 16.000 2 A CIV EV C 0 LT C ST C 0 W K , SERVICE WATER RETURN FRCN "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW Mov-1040 11715-CBM-0788 10F 4 C7 M0 BFLY 16.000 2 A CIV EV C & O
# LT C ST C 0
VP OC SERVICE WATER RETURN FROM "D" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1 SW-MOV-105A 11715-CBM 0TBA 4 0F 4 C3 M0 BFLY 24.000 3 B EV o 34
- ST 0 34 VP OC "B" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC SPRAY HEAT EXCHANGERS 1 $W-MOV-1058 11715-CBM-07BA 4 0F 4 C3 M0 BFLY 24.000 3 B EV O 34 ST 0 34 VP OC "B" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-105C 11715-CBM-07BA 4 0F 4 C3 M0 BFLY 24.000 3 B EV O 34 ST 0 34 VP OC "A" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC SPRAY HEAT EXCHANGERS 1-SV-MOV-105D 11715-CBM-078A 4 OF 4 C3 M0 BFLY 24.000 3 8 EV 0 34 ST 0 34 VP OC
(" (
\
_ . _ _ - _ _ _ _ m
1 i l VIRGINIA POK R COMPANY PAGE: 73 0F 78 l NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 r INSdVICE TESTING PROGRAM - VALVE TABLE b i ( WC .i
. ISO REL CS ALT ;
VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NtMBER NUMBER NUMBER COOR TYPE $1ZE CLASS CAT TYPE TYPE POS - V- CSV- VCN- ,
"A" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-106A 11715-CBM-078B 1 0F 4 88 - M0 BFLY 24.000 3 E VP OC
............................................. l ,
SERVICE WATER RETURN CROSS CONNECTS FROM , RECIRC SPRAY MEAT EXCHANGERS ! 1-SW-MOV-1068 11715-CBM-0788 1 OF 4 A8 M0 BFLY 24.000 3 E VP DC ';
............................................. .l SERVICE WATER ltETURN CROSS CONNECTS FROM RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-108A 11715 CBM-078C 1 0F 2 B3 M0 BFLY 24.000 3 B EV C 0
ST C D [' VP OC "A" SERVICE WATER HEADER SUPPLY !$0LATION TD f COMPONENT COOLING HEAT EXCHANGERS i 1-SW-MOV-108B 11715-CBM 078C 1 0F 2 B3 M0 BFLY 24.000 3 B EV C 0 ST C } O VP OC "A" SERVICE WATER HEADER SUPPLY ISOLATION 70 -I - COMPONENT COOLING HEAT EXCHANGERS . 1 SW-MOV-110A 11715 CBM 0784 4 0F 4 C4 MO BFLY 8.000 3 E VP OC . f SERVICE WATER HEADER SUPPLY To RECIRCULATION ; AIR COOLERS :i 1-SW-MOV-110B 11715-CBM 078A 4 0F 4 C4 MO BFLY 8.000 3 E VP OC f SERVICE WATER HEADER SUPPLY TO RECIRCULATION AIR COOLERS ' 1 $W-MOV-113A 11715 CBM-078A 4 0F 4 87 MO BFLY 10.000 3 E VP OC !
............................................. l SERVICE WATER RETURN ISOLATION FROM FUEL PIT i COOLERS 1-SW-m0V-113B 11715-CBM-078A 4 0F 4 85 MO BFLY 10.000 3 E VP OC
............................................. l SERVICE WATER SUPPLY ISOLATION TO FUEL PIT COOLERS 1 SW MOV-114A 11715-CBM-078A 4 0F 4 C4 MO BFLY 8.000 3 E VP OC
......................... ................... l I
SERVICE WATER HEADER RETURN FROM RECIRCULATION AIR COOLERS 1 SW-MOV 114B 11715-CBM-078A 4 OF 4 C4 'MO BFLY 8.000 3 E VP OC l { SERVICE WATER HEADER RETURN FROM RECIRCULATION AIR COOLERS r
......................e............... ...................... ..... ..... ... ..... ..... .... ... .... .... I i
1 SW-Mov-115A 11715-cam-078A 1 0F 4 E7 M0 BFLY 24.000 3 B EV 0 l ST 0 ' e
1 VIRGINIA POWER COMPANY PAGE: 74 0F 78 NORTH ANEA UNIT 1 REVISION: 07 SECOND INSPECT 10W INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE (- s') g s, ' WC ISO REL CS ALT i VALVE DRAWING SHEET DRWG VALVE VA1VE ASME IWV VALVE TEST TEST REO JUST TEST NUMBER WUMBER NUMBER C00R TYPE SIZE CLA$s CAT TYPE TYPE POS V- CSV- VCN-1-SW-MOV-115A 11715-CBM-07BA 10F 4 E7 MO BFLY 24.000 3 B VP OC SERVICE WATER HEADER SUPPLY ISOLATION VALVE FROM AUXILIARY SERVICE WATER PUMPS 1 SW-MOV-117 11715-CBM-07BA 1 0F 4 C3 M0 BFLY 24.000 3 B EV 0 ST 0 VP OC UNIT 1 AUXILIARY SERVICE WATER PUMP DISCHARGE ISOLATION VALVE 1-SW-MOV-118 11715-CBM-07BA 10F 4 D4 M0 BFLY 24.000 3 E VP DC AUXILIARY SERVICE WATER SUPPLY HEADER CROSS CONNECT VALVE 1-SW-MOV-119 11715 CBM-078A 10F 4 04 M0 BFLY 8.000 3 B EV C ST C VP DC MAKEUP PUMP SUPPLY VALVE 1-SW-MOV-120A 11715-CBM-07BA 4 0F 4 F3 No BFLY 10.000 NC E VP OC AUXILIARY SERVICE WATER RETURN HEADER VALVE
'st 1 SW-MOV 1208 11715-CBM-07BA 4 0F 4 F3 MO BFLY 10.000 NC E VP OC AUXILI ARY SERVICE WATER RETURN HEADER VALVE 1-SW-MOV-121A 11715-CBM 078H 10F 1 B5 M0 BFLY 18.000 3 B EV O ST 0 VP DC SERVICE WATER TO SPRAY ARRAYS STOP VALVE 1-SW-MOV-1218 11715-CBM-078H 1 0F 1 B7 M0 BFLY 18.000 3 8 EV O ST 0 VP OC SERVICE WATER TO SPRAY ARRAYS STOP VALVE 1-SW-MOV-122A 11715-CBM-07DM 1 0F 1 C5 Mo BFLY 18.000 3 B EV 0 ST 0 VP K i SERVICE WATER TO SPRAY ARRAYS STOP VALVE 1-SW-MOV-122B 11715-CBM-078H 1 0F 1 C6 M0 BFLY 18.000 3 8 EV O ST 0 VP OC SERVICE WATER 70 SPRAY ARRAYS STOP VALVE
( 1-SW-MOV-123A 11715-CBM-078M i 0F 1 E4 M0 BFLY 24.000 3 B EV C g ST C 1 I l l 1 i
- VIRGINIA POWER COMPANY. PAGE: 75 0F 78 NORTH ANNA UNIT 1 .
REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93-INSERVICE TESTlWG PROGRAM - VALVE TABLE NC ISO .. REL CS ALT VALVE DRAWING SHEET DR'Ni VALVE i VALVE ASME IW VALVE TEST TEST REQ JUST TEST
'WuMSER NimBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V.
CSV- VCN. 1-SW-MOV 123A 11715-cam-078N 1 0F 1 [4 M0 IFLY 24.000 3 B VP OC SERVICE WATER BYPASS VALVE 1 SW-MOV-1238 11715-CDM-078H 1 0F 1 E8 M0 BFLY 24.000 3 8 EV C ST C i VP OC l SERVICE WATER BYPASS VALVE 1
............................................................. ..... ..... ... ..... ..... .... ... ......... 1 1-SW RV-100A 11715-CSM-078s 1 0F 4 E3 RELIEF VALVE .750 2 C SP 0 "A" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1-SW RV-100s 11715-CsM-0788 1 OF 4 E4 RELIEF VALVE .750 2 C SP 0 "B" RECIRC SPRAY HEAT EXCHANG SERVICE WATER I RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1-SW RV-100C 11715-CBM-0788 1 0F 4 E6 RELIEF VALVE .750 2 C SP O "C" RECIRC SPRAY HEAT EXCHANG SERVICE WATER l RELIEF VALVE, RV DISCHARGE TO CONT SUMP !
............................................................. ..... ..... ... ..... ..... 1
.... ... .... .... i 1-SW-RV.1000 11715 CBM-0788 10F 4 ET RELIEF VALVE .750 2 C SP O l "D" RECIRC SPRAY HEAT EXCHANG SERVICE WATER REllEF VALVE, RV DISCHARGE TO CONT SUMP 1 SW TCV-102A 11715-CBN 078G 1 of 2 C4 Ao CATE 2.000 3 5 EV 0 FS 0 ST -0 SERVICE WATER FROM CHARGING PUMP LUBE DIL COOLER TEMP CONTROL VALVE 1 SV TCV 1028 11715-CBM-078G 1 0F 2 C6 A0 CATE 2.000 3 B EV 0 FS 0 ST. 0 SERVICE WATER FROM CHARGING PUMP LUBE DIL COOLER TEMP CONTROL VALVE 1-SW TCV-102C 11715 CBM 078G 1 0F 2 C8 A0 CATE 2.000 3 8 EV o FS 0 ST 0 SERVICE WATER FROM CHARGING PUMP LUBE CIL COOLER TEMP CONTROL VALVE 2-SW-MOV 2158 11715-CsM 078A 10F 4 E6 M0 BFLY 24.000 3 s EV O i
l- ST 0 VP OC SERVICE WATER HEADER SUPPLY ISOLATION VALVE FROM AUXILIARY SERVICE WATER PUMPS
VIRGINIA POWER COMPANY PACE: 76 0F 78 NORTH ANKA UNIT 1 REVIS10N: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE . rN s ,, ISO REL CS ALT VALVE DRAVING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASE CAT TYPE TYPE POS V- CSV- VCN-1-VG-TV-100A 11715-CBM-090C 1 0F 3 F3 A0 GLOBE 1.500 2 A CIV EV C FS C LT C ST C 54 VP OC VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, OUTSIDE CONT ISOL 1-VG TV-1008 11715-CBM 090C 1 0F 3 D3 A0 GLOBE 1.500 2 A CIV EV C FS C LT C ST C VP OC VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO CAS STRIPPERS, INSIDE CONT ISOL VLV T U4 l 4 i I 1 l l 1 NA
/ i ss
F t VIRGIN!A poler COWANT PAGE: 77 0F 78 l:' NORTH ANNA UNIT 1 REVis!DN: 07' SECOND INSPECTION INTERVAL DATE:'11/05/93 .: INSERVICE TESTING PROGRAN - VALVE TABLE l
~(. !
-( -
!$0- RELCS NC ALTf VALVE DRAWING SHEET DRWG VALVE VALVE ASME iIW VALVE TEST . TEST REQ JUST TEST :
NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV VCN- ,t
...... ....... ...... .... ..... ..... ..... ... ..... .... . . . . - . . . .... .... i 1-VP-012 11715-CaN-072A 2 0F 3 E3 CHECK VALVE 6.000 2 AC CIV CV C . 46 '
'i LT C ;
CONDENSER AIR REMOVAL DISCHARG TO CONTAINMENT INSIDE CONTAIN ISOLATION CHECK VALVE ,
............................................................. ..... ..... ... ..... ..... .... ... .... .... p t
i
+
I I I I i t i t I P 1 9
.h
?
1 5 I P F 4 9 h t I t I
?
f s r - - - . > -
r t ! L m '. 1 t VIRGINIA P0bER COMPANY # AGE: 78 0F 78 -! NORTH ANNA UNIT 1- 'REV!SION: 07. l " SECOND INSPECTION INTERVAL DATE: 11/05/93 ! INSERVICE TESTING PROGRAM - VALVE TABLE 2 b- NC , 150 REL CS
- VALVE NUMBER DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE. TEST TEST TEST REQ JUST ~ Af NUMBER NUMBER COOR TYPE SIZE- CLASS CAT TYPE TYPE Pos V- CSV- VCN- t
...... ....... ...... .... ..... i 1-WT-038 11715-CBM-102A 2 0F 2 FT- CHECK VALVE .750 2 C CV C h
............................................. i.
"A" STEAM GENERATOR CHEMICAL FEED SUPPLT ,
CHECK VALVE
............................................................. ..... ...... ... ..... ..... .... ... .... ....- j 1-WT 050 11715-CBM-102A 2 0F 2 E7 CHECK VALVE .750 2 C CV C "B" STEAM GENERATOR CHEMICAL FEED SUPPLT CHECK VALVE '
1-WT-066 11715 CBM-102A 2 0F 2 D7 CHECK VALVE .750 2 C CV C
............................................. i f
"C" STEAM GENERATOR CHEMICAL FEED SUPPLT CHECK VALVE l t
1-WT-465 13075 CBM 102C 1 0F 1 E6 MANUAL GATE 3.000 2 AE CIV LT .C 6
-i WET LAY UP RETURN FROM "A" STEAM GENERATCR, +
INSIDE CONTAINMENT ISOLATION VALVE i
" ' " " ~ ' ' ' " '" "' "" ^"~
iIhiUd8 ii6I5CB5Ii626'"i0Fi55"'li51LGAi$""'$$6662" " IE' CiV LI"' C
+
WET LAY UP RETURN FROM "A" STEAM GENERATOR, OUTSIDE CONTAINMENT ISOLATION VALVF 1-VT-488 13075-CBM-102C 1 0F 1 D6 MAF.lAL GATE 3.000 2 AE CIV LT C WET LAY UP RETWW PROM *B" SMAM GENERATOR, INSIDE CONTAIN@l1 It0LAT!r VALVE
............................................'J ................. ..... ..... ... ..... ..... .... ... .... ....
1 VT-491 13075-CBM 102C 1 OF 1 D5 MANUAL CATE 3.000 2 AE CIV. LT C WET LAY UP RETURN FROM "B" STEAM GENERATOR, OUTSIDE CONTAINMENT ISOLATION VALVE
- 1-wf-511 13075-CBM-102C 1 0F 1 B6 MANUAL CATE 3.000 2 AE CIV LT C WET LAY UP RETURN FROM "C" STEAM GENERATOR,
.}
INSIDE CONTAINMENT ISOLATION VALVE 1-vi-514
..... ..... ... ..... ..... ..... ... .... .... i 13075 CBM-102C 1 0F 1 B5 MANUAL GATE-3.000 2 AE CIV LT C j WET 1.AY UP RETURN FROM "C" STEAM GENERATOR, ,
OUTSIDE CONTAINMENT ISOLATION VALVE !
............................................................. ..... ..... ... ..... ..... .... ... .... .... i k
i r L r f t l 4 e
.J
I.y. 2.3.5 VALVE INSERVICE' TESTING' PROGRAM RELIEF. REQUESTS-i .
. (./ Relief. requests-identify.those Section XI. Code:
~
requirements considered to be' impractical. The basis-for.the relief request and the alternate testing to be performed is given. O N1PVR7 2-43 Revision.7 November'5,-1993
l RELIEF REQUEST V-1 l
- ( s' :
\_J ^ i Relief Request withdrawn. ;
t RELIEF REQUEST V-2 ; Replaced by Cold Shutdown Justification CSV-1 l t i e i
?
i 3 t i r 9
't, i \" 2-44 i N1PVR7 Revision 7 :
November 5, 1993
RELIEF REQUEST V-3 I. IDENTIFICATION OF COMPONENTS- ) System : Component Cooling Valve (s): 1-CC-84 1-CC-119 1-CC-154 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These check valves must seat upon reversal of flow in order to fulfill their safety functions. The only i exercise method to verify this_ actuation is to perform L a leak rate test /back pressure test. .Since the valves are located inside containment and their systems areL required during power operation,fthey.cannot'be tested: every.three months. The valves.will be exercised only. c .during refueling outages because the small increase'in
. safety gained by testing.during cold shutdown does not justify the burden of draining lines and performing leak; rate tests.
IV. ALTERNATE TESTING Exercise for operability each refueling (not to exceed 24 months) 2-45 N1PVR7 Revision 7 November 5,.1993
I a l l
,, RELIEF REQUEST V-4 , / T j \J' Replaced by Cold Shutdown Justification CSV-5 RELIEF REQUEST V-5 Replaced by Cold Shutdown Justification CSV-6 ~
RELIEF REQUEST V-6 < Replaced by Cold Shutdown Justification CSV-7 RELIEF REQUEST V-7 (
\_ ,f -Replaced by Cold Shutdown Justification CSV-4 RELIEF REQUEST V-8 Replaced by Cold Shutdown Justification CSV-8 aMh 2-46 N1PVR7 Revision 7' '{
November S, 1993
p
,n RELIEF REQUEST V-9 I. IDENTIFICATION OF COMPONENTS System : Chemical & Volume Control Valve (s): 1-CH-MOV-1380 1-CH-MOV-1381 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF Charging flow to the reactor coolant pump seals is required at all times while the pumps are in' operation.
Failure of one of these valves in the closed position-could result in damage to the reactor coolant pump seal, thus placing the plant in an unsafe condition. Also, the valve controllers do not allow for a part-stroke exercise test. The reactor coolant pumps must be secured and reactor coolant pressure must be above 100 psig to perform the exercise tests. IV. ALTERNATE TESTING Exercise every cold shutdown when the reactor coolant pumps are secured and reactor coolant pressure is above 100 psig. h
\/
2-47 N1PVR7 Revision 7 November 5, 1993
s-RELIEF REQUEST V-10
'Q)
I. IDENTIFICATION OF COMPONENTS System : Chemical & Volume control Valve (s): 1-CH-322 1-CH-336 1-CH-380 1-CH-330 1-CH-358 1-CH-402 Class : 1 for 1-CH-330, 336, 358 and 380 2 for 1-CH-322 and 402 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These check valves must seat upon reversal of flow in. order to fulfill their safety functions. The only method to verify this actuation is to perform a leak rate /back pressure test. Since the valves are located inside containment and their systems are required during power operation, they cannot be tested every three months. 1-CH-322 is in the normal charging line g to-the RCS. These lines cannot be drained during short (' cold shutdowns because charging flow is often maintained. 1-CH-336, 358, and 380 are in the RCP seal water supply lines, and 1-CH-402 is in the RCP seal water return line. Seal flow is used during cold shutdown to reduce RCS leakage and-to float the RCP seals. 1-CH-330 is the charging supply to loop fill header, inside containment isolation valve. A local backseat / leak test inside containment is required to verify closure for valve 1-CH-330. The valves will be exercised only during refueling outages because the small increase in safety gained by testing during cold shutdown does not justify the burden of draining lines and performing leak rate tests.
/m 2-48 N1PVR7 Revision 7 November 5, 1993
j RELIEF REQUEST V-10 (Cont.) IV. ALTERNATE TESTING Exercise for operability every refueling (not to exceed 24 months) 1 t
.. I v ,
?
i i N t 8 i 1 2-49 N1PVR7 Revision 7 November 5, 1993
I"'% ~ RELIEF REQUEST V-11
'%)
Replaced by Cold Shutdown Justification CSV-10 RELIEF REQUEST V-12 i Relief Request withdrawn, valve removed from IST Program. RELIEF REQUEST V-13 Relief Request withdrawn. . RELIEF REQUEST V-14 Relief Request withdrawn. RELIEF REQUEST V-15 ' Relief Request withdrawn. i r i E i i j' 2-50 N1PVR7 Revision 7 November 5, 1993 ; 9 9 t'
1 1
.l -
RELIEF REQUEST V ~' I. IDENTIFICATION.0F COMPONENTS L i
' System :
~
Fire Protection- j Valve (s): 1-FP-272 .; Class : 2 II. IMPRACTICAL CODE REQUIREMENTS , i Exercise valve every three months .j
.I ~
III. BASIS FOR RELIEF This check" valve must seat upon reversal'of flow in ' order to fulfill its safety function. .The only method- ;
-to verify this actuation is-to perform a leak rate /back +
pressure test. Since the valve is located inside. .; containment, it cannot be tested every three months.- 1 1-FP-272 is in the containment fire protection' system. . ! Testing this valve will render the fire protection ; system inoperable. It will'be. exercised:only during. t refueling outages because the small increase in safety : J gained by testing during cold shutdown does not justify j the burden of draining the lines and performing a leak q rate test. j IV.' ALTERNATE TESTING 1 Exercise;for operability every refueling (not to exceed , 24 months) j q
~l 4
j q l I
)'
2-51 ' I N1PVR7 ' Revision'7' November 5, 1993 l
~
. -.- . . , , - ~
RELIEF REQUEST V-17
\ .
Replaced by Cold Shutdown Justification CSV-11 RELIEF REQUEST V-18 r i Replaced by Cold Shutdown Justification CSV-12 RELIEF REQUEST V-19 , Relief Request withdrawn. O 4 L I' e
~
2-52 N1PVR7 Revision 7 ; November 5, 1993
1 RELIEF REQUEST V-20 V I. IDENTIFICATION OF COMPONENTS > System : Post Accident Hydrogen Removal Valve (s): 1-HC-14 1-HC-18 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every thres *nn+,hs III. BASIS FOR RELIEF These check valves must seat to provide containment isolation and open to sample hydrogen to fulfill their j safety functions. The only method to verify closure is ( to perform a local leak rate test. Since the valves are located inside containment, they cannot be tested every three months. They will be verified closed only during refueling outages because the small increase in safety gained by testing during cold shutdown does not-g- justify the burden of performing leak rate tests.
'~
To test these valves either partially or full open requires either a locally installed rotameter (inside containment) or significant manipulation of the hydrogen recombiner system. In addition, should a containment pressurization event occur while operating ) the hydrogen recombiners, there is a possibility of i exceeding the design pressure of the recombiner system, ' which is a low pressure system intended for use after the containment depressuizes. They will be verified open at least once ev,ery 18 months during the testing of the hydrogen recombiner system because the small increase in safety gained by testing during normal operation or cold shutdown does-l not justify potential risk of overpressurizing the hydrogen recombiner system, or the added burden of disrupting normal plant operation to manipulate'the recombiner system or of installing the rotameter and performing the test on the more frequent basis. 2-53 N1PVR7 Revision 7 November 5, 1993
RELIEF REQUEST V-20 (Cont.) IV. ALTERNATE TESTING : Exercise to the closed position every refueling (not to exceed 24 months). Exercise to the full open position , at least once every 18 months. , t l i 3 l l i
~
2-54 1 N1PVR7 Revision 7 ! November 5, 1993 l l
1 , I I p_ RELIEF REQUEST V-21 O I. IDENTIFICATION OF COMPONENTS System : Instrument Air ' Valve (s): 1-IA-55 1-IA-149 , Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These check valves must seat upon reversal of flow in : order to fulfill their safety functions. The only method to verify this actuation is to perform a leak rate test. Since the valves are located inside containment, they cannot be tested every three months. ' Valve 1-IA-55 is in the instr:1 ment air supply line to e containment. Testing this valve renders the-instruments and components supplied by instrument. air (g inside containment inoperable. V They will be exercised.only during refueling outages because the smal) increase in safety gained by testing during cold shutdown does not justify the burden of ' performing leak rate tests. IV. ALTERNATE TESTING I Exercise for operability each refueling (not to exceed 24 months) ' 4 O 2-55 t N1PVR7 Revision 7 November 5, 1993 ,
1 l
- )
RELIEF REQUEST V-22 ('~') ! U: Replaced by Cold Shutdown Justification CSV-13 , RELIEF REQUEST V-23 Replaced by Cold Shutdown Justification CSV-14 9
'f RELIEF REQUEST V-24 !
Replaced by Cold Shutdown Justification CSV-15 ! 1 a RELIEF REQUEST V-25 () Relief Request Withdrawn RELIEF REQUEST V-26 Replaced by Cold Shutdown Justification CSV-17 ; P h r 1 I. l .
\## 2-56 .l N1PVR7 Revision 7 ~
November 5, 1993
)
i
i l
.i RELIEF REQUEST V-27 Replaced by Cold-Shutdown Justification CSV-42 l
- i I
U i
?
P r i O ; r-t, i
~j r
i 1 2-57 ' N1PVR7 Revision 7 ; November 5, 1993 e
RELIEF REQUEST V-28 -{~-
\_/
I. IDENTIFICATION OF COMPONENTS System : Reactor Coolant Valve (s): 1-RC-149 Class : 2 ., II. IMPRACTICAL CODE REQUIREMENTS Exercise valve every three months III. BASIS FOR RELIEF This check valve must seat upon reversal of flow in ceder to fulfill its safety function. The only method to verify this actuation is to perform a leak rate test. Since the valve is located inside containment, it cannot be tested every three months.- 1-RC-149 is in the primary grade water to pressurizer relief tank and the #2 seal stand pipes. This line cannot be drained during short cold shutdowns because the PRT is required f-s during normal cold shutdowns. Standpipe level must be '( ) maintained when the RCS is pressurized to control leakage. The valve will be exercised only during refueling outages because the small increase in safety gained by testing during cold shutdown does not justify the burden of draining lines-and performing a leak rate test. IV. ALTERNATE TESTING Exercise for operability each refueling (not to exceed. . 24 months) l Ch 2-58 N1PVR7 Revision 7 November 5, 1993
RELIEF REQUEST V-29 I (~)h Replaced by Cold Shutdown Justification CSV-18 i RELIEF REQUEST V-30 Replaced by Cold Shutdown Justification CSV-19 I RELIEF REQUEST V-31 ; Replaced by Cold Shutdown Justification CSV-20 I RELIEF REQUEST V-32 es t
' k ,) Replaced by Cold Shutdown Justification CSV-21 f
i d t
)
'l i
t
l 2-59 "
N1PVR7 Revision 7 November'5, 1993 ]
't
RELIEF REQUEST V-33
\ __) i I. IDENTIFICATION OF COMPONENTS System : Recirculation Spray Valve (s): 1-RS-123 1-RS-138 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS '
. Exercise valves every three months III. BASIS FOR RELIEF ,
I These check valves must open in order to perform their safety functions. Due to system design, they are not in the Casing Cooling Pump test flowpath. Partial or full stroke exercising these valves with flow would flood the containment sump. IV. ALTERNATE TESTING s, These valves will be grouped tooether and one valve (s_) from this group will be disassen'9 .d and inspected every reactor refueling. A diftwJent valve will be disassembled every reactor refueling, 7 s-2-60
- N1PVR7 Revision 7 November 5, 1993
4 _ RELIEF-REQUEST V-34
- q,) .
Replaced by Cold Shutdown Justification CSV-22 RELIEF REQUEST V-35 ! Replaced by Cold Shutdown Justification CSV-23 t RELIEF REQUEST V-36 ' i Replaced by Cold Shutdown Justification CSV-24 I
?
i i l 4 I i 4 i 0% 2-61 N1PVR7 Revision 7 ' November 5, 1993 I a
4:.. 7_ RELIEF REQUEST V-37 I. IDENTIFICATION OF COMPONENTS System : Safety Injection Valve (s): 1-SI-1 1-SI-16 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF To partial or full flow test these check valves requires taking suction from'the reactor containment-sump which is normally empty. Water would have to be added to the sump. However, the water would pick up. contaminants from the sump. This untreaten water should not be introduced into the system. IV. ALTERNATE TESTING [ These valves'will be grouped together and one valve from this group will be disassembled and inspected every reactor refueling. A different valve will be disassembled every reactor refueling. l
'j I
O 2-62 N1PVR7 Revision 7 .
-l November 5,.1993 cl t
, RELIEF REQUEST V-38 L)
I. IDENTIFICATION OF COMPONENTS System : Safety Injection Valve (s): 1-SI-9 1-SI-18 1-SI-26 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF Due to system design, check valves 1-SI-9 anf 26 are not in the Low Head Safety Injection Pump test flowpaths. They cannot be full or part-stroke tested during power operation because the LHSI pumps cannot overcome reactor coolant system pressure. Valve 1-SI-16 can only be partial stroked every quarter because the quarterly test loop is a mini-flow. loop.
,m
(' During cold shutdown, the reactor coolant system pressure still prevents full-flow testing of the check valves. Partial stroke exercising the valves with flow could cause an overpressurization condition during cold shutdowns. To verify closure of Valves 1-SI-9 and 26 using back flow, the low head safety injection pumps must be tested at design conditions, which can only be done at reactor refueling. By achieving design conditions, adequate seat tightness is verified on the discharge valve to the non-running pump. IV. ALTERNATE TESTING Valves 1-SI-9 and 26 will be exercised to.the full open f and closed position every reactor refueling (not to exceed 24 months). Valve 1-SI-18 will be partial stroke tested every quarter and full flow tested every reactor refueling. jN 1 2-63 N1PVR7 Revision 7 l November 5, 1993 j 1
I
,_ RELIEF REQUEST V-39
- L)
I. IDENTIFICATION OF COMPONENTS System : Safety Injection Valve (s): 1-SI-47 . Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valve every three months
- III. BASIS FOR RELIEF Full or part-stroke exercising this valve during power operation would require charging pump suctions be aligned with the Refueling Water Storage Tank. This alignment would cause a sudden increase in Reactor Coolant System boron inventory. Fell flow for the charging system can only be establi.shed during reactor-refueling when the RCS is depressurized.
To verify valve closure, the refueling water storage tank must be isolated which is a violation of Technical ( ,g/ Specification 3.1.2.1.b during normal operation. The only method to verify closure other than disassembly and inspection is to perform a leak , rate /back pressure test. This valve is also' subject to leak testing, which is performed every reactor-refueling. Verification of closure.will be performed during the leak test every reactor refueling instead of-every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify the burden of draining the lines and performing. ' a leak rate test'. IV. ALTERNATE TESTING Exercise to the partially open position during cold shutdown, exercise to the full open and closed positions every reactor refueling. 2-64 ; N1PVR7 Revision 7 _ ' November 5, 1993 1 Y
,_ RELIEF REQUEST V-40 i -) -
s ' I. IDENTIFICATION OF COMPONENTS System : Safety Injection Valve (s): 1-SI-106 1-SI-110 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS 3 Exercise valva every three months III. BASIS FOR RELIEF These check valves must seat upon reversal of flow in order to fulfill their safety functions. The only method to verify closure i= to perform a leak rate /back ; pressure test. Since the valves are located inside containment, they cannot be tested every three months. These valves will be exercised only during refueling outages because the small increase in safety gained by testing during cold shutdown does not justify the burden of performing a leak rate test.
'~
IV. ALTERNATE TESTING ' 1 Exercise for operability every refueling (not to exceed i 24 months) l 1 i I i l l 1 I i s 2-65 N1PVR7 Revision 7 November _5, 1993 i 5
i i n -l RELIEF REQUEST V-41 'f I. IDENTIFICATION OF COMPONENTS System : Safety Injection ! i Valve (s): 1-SI-83 1-SI-195 l 1-SI-86 1-SI-197' l 1-SI-89 1-SI-199 l Class : 1 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These-Safety Injection check valves must open and close-to fulfill their. safety functions. They cannot be-full 3 or part-stroke exercised to the open position during ' power operation because this would_ thermally shock-the-injection system and cause unnecessary plant transients. Flow cannot be established in the low head injection lines during normal-plant operation. l
) During cold shutdown, the Reactor Coolant' System pressure still prevents full design flow. Also, a :
partial or full stroke test could cause'an i overpressurization of the Reactor Coolant-System and ' force a safety system to function. These valves can only be tested ~to the closed position ; by draining the lines and performing a back seat leak i test. IV. ALTERNATE TESTING - Exercise to the open position.using flow every reactor refueling. Exercise to the closed position 1every d reactor refueling per Technical Specification ' 4.4.6.2.2. . 1 1 I l O' 2-66 N1PVR7 Revision 7 November 5, 1993 1 j
i RELIEF REQUEST V-42 , ln1 -V. I. IDENTIFICATION OF COMPONENTS System : Safety Injection , Valve (s): 1-SI-125 1-SI-144 1-SI-127 1-SI-159 3 1-SI-142 1-SI-161 ' Class : 1 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves for operability every three months , III. BASIS FOR RELIEF i These valves cannot be partial or full flow tested [ during normal operation because the accumulator i pressure _(600 to 650 psig) is below Reactor Coolant ' System pressure and the injection of borated water' would upset the reactor coolant chemistry. During cold shutdown, the RCS pressure may still (~ prevent full flow testing. Also, discharging the
\
q accumulators would challenge the Low Temperature Overpressure protection System. . t A partial flow test is not practical during cold shutdowns. The flow from the accumulator is dependent on the pressure differential between the accumulator and the RCS. The pressure differential cannot be controlled to the fine degree necessary to preclude ; dumping too much water into the pressurizer, thus- ; making it difficult to control pressurizer' level while pressure is being reduced during cooldown. Also, the ! RCS temperature is high during short cold shutdowns. l Dumping cold accumulator water into the RCS could > thermally shock the system. The accumulators must be isolated to verify _ closure
- using back flow for valves 1-SI-127, 144 and 161.. The small increase in safety gained by performing the back seat check valve tests every cold shutdown versus every- i reactor refueling does not justify the added burden of the increased test frequency. ,
\
2-67 N1PVR7 Revision 7 1 November 5, 1993
, RELIEF REQUEST V-42 (Cont.)
The use of non-intrusive monitoring techniques are being evaluated for confirming full disk movement. If non-intrusive techniques can provide a " positive means" for verifying obturator movement, a sampling program will be used as described below due to the burden of applying these techniques in the field. IV. ALTERNATE TESTING . During the first refueling outage where non-intrusive ; techniques are used, all valves in the group will be r tested to verify that the techniques verify valve > obturator movement. During subsequent refueling outages, flow testing will be performed on all valves in the group, but the non-intrusive techniques need be applied only to one valve in each group, on a rotating , basis, unless indications of problems are identified. In this case, all valves in the group will be. subjected to the non-intrusive techniques. Valve 1-SI-125, 127, 142 and 159 will be in one group, and valves 1-SI-144 and 161 will be in the other group. Because valves 1-SI-144 and 161 are downstream from where RHR connects to the SI line, they experience different service g- conditions than the other valves. The test frequency ( is in accordance with Generic Letter 89-04, Position 2. The flow test will consist of discharging the accumulator from an initial pressure that is less than 600 psig. Discharging the accumulator at a lower initial pressure reduces the severity of the transient and the risk of adverse effects on the reactor coolant system. The low pressure test should provide enough flow to force the disk to the full open position. If full disk movement cannot be confirmed using non-intrusive monitoring, these valves will be placed into l two groups and one valve from each group will be disassembled and inspected every other reactor refueling. The justification for the extended disassembly and inspection schedule is available at the station. Valves 1-SI-127, 144 and 161 will be confirmed closed every reactor refueling. 2-68 N1PVR7 Revision 7 November 5, 1993 i
1 I i
,-q RELIEF REQUEST V-43 v
I. IDENTIFICATION OF. COMPONENTS System : Safety Injection Valve (s): 1-SI-79 1-SI-185 1-SI-211 1-SI-90 1-SI-201 1-SI-213 1-SI-95 1-SI-206 1-SI-99 1-SI-207 1-SI-103 1-SI-209 Class : 1 for 1-SI-90, 95, 99, 103, 201, 209, 211 and 213 ; 2 for 1-SI-79, 185, 206, 207 II. IMPRACTICAL CODE REQUIREMFETS Exercise valves every three months III. BASIS FOR RELIEF These Safety Injection check valves must open and close ' to fulfill their safety function. They cannot be full , or part-stroke _ exercised to the open position'during ! I- power operation because this would cause safety injection flow into the Reactor Coolant System which would thermally shock the injection. system and cause unnecessary plant transients. Flow cannot be established in the low head injection lines during normal plant operation. _! During cold shutdown, the Reactor Coolant System j pressure still prevents full design flow. Also, a : partial or full stroke test could cause an overpressurization of the Reactor Coolant System and ' force a safety system to function. . l These valves can only be tested to the closed position ' by a back seat leak test, which_ requires the draining _ , of the lines. J IV. ALTERNATE TESTING -f Exercise to the open position using flow every reactor f refueling. Confirm valve closure by leakage testing. ! every reactor refueling. :
't d 2-69 !
N1PVR7 Revision 7 November 5, 1993
RELIEF REQUEST V-44 , ,9 .Q I. IDENTIFICATION OF COMPONENTS System : Safety Injection Valve (s): 1-SI-190 1-SI-192 1-SI-194 Class : 1 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These Safety Injection check valves must open and close to fulfill their safety function. They cannot be full-or part-stroke exercised to the open position during power operation because this would thermally shock.the injection system and cause unnecessary plant transients. rs During cold shutdown, the Reactor Coolant System .( )
, pressure still prevents full design flow. Also, a partial or full stroke test could cause'an overpressurization of the Reactor Coolant System and force a safety system to function.
The only test methods to individually back seat these. valves are to perform leak tests or to use downstream pressure provided by the low head safety injection pump tests. Either test can only be performed during reactor refueling. IV. ALTERNATE TESTING Exercise to the open position _using flow and to the closed position every reactor refueling. .(" Y- 2-70 i N1PVR7 Revision 7 November 5, 1993 i
q RELIEF REQUEST V-45 (. (_) 4 I. IDENTIFICATION OF COMPONENTS System : Service Water Valve (s): 1-SW-114 1-SW-140 1-SW-116 1-SW-150 1-SW-120 1-SW-130 Class : 2 for 1-SW-120, 130, 140, 150 3 for 1-SW-114, 116 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF Full or part-stroke exercising these valves would flow Service Water into the Recirculation Spray Heat Exchangers. Per FSAR Section 6.2.2.2.5, in order to ; ensure long term reliability of the heat exchangers, following each periodic test the heat exchangers are drained, purged with air and maintained in d f layup. (< y, s) The logistics of this procedure make testing <t cold shutdown impractical considering the small increase in system safety gained from exercising. IV. ALTERNATE TESTING Exercise for operability every refueling (not to exceed 24 four months) l i 5 h i \'- 2-71 N1PVR7 Revision 7 November 5,.1993 l
~
i i
l I
- RELIEF REQUEST V-46 !
73 '\m / , I. IDENTIFICATION OF COMPONENTS j System : Vacuum Priming Valve (s): 1-VP-12 l Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valve every three months III. BASIS FOR RELIEF This check valve must seat upon reversal of flow in order to fulfill its safety function. The only method , to verify this actuation is to perform a leak rate ' test. Since the valve is located inside containment, it cannot be tested every three months. The valve will be exercised during refueling outages because the small increase in safety gained by testing during cold shutdown does not justify performing a leak rate test.
- s. IV. ALTERNATE TESTING >
Exercise for operability each refueling (not to exceed 24 months)
^% !
\ 2-72 N1PVR7 Revision 7 i November 5, 1993 .
_ RELIEF REQUEST V-47 \s' I.-IDENTIFICATION OF COMPONENTS System : CH Valve (s): 1-CH-254 1-CH-267 1-CH-279 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valve every three months III. BASIS FOR RELIEF With present plant design, these valves can only be partial stroke exercised during power operation because the charging pumps cannot achieve design accident flow when pumping into the reactor coolant system at operating pressure. The only available flow path to test these valves is into the reactor coolant system. ; During cold shutdown, exercising these valves.could result in overpressurization of the reactor coolant (-x) .s ,f system and could force a safety system to function. IV. ALTERNATE TESTING Exercise closed every three months and exercise full open every reactor refueling. Valves are partial exercised open during normal operation when the l charging train is in service. ! '-) 2-73 N1PVR7 Revision 7 November 5, 1993
a l i RELIEF REQUEST V-48 Relief Request Withdrawn j RELIEF REQUEST V-49 Relief Request Withdrawn , i i
.i i
5 2-74 N1PVR7 Revision 7 November 5, 1993 ,
, RELIEF REQUEST V-50
-I . IDENTIFICATION OF COMPONENTS System : Containment Atmosphere Cleanup Valve (s): 1-HC-5 Class : NC
.i II. IMPRACTICAL CODE REQUIREMENTS Full-stroke exercise valve for operability III. BASIS FOR RELIEF i This check valve cannot be full flow tested because '
instrumentation is not installed to measure flow or differential pressure. IV. ALTERNATE TESTING , This valve will be disassembled and inspected every reactor refueling and partial flow tested every three months. . t l i I O 2-75 N1PVR7 Revision 7 November 5, 1993
o i RELIEF REQUEST V-51 Relief Request Withdrawn'
~
j RELIEF REQUEST V-52 Relief Request Withdrawn O ! i i i r 2-76 N1PVR7 Revision 7 November 5, 1993 - O
i p, RELIEF REQUEST V-53 ! ) L/- I. IDENTIFICATION OF COMPONENTS System : SI Valve (s): 1-SI-4 1-SI-21 2 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves to the closed position every three months III. BASIS FOR RELIEF Due to the plant configuration, these valves cannot be I verified closed using system flow. The only method to verify closure other than disassembly and inspection is , to perform a back pressure test using a primary grade water supply as the pressure source. To perform the back pressure test on these 3/4" check' valves, each LHSI pump must be removed from service for . s approximately two hours. With one ECCS train out of ! service, the plant must enter the Technical Specification. Action Statement per Paragraph 3.5.2.a and proceed to hot shutdown within 72 hours. Including the preparation for the test which consists of connecting primary grade water to the test volume using supply hoses, the entire test for each valve takes several hours to perform. Also, the seal water line, which may contain contaminated water, must be ' drained and vented. Considering that one train of ECCS must be removed from service for an extended period of time which degrades the safety of the plant, and the difficulty in performing the back pressure test, testing these 3/4" check valves to the closed position every three months is not practical. These valves are also subject to leak testing, which is performed every reactor refueling. A leak test provides more information concerning the condition of the valve' seats then just a back pressure test. When compared to the Code requirements for a backseat te,t performed every cold shutdown, the performance of a leak test every refueling outage is an alternative that provides an acceptable level of quality and safety.. , ( A- 2-77 N1PVR7 Revision 7 November 5, 1993 r
l RELIEF REQUEST V-53 (Cont.) n sj IV. ALTERNATE TESTING i t 4 i Exercise-to the closed position every reactor i refueling. r S r
)
i t 1 I c i i i i i, l i l J N1PVR7 2-78 Revision 7 i i November 5, 1993 i l i I
I r RELIEF REQUEST V-54 %) I. IDENTIFICATION OF COMPONENTS System : Various Valve (s): Valves affected by this request are identified in the Valve Table Class : II. IMPRACTICAL CODE REQUIREMENTS Section XI, IWV-3417(a) " Corrective Action" III. BASIS'FOR RELIEF-These valves have normal stroke times of less than 2 seconds; therefore, they can be considered rapid acting valves. IV. ALTERNATE TESTING Whenever the stroke time of these valves exceeds 2 seconds, IWV-3417(a) will be applied. Notes: .The list of affected valves in the Valve Table
~
may change due to maintenance activities which= affect valve performance. An updated list of rapid acting valves is maintained by the site ISI personnel. 2-79 N1PVR7 Revision 7 November 5, 1993
8 j- . RELIEF REQUEST V-55 , LJ-Replaced by Non-Code Alternative Testing Description VNC-4 L RELIEF REQUEST V-56 Relief Request Withdrawn O 9 1 2-80 N1PVR7 Revision 7 November S, 1993
r RELIEF _ REQUEST;V-57 I. IDENTIFICATION OF COMPONENTS System : Reactor Coolant Valve (s): 1-RC-SOV-101A-1 1-RC-SOV-101A-2 1-RC-SOV-101B-1 1-RC-SOV-101B-2 Class : 1 L II. IMPRACTICAL CODE REQUIREMENTS l Exercise valves every three months III. BASIS FOR RELIEF These valves are the Reactor Vessel Head Vent Valves. . Full or part-stroke exercising these valves'at power-1 could release reactor coolant into tha reactor vessel. refueling cavity. Stroking of these' valves.has been. performed while the Reactor Coolant System.was pressurized. This test revealed that.when-the upstream-
<- valve was stroked, the downstream valve-tended to lift due-to the motive force of the' steam. As long as these valves remain ^ closed under RCS pressure, they are an effective isolation boundary. However, these valves should not be stroked while the Reactor Coolant System is pressurized. These' valves will be exercised during
, each cold shutdown when the Reactor Coolant System is l' depressurized. IV. ALTERNATE TESTING Exercise for operability during cold shutdown when the Reactor coolant System is depressurized (but not more frequently than once per three months). 2-81
' N1PVR7- Revision 7 November 5, 1993
RELIEF REQUEST V-58 i Relief Request Withdrawn
- t i
?
b i 1 1
-l \
i e i i i l 2-82 ' N1PVR7 Revision 7 November 5, 1993 ..! l l
f y- \ RELIEF REQUEST V-59
'm I. IDENTIFICATION OF COMPONENTS System : Various Valve (s): Valves affected by this request are ,
identified by Table B Class : II. IMPRACTICAL CODE REQUIREMENTS . Leakage rate measurements shall be compared with previous measurements and with the permissible leakage rates specified by the plant owner for a specific valve. III. BASIS FOR RELIEF The piping configurations for some containment penetrations do not allow for the individual leakage testing of the containment isolation valves. - IV. ALTERNATE TESTING
-n y ,)
l In cases where containment isolation valves cannot be individually leakage tested, the containment isolation valves are grouped based on the configuration restraints and the groups are assigned permissible , leakages. The groups are subject to the acceptance criteria described in IWV-3427(a). :
?
-P i
'?
i 2-83 ; N1PVR7 Revision 7 l November 5, 1993
j_,- RELIEF REQUEST V-59 (Cont.) ( T TABLE B G ]. VALVES LEAK TESTED IN GROUPS Valve Class System 1-SI-MOV-1867C 2 Safety Injection 1-SI-MOV-1867D 1-CH-402 2 Chemical and Volume 1-CH-MOV-1380 Control 1-SI-MOV-1890C 2 Safety Injection
. 1-SI-MOV-1890D 1-HV-MOV-100B 2 Containment Purge 1-HV-MOV-102 1-HV-MOV-100D 2 Containment Purge 1-HV-MOV-101 t
()) b k 2-84 N1PVR7 Revision 7 i November 5, 1993 i i
+
7 RELIEF REQUEST V-60 (ui ' I. IDENTIFICATION OF COMPONENTS System : Various Valve (s): All Valves Subject to Leakage Testing (Category A Valves) Class : II. IMPRACTICAL CODE REQUIREMENTS . IWV-3427(b) - Specifies corrective actions in addition t to IWV-3427(a) which include increased frequencies for valve sizes of six inches and larger, and repairs or replacements. , III. BASIS FOR RELIEF Most valves that are leak rate tested are tested in the "as found" condition, subject to maintenance and retested in the "as left" condition. The valve maintenance is performed on a routine basis and it effectively resets the leakage to a small amount. Therefore, basing corrective actions on previous test (^)g (,, results or projections serves no useful function. IV. ALTERNATE TESTING None. The requirements of IWV-3427 (b) will not be implemented. O
-s l 2-85 -
N1PVR7 Revision 7 November 5, 1993
/m RELIEF REQUEST V-61 k)s ,
Relief Request Withdrawn ' 4 i 1 1 I l i j l l l l 1 2-86 N1PVR7 Revision 7 November 5, 1993 i l
i
,_ RELIEF REQUEST V-62 Q,I I. IDENTIFICATION OF COMPONENTS System : Component Cooling '
Valve (s): 1-CC-546 1-CC-559 ' 1-CC-572 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF f These check valves must seat upon reversal of flow in order to fulfill their safety functions. The only exercise method to verify this actuation is to perform a leak rate test /back pressure test which would involve isolating the containment air cooling coils. The containment recirculation air cooling coils are required for normal operation to maintain. containment temperature below technical specification limits. ((S) Therefore, these valves cannot be tested every three months. They will be exercised only during refueling outages because the small increase in safety gained by testing during_ cold shutdown does not justify the burden of draining the lines and performing a leak rate test. , IV. ALTERNATE TESTING Exercise for operability every reactor refueling (not to exceed 24 months) 6 O ('l 2-87 N1PVR7 Revision 7 i November 5, 1993
i' RELIEF REQUEST V s3 tN NY I. IDENTIFICATION OF COMPONENTS System : Service Water Valve (s): 1-SW-3 1-SW-10 Class : 3 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months. III. BASIS FOR RELIEF These check valves cannot be full flow tested during normal operation or cold shutdown because the Recirculation Spray Heat Exchangers must be included in the flow path in order for full flow conditions to be. established. As described in Relief Request V-45, introduction of service water to the Recirculation Spray Heat Exchangers is prohibited without subsequently draining the heat exchangers. This r requirement makes testing during normal operation or ( cold shutdowns impractical. Monitoring the discharge pressure gauge of the non-running pump would reveal gross failure of'the , check valve. However, this test may not detect leakage. ' past the valve due to a partially stuck open disk. The service water pumps are deep draft pumps with enough tolerance between the impellers and the pump casing to ; pass significant flow without pressurizing the
- discharge piping to a detectable degree.
The verification of full disk closure using back flow can only be performed when design flow is achieved during the service water pump tests. Verification of . design flow for the running pump demonstrates adequate back seating for the discharge check valves of the non-running pumps. However, the observation of the , non-running pump discharge gauge to detect gross i failure can and should be performed every three months.
.l j
J
~3 Al 2-88 N1PVR7 Revision 7 l November 5, 1993 !
i
k. ia RELIEF REQUEST V-63 (Cont.)
..O IV.' ALTERNATE TESTING These valves will be partial flow tested every three months, . and full flow and' closure tested ever; reactcr .
refueling.- The'non-running pump disc hrge' gauge will~ be observed once-every.three months 1.n detect gross failure of the disk to seat.- O - g~ 2-89 N1PVR7 Revision 7 November 5, 1993
+*
RELIEF REQUEST V-64
\
Replaced by Non-Code Alternative Test Description VNC-2 L
-l r
i
?
e
\
t t r i t i 2-90 N1PVR7 Revision 7 November 5, 1993
f RELIEF REQUEST V-65 w(~,') ^ I. IDENTIFICATION OF COMPONENTS System : Component Cooling Valve (s): 1-CC-111 1-CC-146 1-CC-181 Class : 3 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months. III. BASIS FOR RELIEF These check valves must be locally back pressure tested to verify closure. Since the valves are located inside containment, they cannot be back pressure tested during normal operation. The valves will be tested every refueling outage because the small increase in safety gained by testing during cold shutdown does not-justify the burden of performing a back pressure test. O () IV. ALTERNATE TESTING Exercise to the close position every reactor refueling. I
\-s/ 2_91 N1PVR7 Revision 7 November 5, 1993
, RELIEF REQUEST V-66 v
I. IDENTIFICATION OF COMPONENTS System : Various Valve (s): All power operated valves . Class : II. IMPRACTICAL CODE REQUIREMENTS IWV-3417(a) - specifies corrective action based on
" alert" criteria established from the previous test time.
III. BASIS FOR RELIEF Testing of. power operated valves will be performed to the guidelines presented in ASME/ ANSI OM (Part 10) Sections 4.2.1.8 and 4.2.1.9 as approved for use by Section XI, Article IWV-1000, 1986 Edition with Addenda through 1988. These guidelines represent current industry practices when using stroke times as a means for determining valve degradation and provide improved
<~g methods for determining acceptance criteria.
]
IV. ALTERNATE TESTING Determine stroke time acceptance criteria per ASME/ ANSI OM (Part 10), Section 4.2.1.8 and implement corrective action per Section 4.2.1.9. 4 i
/~'
2-92 N1PVR7 Revision 7 November 5, 1993
-i i
.1 RELIEF REQUEST V-67
(
"Q_3) ,
I. IDENTIFICATION OF COMPONENTS System : Recirculation Spray. Valve (s): 1-RS-18 1-QS-11 1-RS-27 1-QS-19 , Class : 2 , II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months. III. BASIS FOR RELIEF
?
These valves must seat to maintain containment i integrity and open to allow flow to the containment spray headers. Partial or full flow testing these valves would flow water to the spray arrays and : saturate containment. These valves can be mechanically exercised to the open and closed positions. However, ; the valves are located inside containment and require the construction of scaffolding before they can be
.(~g exercised. The small increase in safety gained by !
(',) exercising the valves during cold shutdown does not justify the burden of constructing the scaffolding. These valves are containment isolation valves and are leak tested every reactor refueling. IV. ALTERNATE TESTING These valves will be exercised to the open and closed positions every reactor refueling. - 1
/x
('-) 2-93 N1PVR7 Revision 7 November 5, 1993
, RELIEF REQUEST V-68 [
t i Relief Request Withdrawn ; r
.i f
t k r
-i 1
-k l
s 8: i i
~
2-94 N1PVR7 Revision 7 i November 5, 1993
- -RELIEF REQUEST V-69 (3
'u.) '
I. IDENTIFICATION OF COMPONENTS System : Various Valve (s): All Containment Isolation Valves' Subject to Appendix J Testing - These valves are identified by the ; abbreviation "CIV" under the Isolation Valve Type Column in the Valve Table. Class: II. IMPRACTICAL CODE REQUIREMENTS , IWV-3427 (a) - Valves with leakage rates exceeding the permissible values shall be replaced or repaired. III. BASIS FOR RELIEF , Permissible valve leakage rates are based on each 4 valve's possible contribution'to the' total leakage rate for the containment system. The total containment leakage rate must be less than 0.6La as defined in Technical Specification 3.6.1.2. Exceeding an : f- individual valve's permissible leakage rate may have no (_]j affect on the containment's ability to maintain an overall leakage rate less than 0.6La. Also, there may be plant conditions, or schedule constraints, that preclude repair or replacement of a valve when the individual leakage limit is. exceeded, but the overall leakage limit for the Type C-tested valves is met. In these cases, imposing the Code' requirements of repair or replacement would create an undue burden with no compensating benefit to quality _ and safety when the bases for leakage limits is met for the overall limit necessary to ensure containment integrity. IV. ALTERNATE TESTING In addition to repair or replacement as corrective actions, an evaluation can be performed which demonstrates that even if a valve has exceeded its permis sible leakage rate, the overall containment leakage rate will be maintained below 0.6La until the , next Type C tests. No repair or replacement is (~ 3
)
2-95 N1PVR7 Revision 7 November 5, 1993 _
~._, RELIEF REQUEST V-69 (Cont.) necessary if the evaluation is performed. However, , when the plant conditions are not such that a repair or replacement would adversely impact plant startup and/or continued operations, an evaluation is not appropriate. ' I I 2-96 N1PVR7 Revision 7 I November 5, 1993
'l RELIEF REQUEST V-70 /"T .) ,
i I. IDENTIFICATION OF COMPONENTS System : CompGnent Cooling Valve (s): 1-CC-193 1-CC-198 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves open and closed every three months III. BASIS FOR RELIEF Valves 1-CC-193 and 1-CC-198 are check valves in the component cooling lines to the RHR heat exchangers and ; must close for isolation and open to allow RHR flow. The only exercise method to verify closure is to perform a leak rate test /back pressure test. These lines cannot be drained for back seat testing because the RHR system is needed during cold shutdown to control the RCS temperature. () To establish full flow through Valves 1-CC-193 and 198 for testing to the full open position, increased component cooling flow must be directed through the RHR heat exchangers. During cold shutdown and reactor refueling when fuel is in the vessel, increased flow to - the RHR heat exchangers reduces the volume of the RCS inventory by reducing the RCS temperature. This reduction in volume can be large enough as to cause excessive makeup demands to the RCS. Therefore, the full flow test should be performed during reactor refueling when the vessel is defueled. The vessel is defueled every refueling outage. IV. ALTERNATE TESTING Exercise for closure and full open every reactor refueling (not to exceed 24 months). Partial stroke open every quarter. P J r~ 2-97 ! N1PVR7 Revision 7 I November.5, 1993 j i
I 1 i l I i i RELIEF REQUEST V-71 O ] u Relief Request Withdrawn
)
-l .
-i 1
f i i i r p
.1, 1
l I 1 0 N1PVR7 2-98 Revision 7 I l November 5,.1993 ! 4
RELIEF REQUEST V-72 (D \. f I. IDENTIFICATION OF COMPONENTS System : Chemical & Volume Control System- ' Valve (s): 1-CH-215 > Class : 2
- II. IMPRACTICAL CODE REQUIREMENTS Exercise valve closed every three months III. BASIS FOR RELIEF Due to the plant configuration, this valve cannot be verified closed using flow. The only method to verify closure other than disassembly and inspection is to perform a leak rate /back pressure test.
During normal operation, this valve cannot be isolated to perform a back pressure test because normal letdown and charging flow would be interrupted. Also, if the valve was isolated daring normal operation, the g3 charging pumps would have to be secured. O This valve is also subject to leak testing, which is performed every reactor refueling. Verification of closure will be performed during the leak test every reactor refueling instead of every cold shutdown because the small' increase in safety gained by testing during cold shutdown does not justify the burden of ' performing a leak rate test. IV. ALTERNATE TESTING Exercise to the closed position every reactor refueling. r~ k 3-
./
2-99 N1PVR7 Revision 7 ; November 5, . 1993 j i I
,_ RELIEF REQUEST V-73
-l i u.) I. IDENTIFICATION OF COMPONENTS System : Service Water Valve (s): 1-SW-22 Class : 3 II. IMPRACTICAL CODE REQUIREMENTS Exercise valve open every three months III. BASIS FOR RELIEF Full accident flow cannot be established through this auxiliary service water pump discharge check valve using the normal system lineup because the accident heat loads and corresponding demand on the service water system cannot be duplicated. The accident flow can be established using a lake-to-lake configuration. However, the lake-to-lake lineup could contaminate Lake Anna with chemicals used in treating the service water system. Therefore, the lake-to-lake lineup'is never f m. used. b IV. ALTERNATE TESTING < This valve will be disassembled and inspected on a ' reactor refueling test frequency and partial flow tested every three months. 2-100 N1PVR7 Revision 7 I November 5, 1993 l
RELIEF REQUEST V-74 O -I. IDENTIFICATION OF COMPONENTS System : Residual Heat Removal-Valve (s): 1-RH-7 1-RH-15 Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Exercise valve open every three months III. BASIS FOR RELIEF These RHR pump discharge check valves can only be. partial or full stroke exercised to the open position and verified closed during the testing of RHR pumps 1-RH-P-1A and 1-RH-P-1B. The' low pressure pumps-take. suction'from and discharge to the. reactor coolant-system which operates at 2235 psig. This pressure is- _, well above the operating pressure of.the pumps, therefore, testing during normal operation is not-o possible. During cold shutdowns of short duration or if'the' ' reactor coolant pumps are left running-during the cold shutdown, both trains of RHR may be, required for decay heat removal and to maintain RCS~ temperature. Taking one train of RHR out of service for testing purposes. even for a short period could allow the RCS temperature to increase to the point that the pressurizer: power :j
)
operated relief valve would be challenged. Therefore, these pumps and the. discharge check valves should only be tested during reactor refuelings. j IV. ALTERNATE TESTING l Exercise to the open and closed positions every reactor refueling.. O N1PVR7 2-101 Revision 7' November 5, 1993 5
r 2.3.6 VALVE INSERVICE TESTING PROGRAM COLD SHUTDOWN "N JUSTIFICATIONS (G Section XI, Paragraphs IWV-3410 and IWV-3520 allow for the full-stroke exercising of valves during Cold Shutdown (but not more frequently than every three months) if the valves cannot be exercised during normal operation. Therefore, no request for relief from testing every three months is necessary. However, the code does require that these valves be specifically identified by the owner. The cold shutdown justifications identify and provide the technical basis for valves exercised during cold shutdown but not during normal operation. (~ O (~. 2-102 N1PVR7 Revision 7 November 5, 1993
1 ,-~ COLD SHUTDOWN JUSTIFICATION CSV-1 \_/ I. IDENTIFICATION OF COMPONENTS System : Component Cooling 7 Valve (s): 1-CC-TV-101A, B 1-CC-TV-102A, B, C, D, E, F 1-CC-TV-104A, B, C Class : 2 II. COLD SHUTDOWN JUSTIFICATION Failure of these valves in the closed position would result in a loss of component cooling flow to the Reactor Coolant Pumps thermal barriers, lube oil, stator and/or shroud coolers. The increased level of safety gained from exercising these valves during power operation does not justify the operational consequences should they fail in the closed position. The valve controllers do not allow for a part-stroke exercise test. ,0 k. ( 2-103 N1PVR7 Revision 7 November 5, 1993
COLD SHUTDOWN JUSTIFICATION CSV-2
.,3.
t U Replaced by Relief Request V-62 s i t O. : 9 l l i 2-104 N1PVR7 Revision 7 November S, 1993 1
n. t-
,_ COLD SHUTDOWN JUSTIFICATION CSV-3 \_f I. IDENTIFICATION OF COMPONENTS ,
System : CH Valve (s): 1-CH-84 1-CH-102 i Class : 3 j ( II. COLD SHUTDOWN JUSTIFICATION To achieve full flow through these check valves, a flow path must be established to the reactor coolant system. This test would allow the injection of boric acid into i the reactor coolant system which would upset the boron concentration in the primary plant water. These valves will be partial stroke exercised every quarter. m, O 2-105 N1PVR7 Revision 7 November 5, 1993
.]
l COLD SHUTDOWN JUSTIFICATION CSV-4 ! I. IDENTIFICATION'OF COMPONENTS-l System :- Chemical & Volume Control ~ System Valve (s): 1-CH-MOV-1350 1-CH-238 1-CH-240 > 1-CH-241 ! 1-CH-242
.i class : 2 i II. COLD SHUTDOWN JUSTIFICATION Full or.part-stroke exercising these valvee during' j power operation would cause a. sudden increase in reactor coolant' system boron. inventory by providing-flow from the emergency and alternate boration paths to ._.
charging-pump suctions. Also, the valve controller for 1 1-CH-MOV-1350 does not allow for a'part-stroke exercise
- test. The increased level of. safety-gained from full ,
or part-stroke exercising these valves.during power operation does not justify the-operational consequences. , 9 associated with reactivity transients. Manual valve 1-CH-241 will be str$ked open when.the
~
alternate boration path is established _every cold j shutdown. The increased level of _ safetyf gained by exercising this valve every quarter does~not justify the added burden of performing.a separate test just.for ' the manual valve.
~!
- I l
0 O N1PVR7-2-106 ; t Revision 7 November 5, 1993' ! l
. . - . .. L
, ,em COLD SHUTDOWN JUSTIFICATION CSV-5 , I. IDENTIFICATION OF COMPONENTS System . Chemical & Volume Control System Valve (s): 1-CH-TV-1204A 1-CH-LCV-1460A 1-CH-TV-1204B 1-CH-LCV-1460B Class : 2 II. COLD SHUTDOWN JUSTIFICATION Exercising these valves during power operation ' interrupts letdown flow from the reactor coolant system : (RCS) to the volume control tank. If the va.1ves should fail closed, reactor coolant inventory contrcl would be lost. The pressurizer level control program controls reactor coolant inventory by regulating the operation of the charging flow control valve so that the charging input flow to the RCS and reactor coolant pump seal injection flow into the RCS matches letdown flow. Also, exercising these valves during normal operation s
'~
will interrupt letdown flow through the regenerative heat exchanger. This flow interruption would allow a slug of relatively cool charging water to thermal shock the nozzle connecting the 3" charging line-to the 27" loop 2 cold leg injection line. The valve controllers do not allow for a part stroke exercise test. f 2-107 N1PVR7 Revision 7 ) November 5, 1993 I J
i I _, _ COLD SHUTDOWN JUSTIFICATION CSV-6 o I. IDENTIFICATION OF COMPONENTS System : Chemical & Volume Control System Valve (s): 1-CH-MOV-1115B, C, D, E Class : 2 II. COLD SHUTDOWN JUSTIFICATION Full or part-stroke exercising these-valves during power operation would require that charging pump suction be aligned with the Refueling Water Storage Tank. That alignment would cause a sudden increase in reactor coolant system boron inventory. The increased level of safety gained from full or part-stroke exercising these valves during power operation does not justify the operational consequences of reactivity transients. U L 2 r 2-108 , N1PVR7 Revision 7 ! November 5, 1993
r
,- COLD SHUTDOWN JUSTIFICATION CSV-7 s>
m I. IDENTIFICATION OF COMPONENTS System : Chemical & volume Control System Valve (s): 1-CH-MOV-1289A, B Class : 2 II. COLD SHUTDOWN JUSTIFICATION Varying letdown flow through the Regenerative Heat-Exchanger will cause variations'in charging flow-temperatures. This is not desirable since decreated charging temperatures result in reactivity increases and thermal stress on the piping and heat exchangar. Full or part-stroke' exercising these valves during power operation would isolate the normal charging flow path from the charging pumps to the Reactor Coolant System. .Also, the valve controllers do not allow for a part-stroke exercise test. The small increase in safety gained by exercising these valves every three months does not justify the operational consequences of providing an alternate charging flow path during power operation. 2-109 N1PVR7 Revision 7 November 5, 1993 a.z
- 1
,_, COLD SHUTDOWN JUSTIFICATION CSV-8 '
( .
- i.
Cold Shutdown Justification Withdrawn-COLD SHUTDOWN JUSTIFICATION CSV-9 Replaced by Relief Request V-9 $ 4 COLD SHUTDOWN JUSTIFICATION CSV-10 i Cold Shutdown Justification Withdrawn /~~ i
\~
i 4, i i t 5 I i i i 2-110 , N1PVR7 Revision 7 ! November 5, 1993
]
... i
COLD SHUTDOWN JUSTIFICATION CSV-11 I. IDENTIFICATION OF COMPONENTS System : Feedwater Valve (s): 1-FW-FCV-1478 1-FW-MOV-154A-1-FW-FCV-1479 1-FW-MOV-154B 1-FW-FCV-1488- 1-FW-MOV-154C r 1-FW-FCV-1489 1-FW-FCV-1498 1-FW-FCV-1499 i Class : NC II. COLD SHUTDOWN JUSTIFICATION These valves are in positions r>equired to sustain power operation. Full stroke exercising the valves would result in a reactor trip. The main feedwater regulating valves 1-FW-FCV-1478, 1488 and 1498 will be partial stroke exercised every three months. rs The bypass valves 1-FW-FCV-1479, 1489 and 1499 are used i only during plant startup. During this startup period, their safety function is-to close. During normal operation, these valves remain closed and, thus are passive in the closed position. Therefore, the bypass valves do not need to be partial stroke' tested every-three months. The valve controllers for the motor operated valves 1-FW-MOV-154A, B and C do not allow for a part stroke exercise test. 2-111 N1PVR7 Revision 7 November 5, 1993
s, COLD SHUTDOWN JUSTIFICATION CSV-12 7 I. IDENTIFICATION OF COMPONENTS System : Feedwater Valve (s): 1-FW-47 1-FW-79 1-FW-111 .l l Class : 2 II. COLD SHUTDOWN JUSTIFICATION i l i These check valves must seat upon reversal of flow to I fulfill their safety functions. The only method to verify this actuation is to perform a back pressure test. Since the valves must be open to sustain power operation, they cannot be tested every three months. 9
;.j i .;,
t
.;.};.1}li 2-112 N1PVR7 Revision 7 November 5, 1993
COLD SHUTDOWN JUSTIFICATION CSV-13 U I. IDENTIFICATION OF COMPONENTS System : Main Steam Valve (s): 1-MS-NRV-101A, B, C Class : 2 II. COLD SHUTDOWN JUSTIFICATION Valve Descriotion The main steam non-return valves (NRVs) at North Anna _ Power Station are located in the main steam valve house and are a globe type stop check design. The valves measure approximately 16 feet from the bottom of the valve body to the top of the hand wheel and weigh almost 24,000 lbs. The disk is welded to a hollow piston and the whole assembly is free to move about 25 vertical inches within the valve body cylinder. The disk measures 25.5 inches across and the disk and piston assembly weighs approximately 1,200 lbs. When the main steam system is not inservice, a motor ,e operator is used to run the valve stem down onto the disk to secure the main steam line. The valves open to allow steam to the turbine. For accident conditions, the non-return valves in conjunction with the main steam trip valves prevent the blowdown of more than or.e steam generator for any break location, even if one valve fails to close. For example, for a break upstream of the trip valve in one line, the closure of either the non-return valve in that line or the trip valves in the other lines prevents the blowdown of the other steam generators. Method of Testina The piping downstream of each non-return valve leads ~to a common distribution manifold and cannot be isolated.. Therefore, performing a back seat test using flow is not practical. Also, valve disassembly and inspection are not practical alternatives due to the size of the valve and the weight of the disk. t
\
2-113 N1PVR7 Revision 7 November 5, 1993
,, COLD SHUTDOWN JUSTIFICATION CSV-13 (Cont.)
_(u/ ) However, an alternative exists to verify that the disk moved to the valve seat during reactor coolant system (RCS) cooldown. When the RCS temperature is between 350 9? and 195 9P during the cooldown process, the main steam trip valves are closed. Then the main steam non-return valves close in response to the loss of steam flow. After the main steam trip valve is closed, the Valve Operation Test and Evaluation System (VOTES) can be used to determine the position of the disk of the NRV.. After the main steam flow is stopped, the non-return valve stem is run down onto the disk after the disk returns to the seat. A change in tdum running force within the normal travel of the stem indicates a-resistance to stem movement (i.e., a stuck disk). Verifying that the stem travels to the seated disk with nominal changes in the running force indicates that the disk is on the seat. The test requires that the. cooldown process be delayed between one to two hours to setup the instrumentation and to perform the test on-each of three valves. Virginia Power owns the VOTES equipment and has personnel trained to use the g-) equipment and interpret the results. V The VOTES consists of a force sensor mounted on the valve, valve switch current probes and a motor current probe. The force sensor detects the strain experienced by the yoke as the valve stem moves. Strain is ' converted to force. The valve switch probes determine the status of the torque and limit switches, and the open and closed bypass switches in the motor operator control circuit over the course of stem travel.' To-attach the switch and motor current probes, the power to tr a valve must be interrupted. Testina Frecuency Discussion Full stroke or part stroke exercising of these valves during power operation would result in a turbine and reactor trip. Plant cooldown procedures require that the NRV stem be run down onto the disk to isolate the main steam system ' after main steam flow is stopped. The VOTES testing must be performed when the NRVs are initially closed during the cooldown to accurately assess the piston- ! disk assembly's as-found position. As indicated above, j () L 2-114 j l N1PVR7 Revision 7 ; Novembcr 5, 1993 l l 2
-l
/\ COLD SHUTDOWN JUSTIFICATION CSV-13 (Cont.) 'tY the VOTES test will delay the cooldown process from between one to two hours. Some cold shutdown. outages are forced outages that result from exceeding a Technical Specification-limit such as unidentified RCS leakage. The emphasis in a forced outage cooldown is to reach cold suutdown as rapidly as possible and to mitigate the cause of the forced outage. Stopping this process to perform the VOTES test would complicate the operators task to secure the plant and may reduce plant > safety. How;ver, during planned cold shutdowns where there are no mitigating circumstances, there is adequate time to notify the test personnel, carry the equipment into the field and perform the test. There is no evidenca in the valve history that a valve has stuck in the partial open position. The piston-disk assembly is not attached to any other internal part, the 1,200 lb piston-disk assembly is maintained parallel within the valve body cylinder and the main steam system is very clean. Consequently, there no mechanism to prevent the disk from dropping from the full open position to the valve seat. e- The VOTES test described above will be performed on ( ,s) each main steam non-return valve during the cooldown process going into each planned cold shutdown. This test will not be performed more often then once every three months. O 2-115 N1PVR7 Revision 7 November 5, 1993
i
; 'h COLD SHUTDOWN JUSTIFICATION CSV-14 ,
I. IDENTIFICATION OF COMPONENTS , System : Main Steam I i
-Valve (s):. 1-MS-TV-109-
'l Class : 2 l II. COLD SHUTDOWN JUSTIFICATION i
Full or part-stroke exercising this valve during-power { operation.would cause undesirable pressure transients- " in the High Pressure Secondary-Drains System. 'Also, , the: valve controller does not allow for a1part-stroke ! exerciso test.- The increased level ~of safety gained ; from exercising this_ valve during power. operation does : not justify the operational consequences of these~ - pressure variations. j
-i
'r
[
.3 L
U
't
}
i _i
'i
.l O 2-116 i i
l
'N1PVR7 Revision 7 j
-November _5, 1993 i
...,..4
, . ._, .i . .
i l l
. - COLD SHUTDOWN JUSTIFICATION CSV-15 <
J . Cold Shutdown Justification withdrawn i c
.;r O t k
e 4 t i O.- 2-117 ' N1PVR7 Revision 7 .; November 5, 1993 .j i
4
,_ . COLD SHUTDOWN JUSTIFICATION CSV-16 N_/
I. IDENTIFICATION OF COMPONENTS System : Main Steam Valve (s): 1-MS-TV-101A, B, C Class : 2 II. COLD SHUTDOWN JUSTIFICATION These valves are in positions required to sustain power operation. Full or part-stroke exercising these valves during normal operation would result in a reactor trip and safety injection. Also, the. valve controllers do not allow for a part-stroke exercise test. These valves are tested during cold shutdown (heatup or cooldown). t 2-118 r N1PVR7 Revision 7 ; November 5,.1993
l t COLD SHUTDOWN' JUSTIFICATION CSV-17 Replaced by Relief Request V-67 ; 1 w O i 1 J
-I 3
i l l l 1 1 0 N1PVR7 2-119 i Revision 7 ! November 5, 1993 l
COLD SHUTDOWN JUSTIFICATION CSV-18 -l,_,)
%J IDENTIFICATION OF COMPONENTS I.
System : Residual Heat Removal Valve (s): 1-RH-MOV-1700 1-RH-MOV-1701 1-RH-MOV-1720A, B ' Class : 1 II. COLD SHUTDOWN JUSTIFICATION These valves. isolate the Residual Heat Removal System, which is a 600 lb class system, from the Reactor Coolant System during power operation. These valves are normally closed and cannot be opened when Reactor-Coolant System pressure is above 418 psig due.to system . interlocks. Therefore, the valves cannot be full or ' part-stroke exercised during power operation. Also, ! the valve controllers do not allow for a part-stroke exercise test. O
)
i 2-120 ; N1PVR7 Revision 7 l November 5, 1993
.i COLD SHUTDOWN JUSTIFICATION CSV-19 Replaced by Relief Request V-74 I
s F j 2-121 N1PVR7 Revision 7 November 5,.: 1993
, COLD SHUTDOWN JUSTIFICATION CSV-20
( I. IDENTIFICATION OF COMPONENTS System : Residual Heat Removal Valve (s): 1-RH-FCV-1605 1-RH-HCV-1758 Class : 2 II. COLD SHUTDOWN JUSTIFICATION The position of these valves is determined by demand controllers and must be observed' locally to verify proper valve operation. These valves are located inside containment, therefore, they cannot be full or part-stroke exercised every three months. O i 2-122 N1PVR7 Revision 7. November 5, 1993
i l COLD SHUTDOWN JUSTIFICATION CSV-21 ' .-(.- v Replaced by Relief Request V-67' J COLD SHUTDOWN JUSTIFICATION CSV-22 : Cold Shutdown Justification Withdrawn e 1 1 t .h ! i i t
,m-(\s) ~ 2-123 ;
N1PVR7 Revision 7 i i November 5, 1993. i l l
1 I l i COLD SHUTDOWN JUSTIFICATION CSV-23 .(,g , $) I. IDENTIFICATION OF COMPONENTS System : Safety Injection Valve (s): 1-SI-MOV-1836 1-SI-MOV-1869A, B 1-SI-MOV-1890A, B Class : 2 II. COLD SHUTDOWN JUSTIFICATION These valves provide isolation for alternate safety injection paths to the Reactor Coolant System. As required by Technical Specifications 3/4.5.2.a, they are closed with power removed from the valve actuators during Modes 1, 2, and 3. Full or part-stroke exercising these valves during power operation would be in violation of Technical Specifications. Also, the valve controllers do not allow for a part-stroke exercise test. 2-124 N1PVR7 Revision 7 November 5, 1993
0, N
.. COLD SHUTDOWN JUSTIFICATION CSV-24 i I.-IDENTIFICATION OF COMPONENTS System : Safety Injection ~!
Valve (s): 1-SI-MOV-1865A,.B, C j Class : 2 II. COLD SHUTDOWN ~ JUSTIFICATION- , i The Accumulator Discharge Isolation Valves are in their ! safety positions.with power removed from the valve- t actuators during Modes 1, 2, and 3, and when'the i ' pressurizer pressure is greater.than 1000 psig as . specified in Technical Specifications 3/4.5.1. These , valves could be called upon to open in Mode 3 when the pressurizer is less than 1000 psig. Full or.part-stroke exercising during power operation would be in violation of Technical Specifications and decrease , plant safety. Also, the valve controllers do not allow ]* for a part-stroke exercise test. j l t N l 1 I i 2-125 N1PVR7 Revision 7- _ l November 5, 1993
.- u
- 4
~
, _ . , COLD SHUTDOWN JUSTIFICATION CSV-25
\ ,
(' m,/ ' Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-26 I Cold Shutdown Justification Withdrawn i COLD SHUTDOWN JUSTIFICATION CSV-27 - Cold Shutdown Justification Withdrawn f COLD SHUTDOWN JUSTIFICATION CSV-28 t ( ) Replaced by Relief Request V-70 2-126 N1PVR7 Revision 7 l November 5, 1993 11
o E , l I
,e- COLD SHUTDOWN JUSTIFICATION CSV-29 \_)
I. IDENTIFICATION OF COMPONENTS System : Auxiliary Peedwater Valve (s): 1-FW-61 1-FW-95 1-FW-63 1-FN-125 Class : 3 II. COLD SHUTDOWN JUSTIFICATION These valves cannot be partial or full flow tested during normal operation because the dedicated auxiliary feedwater flow paths would have to be isolated. These dedicated flow paths sre required by the Technical Specifications for normal operation. O I k 2-127 N1PVR7 Revision 7 November 5, 1993'
i l
.l l
COLD SHUTDOWN JUSTIFICATION CSV-30 ( I. IDENTIFICATION OF COMPONENTS : System : Instrument Air , Valve (s): 1-IA-944 1-IA-963 1-IA-948 1-IA-967 1-IA-952 1-IA-971 ! 1-IA-959 1-IA-975 Class : NC II. COLD SHUTDOWN JUSTIFICATION Check valves 1-IA-944, 948 and 952 isolate the normal instrument air supply from the backup bottled air supply for the main steam pressure control valves 1-MS-PCV-101A, B and C. Valves 1-IA-959, 963 and 971 isolate the normal instrument air supply to the , auxiliary feedwater valves 1-FW-HCV-100A,.B and C. ' Valves 1-IA-967 and 975 isolate the normal instrument air supply to the auxiliary feedwater valves 1-FW-PCV-159A and B. To back seat test check valves 1-IA-944, 948 and 952, O, _ the instrument air system must be isolated to all three main steam pressure control valves and the lines vented. To back seat test check valves 1-IA-959, 963, 967, 971 and 975, the instrument air system must be isolated to all five auxiliary feedwater valves and the lines vented. Isolating this many valves that are important to safety during normal operation would ; degrade the safety of the plant and be disruptive to , plant operation. ' i
'l i
l l i [- I[s 2-128 N1PVR7 Revision 7 i November 5, 1993
L
,, . COLD SHUTDOWN JUSTIFICATION CSV-31 I. IDENTIFICATION OF COMPONENTS System : Auxiliary Feedwater Valve (s): 1-FW-HCV-100A 1-FW-HCV-100B 1-FW-HCV-100C Class : 3 II. COLD SHUTDOWN JUSTIFICATION Stroke time is dependent on how quickly the operator can turn the knob.to the potentiometer which controls valve position. Several turns of the knob are necessary to full stroke the valve. Isolating instrument air and electrical power to the valve during-the performance of the fail safe test is the only valid method for full stroke exercising and stroke timing these valves. The fail safe test cannot be performed during normal operation because these valves must be available in the event of a reactor trip.
C 2-129 N1PVR7 Revision 7 November 5, 1993
~
COLD SHUTDOWN JUSTIFICATION CSV k I. IDENTIFICATION'OF COMPONENTS System : Auxiliary'Feedwater Valve (s): 1-FW-PCV-159A 1-FW-PCV-159B Class : 3 II. COLD SHUTDOWN JUSTIFICATION During normal operation,_these valves controluauxiliary feedwater header pressure and cannot be full stroked. Isolating-instrument air and electrical' power'to the valve during the_ performance of the fail safe test is.- the only valid method for full stroke exercising;and stroke timing these valves. The fail safe _ test cannot be performed during normal operation because these. valves must be-in service. O 1
- i. '
2-130
'N1PVR7 Revision 7 November 5,.1993 1.'s____ _ -
k , ~ . COLD SHUTDOWN JUSTIFICATION CSV-33 (,/ I. IDENTIFICATION OF COMPONENTS System : Main Steam Valve (s): 1-MS-TV-113A 1-MS-TV-113B 1-MS-TV-113C _ Class : 2 II. COLD SHUTDOWN JUSTIFICATION During normal operation, steam condenses in.the bypass lines because these valves are normally closed. Exercising these valves during normal operation would introduce a water slug to the turbine. i l O N1PVR7 2-131 l Re;2sion 7 ! November 5, 1993 l I l l
i
, COLD SHUTDOWN JUSTIFICATION CSV-34 i \
LJ I. IDENTIFICATION OF COMPONENTS System : Service Water Valve (s): 1-SW-MOV-101A 1-SW-MOV-105A 1-SW-MOV-101B 1-SW-MOV-105B 1-SW-MOV-101C 1-SW-MOV-105C , 1-SW-MOV-101D 1-SW-MOV-105D Class : 3
. II. COLD SHUTDOWN JUSTIFICATION Dur y 'ormal operation, the lines between the Service Wat r 71y and return header isolation valves given above and the recirculation heat exchanger isolation valves (1-SW-MOV-103A, B, C and D, and 1-SW-MOV-104A, B, C and D) are maintained dry to ensure that no service water enters the heat exchangers. Stroking the header isolation valves described above would introduce ,
service water into the lines. These lines would have to be' drained utter each test. .O LJ i (Gx-)' 2-132 N1PVR7 Revision 7 November 5, 1993
COLD SHUTDOWN JUSTIFICATION CSV-35 V I. IDENTIFICATION OF COMPONENTS System : Service Water Valve (s): 1-SW-630, 631 1-SW-641, 644 1-SW-647, 648 1-SW-658, 661 1-SW-664, 665 1-SW-686, 689 Class : 3 II. COLD SHUTDOWN JUSTIFICATION These check valves must open to allow service water to the charging pump lube oil coolers, seal coolers and gear box coolers. Flow through these valves can be detected by differential pressure instrumentation across the coolers. However, full flow conditions would have to be measured by using temporary ultrasonic flow instrumentation. The ultrasonic flow transducers and their Lounting carriages must be installed and the transducers referenced to a no flow condition before
) each test. After each test, the equipment must be removed from the field and decontaminated if necessary.
This process must be performed six times for the 12 valves listed above. Therefore, use of the.ultracanic flow instrumentation is very labor intensive and not practical fer quarterly testing. These valves will be partial stroke exercised every quarter. I\- 2-133 N1PVR7 Revision 7 November 5, 1993
'r COLD SHUTDOWN JUSTIFICATION CSV-36
'.t,.')
LJ Cold shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-37 Cold Shutdown Justification Withdrawn n 2-134 N1PVR7 Revision 7 November 5, 1993
l COLD SHUTDOWN JUSTIFICATION CSV-38 l
)
kJ ' I. IDENTIFICATION OF COMPONENTS System : Chemical and volume control ; Valve (s): 1-CH-252 . 1-CH-264 i 1-CH-277 Class : 2 l II. COLD SHUTDOWN JUSTIFICATION , These check valves must open to allow charging pump recirculation. There is no permanently mounted instrumentation to measure full flow on the recirculation line. Therefore, full flow conditions will have to be measured by using temporary ultrasonic flow instrumentation. The ultrasor.ic flow transducers and their mounting carriages must be installed and the transducers referenced to a no flow condition before each test. After each test, the equipment must be removed from the field and decontaminated if necessary. This process must be performed three times for the f5 three valves listed above. Therefore, use of the (~,) ultrasonic flow instrumentation is very labor intensive > and not practical for quarterly testing. Test experience has shown that the discharge pressure drop is undetectable when flow through the .
?
recirculation line is established in conjunction with normal charging. Therefore, quarterly partial flow-testing is not verifiable. l 1 j l l 1 6 l 2-135 N1PVR7 Revision 7 November 5, 1993 l
e
, COLD SHUTDOWN JUSTIFICATION CSV-39 . N~j r I. IDENTIFICATION OF COMPONENTS System : Service Water Valve (s): 1-SW-252 1-SW-255 ;
Class : 3 II. COLD SHUTDOWN JUSTIFICATION , These check valves must open to allow service water to the charging pump coolers. Downstream instrumentation can be used to verify the presence of flow in the valves. However, individually full flow testing each check valve requires securing the parallel service ' water supply header to the charging pump seal coolers. To ensure an uninterrupted redundant service water supply to the charging pump seal water coolers, these check valves will be full flow tested during cold shutdown but not more frequently then once every three months. The valves will be partial flow tested every three months. O r i O 2-136 N1PVR7 Revision 7 November 5, Ir13
I COLD SHUTDOWN JUSTIFICATION CSV-40 ' %./ I. IDENTIFICATION OF COMPONENTS System. : Auxiliary Feedwater Valve (s): 1-FW-062 1-FW-149 1-FW-064 1-FW-155 1-FW-094 1-FW-166 1-FW-096- 1-FW-172 1-FW-126 1-FW-184 1-FW-128 1-FW-190. Class : 3 II. COLD SHUTDOWN JUSTIFICATION Each auxiliary feedwater pump is required by Technical Specification 3.7.1.2 to be aligned to an individual steam generator in modes 1, 2 or 3. The manual valves-listed above_are positioned to provide these dedicated : flow paths. During a main feed line break.or steam line break, no credit is taken for operator' action during tha first 30 minutes. When manual operatcr action is taken the faulted steam generator is isolated f3 and manual flow control is required. The auxiliary (j feedwater pumps are realigned using the. manual valves. Therefore, the manual valves must be known to be operable. However, exercising the valves during normal operation would violate the technical specifications and reduce plant safety without a corresponding increase in component reliability. These valves ~ remain in their aligned positions during normal operation and are not subject to wear. Exercising the valves during each cold shutdown is adequate to demonstrate that these valves can be manipulated in case the auxiliary feedwater paths need to be changed. ,O %.j 2-137 N1PVR7 Revision 7 November 5, 1993 ,
\
,. COLD SHUTDOWN JUSTIFICATION CSV-41 ;
N_) I. IDENTIFICATION OF COMPONENTS System : Auxiliary Feedwater Valve (s): 1-FW-145 1-FW-180-1-FW-162 1-FW-227 Class : 3 II. COLD SHUTDOWN JUSTIFICATION These normally locked closed manual valves are opened-as required by the abnormal operating procedures to provide service water to the auxiliary feedwater pumps in the event of an accident where all normal auxiliary feedwater pump supplies have been exhausted. Opening these valves every three months to fulfill quarterly testing requirements would accelerate the. buildup of sludge in the supply lines from the service water system. The supply lines are flushed once every 18 months to reduce the buildup of sludge and to identify if there is any accumulation of asiatic clams or.shell debris in the lines. Because these manual valves f-' remain in the closed position during normal operation ( and are not subject to wear, exercising these valves on a cold shutdown test frequency (but not more frequently ' then once every three months), is. adequate to demonstrate that the valves can be opened in the case where service water is required as a supply for the auxiliary feedwater pumps. 1 [ 2-138 N1PVR7 Revision 7 November 5, 1993 l m-
l E l ry COLD SHUTDOWN JUSTIFICATION CSV-42 L-] ' i I. IDENTIFICATION OF COMPONENTS System : Reactor Coolant Valve (s): 1-RC-PCV-1455C 1-RC-PCV-1456 ; Class : 1 II. COLD SHUTDOWN JUSTIFICATION Full or part-stroke exercising these valves during power operations would cause high differential pressure across the PCV Block Valves. Although these valves are designed to accommodate this differential pressure, cycling would eventually degrade the block valves '; seating capability, thus decreasing plant safety. Also, the valve controllers do not allow for a part- ' stroke exercise test. These valves will be full-stroke i exercised during cold shutdowns. O 1 1 I i l Il f' L i
'A~ i 2-139 N1PVR7 Revision 7 November 5, 1993 1
-l
.. 2.3.7 ALTERNATIVE TESTING FOR NON-CODE VALVES p)
\m According to the minutes of public meeting on Generic Letter 89-04, " Paragraph (g) of 10CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed intervice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a
' request for relief' to be submitted to the staff.
Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3. North Anna Power Station has elected to include certain 3 non-Code components in the ASME IST program. Where the (j Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability. The alternate testing is described in this section. There may be other deviations from Code provisions that are not described in this section. For these cases, documentation is available at the plant site. As indicated in the minutes of public meeting on Generic Letter 89-04, a ' request for relief' need not be submitted for non-Code components. Therefore, the alternative tests described in this section are not
' requests for relief' but are provided for information. -l \~> 2-140 N1PVR7 Revision 7 d November 5, 1993 i
NON-CODE ALTERNATIVE TESTING VNC-1
,~ d i
I. IDENTIFICATION OF COMPONENTS System : Service Air ' Valve (s): 1-GN-225 1-IA-2152 1-GN-451 1-IA-2153 1-IA-2154 1-IA-2155 Class : NC II. IMPRACTICAL CODE REQUIREMENTS Exercise valves to the closed position every three months Exercise each valve individually III. BASIS FOR ALTERNATE TESTING Due to the plant configuration,'these valves cannot be-verified closed using flow. The only method to verify closure other than : i'- disassembly and inspection is to perform a local leak rate /back pressure test. To perform the leak rate /back pressure test, the normal instrument air and nitrogen 1 supplies to the PORVs must be isolated. The PORVs are required to be operable during normal operation. Also, ' these valves are located inside containment and are inaccessible during normal operation. These valves are also subject to leak testing, which is-performed every reactor refueling. Verification of closure will be performed during the leak test every-reactor refueling instead of every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify _the burden of performing a back pressure test. Valves 1-IA-2152 and 2153 are in series and valves 1-IA-2154 and 2155 are in series. There are no vents in between the two sets of valves; therefore, these valves , cannot be individually back pressure tested or leak' i tested. O k-- 2-141 N1PVR7 Revision 7 November 5, 1993
i
~s NON-CODE ALTERNATIVE TESTING VNC-1 (Cont.)
( q,/ )' IV. ALTERNATE TESTING Exercise to the closed position every reactor refueling. Valves 1-IA-2152 and 2153, and valves 1-IA-2154 and 2155 will be back pressure / leak tested in groups. If the group of valves fails the test, both valves in the group will be subject to repair or replacement. The leak test for valves 1-IA-2152, 2153, 2154'and 2155, and 1-GN-225 and 451 will consist of recording ' the nitrogen bottle pressure, waiting a given period of time and then recording the bottle pressure again. -The results will be compared to appropriate acceptance criteria. v s
/~-
N-2-142 N1PVR7 Revision 7 November 5, 1993
p NON-CODE ALTERNATIVE TESTING VNC-2 t >- (,/ I. IDENTIFICATION OF COMPONENTS System : Instrument Air Valve (s): 1-IA-925 1-IA-926 1-IA-934 1-IA-935 Class : NC II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months. Back seat test each valve individually. III. BASIS FOR ALTERNATE TESTING Back seating these valves requires that the lines + upstream cf the valves be vented. The 1-IA-925 and 926 valves are in series with no vent valves in between, as are 1-IA-934 and 935. Therefore, there is no way to individually leak test or back seat these valves. ' ( 'h IV. ALTERNATE TESTING These valves will be leak /back seat tested in groups. I The leak test will consist of pressurizing the volume upstream of the two valves in series and-venting ' downstream of the valves. Then the upstream test t volume will be isolated. If a given differential pressure across the two valves in series can be maintained for a predetermined period of time, the test will be satisfactory. The actual leak rate will not be measured. If the group fails the leak /back seat tests, ' both valves in the group will be disassembled,. inspected and repaired if necessary. l V 2-143 N1PVR7 Revision 7 November 5, 1993
1 i i NON-CODE ALTERNATIVE TESTING VNC-3 N sl ' i I. IDENTIFICATION OF COMPONENTS System : Instrument Air ' Valve (s): 1-IA-944 1-IA-963 1-IA-948 1-IA-967 1-IA-952 1-IA-971 1-IA-959 1-IA-975 Class : NC II. IMPRACTICAL CODE REQUIREMENTS Determine leakage for Category A valves III. BASIS FOR ALTERNATE TESTING Check valves 1-IA-944, 948 and 952 isolate the normal instrument air supply from the backup bottled air supply for the main steam pressure control valves 1-MS-PCV-101A, B and C. Valves 1-IA-959, 963 and 971 isolate the normal instrument air supply.to the auxiliary feedwater valves 1-FW-HCV-100A, B and C. g3 Valves 1-IA-967 and 975 isolate the normal instrument (_j air supply to the auxiliary feedwater valves 1-FW-PCV-159A and B. The purpose of the bottled air supplies is to ensure , that the main steam PCVs and t2ua auxiliary' feedwater. valves can be remotely operated following an accident. The bottled air supplies must be able to cycle the main valves a specified number of times over a predetermined ocriod in order to meet their design requirements. In lieu of a leakage test for the isolation check valves given.above, the main valves will be cycled the required number of times over the required period with the normal air supply isolated'and vented. This test provides verification that the isolation check valves are leak tight enough to allow the main valves to perform their safety functions. D V 2-144 N1PVR7 Revision 7 November 5, 1993 -
e: 1 NON-CODE ALTERNATIVE TESTING VNC-3 (Cont.) k_ IV. ALTERNATE TESTING In lieu of a leakage test for the isolation check. valves given above, the main valves will be cycled the required number of times over the required period as defined by their design requirements with the normal air supply isolated and vented. 1 O
/~T
(,_s) i 2-145 N1PVR7 Revision 7 November 5, 1993
i i NON-CODE ALTERNATIVE TESTING VNC-4
.<'~T ,
N~s] b I. IDENTIFICATION'OF COMPONENTS ' system : Emergency Diesel Air Services ; Valve (s): 1-EG-SOV-600HA 1-EG-SOV-600JA 1-EB-15 1-EG-SOV-601HA 1-EG-SOV-607JA- 1-EB-34 , 1-EG-SOV-600HB 1-EG-SOV-600JB 1-EB-65 1-EB-84 Class : NC i II. IMPRACTICAL CODE' REQUIREMENTS Section XI, IWV-3410 " Valve Exercising Test" j t III. BASIS FOR ALTERNATE TESTING The solenoid valves have actuation times considerably I under a second and there is no visual reference on the solenoid valve to determine when it has stroked. Therefore, the stroke time cannot be measured. The solenoid valves are activated every month to start the diesels. Both air banks are discharged when performing the monthly test. After the test, the air bank pressure is recorded to verify a decrease in pressure, which confirms that the air banks discharged properly. Flow through check valves 1-EB-15, 34, 65 and 84 cannot be measured because instrumentation is not installed. However, failure of these valves to promptly stroke to ' their proper positions will affect the-starting. time of the diesel when the diesel is started from-just one sir ' bank. A diesel alarm will activate if the starting time exceeds start failure requirements.' Verification that the diesel starts without an alarm constitutes a full atroke test for the check valves. The test to start-the diesels on one air bank is performed on'.a rotating basis once every six months. Based-on this rotation, each check valve will be full flow tested once every 18 months. i O k. 2-146 N1PVR7 Revision 7 November 5, 1993
i
,-~. NON-CODE ALTERNATIVE TESTING VNC-4 (Cont.)
L.) ; IV. ALTERNATE TESTING ' The solenoid valve will be full stroke exercised and check valves will be partial stroke exercised monthly by observing that the valves perform their intended function (if the diesel starts, the air bank pressures decrease and the air supply manifold maintains its integrity, then the solenoid and check valves.were stroked successfully). Every 18 months, the check valves will be full stroke tested by discharging only one air bank to start the- , diesel. The failure of either the solenoid or check valves to open will promptly give a diesel alarm. Further investigation would identify problems with the ; operability of these valves. The die sl start time will be recorded and compared to a maximum allowable start time during this test.
\- 2-147 N1PVR7 Revision 7 November 5, 1993 i.
2.4 . REPORTING OF INSERVICE TEST RESULTS ('% \s,) 2.4.1 PUMP INSERVICE' PROGRAM 1 Records of Pump Inservice Test Results will be maintained in accordance with the intent of Article IWP-6000. Files will be established for each pump and will include:' '
- 1) Pump identification by equipment number and manufacturer.
- 2) The record of test will include: ,
- a. date of test,
- b. measured and observed quantities,
- c. comparison of allowable ranges of test values and analysis of deviations,
- d. requirements of corrective actions and, l
- e. signature of person or persons responsible for conducting and analyzing the test.
- 3) The inservice test plans are contained in the O applicable surveillance test. procedure.
- 4) Summaries of corrective action will'be indexed by maintenance report number, etc.-
The Pump Inservice Test Program, associated
- surveillance test procedures and results.will be kept at North Anna-Power Station. They will be available for audit by Authorized Nuclear Inspectors and the NRC.
2.4.2 VALVE INSERVICE PROGRAM Records of Valve Inservice Test Results will be , maintained in accordance with the' intent of Article IWV-6000. Files will be established for each valve and will include:
- 1) Valve identification by equipment number, size, valve type, actuator type, ASME class, IWV category, drawing number and coordinate, testing requirements and frequencies.
- 2) The record of test will include:
O. 2-148 , N1PVR7 Revision 7 November 5, 1993
1 l 1
- a. date of test, Ams / b. measured and observe quantities where i applicable,
- c. comparisons with allowable ranges of test values and analysis of deviations,
- d. requirements for corrective action and,
- e. signature of the person or persons responsible for conducting and analyzing the test.
The Valve Inservice Test Program, associated surveillance test procedures and results will be.kept at North Anna Power Station. They will be available for audit by the Authorized Nuclear Inspectors and the NRC. O P t [ I L 2-149 N1PVR7 Revision 7 November 5, 1993
I 2.5 QUALITY ASSURANCE PROGRAM V The Pump and Valve Inservice Test. Program activities will be conducted in accordance with the Nuclear Operations Department Standards Manual and Technical Specifications for North Anna Power Station.
.y k
t ~ 2-150 N1PVR7 Revision 7 November 5, 1993
y, ce
?
, 't i t !l 1 i ti 1
s
!? . , 4
[ M_ p > c a-3 E_aw-
._ -=; r. ==~tm 0f 2 f3hl - - ~r a '
,ag#y.w cir; % @e Lw !!!$ .- m! 4 . u
--- - - ~ ;
.o i h, ,
w - l
, ,f ---
] VIRGINIA ELECTRIC AND.' [?
{
- POWER COMPANY [
a l' . NORTII ANNA UNIT 2 7 , JI I T@W ' INSERVICE TESTING PROGR P SECOND INSPECTION INTERVAL ~ I j,$ DEC.14,1990 - DEC.14, 2000
)gh, . - REVISION ,-
- 7. --
.. ._ , . . . . d t .. j .i n
9 Q. -
,t 1 !
I
.f .
f .a }: s
?!
ri 1
' - k, 3 .,
2 -
' l, 4 -
b
.,s,., ,
..,. _,....m..m----- -
fn _]
~
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 [j - IST PROGRAM, REVISION 7 l
\s / ,
The following summary describes the changes from Revision 6 to Revision 7 of the North Anna Unit 2 Inservice Testing (IST) ' Program Plan. In addition to describing the changes to the program, the summary indicates the approval mechanism for each relief request given in Sections 2.2.6 and 2.3.5. The changes in i the IST Program result from a review of the scope of the program - and from the NRC Safety Evaluation Report (SER) for Revision 6, ! dated September 17, 1993. i 2.2.5 PUMP INSERVICE TESTING TABLE - UNIT 2 PUMP HUMBEB COMMENT / PROGRAM CHANGE 2-CC-P-1A Program change: Added Relief Request P-16. 2-CC-P-1B 2-CH-P-1A 2-CH-P-1B 2-CH-P-1C () 1-CH-P-2C 1-CH-P-2D Relief' Request P-13, which deals with instrument accuracy, no longer applies to j these pumps. Program change: Deleted reference to Relief Request P-13. Added Relief Request P-16. i 2-EG-P-2HA These non-Code diesel fuel oil transfer pumps 2-EG-P-2HB are positive displacement pumps. The ASME OM 2-EG-P-2JA Code-1987, Part 6, with Addenda to OMa-1988, 2-EG-P-2JB Table 2, requires that only discharge pressure need be measured for positive displacement pumps. Per the requirements of OM Part 6, discharge pressure instead of inlet and differential pressure will be measured. Non-Code Alternative Testing description PNC-1 was added to document this i fact. Relief Request P-4 is being withdrawn l and the contents of P-4 moved to PNC-1. l Program change: Non-Code Alternative Testing description PNC-1 was added and l Relief Request P-4 is being withdrawn. j 1 k_
4
SUMMARY
OF CHANGES TO NORTH' ANNA UNIT 2 (~ IST PROGRAM, REVISION 7 \_,. 2-FW-P-2 Relief Request P-13, which deals with 2-FW-P-3A instrument accuracy, no longer applies to ' 2-FW-P-3B these pumps. Also, a full flow test loop was ! installed that allows these pumps to be , tested to the requirements of Section XI on a i quarterly basis. Program change: Deleted reference to Relief Request P-13 and deleted Relief Request P-14. Added Relief Request P-16.
- 2-QS-P-1A Relief Request P-13, which deals with 2-QS-P-1B instrument accuracy, no longer applies to 2-RH-P-1A these pumps.
2-RH-P-1B Program change: Deleted reference to Relief Request P-13. Added Relief Request P-16. 2-RS-P-1A Withdrew Relief Request P-6. 2-RS-P-1B t'\ , ( ) 2-RS-P-2A Withdrew Relief Request P-7. 2-RS-P-2B 2-RS-P-3A The system resistar. e description was changed 2-RS-P-3B from FIXED to VAR. ;telief Request P-13 no longer applies to these pumps. Program change: Deleted reference to Relief Request P-13 and replaced FIXED with VAR. Added Relief Request P-16. 2-SI-P-1A The lube oil description was changed from N/A 2-SI-P-1B to Q. Relief Request'P-13 no longer applies to these pumps. Program change: Deleted reference to Relief Request P-13 and added lube oil check. 2-SW-P-1A Relief Request P-13 for flow instrumentation I 2-SW-P-1B no longer applies to these pumps. ' 2-SW-P-4 Program change: Deleted reference to flow l instrumentation in Relief Request P-13. 2 i 1 1
{f
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2
,C - IST PROGRAM, REVISION 7 .(
i 2-HV-P-20A The ASME classification was upgraded from 2-HV-P-20B non-Class to Class 3. 2-HV-P-20C + 2-HV-P-22A Program change: Replaced non-Class with ! 2-HV-P-22B Class 3. Added Relief Request P-16.
- 2-HV-P-22C
-l
?
O 1 l l l l
; i 7
l l O 3
1 -( ) - q_j
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 2.2.6 PUMP INSERVICE TESTING PROGRAM RELIEF REQUESTS The following summarizes the changes to relief requests { since Revision 6. It also contains a description of the { approval mechanism for each relief request. That is, the summary indicates whether the approval is:
- 1) through a position in Generic Letter 89-04,
- 2) through a previously issued NRC SER or
- 3) obtained using a relief request that will need approval by the NRC. Relief requ marked with an asterisk ,ests requiring NRC approval are UNIT 2 '
RELIEF > EED_UIS_T COMMENT / STATUS P-1 No change. This relief request was approved by Q the NRC in the SER for Revision 6 dated September (_) 17, 1993. P-2 and 3 These relief request numbers are no longer active. P-4 This relief reauest is beina withdrawn. The basis j for relief was moved to Alternative Testing i description PNC-1 and revised to enhance clarity. P-5* The test frequency was changed from cold shutdown to reactor refueling. Also, the basis for relief was expanded to describe the conditions where the residual heat removal system is needed during cold shutdowns. The Revision 6 version of P-5 was approved by the NRC in the SER for Revision 6 dated September 17, 1993. ' P-6 This relief reauest is beina withdrawn. According to the SER for Revision 6 dated September 17, 1993, the testing described for the inside recirculation spray pumps in Revision 6 is in i accordance with the requirements of OM Part 6. Therefore, relief is not necessary as long as all related requirements in OM Part 6 are met. 4 .
-i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 [) D IST PROGRAM, REVISION 7 P-7 This relief reauest is beine withdrawn. According .i to the SER for Revision 6 dated September 17, the , testing described for the outside recirculation ' spray pumps in Revision 6 is in accordance with , the requirements of OM Part 6. Therefore, relief is not necessary as long as all related requirements in OM Part 6 are met. P-8 This relief request number is no longer active. P-9* The discussion dealing with static inlet pressure was expanded to explain why just using the discharge pressure for these deep draft pumps is a more conservative application of the Section XI ; acceptance criteria then using differential pressure and to describe the burden associated with recording the static suction pressure. This revision is in response to concerns raised by the NRC in their SER dated September 17, 1993. P-10* The discussion dealing with static inlet pressure
-~
was expanded to explain why just using the (). discharge pressure for these deep draft pumps is_a more conservative application of the Section XI acceptance criteria then using differential pressure and to describe the burden associated with recording the static suction pressure. This revision is in response to concerns raised by the NRC in their SER dated September 17, 1993. P-11 This relief request number is no longer active. P-12 Reference to the third degree polynomial was deleted from the alternate testing section. Also, reference to establishing the pump curve using a . minimum of six points was replaced by reference to ! using a minimum of five points. The use of five points to describe the pump curve was taken from guidance provided by the NRC in their SER for the Surry Units 1 and 2 IST Programs which was ' received in March of 1993. The Revision 6 version of P-12 was approved by'the NRC in their SER dated September 17, 1993. The approval was granted as long as the calculated curve bounds the operational band in which the pump operates. ' O 5 t
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 (]
'\_/
IST PROGRAM, REVISION 7 P-13* Reference to the accuracy for the calculated differential pressure was deleted and the number , of instruments that exceed the Section XI accuracy requirements was reduced. Also, the flow accuracy > for the charging pumps (2-CH-P-1A, B and C) was changed from 2.5% to 2.34%, and the discharge pressure accuracies for the service water pumps (2-SW-P-1A, 1B and 4) were changed from 2.69% to 3.18% for pumps 1A and 1B, and to 2.61% for pump
- 4. The Revision 6 version of P-13 was approved-by the NRC in their SER dated September 17, 1993. .
P-14 This relief reauest is beine withdrawn. Full flow test loops were installed for the auxiliary feedwater pumps. Therefore, this relief request is no longer necessary. P-15' Reference to running the boric acid transfer pumps on the recirculation flow path for three minutes was deleted. This relief request was submitted to the NRC by letter dated October 17, 1990. Except for the duration of the run period prior to g~ measuring the test quantities, the alternate testing complies with Generic Letter 89-04, Attachment 1, Position 9. The Revision 6 version of P-15 was approved by the NRC in their SER dated September 17, 1993. P-16* This relief request is being submitted to address the situation of having to measure the static inlet pressure for a pump that is in operation prior to the test. . ww t \~ 6
a Li ! l i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 i ; f') IST PROGRAM, REVISION 7 L/ 2.2.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS Starting with Revision 7 to the IST Program, non-Code pumps that are included in the IST Program but are not tested to the provisions of the Code will be discussed in this new section. Although a request for relief is not' required.for non-Code components, the reasons for why the code provisions are not met and the alternative testing ? description should be documented with the IST Program. ; NON-CODE ALTERNATIVE - TESTING , DESCRIPTION COMMENT PNC-1 The diesel fuel oil transfer pumps are positive displacement pumps. One characteristic of ' positive displacement pumps is that the discharge pressure is independent of inlet pressure. Therefore, to determine pump degradation, only ; 7-sg discharge pressure need be measured. Also, the : s j basis from Relief Request P-4 was moved into PNC-
- 1. This basis deals with the Code required five ,
minute run time before the test quantities are measured. I j l (Y Q s f y i l l
o t
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 f') V IST PROGRAM, REVISION 7 : 1 2.3.4 VALVE INSERVICE TESTING TABLE Valves marked with an
- are being added to the IST Program. :
UNIT 1 VALVE NUMBER COMMENT / PROGRAM CHANGE 2-AS-FCV-200A These normally open valves are on the 2-AS-FCV-200B auxiliary steam supply line to the condenser air ejectors. They automatically close in the event of a containment isolation signal. ; Although they have an automatic trip function, closing of these. valves has no specific function with respect to accident recovery or mitigation. Program change: The valves were removed from the IST Program. i O) (_ 2-CA-026 This non-Code control room bottled air supply ! discharge check valve is adequately tested as part of the control room bottled air supply test. Because the valve is non-Code and ' adequately tested outside the IST Program, this valve is being removed from the IST
'rogram.
Program change: The valve was removed from the IST Program. 2-CC-008 These valves open to provide flowpaths for 2-CC-025 constant vents from the CC pump casings to the surge tank to ensure the pumps are i maintained full of water. Venting of these > pumps is not considered to be critical to e their performance. Backflow through this line to an idle pump is insignificant due to - the small size of the line. Program change: The valves were removed from j the IST Program. 8 1
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 3 (~ IST PROGRAM, REVISION 7 ' I 2-CC-RV-202 This valve protects the non-regenerative heat ~ exchangers from over-pressure in the event an isolated heat exchanger is subjected to heating. Since this valve is a thermal , relief valve and performs no specific safety function, testing is not required. . Program change: The valve was removed from " the IST Progrea. , 2-CC-RV-203 This valve protects the seal water heat exchangers from over-pressure in the event an isolated heat exchanger is subjected to heating. Since this valve is a thermal relief valve and performs no specific safety function, testing is not required. , Program change: The valve was removed from the IST Program. 2-CC-RV-226 This relief valve protects the excess letdown heat exchanger (shell side) from over-pressure as a result of thermal expansion when the heat. exchanger is isolated. It is ' unlikely that CC to the heat exchanger would l be isolated and even if it were, damage to this non-safety-related heat exchanger would be inconsequential. Note.that protection of the header is provided by 2-CC-RV-228A and B. Program change: The vel.ve was removed from the IST Program. i ( - CH-13 3
- During normal operation this check valve i opens to provide flow from.the VCT's to the
{ charging pump suction headers. Under ; accident conditions when the upstream motor- { operated valves are closed, it provides i recirculation pathways from the charging pump 1 minimum flow lines to the charging pump suction headers. This valve must close to-prevent contaminated water from entering'the VCT after recirculation mode transfer. b 9
-l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 (]- IST PROGRAM, REVISION 7 \/ m Program change:- The valve was added to the IST Program to be tested to the full open position every three months and closure and leak tested every reactor refueling. Refer to Relief Request V-73. l r This primary grade water supply to make-up 2-CH-140 blender manual valve is outside the ISI class boundaries'and performs no safety function. ' Credit for isolation of this line during emergency boration is attributed to the downstream air-operated valve. Program change: The valve was removed from the IST Program. ; 2-CH-176 These charging pump discharge reciiculation ; 2-CH-191 line check valves open to pro ~ide flowpaths 2-CH-206 from the charging pumps' discharge to the seal water return lines in order to protect (x-')g _ the charging pumps from overheating during low or minimal flow operations. Since the , pump suction headers are' common and recirculation is not secured except when~in i recirculation cooling when the individual . pump recirculation valves are closed, t backflow through an idic pump via these lines has no safety consequence. Thus, no closure test is required for these valves. Program change: The closure test was deleted. 2-CH-FCV-211,A* This normally-closed (fail closed) valve , opens ao required to supply water to the VCT or charging pump suctions in order to control the reactor coolant system boric acid ) concentration during normal boration (dilution) and plant shutdown. During manual j emergency boration it must be closed'to prevent diversion of boric acid into the primary water system. ! Program change: The valve was added to the ; i 1 10 i
i.
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 L (D IST PROGRAM, REVISION 7
\m l IST Program to be tested to the closed position every three months and to have its remote position indicator verified every 24 months.
2-CH-FCV-2160 This normally-closed (administratively controlled) valve remains ~ closed during plant operation and accident recovery to ensure safety injection flow from the charging pumps is directed to the safety injection headers and to provide containment isolation. Thus it is categorized as passive and no exercising is required. Program change: A remote position
' indication verification test was added to be performed every 24 months and the closure test was deleted.
r-s 2-CH-HCV-2303A These normally open valves may be closed at
'q 2-CH-HCV-2303B operator discretion during an accident to 2-CH-HCV-2303C isolate an individual reactor coolant pump in the event of a pump. seal failure. The abnormal operating procedure requires closure within 5 minutes of discovering a seal leak.
Under accident conditions this function is redundant with that of containment isolation valves 2-CH-MOV-2380 and 2381 which isolate all three seals. Thus, these valves are not required to be in the Program. Program change: The valves were removed from the IST Program. 2-CH-LCV-2460A* These normally open letdown isolation valves 2-CH-LCV-2460B' are closed in the event of an accident where continued letdown flow.is undesirable and automatically close on low pressurizer level to retain reactor water inventory. This would be important in the case of a small-break LOCA where containment isolation does not occur. Also, in the event of an incident that results in a containment isolation
,- signal, these valves must close to isolate 11
5 j'
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 L IST PROGRAM,-REVISION 7 La_) . downstream low-pressure ~ piping and to prevent lifting of downstream relief valve 2-CH-RV- ' 2203. They fail closed on loss of electric i power or air header pressure. Program change: The valves were added to the' IST Program to be tested to the closed -! position every cold shutdown and to.have . ; their remote position' indicators verified every 24 months. Refer to Cold Shutdown Justification CSV-5. I 2-CH-MOV-2115B After recirculation mode transfer, there 2-CH-MOV-2115D !
. exists a path for contaminated sump water '!
through the piping from the suction of the ; charging pumps to the RWST. These valves ; isolate this piping and should be leak l tested. ' Program change: Leakage testing was added. 2-CH-MOV-2267A* These normally-open valves remain open~ I 2-CH-MOV-2269A* following an accident.to provide flowpaths 2-CH-MOV-2270A* from the RWST and LHSI Train "B" to each of > the charging pumps during an accident and for. ; post-accident recirculation. Thus,' they are: ' considered to be passive. Program change: The valves were added to the ,; IST Program to have their remote position
~ indicators verified every 24 months.
2-CH-MOV-2267B* .These normally-open valves would remain open 2-CH-MOV-2269B* following-an accident to provide flowpaths 2-CH-MOV-2270B' from the "A" LHSI Pumps to each of the' charging pumps during post-accident recirculation. Thus, they are considered to-be. passive. Program change: The valves were added to the IST Program to have their remote position' indicators verified every 24 months. 12
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7
}
2-CH-MOV-2373 This valve is normally open to provide a flowpath from the charging pumps common discharge to the seal water return line in order to protect the charging pumps from > overheating during low or minimal flow operations. It may be closed by-the operator to maximize flow to the RCS during safety injection; however, this action is not desirable since it affects all three pumps and the individual pump minimum flow isolation valves (2-MOV-2275A-C) provide adequate means of isolation. Since the valve need not be repositioned during an accident it is considered to be passive. Program change: The exercise test was deleted. 2-CH-RV-2209 This valve provides over-pressure protection for the low-pressure letdown piping and components downstream of the non-regenerative ( heat exchangers but does not have any specific function with respect to plant shutdown or accident mitigation. Program change: The valve was removed from the IST Program. 2-CH-RV-2257 This valve protects the volume control tanks and associated components from over-pressure. It performs no specific safety function related to accident mitigation. During and following an accident, the VCT is typically isolated from the charging pump suction headers. Therefore, this valve need not be included in the test program. Program change: The valve'was removed from the IST Program. 2-CH-RV-2382A This valve protects the seal water leakoff piping from over-pressure during an accident when the associated piping segment is isolated and may be subjected to heating or J 13 l 1
)
I
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 /3 IST PROGRAM, REVISION 7 O seal failure. The portion of piping being protected is not critical. Thus, testing of this valve per the IST Program is not required. Program change: The valve was removed from the IST Program. 2-CV-08* These valves must open to allow the removal 2-CV-15' of hydrogen from the containment atmosphere following an accident. Program change: The valves were added to the IST Program to be tested to the open position every three months. 2-CV-TV-200 This valve is a normally closed (administratively controlled) air-operated valve opened only during operation of thn containment hogger at plant startup. Thts it ((s,) is considered to be passive. Program change: The exercise test was deleted. 2-EB-015 Program change: Relief Request V-56 is being 2-EB-034 withdrawn and replaced by Non-Code 2-EB-061 Alternative Testing Description VNC-4. 2-EB-078 2-EG-SOV-700HA 2-EG-SOV-701HA 2-EG-SOV-700HB 2-EG-SOV-700JA 2-EG-SOV-707JA 2-EG-SOV-700JB 2-EB-041 These non-Code valves open to provide 2-EB-051 flowpaths from the air dryers to the EDG 2-EB-068 starting air. receivers and close to prevent 2-EB-085 blowdown of the receivers through the compressors when they shut down. Since receiver pressures are monitored and alarmed such that at " time zero" in the accident it
.~
can be assumed they are charged to the 14
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 '/D IST PROGRAM, REVISION 7 V required minimum pressure at the onset of an accident and the capacity of the tanks allows for the minimum of three engine starts required, compressor operation is not required. Thus, exercising these valves to > the open position is likewise not required (Air compressors are not safety-related). However, these valves must close and remain leak tight to preserve the air inventory in-the receivers. Therefore, each of these , valves should be leak tested to verify its capability to perform its safety function. Program change: Leakage testing was added to be performed very reactor refueling. 2-EG-260 Flow instrumentation has been installed on 2-EG-272 the diesel fuel oil transfer pump discharge 2-EG-284 piping. Therefore, these valves can be full 2-EG-289 flow tested every three months. /~ Program change: Relief Request V-50 is being (,3 ) withdrawn. Also, the valve number prefix was changed from "1" to "2". 2-EG-RV-204A Program change: The valve numbers were 2-EG-RV-204B changed from Unit i numbers to Unit 2 2-EG RV-206A numbers. 2-EG-RV-206B 2-EG-SOV-701HA These non-Code valves are normally open to 2-EG-SOV-707JA ensure the air start header (and_ engine cylinders) remain de-pressurized during idle periods. They close during the starting. sequence and reopen to protect the air supply line. Each line has an orifice which permits ' pressurizing'of the starting air header even if the SOV failed to close. Therefore, no-closure testing is required. However, these ' valves should be tested open. Program change: The closure test was replaced by an open test. ' ( i 15 :
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 (~] %) IST PROGRAM, REVISION 7 ,
~
2-FP-79 This valve is designated as a containment isolation valve and is leak tested per 10CFR50, Appendix J. Program change: Leakage testing was added. 2-FP-82 This valve is no longer subject to Type C leakage testing. Program change: The valve was removed from-the IST Program. 2-FW-064* These valves are manipulated as required by l 2-FW-066* the abnormal operating procedures to align 2-FW-096* each of the motor-driven pump headers to the 2 -FW-0 9 8
- steam generators via the desired control ,
2-FW-128' valve (MOV or HCV). 2-FW-130* t Program change: The valves were added to the IST Program to be exercised to the open and O closed positions every cold shutdown. Refer to Cold Shutdown Justification CSV-40. l. 2-FW-070 These valves open on initiation of auxiliary 2-FW-102 feedwater flow to provide flowpaths from the 2-FW-134 AFW pumps to the steam generators. They_ ' close in the event of a ruptstre (passive failure) of the upstream AFW piping . Since l this evaluation does not postulate passive failure of ISI-classed components, testing of the closure function is not required. Therefore, Relief Request V-62, which deals with closure testing, is being withdrawn.. . Program change: The closure test was-deleted. 2-FW-147* These normally locked-closed manual valves j 2-FW-164* are opened as required by the abnormal . 2-FW-182* operating procedures in the event of an accident where all of the normal sources of i steam generator makeup water have been exhausted (or are otherwise unavailable). 16
1
SUMMARY
OF. CHANGES TO NORTH ANNA UNIT 2
'/ -IST PROGRAM, REVISION 7 A]/
s- ' e i The emergency condensate storage tanks are: only sized to provide' sufficient makeup'to ' allow the AFW system to satisfy'its safety i function for hot shutdown. .The next safety-- related backup water' supply is the service. water system. Thus, these valves.should be , exercised in'the open direction.-
\
Program change: The valves.were added to the ' IST Program to be exercised to the open-i. ~ position every cold > shutdown. Refer to Cold' .; Shutdown Justification CSV-41. ' 2-FW-156 These valves open to provide flowpaths'from 2-FW-172 their respective AFW pumps to the. designated 2-FW-192 steam generator. Since each pump is aligned to a single steam generator, reverse flow through an idle pump is of no concern. Therefore, Cold Shutdown Justification CSV-25, which-deals with closure testing, is , being withdrawn.
.O Program change: The closure test was -1 deleted. ,
t 2-FW-157' These manual valves are manipulated as 2-FW-173* required by the abnormal operating procedures' ' 2-FW-174* to align each AFW pumps 1to a desired header : 2-FW-193* (MOV or HCV) and to isolate theLunused line. ' 2-FW-194* 2-FW-317' Program change: The valves werefadde'd to the IST Program to be exercised to the open-and--
- closed positions'every cold shutdown. Refer to Cold Shutdown Justification CSV-40.
2-FW-150 These check valves open.to ensure minimum l 2-FW-167 recirculation flow through-the auxiliary- 1 2-FW-185 feedwater pumps to prevent pump damage-in the event ~of isolation of an AFW discharge line. Since' flow through these lines is. limited by. , inline orifices-and the head on these' lines. is merely that of the emergency condensate j tank, there is no adverse operational-
~
consequence if these valves failed to prevent 17 i i l
. . . . ---es -. "
I I
SUMMARY
OF CHANGES 'IO NORTH ANNA UNIT 2 (~) V IST PROGRAM, REVISION 7 reverse flow. Therefore, Cold Shutdown Justification CSV-25, which deals with closure testing, is being withdrawn. Program change: The closure test was deleted. 2-FW-202* This normally locked-clcsed manual valve is opened in the event of an accident where all j of the normal sources of steam generator makeup water have'been exhausted (or are otherwise unavailable). The emergency , condensate storage tanks are only sized to provide sufficient makeup to allow the AFW system to satisfy its safety function for hot shutdown. The next safety-related backup water supply is the service water system. Thus, this valve should'be exercised in the open direction, f-- Program change: The valve was added to the ( IST Program to be exercised to the open position every cold shutdown. Refer to Cold Shutdown Justification CSV-41. t 2-FW-609 These valves open to ensure flow-through the ' 2-FW-610 AFW pumps and to provide cooling water flow 2-FW-611 to the respective bearing oil cooler. The potential for reverse flow through a cooler is of no consequence to the safety functions of'the AFW pumps. Therefore, Cold Shutdown Justification CSV-25, which deals with closure testing, is being withdrawn. Program change: The closure test was deleted. 2-FW-FCV-2479 These feedwater bypass regulating valves do 2-FW-FCV-2489 not have remote position indication. Also, 2-FW-FCV-2499 these valves do not need to be partial stroke exercised as explained in Cold Shutdown i Justification CSV-11. Program change: The remote position 18 l
l j
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 Ih
^q.) IST PROGRAM, REVISION 7 1 indicator verification test was deleted.
2-FW-MOV-200A Valves 2-FW-MOV-200A and C are normally 1 2-FW-MOV-200C closed during plant operation. During the course of an accident, the operator may manually position these valves as required to modulate flow to the steam generators, or to isolate the affected steam generator in the case of a tube rupture or steam leak. ~Thus ; these valves should be exercised in both ' directions. i Program change: The closure test was added to be performed every three months. 1 2-FW-RV-201 This valve was installed to protect the emergency conder. sate storage tanks from over-pressure in the event of operator error or regulator failure while pressurizing from the
) plant nitrogen system. The piping from the
(/ q, plant nitrogen system has been removed and the associated tank penetration permanently opened for a vent. Therefore, pressurization is not possible. Program change: The valve was. removed from the IST Program. 2-GN-RV-208A-1* These relief valves protect the PORV air and 2-GN-RV-208A-2* nitrogen supply piping from over-pressure in 2-GN-RV-208A-3* the event that a pressure control valve 2 -G N-RV-2 0 8 B-1* should malfunction. An over-pressure 2-GN-RV-208B-2* condition could also result from a 2-GN-RV-208B-3* temperature transient in containment. . Program change: The valves were added to the-IST Program to be setpoint tested per OM-1. 2-GN-101* These non-Code valves open to provide i GN-102* flowpaths for nitrogen from the safety ; injection nitrogen header to the nitrogen reserve tanks and the PORVs. Since the g- reserve tanks are normally maintained in a 19 i i
SUMHARY OF CHANGES TO NORTH ANNA UNIT 2 .[ IST PROGRAM, REVISION 7 ( charged condition, there is no requirement for these valves to open upon accident initiation. They close to maintain the nitrogen pressure in the reserve tanks in'the event of a loss of pressure in the nitrogen supply piping. Program change: The valves were added to the IST Program to be tested to the closed position and leak tested every reactor refueling. Refer to Non-Code Alternative. Testing description VNC-1. 2-HC-015 These valves are opened periodically 2-HC-020 following an accident to sample and process hydrogen from the containment atmosphere and; thus, are considered to be active in the open and closed direction. Program change: The open test was added to r' the program to be performed once every 18 months. Refer to Relief Request V-20, 2-HC-70 These non-Code valves open to provide return 2-HC-TV-209A pathways from the High Radiation Sampling 2-HC-TV-209B Subsystem (HRSS) panels and the HRSS waste tank to the return header leading to the containment. They close to prevent recirculation through the idle sample panel should a discharge valve be open. .The HRSS-function is not considered critical for accident recovery or mitigation. Program change: The valves were removed from the IST Program. 2-HC-TV-208A These valves open to provide return pathways 2-HC-TV-208B from the High Radiation Sampling Subsystem (HRSS) panels and the HRSS waste tank to the return header leading to the containment. The HRSS function is not considered critical for accident recovery or mitigation. fs Program change: The open test was deleted. 20
t
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7
. 1 2-HV-MOV-211A Program change: The ASME Class was upgraded 2-HV-MOV-211B from non-Class to Class 3.
2-HV-MOV-211C 2-HV-MOV-213A 2-HV-MOV-213B 2-HV-MOV-213C 2-HV-PCV-2235A1 2-HV-PCV-2235A2 2-HV-PCV-2235B1 2-HV-PCV-2235B2 2-HV-PCV-2235C1 2-HV-PCV-2235C2 2-HV-RV-2200 2-HV-RV-2201 2-HV-RV-2202A 2-HV-RV-2202B 2-HV-RV-2202C 2-HV-RV-2205A 2-HV-RV-2205B 2-HV-RV-2205C ,A 2-HV-SOV-2200A ' ? 2-HV-SOV-2200B 2-HV-SOV-2200C 2-HV-MOV-211B These valves have no remote position 2-HV-MOV-211C indication. Also, the ASME Class was 2-HV-MOV-213B upgraded from non-Class to Class 3. 2-HV-MOV-213C Program change: The remote position indication verification tested was deleted and the ASME Class changed to Class 3. 2-HV-MOV-215-1 These valves are normally closed and may be 2-HV-MOV-215-2 cycled occasionally.to clear a fouled 2-HV-MOV-216-1 strainer. However, if necessary the 2-HV-MOV-216-2 strainers could be cleared manually. ' Program change: The valves were removed from the IST Program. 2-HV-TV-2306A These trip valves provide flowpaths from the 2-HV-TV-2306B control room bottled air supply tanks to'the
- control room via the ventilation system.
(-) 21 i I
l l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 '(T IST PROGRAM, REVISION 7 Q) These non-Code valves are adequately tested during the control room bottled air system tests and need not be included in the IST Program. Program change: The valves were removed from' the IST Program. 3-IA-396 These valves open to provide flowpaths for 2-IA-397 air from the normal instrument air supply 2-IA-405 header to the main valve operators and , 2-IA-406 controllers of dampers 2-HV-2301A and B. Since.the normal air supply is not relied upon to operate the dampers, no exercising in the open direction is required. In the event of a loss of pressure in the respective. air supply header they close to prevent blowdown of the reserve air volume tank into the depressurized header. Note that following the loss of-pressure in the main header, back-leakage through-these valves must be ( limited to that amount that will ensure the - air bottle supply will be available to operate the main valves for a specified period during the accident scenario. Thus, these valves should be verified to be leak , tight. Relief Request V-65 is being withdrawn and replaced by Non-Code Alternative Testing description VNC-2 for these non-Code valves. Also, the leak test method to be used for these valves is included in VNC-2. Program change: The IWV category was changed from C to AC and a leak test was added to be performed every reactor refueling. L 2-IA-497* These non-Code valves open to provide : 2-IA-499* flowpaths for air from the normal instrument-air supply-header to the Units 1 and 2 : hydrogen recombiner system isolation valves. l Since the normal air supply is not relied . 1 upon to operate the valves, no exercising in the open direction is required. In the event ; { _~ \ 22
f l 6
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 s_, of a loss of pressure in the respective air supply header they close to prevent blowdown of the reserve air volume tank into the de-pressurized header. Testing of the main isolation valves, in itself, will not verify that these valves have adequate leak tightness to protect the inventory in the reserve tank. Program change: The valves were added to the IST Program to be tested closed every three months and leakage tested every reactor , refueling. 2-IA-504 These valves open to provide a flowpath for 2-IA-510 air from the normal instrument air supply 2-IA-516 header to the main valve operators. Since the normal air supply is not relied upon to operate the main valves, no exercising in-the open direction is required. In the event of , f-- a loss of pressure in the respective air (~ supply header, they close to prevent blowdown of the reserve air bottle into the , depressurized header. Note that fo:>aving the loss of pressure in the main huus" r , back-leakage through these valves mu t be : limited to that amount that will ensure the ! air bottle supply will be available to operate the main valves for a specified , period of time during the accident scenario. Thus, these valves should be verified to be leak tight. - 4 In lieu of a leakage test for the isolation check valves, the_ main valves will be cycled the required number of times over the required period as defined by their design requirements with the normal air' supply 1 isolated and vented. i Program change: The IWV category was changed { from C to AC and a leak test was added to be j performed every reactor refueling. Non-Code ' Alternative Testing description VNC-3 documents the alternative leak testing. p 23 i i i
SUMMARY
OF CHANGES TO NORTH' ANNA UNIT 2 () IST PROGRAM, REVISION 7 i 2-IA-525 These valves open to provide flowpaths for : 2-IA-531 air from the normal instrument air supply i 2-IA-537 header to the main valve operators and controllers of 2-FW-HCV-200A-C. Since the normal air supply is not relied upon to i operate the main valves, no exercising in the-open direction is required. In the event'of a loss of pressure in the respective air supply header, they close to prevent blowdown of the reserve air volume tank into the depressurized header. Note that following the loss of pressure in the-main header, back-leakage through these valves must be limited to that amount that will ensure the air bottle supply will be'available to operate the main valves for a specified period during the accident scenario. Thus, these valves should be verified to be leak tight. ' O In lieu of a leakage test for the isolation check valves, the main valves will be cycled the required number of times over the required period as defined by their design ' requirements with the normal air supply isolated and vented. Program change: The IWV category was changed from C to AC and a leak test was added to be ! performed every reactor refueling. Non-Code . Alternative Testing Description VNC-3 documents the alternative leak testing. . 2-IA-543 These valves open to provide flowpaths for , 2-IA-549 air from the normal instrument air supply . header to the main valve operators and ! controllers of 2-FW-PCV-259A and B. Since ! the normal air supply is not relied upon to ' operate the main valves, no exercising in the open direction is required. In the event of i a loss of pressure in the respective air supply header, they close to prevent blowdown . of the reserve air bottles into the I depressurized header. Note that following l the loss of pressure in the main header, 24 '! a i j
i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT.2 f'N; s_- IST PROGRAM, REVISION 7 back-leakage through these valves must be limited to that amount that will ensure the air bottle supply will be available to operate the main valves for a specified time ; period during the accident scenario. Thus, these valves should be verified to be leak t tight. In lieu of a leakage test for the isolation check valves, the main valves will be cycled the required number of times over the-required period as defined by their design requirements with the normal air supply isolated and vented. ' Program change: The IWV category was changed from C to AC and a leak test was added to be performed every reactor refueling. .Non-Code ! Alternative Testing Description VNC-3 documents the alternative leak testing. p) (, 2-IA-2130* These valves open to provide a flowpath for 2-IA-2131' air from the normal containment air supply , 2-IA-2132* header to the PORV operators. Since the 2-IA-2133' normal air supply is not relied upon to operate the main valves, no exercising in the i open direction is required. In the event of a loss of pressure in the respective air a supply header, they close to prevent blowdown of the air bottle into the depressurized header. Note that following the loss of , pressure in the main header back-leakage through these valves must be limited to that , amount that will ensure the air bottle supply will be available to operate the main valves .; during the accident scenario. Thus, these valves should be leak tested as.well-as' 4 exercised. 1 Program change: These valves were added to-the IST Program to be back seat tested and leakage tested every reactor refueling. Refer to Non-Code Alternative Testing Description VNC-1. 25 I._
i I I
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 i () - IST PROGRAM, REVISION 7 (_s/ 4 1 2-MS-117 These valves can be back seat tested every 2-MS-119 three months. Therefore, Relief Request V-53 2-MS-121 is being withdrawn. . Program change: Valves will be closure tested every three months instead of every reactor refueling. 2-MS-NRV-201A Program change: The test method was changed 2-MS-NRV-201B to use the Valve Operation Test and 2-MS-NRV-201C Evaluation System (VOTES) to verify disk , position. Refer to Cold Shutdown Justification CSV-13. s 2-MS-NRV-203A These motor-operated stop-check valves are ! 2-MS-NRV-203B opened only during plant startup to provide 2-MS-NRV-203C flowpaths for steam from each of the steam generators to equalize pressure across the main line non-return valves. They remain closed during normal operation. The upstream. ' Os trip valve 2-MS-TV-213A, B and C will isolate the line if necessary. Therefore, the stop- .i check valves are passive. Program change: The valves were removed from the IST Program. 2-MS-PCV-201A These valves provide a means of rejecting 2-MS-PCV-201B reactor core heat when the main condenser 2-MS-PCV-201C heat sink is unavailable. In the event of a small break LOCA these valves would be opened ; to remove heat and reduce reactor coolant j system pressure until RHR system operational limits are achieved. .The valves are required i to close, if open, to limit release of j fission products in the event'of a steam generator tube rupture. Although it is-unlikely that a tube rupture incident would l occur simultaneously with a plant condition j where opening of these valves is required, l the emergency operating procedure (EOP) ! identifies the need for closure in such an ! event and, for that reason, is considered prudent to include a requirement for 26 i
e
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7
)
exercising in the closed direction. Since there are several cases where the EOP's depend on these valves to operate under accident conditions to effect a safe and orderly plant shutdown, it is prudent to include them in the test program. These valves open with air and close on loss of air pressure or electric power. Program change: The open test was added to be performed every three months and.their remote position indicators will be verified every 24 months. The closure test frequency was changed from every cold shutdown to every three months. . 2-MS-TV-213A Program change: A fail safe _ test was added. 2-MS-TV-213B 2-MS-TV-213C 2-MS-TV-215' This normally open (passive) valve provides a flowpath for steam from the steam generators to the steam-driven AFW Pumps. The valve closes to shutdown the AFW pump turbine in the event of turbine overspeed - not a safety function. Program change: . The-' valve was added to the IST Program to have its remote position indicator verified every 24 months. 2-QS-MOV-200A These valves are normally-open to provide 2-QS-MOV-200B flowpaths from the RWST's to the quench spray pumps. Since.they are not normally closed,
- except for maintenance, they are considered ,
to be passive and no exercising is required.- Program change: The exercise test was , deleted. ( 27 u e i
t
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 ' ~\sa [) IST PROGRAM, REVISION 7 2-RC-HCV-2556A* Since these valves are normally closed , 2-RC-HCV-2556B* (administratively controlled) and remain ; 2-RC-HCV-2556C' closed whenever the RCS is pressurized,'they are determined to be passive and exercising is not required. However, their remote position indicators need to be verified. Program change: These valves were added to the IST Program to have their remote position , indicators verified every 24 months-2-RC-PCV-2455C The test frequency was changed from during ; 2-RC-PCV-2456 cold shutdowns when the RCS is depressurized to every cold shutdown and Relief Request V-27 was withdrawn and replaced with Cold
- Shutdown Justification CSV-42.
Program change: Test frequency was changed to every cold shutdown. () 2-RC-SOV-202A-1 2-RC-SOV-202A-2 These valves are opened as needed to vent non-condensible gases trapped in the 2-RC-SOV-202B-1 pressurizer. This is considered to be a ; 2-RC-SOV-202B-2 backup function to that of the PORV's and ; thus are not relied upon in an accident. Program change: These valves were removed from the IST Program. t 2-RH-7 These RHR pump discharge check valves can 2-RH-15 only be tested during the RHR pump tests. The pump. test frequency has been changed from cold shutdown to reactor refueling. ' Program change: The test frequency was changed from cold shutdown to reactor : refueling. Refer to-Relief Request V-75. ! l 2-RH-MOV-2700 These valves are opened to provide flowpaths ] 2-RH-MOV-2701 for reactor coolant from the RCS to the ! suctions of the RHR pumps to.effect shutdown j cooling recirculation from the RCS to the RHR heat exchangers. They are closed and remain j 1 O.. 28 1 i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 s so during plant operation to isolate the low pressure portions of the RHR System from the high pressure of the RCS. Therefore, these valves have no requirement to change position to perform their closed function. Thus, testing in the closed direction-is not required. Program change: The closure test was deleted. 2-RH-MOV-2720A These valves are opened to provide flowpaths-2-RH-MOV-2720B for reactor coolant from the discharge of the RHR heat exchangers to the RCS to effect. shutdown cooling recirculation from the RHR heat exchangers back to the RCS. They are normally closed and remain so during plant operation to isolate the low pressure , portions of the RHR System from the high F pressure of the RCS. There is no requirement for the valves to change position to perform. Os their closed function, thus they are passive in the closed position. Program change: The closure test was deleted. 2-RM-TV-200D This valve is no longer subject to Type C leakage testing per Appendix J. Program charge: The leakage testing was deleted. 2-RS-103 These valves open to provide flowpaths from 2-RS-118 the casing cooling pumps to the suctions of the outside recirculation spray pumps. They close to prevent backflow through an idle pump. However, if a pump is idle the casing cooling discharge valve (2-MOV-RS-201A and B) will automatically close to isolate the line due to the action of the associated casing cooling flow switch. Program change: The closure test was 29 e
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 /' IST PROGRAM, REVISION 7 ( deleted. " 2-RS-MOV-255A These valves are normally-open (automatically 2-RS-MOV-255B open if closed) to provide flowpaths from the containment sump and the casing cooling pumps - to the outside recirculation spray pumps (passive function). They are considered to be active in the closed direction since they ' are designated as containment isolation .; valves (non-leak tested). They also would be closed if a leak were to develop in the , outside recirculation spray system. In the course of an accident there could be intermittent operation of the recirculation , spray system that would require closing and ; opening these valves. Program change: The closure test was added to be performed every three months. - ( 2-SI-006 2-SI-029 These valves open to provide flowpaths from the RWST's to the LHSI pump seal. The RWST head provides sealing pressure during idle periods to prevent seal leakage when a pump is not in operation. When.the related LHSI pump is running, the seal pressure is ; supplied from the pump discharge and.these ~ valves must close to prevent recirculation to the respective RWST. This function is primarily related to operations while in'the . recirculation mode. Seal leakage-from an I idle pump is not considered a critical i function. Thus, exercising in the open direction is not required. , After recirculation mode transfer, these valves isolate the RWST from contaminated > sump water. Therefore, they should be leak tested. t Program change: The open test was deleted , and the leak test was added. : l 30 1 _ _ _ _ .__-______i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 / IST PROGRAM, REVISION 7 2-SI-012 These valves open to provide _flowpaths for 2-SI-035 the LHSI pump minimum flow to ensure adequate pump cooling during low-flow conditions. They have no function to-close that is related to accident recovery or mitigation._ Program change: The closure test was deleted 2-SI-18 After recirculation mode transfer, there exists a path for contaminated sump water through the piping from the suction of the charging pumps to the RWST. This valve isolates the piping and should be leak tested. Program change: Leakage testing was added and the closure test frequency was changed from cold shutdown to reactor refueling. Refer to Relief Request 7-40. () 2-SI-151 2-SI-168 These valves are normally closed and upon depressurization of the RCS during a LOCA 2-SI-185 open to provide flowpaths from each of the SI Accumulators to the RCS cold legs. There is no specific safety function for these valves to close following discharge from the associated accumulator. Thus, they need not be tested in the closed direction. Program change: The closure test was deleted. 2-SI-HCV-2853A These valves are normally closed (fail 2-SI-HCV-2853B closed) and.are only required to open from 2-SI-HCV-2853C time to time to adjust the pressure within the respective accumulators'to assure compliance with the Technical Specification requirements for SI accumulator pressure and-level. Following an accident where gross blowdown of the RCS does not occur and there is insufficient inventory of water in the containment sump for recirculation, the accumulator discharge motor-operated valves (2-SI-MOV-2865A, B and C) will be closed 31
l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 (j!T
~
IST PROGRAM, REVISION 7-prior to depressurization to preclude injecting large quantities of nitrogen into the RCS that could ultimately cause the RHR pumps to become air bound. The alternate method of preventing nitrogen injection into the RCS requires using these valves to vent > the accumulators; however, since these vent valves require instrument air to open, it is assumed that this option is unavailable. Thus, during emergency cooldown operations, no credit is taken for venting the accumulators since the air supply to the operators is not considered to be reliable and the outlet motor-operated valves would be closed. During post-accident conditions, , these valves will remain closed until plant conditions are stable and long-term recovery ; valve lineups are established. - Program change: These valves were removed from the IST Program. 2-SI-HCV-2936 This valve is normally closed (fail closed) and is only required to be opened infrequently to reduce the pressure (vent) within the accumulators. Since the valve is opened intermittently during operation and receive a Phase A signal to close, it is considered an active valve and should be tested in the closed direction. During emergency cooldown operations no credit is taken for venting the accumulators and this valve will remain-closed until plant conditions are stable and long-tcr; recovery valve lineups are established. Program change: The open test was deleted. 2-SI-MOV-2863A These normally-closed valves automatically 2-SI-MOV-2863B open when SI is initiated and the respective-RWST reaches its Low-Low level'setpoint to provide a pathway from the LHSI pumps to.the HHSI pumps while in the recirculation mode. As an alternative, they may be closed to direct LHSI pump recirculation flow directly 32
SUMMARY
OF CHANGES TO NORTfi ANNA UNIT 2 N IST PROGRAM, REVISION 7-(O to the RCS instead of the HHSI pumps. Program change: The closure test was added. 2-SI-MOV-2865A During plant operation at power these valves 2-SI-MOV-2865B remain open with.the power to their motor 2-SI-MOV-2865C controller removed; however, during startup they could be closed at RCS pressures of 1000 psig or less per Technical Specification Section 3.5.1 thus they are considered to be active in the open direction. Following an accident where gross blowdown of the RCS does not occur and there is insufficient inventory of water in the containment sump for-recirculation, these valves will be closed prior to depressurization to preclude injecting large quantities of nitrogen into the RCS that could ultimately cause the RHR pumps to become air bound. There is no case where these valves would be reopened after closure during an accident. The alternate 0s method of preventing nitrogen injection into the RCS requires venting of the accumulators; however, since the valves associated with the venting process require instrument air to open, it is assumed that this option is unavailable. Program change: The closure test was added. 2-SI-MOV-2885A After recirculation mode transfer, there 2-SI-MOV-2885B exists a path for contaminated sump water 2-SI-MOV-2885C through the piping from the discharge of the 2-SI-MOV-2885D low head safety injection pumps to the RWST. These valves isolate the' piping and should be leak tested. Program change: Leakage testing was added. 2-SI-RV-2857B These valves protect the high head safety injection line downstream of the boron injection tank from over-pressure. This is primarily a thermal relief to protect from ,- pressure developed by the heat tracing in the 33
5 i l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 ().- IST PROGRAM, REVISION 7 isolated portion of the piping and BIT. . Therefore, they do not require testing per the IST Program. , Program change: The valve was removed from-the IST Program. 2-SI-RV-2858A These valves protect the SI accumulators and ! 2-SI-RV-2858B associated piping and components from 2-SI-RV-2858C overpressure. Since the accumulator system is a passive system and not subject to operational pressure transients, the only potential source of over-pressure of an , accumulator is overfilling with nitrogen. J Specifically, in-leakage from the RCS does . not present a significant potential for over-pressurization since the volume in the tanks allows sufficient time for operator action by draining or isolating the affected tank (s) to prevent exceeding design limits should r" j} significant in-leakage develop during plant ; ( ,/ operation. If in-leakage were so great as to preclude operator action, then the plant - would be shutdown as required to satisfy the requirements of Technical Specification 3.4.6.2. , i Program change: The valves were removed from the IST Program. 1 2-SI-TV-201 This valve is normally closed. It is opened - infrequently to reduce the pressure in the SI ' accumulators. During emergency ~cooldown i operations no credit is taken for venting the - accumulators. Thereforo, this valve need not be tested in the open direction. Program change: The open test was deleted. 2-SS-TV-203A These valves are opened to draw samples from 2-SS-TV-203B the.RHR system when in operation. Since the RHR system would only be operating at or near cold shutdown, it is not likely that they-would be opened during an accident resulting O 34 ! l l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7
)
in containment isolation. Therefore, they are considered to be passive valves for their function of containment isolation. Program change: The exercise test was deleted. 2-SV-TV-202-1 This normally closed valve is opened following a steam generator tube leak or rupture or on receipt of a high radiation sigaal from the vent stack monitoring instrumentation when~it is desirable to have the main condenser air ejectors lined up to discharge into containment. Although this is identified as a stop in the emergency procedure, such action is considered to be precautionary and preferable but not mandatory for accident mitigation. Program change: The open test was deleted. ,n k - 2-SV-TV-202-2 This normally open valve is closed following a steam generator tube leak or rupture or on receipt of a high radiation signal from the vent stack monitoring instrumentation when it is desirable to have the main condenser air ejectors lined up to discharge into containment and receive a Phase A signal to close. Although this is identified as a step in the emergency procedure, closure of this valve is precautionary and not required to meet 10CFR100 limits during prescribed accidents. Program change: The valve was removed from the IST Program. 2-SV-TV-203 This normally closed valve is opened following a steam generator tube leak or rupture when it is desirable to have the main condenser air ejectors lined up to discharge into containment. Although this is identified as a step in the emergency s procedure, such action is considered to be 35
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 ' /Y IST PROGRAM, REVISION 7 -b precautionary and preferable but not mandatory for accident mitigation. Program change: The open test was deleted. 2-SW-3 Observation of the non-running pump's 2-SW-10 discharge pressure gauge every three months-was added to Relief Request V-64 to enhance the verification of check valve closure. Program change: Added quarterly closure test. 2-SW-24 Program change: The valve was moved from Relief Request V-64 to V-74. 2-SW-MOV-202A During normal plant operation these valves 2-SW-MOV-202B are normally open and they would be closed to r- isolate a ruptured header. .Since passive lg,)j failure is not considered for this evaluation and operationally they can be in any position, no exercising of these valves is required. Program change: The exercise test was deleted. 2-SW-MOV-206A During normal plant operation these valves 2-SW-MOV-206B are open. They would be closed to isolate a ruptured header. Since passive failure is not considered for'this evaluation and operationally they can be in any position, no exercising of these valves is required. Program change: The exercise' test was deleted. 2-SW-MOV-210A" During plant operation these valves are 2-SW-MOV-210B* normally closed with their breakers locked open. If open when a CDA signal is received, they will automatically close for containment isolation and service water conservation. 36
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2
) IST PROGRAM, REVISION 7 x~_ -
Since they are normally closed they are considered to be passive and no exercising is required. Program change: These valves were added to the IST Program to have their remote position indicators verified every 24 months. 2-SW-MOV-213A During plant operation these valves are 2-SW-MOV-213B normally locked closed and are only opened as a emergency backup supply of cooling water to the fuel pit coolers. Since component cooling is a safety grade system and considered to be highly reliable, this backup capability is considered to be a convenient operational backup and not required for accident mitigation. Therefore, exercising of these valves is no't required. If open when a CDA signal is received, they would be cloaed for service water conservation and to
<x minimize non-essential heat loads. Since
(' ) they are normally closed they are considered to be passive and no exercising is required. Program change: The exercise test was deleted. I 2-SW-MOV-214A* During plant operation these valves are 2- SW-MOV-214 B* normally closed with their breakers locked open. If open when a CDA sigrmi is received, they will automatically close for containment isolation and service water conservation. Since they are normally closed they are considered to be passive and no exercising is required. 2 Program change: These valves were added to the IST Program to have their remote position indicatgrs verified every 24 months. 2-SW-MOV-219* This valve opens to rovide a flowpath for makeup to the reservoirs via the screen wash pumps. Since this mode of makeup is not relied upon during an accident, exercising in
) 37
x
SUMMARY
OF CHANGES TO NORTH ANNA-UNIT 2 l [) T_,/ IST PROGRAM, REVISION 7 ; the open direction is.not r9 quired. In the event an accident occurs while this valve is open, it would be closed to isolate the non-classed portions cI the system from the safety-related portions. Program change: This valve was added to the IST Program to be tested to the closed r position every three months and to have its remote position indicator verified every 24 months. 2-SW-MOV-220A* During plant operation these valves are 2-SW-MOV-220B* normally c~3 sed except when in the lake-to-lake cooling mode. Since the plant irs seldom, if ever, in this mode, these valves are passive in the closed position. Since each line must remain closed to retain the water in the service water reservoir, it is prudent to verify the accuracy of the remote , position indication of these valves. # Program change: These valves wer2 added to the IST Program to h! 're their remote position' indicators verified e<ery 24 months. 2-SW-RV- These valves open to provide over-pressure 2-SW-RV-2 protection for an isolated heat exchanger. Since the only time a heat eachanger.would be isolated is when it is out of service and unsvallable, protection of the heat _ exchanger is not significant. Therefore, testing of : these valves is not required. Program change: The valves were removed from the IST Program. i r W 38 i J
'I k
l I
-1.
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 :
?['T - IST PROGRAM, REVISION 7' l %)
2.3.5 VALVE. INSERVICE TESTING' PROGRAM RELIEF REQUESTS The following summarizes the changes to relief requests since Revision 6. It also contains a description of the approval mechanism for each relief request. That is, the ' summary indicates whether the approval is: *
- 1) through a position in Generic Letter 89-04,
- 2) through a previously issued NRC SER or
- 3) obtained using a relief request that will need approval i by the NRC. Relief requests requiring NRC approval are marked with an asterisk *.
UNIT 2 RELIEF REOUEST COMMENT / STATUS V-1 and These relief request numbers are no longer active. V-3 The basis for going from a-cold shutdown tesP frequency to a reactor refueling frequency was expanded. Also, reference to a partial stroke test was deleted. The only safety function for valves 2-CC-78, 115 and 152 is to close. An open test is not required in conjunction with a closed
, test for valves that only need to close. The Revision 6 version cf V-3 was approved by the NRC in their SER dated September 17, 1993. The minor changes made to V-3 should not affect the conclusion reached by the NRC in their SER.
V-4 to V-8 These relief request numbers are no longer active. V, No change. This relief request was approved by the NRC in the SER for Revision 6 dated September. 17, 1993. V-10 The basis was expanded for valve 2-CH-332. Also, reference to a partial stroke test was deleted. The only safety function for' valves 2-CH-260, 284, 308, 331, 332 and 435 is to close. An open test is not required in conjunction with a closed-t'est O b 39 r
f
}
SUMMARY
OF CHANGES-TO NORTH ANNA UNIT 2 (~D IST PROGRAM, REVISION 7 'L) for valves that only need to close. The Revision 6 version of V-10 was approved by the NRC in their SER dated September 17, 1993. .The minor changes - made to V-10 should not affect the conclusion ' . reached by the NRC in their SER. V-11 to These relief request numbers are no longer active. : V-13 V-14 This relief reauest is beina withdrawn. It was determined that valve 2-CV-TV-200 is a passive valve and is not subject to an exercise test. Therefore, Relief Request V-14, which dealt with the exercise test, is not necessary. V-15 This relief request number is no longer active. i V-16 Reference to a partial stroke test was deleted. The only safety function for the normally closed valve 2-FP-79 is to close. An open test is not , required in conjunction with a closed test for ' valves that only need to close. .The Revision 6 ()s ( version of V-16 was approved by the NRC in-their SER dated September 17, 1993. The minor change . made to V-16 should not affect the' conclusion reached by the NRC in their SER. V-17 to These relief request numbers are no longer active. V-19 V-20* This relief request was revised to addressed the , open test for valves 2-HC-15 and 20. The open- ' test was added in Revision 7 to the IST Program. The alternative testing methods meet the requirements of Generic Letter 89-04, Attachment 1, Positions 1 and 3. The test frequency for the new open test needs approval from the NRC. The Revision 6 version of V-20 was approved by the NRC in their SER dated September 17, 1993. V-21 Reference to a partial stroke test was deleted. The only safety function for these normally closed instrument air valves is to close. An open test is not required in conjunction with a closed test for valves that only need to close. The Revision 6 version of V-21 was approved by the NRC in their
- SER dated September 17, 1993. The minor change Y 40'
SUMMARY
OF CHANGES TO NORTH' ANNA UNIT 2 y IST PROGRAM, REVISION 7 t
' J made to V-21 should not affect the conclusion reached by the NRC in their SER.
V-22 to These relief request numbers are no longer active. V-26 V-27 This relief reauest is beine withdrawn. This relief request is being replaced by Cold Shutdown Justification CSV-42 and the test frequency for the PORV's 2-RC-PCV-2455C and 2456 changed to every cold shutdown. This change is in response to NRC concerns described in their SER dated September 17, 1993. V-28 Reference to a partial stroke. test was deleted. The only safety function for the normally closed valve 2-RC-162 is to close. An open test is not required in conjunction with a closed test for valves-that only need to close. The Revision 6 version of V-28 was approved by the NRC in1their SER dated September 17,'1993. The, minor change made to V-28 should not affect-the conclusion reached by the NRC in their SER. V-29 i.o These relief request numbers-are no longer active. V-32 V-33 Reference to back raat testing valves 2-RS-103 and 138 was deleted. The Revision 6 version.ofLV-33 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-33.- should not affect the conclusion reached:by the NRC in theit SER. The alternative testing conforms to NRC Generic Letter 89-04,-Attachment 1, Position 2. V-34 This relief request number is no' longer active. V-35 No change. This relief request was approved-by the NRC in the SER for Revision 6 dated. September 17, 1993. V-36 This relief request numberfis no' longer active. V-37 No. change. T51s relief request was approved by the NRC in the.SER for Revision 6 dated-September-17, 1993.
i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 / IST PROGRAM, REVISION 7 V-38 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September ; 17, 1993. V-39 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. < V-40* Reference to leakage testing was added for valve 2-SI-18. Also, the frequency for closure testing was changed from every cold shutdown to every reactor refueling to coincide with the leakage test frequency. The test frequency for the closure test needs approval from the NRC. The Revision 6 version of V-40 was approved by the NRC in their SER dated September 17, 1993. V-41 Reference to a partial stroke test was deleted. The only safety function for valves 2-SI-132 and 136 is to close. An open test is not required in conjunction with a closed test for valves that only need to close. The Revision 6 version of V-(
~
41 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-41 should not affect the conclusion reached by the NRC in their SER. V-42 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-43 Reference to using a sampling program for non-intrusive testing for the SI accumulator discharge check valves was added. The sampling program is similar to the one given in Generic Letter 89-04, ; Attachment 1, Position 2 for check valve disassembly and inspection. This change is in response to NRC qualifications for approval of the relief request that are described in their SER dated September 17, 1993. Also, reference to closure testing for valves 2-SI-151, 168 and 185 was deleted because the closure test for these valves was deleted from the program. The minor change of deleting the closure tests should not affect the conclusion reached by the NRC in their SER. s. \ 42 i
4 C
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 V-44 No change. This relief request was approved by tha NRC in the SER for Revision 6 dated September 17, 1993. V-45 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-46 Reference to FSAR Section 6.2.2.2.5 was added in , Revision 7. The Revision 6 version of V-46 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-46 should ' not affect the conclusion reached by the NRC in their SER. V-47 Reference to a partial stroke test was deleted. The only safety function for valve 2-VP-24 is to close. An open test is not required in conjunction with a closed test for valves that , only need to close. The Revision 6 version of V- ' 47 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-47 (-) should not affect the conclusion reached by the NRC in their SER. V-48 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-49 This relief request number is no longer active. V-50 This relief reauest is being withdrawn. Flow instrumentation has been installed. Therefore, the diesel fuel oil pump discharge check valves can be full flow tested every three months.- V-51 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-52 This relief request number is no longer active. V-53 This relief reauest is beino withdrawn. The mainsteam to the turbine driven auxiliary feedwater pump check valves (2-MS-117, 119 and 121) can be exercised' closed every three months.
.f
43
i l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 ) IST PROGRAM, REVISION 7 l [')T R.
'1 V-54* The method of closure testing was changed from disassembly and inspection to back seat / leak testing for valves 2-SI-6.and 29 every reactor refueling. Also, the basis was expanded to '
justify the reactor refueling test frequency. The Revision 6 version of V-54 was approved by the NRC , in their SER dated Septemoer 17, 1993. ' V-55 The list of rapid acting valves was deleted. This list is maintained by the site ISI engineer. The Revision 6 version of V-55 was approved by the NRC ' in their SER dated September 17, 1993. The minor change made to V-55 should not affect the conclusion reached by the NRC in their SER. V-56 The relief reauest is beine withdrawn and replaced by Non-Code Alternative Testing Description VNC-4. The basis for relief was revised slightly to enhance clarity. Because the diesel air-start valves are non-code components, approval is not > required from the NRC to deviate from Code i provisions. V-57 This relief request number is no longer active. V-58' The basis was expanded to describe the risks , associated with stroking the vessel head vent valves while the RCS is pressurized. This change is in response to NRC concerns described in their SER dated September 17, 1993. Also, valves 2-RC-SOV-202A-1, 202A-2, 202B-1 and 202B-2 were deleted , from the IST Program and are being deleted from ' this relief request. V-59 Valves 2-HV-MOV-200A and C were deleted from the relief request. The Revision 6 version of V-59 was approved by the NRC in their SER dated September 17, 1993. The minor change made to V-59 should not affect the conclusion reached by the NRC in their SER. V-60 This relief request number is no longer active. V-61 No change. This relief request was approved by '\ the NRC in the SER for Revision 6 dated September 17, 1993. t L' 44
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2
/^^' IST PROGRAM, REVISION 7
'Q,) -
~ -
V-62 The relief reauest is beina withdrawn. The closure test was deleted for valves 2-FW-70, 102 and 134. Therefore, the request for relief is no longer necessary. V-63 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-64 The alternative testing was expanded to include observation of the discharge pressure gauge on the non-running pump every three months. This test was added in response to NRC concerns described in their SER dated September 17, 1993. Even without this change, the NRC approved the relief request in their SER for Revision 6 dated September 17, 1993. Valve 2-SW-24 was deleted from this relief request and put into Relief request V-74. This minor change should not affect the conclusion reached by the NRC in their SER. g- V-65 The relief reauest is beina withdrawn and replaced g
' by Non-Code Alternative Testing Description VNC-2.
Reference to back seat / leak testing the non-Code instrument air valves 2-IA-396, 397, 405 and 406 every reactor refueling was added. Also, the method for performing the leak test was added. V-66 No change. This relief request was approved'by the NRC in the SER for Revision 6 dated September 17, 1993. V-67 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September 17, 1993. V-68 No change. This relief request was approved by the NRC in the SER for Revision 6 dated September-17, 1993. V-69 This relief request number is no longer active. V-70 This relief request deals with using an evaluation instead of repair as corrective action for Appendix J valves that exceed their maximum leakage but do not allow the overall leakage to-exceed 0.6La. V-70 was originally submitted on 45 5.
j j
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 I , I 1 IST PROGRAM, REVISION 7 Q 1 i June 14, 1990. Following a meeting with the NRC held on September 6, 1990, V-70 was withdrawn per ; guidance from.the NRC. The SER dated September " 17, 1993, approved the original version of V-70 with certain restrictions. V-70 is being i resubmitted with the restrictions included and is ! considered approved for use by the SER. V-71 The basis was expanded to indicate that the vessel' is defueled every reactor refueling. This change is in response to NRC concerns described in their SER dated September 17, 1993. With the clarification included, V-71 is considered approved for use by the SER. V-72 The relief renuest is beine withdrawn. Valves 2-CA-26, 2-HV-TV-2306A and 2-HV-TV-2306B were ' deleted from the IST Program. Therefore, Relief Request V-72 is.no longer necessary. ' V-73* This relief request is being added to the program. ' Due to the plant configuration, the VCT discharge ( check valve 2-CH-153 cannot be verified closed using flow. The only method to verify closure other than disassembly and inspection is to perform a leak rate /back pressure test. During normal operation, this valve cannot'be isolated to perform a back pressure test because normal letdown and reactor coolant flow would be interrupted. This valve is also subject to leak testing, which is performed every reactor refueling.
- Verification of closure will be performed during the leak test every reactor refueling instead of.
every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify draining the lines and performing a. , leak rate test. V-74 This relief request is being added to the program. Full accident flow cannot be established through the auxiliary service water pump discharge check ' valve 2-SW-24 using the normal system lineup-because the accident heat loads and corresponding ,
; demand on the service water system cannot be '
46
4e
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 V} [^ IST PROGRAM, REVISION 7 duplicated. The accident flow can be established using a lake-to-lake configuration. However, the lake-to-lake lineup could contaminate Lake Anna with chemicals used in treating the service water system. Therefore, the lake-to-lake lineup is never used. This check valve can be disassembled while tht plant is operating. To allow for flexibility in planning for refueling outages and still meet the intent of Generic Letter 89-04, Attachment 1, Position 2, the valve will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. Because V-74 meets the requirements of Generic Letter 89-04, Attachment 1, Position 2, no approval by the NRC is necessary prior to implementation. V-75* This relief request replaces Cold Shutdown Justification CSV-19 for valves 2-RHR-7 and 15. These RHR pump discharge check valves can only.be es tested during the RHR pump tests. During cold-( ,) shutdowns of short duration or if the reactor r coolant pumps are left running during the cold shutdown, both trains of RER may be required for decay heat removal and to maintain RCS temperature. Taking one train of RHR out of . service for testing purposes even for a short period could allow the RCS temperature to increase-to the point that the pressurizer power operated , relief valve would be challenged. Therefore, these pumps and the discharge check valves should r only be tested during reactor refuelings. 1 i
~%
l 47 l
1 i
SUMMARY
OF CHANGES TO NORTH' ANNA UNIT 2 , IST PROGRAM, REVISION 7 2.3.6 VALVE INSERVICE TESTING PROGRAM COLD SHUTDOWN JUSTIFICATIONS - UNIT 2 l COLD SHUTDOWN JUSTIFICATION COMMENT / STATUS i CSV-1 No change. CSV-2 This CSV number is no longer active. CSV-3 No change. i CSV-4 Reference to valve 2-CH-140 was deleted. CSV-S Valves 2-CH-TV-2204A and B were added. Also, more technical bases were added to the justification. CSV-6 and 7 No change. CSV-8' Justification is being withdrawn because the-e jg exercise test for valve 2-CH-MOV-2373 was' deleted () from the IST program. CSV-9 This CSV number is no longer active. CSV-10 Justification is being withdrawn because the exercise test for valve 2-CH-FCV-2160 was deleted. , CSV-11 The justification was' expanded to say that the l feedwater bypass valves 2-FW-FCV-2479, 2489 and -l 2499 do not have to be partial stroke exercised i every three months and the motor operated valves 'l 2-FW-MOV-254A, B and C cannot be partial' stroke ! exercised. CSV-12 Reference to a partial stroke test was' deleted. The only safety function for valves 2-FW-62, 92' _ i
'and 126 is to close. An open test is'not required :
in conjunction with a closed test for valves that ! only need to close. l 1 CSV-13 The justification was revised to describe the use of VOTES to determine the position of the disk _on 1 the main steam'non-return valves. I 48 i
=!
'l
s w i j
SUMMARY
,OF CHANGES TO NORTH ANNA UNIT.2 f~ IST PROGRAM, REVISION 7 CSV-14 No change. CSV-15 This CSV number is no longer active. CSV-16 No change. 1 CSV-17 This CSV nunber is no longer active. CSV-18 Nu change. l CSV-19 Replaced by Relief Request V-75. CSV-20 No change. CSV-21 to 23 Tnese CSV numbers are no longer active. CSV-24 No change. f CSV-25 Justification is being withdrawn because the closure test for the auxiliary feedwater check , valves was deleted. () CSV-26 This CSV number is-no longer active. CSV-27 Justification is being withdrawn br:cause the main steam PCVs 2-MS-PCV-201A, B and C can be isolated and tested every-three months. CSV-28 and 29 These CSV numbers are no longer active. CSV-30 No change. CSV-31 The technical basis was expanded. CSV-32 and 33 No change. CSV-34 References to valves 2-MS-NRV-203A, B, C and D were deleted because these valves were deleted from the IST Program. CSV-35 to 36 No change. CSV-37 Justification is being withdrawn because valves 2-CH-HCV-2303A, B and C were deleted from the IST Program.
',Q ' k) 49
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 (~ IST PROGRAM, REVISION 7
- Q) .
v CSV-38 Justification is being withdrawn because valves 2-CC-8 and 25 were deleted from the IST Program. CSV-39 The cold shutdown justification was revised to delete the partial flow testing requirement for the charging recirculation check valves 2-CH-176, 191 and 206. CSV-40 This cold shutdown justification was added to the program to describe why the auxiliary feedwater sanual lineup valves should not be exercised during normal operation. CSV-41 This cold shutdown justification was added to the program. The normally locked closed auxiliary feedwater manual valves discussed in this relief request are opened as required by the abnormal operating procedures to provide service water to the auxiliary feedwater pumps in the event of an accident where all normal auxiliary feedwater pump supplies have been exhausted. Opening these x valves every three months to fulfill quarterly testing requirements would accelerate the buildup of sludge in the supply lines from the service water system. The supply lines are flushed once every 18 months to reduce the buildup of sludge and to identify if there is any accumulation of asiatic clams or shell debris in the lines. Because these manual valves remain in the closed position during normal operation and are not subject to wear, exercising these valves on a cold shutdown test frequency is adequate to demonstrate that the valves can be opened in the case where service water is required as a supply for the auxiliary feedwater pumps. CSV-42 This cold shutdown justification for the power operated relief valves 2-RC-PCV-2455C and 2456 is ! being added to replace Relief request V-27. O v 50 l
I i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 - [ IST PROGRAM, REVISION 7 '
~ -
2.3.7 ALTERNATIVE TESTING FOR NON-CODE VALVES Starting with Revision 7 to the IST Program, non-Code valves that are included in the IST Program but are not tested to the - provisions of the Code will be discussed-in this new section. Although a request for relief is not required for non-Code . components, the reasons for why the Code provisions are not met ! and the alternative testing description should be documented with the IST Program. ; . NON-CODE ALTERNATIVE i TESTING DESCRIPTION COMMENT VNC-1 Due to the plant configuration, the PORV service t air valves cannot be verified closed using flow. ! The only method to verify closure other than disaasembly and inspection is to perform a local ' (~ leak rate /back pressure test. To perform the leak L, rate /back pressure test, the normal instrument air , and nitrogen supplies to the PORVs must be isolated. The PORVs are required to be operable during normal operation. Also, these valves are located inside containment and are inaccessible ' during normal operation. These valves are also subject to leak testing, which is performed-every reactor refueling. Verification of closure will be performed during the leak test every reactor refueling instead of every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify the burden of performing a back pressure test.
?
Valves 2-IA-2130 and 2131 are in series and valves ; 2-IA-2132 and 2133 are in series. There are no vents in between the two sets of valves; therefore, these valves cannot be individually ' back pressure tented or leak tested. VNC-2 Relief Request V-65 was replaced by this non-Code i alternative testing description because the valves in V-65 (2-IA-396, 397, 405 and 406) are non-Code. .L 51
e F
SUMMARY
OF CHANGES TO NORTH AN'NA UNIT 2 I' IST PROGRAM, REVISION 7 b)
~ .-
Also, the following leak test method description was added. The leak test will consist-of pressurizing the volume upstream of the two valves in series and venting downstream of the valves. Then the upstream test volume will be isolated. If a given differential pressure across the two valves in series can be maintained for a , predetermined period of time, the test will be satisfactory. The actual leak rate will not be measured. VNC-3 In lieu of a leakage test for the non-Code isolation check valves 2-IA-504, 510, 516, 525, 531, 537, 543, and 549, the main valves will be cycled the required number of times over the required period as defined by their design requirements with the normal air supply isolated and vented. VNC-4 Relief Request V-56 was replaced by this non-Code alternative testing description because the diesel air start system valves in V-56 are non-Code. VNC-5 Non-Code check valves 2-IA-497 and 499 close in . the event of a loss of pressure in the respective instrument air supply header to prevent _ blowdown of the nitrogen reserve volume tank which supplies the hydrogen recombiner system isolation valves.. Testing the check valves to the closed position requires that the instrument air supply be isolated to both Units 1 and 2 hydrogen recombiner isolation valves, the high radiation sampling subsystem, and various liquid waste and boron- ! recovery system components. Isolating the instrument air supply to these systems every three ' months to perform the back pressure test would be disruptive to normal plant operation. Therefore, these valves should not be closure tested every ; three months. ! The check valves are also subject to leak testing at least once every 24 months. These check valves will be closure tested at least once every 24 months during the leak test because the small increase in safety gained by performing the back pressure test every cold shutdown does not justify ! the disruption of normal operating activities of 52 l l
^
i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 ( ; IST PROGRAM, REVISION 7 i the opposite unit or the added burden of performing the back pressure test on the more frequent schedule. I 1 a O ! i l l O 53 P b
~ .-
VIRGINIA EG efhIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE TESTING PROGRAM PLAN ' FOR PUMPS AND VALVES SECOND INSPECTION INTERVAL DECEMBER 14, 1990 - DECEMBER 14, 2000 REVISION 7
)
f a V
1 V 1 I ABSTRACT
,/)
(,_, VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE TESTING PROGRAM PLAN ! FOR-PUMPS- AND VALVES SECOND INSPECTION INTERVAL DECEMBER 14, 1990 TO DECEMBER 14,.2000 'i The interval for which the North Anna Unit 2 Inservice Testing- [ Program (IST) program is applicable commenced on December 14, 1990, and will end on December 14, 2000. The Inservice Testing Program was developed employing 10CFR50 which references ASME Section XI, 1986 Edition, and Reg. Guide 1.26. Quality Groups A, B, and C are the same as ASME Classes 1, 2, ar.d 3 respectively. Section 1: Introduces the Inservice Testing Program. Section 2: Describes the Class.1, 2, and 3 pump and valve Inservice Testing Program developed in accordance with Subsections IWP and IWV of ASME Section XI. Certain pumps and valves within the boundaries defined by the ISI classification Boundary Drawings are subject to testing except where relief from O - examination is noted in Section 2. A Component listing is also provided in Section 2. t I \ V 11 N2PVR7 Revision 7 November 5, 1993 4
'k
)
5- . l TABLE OF CONTENTS l SECTION TITLE PAGE ' i Assignment 11 Distribution Record f 111 Abstract i iv Table of Contents 1 Introduction i 2 Inservice Testing Program Plan l for Pumps and Valves
.i ^
111 N2PVR7. Revision 7. November 5, 1993 l t (
e^%
.h'
~ -
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES SECOND INSPECTION INTERVAL DECEMBER 14, 1990 - DECEMBER 14, 2000 REVISION 7 l 1 1-1 N2PVR7 Revision 7. November 5, 1993 L _ - - _ _ _ _ _ _ - - - . _ _ - - - - - -_---------.-.-----1------------ - - _ - - - - - --
'Y
[d
1.0 INTRODUCTION
1.1 GENERAL INFORMATION North Anna Power Station Unit 2 is a Pressurized Water Reactor located on Lake Anna in Louisa County, Virginia. The plant employs a Westinghouse Electric Corp. Nuclear Steam System. The Inservice Test b 7 (IST) Program Plan for Pumps and Valves for North Jnr,5 Station Unit 2 was developed in compliance with the ales and regulations of 10CFR50.55a and Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Edition. Where these rules are determined to be impractical, specific relief is requested in writing. The Inservice Testing Program for Class 1, 2, and 3 and certain non-Code class pumps and valves is applicable for the second ten year interval beginning December 14, 1990 and ending December 14, 2000. ) 1.2 SYSTEM CLASSIFICATION The construction permit for North Anna Unit 2 was issued on February 19, 1971. At that time, the ASME Boiler and g-~g Pressure Vessel Code covered only pressure vessels. Pumps ( ,) and valves were built primarily to the rules of USAS B31,7. Essentially, North Anna Power Station was designed and constructed prior to the origination of the ASME Code classifications named Class 1, 2, and 3. Therefore, t'e system classifications used as a basis for the Inservice Testing Program are based on the requirements set forth.in 10CFR50 and Regulatory Guide 1.26. Pursuant to 10CFR50.55a paragraph (g) (1) , inservice testing requirements of Section XI of the ASME Code are then assigned to these components, within the constraints of existing plant design. Classification Boundary Drawings (CBD's) documenting the system classifications and defining the scope of the ISI and IST Programs, were developed to aid in the review and implementation of the subject programs. (D \_/ 1-2 N2PVR7 Revision 7 November 5, 1993
p , i i es \ 1.\, /
~ _.
r VIRGINIA ELECTRIC AND POWER COMPANY , NORTH ANNA POWER STATION-UNIT 2 , INSERVICE TESTING PROGRAM PLAN-FOR PUMPS AND VALVES SECOND INSPECTION INTERVAL i L s N2PVR7 Revision.7 November 5, 1993
L1 F SECTION 2 TABLE OF CONTENTS [J~) , 2.0 INSERVICE TESTING PROGRAM -PLAN FOR PUMPS AND VALVES ' PAGE
2.1 INTRODUCTION
...................................... 2-3 2.2 PUMP INSERVICE TESTING PROGRAM DESCRIPTION l 2.2.1 Program Development Philosophy............ 2-4 [ 2.2.2 Program Implementation.................... 2-5 ! 2.2.3 Program' Administration.................... 2-5 2.2.4 Pump Testing List......................... 2-5 2.2.5 Pump Inservice Testing Table.............. 2-8 , 2.2.6 Pump Inservice Testing Program Relief
- Requests.................................. 2-14 2.2.7 Alternative Testing for Non-Code Pumps.... 2-34 2.3 VALVE INSERVICE TESTING PROGRAM DESCRIPTION 2.3.1 Program Development Philosophy............ 2-37 2.3.2 Program Implementation.................... 2-38 2.3.3 Program Administration.................... 2-40 '
2.3.4 Valve Inservice Testing Table............. 2 ' 2.3.5- Valve Inservice Testing Program Relief l
. Requests.................................. 2-43
' 2.3.6 Valve Inservice Testing Program Cold Shutdown Justifications............................ 2-104 2.3.7 ' Alternative Testing for Non-Code Valves... 2-140-l 2.4 REPORTING OF INSERVICE TESTING RESULTS 2.4.1 Pump Inservice Testing Program............ 2-149 2.4.2 Valve Inservice Testing Program........... 2-149 2.5 QUALITY ASSURANCE PROGRAM................... 2-151 s
i 2-2 l N2PVR7 Revision 7 November 5, 1993 ' l
.j
i \ ;R Q? v W, d
't, O' p
1 IMAGE EVALUATION to q, A Q, O / f
/// \ ' .h*
% TEST TARGET (MT-3) & [, g, gjp /f/p, n. 4 , R?
%q$
$i /Q rgy*
+% 7<a 1.0 F~ 7" F+
L*32. p 2.2
,p nim 4
'l2.0 j,l g'- -
la= 01.8
!!asas 1.25 1.4 j i.6
;=
150mm > 4 -- 6" > 4 Y' 4IP 'ki*g + 4% 4 #+%+ r,", , . r // w, ,a,;> ,s %% goy ,. ///xxN Q sy.
,/ /
/ ..-,,
e r; A x. d,g3 4 N
.a e a
R. Y*
& ~&
,;;ey-;vq, n m:,
0 1'5 IMAGE EVALUATION
/
O e
/e /
Q %< ?'
/
\/p 'i. *
/1
'$g#? TEST TARGET (MT-3) e/4@% db 4, sv 9
%f// gp) ,//
+ $
l.0 ,_ m '," mF ira Y l'+ I.I :
' "=_h I l.8
! ===
1.25 l.4 lj L6 __ ume
- 150mm >
4 6" > 4_ ..
.q*?
A.
%t 43 4 ///h x 4, -
.e. -
^ \
~~~.. #fk 3 e r / 7 C'"~
*v \gN , ,
k @;;g. ne v l o;, / t ,
I ,. 4 4 p / y
.p o
0 e Q, v W. 0:c *,
$ Q,
//jj///j to F IMAGE EVALUATION
\)j//o/ 'E[,^ 9$9 TEST TARGET (MT-3) /',[I pg
$'7Y/ g b '
k'gi k'
+4 +
1.0 E '" E'? o L:" p22 L. , nu -' l,l en $M t ll; n==s 1.25 1.4 l 1.6 l nl.
=mm 150mm >
4 6" - > A% A w n; y . 4r - e+ s+*///o ,. xi s , e+ sg
,/
,e 4f,p,;9.
v ,4 @3' C-/ s, (s a
- i. . *S*'
7' l?3
b A' 4 / e O
w"' e ,
\f SQM'e ~~
IMAGE EVAL.UATION 'e
% 9," b j/ '(' *i9
\//o/ TEST TARGET (MT-3) j0 ((4.(pg f Ik
$k/ g-[ f
+ %
l.O 3"
~ . . - y%n L. L u -
i f-- hbk l l.8 haz=2 1.25 1.4 1.6
, _ _ == me 4 --
150mm > g______...__. . . - - 6" >
<h '
"e #484 ff77+\\
4%
%),fi;,;7 h 4)47f 44 4fk;u%o II
,g:-
a /fx v
,Vij/,. t c
s
-6qd, 4wV .+
0 (7/ ,
\
3
Code Class, test quantities to be measured, test frequency, and relief requests if required. The following is a brief explanation of the abbreviations used in the Pump Inservice Test Table. NC - Non-class i I Var. - Variable Resistance System j Fixed - Fixed Resistance System Q - Quarterly Test Frequency 1 CS - Cold Shutdown Test Frequency (not-more frequently than quarterly) ; i RR - Reactor Refueling (nominally 18 months, not to i exceed 24 months) j l 2Y - 24 Months j N/A - Not applicable or impractical, relief requests ! will explain in detail _; 2-8 N2PVR7 Revision 7 November 5, 1993 l i .) e i ? Under Speed, N/A applies to constant speed pumps which do not require the measurement of speed. Therefore, no-
- f-((~)'N - relief is necessary.
Under Lube Oil,-N/A applies to pumps that have a i lubrication system with no level or pressure j indication. Therefore, no relief is necessary. 1
-i i
.i l
l I
i 1
4 i
3 i
/"
I i 2-9 N2PVR7 Revision 7 November 5, 1993 ;
)
i
O O O PUMP INSERVICE TESTING TABLE .
Relief "
Pump ASME System (1) Inlet Differential Flow Lube Bear Request Ident Class Resist Speed Pressure Pressure Rate Vibration Oil Temo. (P- 1 2-CC-P-1A 3 VAR. N/A O O O O O N/A 1.12.13.16 2-CC-P-1B 3 VAR. N/A O O ^ O O N/A 1.12.13.16 2-CH-P-1A 2 VAR. N/A O O O O O N/A 1.13.16 2-CH-P-1B 2 VAR. N/A O O O O O N/A 1.13.16 2-CH-P-1C 2 VAR. N/A O O O O O N/A 1.13.16 1-CH-P-2C 3 FIXED N/AS O O RR O O N/A 1.15.16 1-CH-P-2D 3 FIXED N/Am o O RR O O N/A 1.15.16 1
2-EG-P-2HA NC VAR. N/A N/A N/A O O N/A N/A 1.PCN-1 2-EG-P-2HB NC VAR. N/A N/A N/A 0 0 N/A N/A 1.PCN-1 2-EG-P-2JA NC VAR. N/A N/A N/A O O N/A N/A 1.PCN-1 2-EG-P-2JB NC VAR. N/A N/A N/A O O N/A N/A 1.PCN-1 2-10 N2PVR7 Revision 7 November 5, 1993
. . . . ~ . - _ . . -._. . - _.,_ -. ~ . - . _ . _ - - - - . - - - . - . .- - -_ __ _ _ _ _ _ _ - . - . _ _ . _ _ . .
O O O l
i PUMP INSERVICE TESTING TABLE Relief
! Pump ASME System (1) Inlet Differential Flow Lube Bear Request l Ident Class Resist Speed Pressure Pressure Rate Vibration Oil Temp. (P- )
! 2-FW-P-2 3 VAR. O O O O O O N/A 1.16 2-FW-P-3A 3 VAR. N/A O O O O O N/A 1.16 2-FW-P-3B 3 VAR. N/A O O O O O N/A 1.16 2-OS-P-1A 2 FIXED N/A O O O O O N/A 1,16 2-OS-P-1B 2 FIXED N/A O O O O O N/A 1.16 2-RH-P-1A 2 VAR. N/A RR RR RR RR RR N/A 1.5.16-2-RH-P-1B 2 VAR. N/A RR RR RR RR RR N/A 1.E' 16 2-RS-P-1A 2 VAR. N/A RR RR RR RR N/A N/A !
1 2-RS-P-1B 2 VAR. N/A RR RR RR TR N/A N/A 1 2-RS-P-2A 2 VAR. N/A 2Y 2Y 2Y 2Y N/A N/A 1 2-RS-P-2B 2 VAR. N/A 2Y 2Y 2Y 2Y N/A N/A 1 2-RS-P-3A 3 VAR. N/A O O O O O N/A 1.16 2-RS-P-3B 3 VAR. N/A O O O O O N/A 1.16 2-11 N2PVR7 Revision 7 November 5, 1993
.m (v- l' PUMP INSERVICE TESTING TABLE Relief Pump ASME System (1) Inle? Differential Flow Lube Bear Request Ident Class Resist Speed Pressure Pressure Rate Vibration Oil Temp. (P- 1 2-SI-P-1A 2 FIXED N/A O O O O O N/A 1 2-SI-P-1B 2 FIXED N/A O O O O O N/A 1 2-SW-P-1A 3 VAR. N/A N/A N/A O O O. N/A 1.9.12-2-SW-P-1B 3 VAR. N/A N/A N/A O O O N/A 1.9.12 2-SW-P-4 VAR. N/A N/A N/A O O O N/A 1.10.12 2-HV-P-20A 3 VAR. N/A O O O O N/A N/A 1.16 2-HV-P-20B 3 VAR. N/A O O O O N/A N/A 1.16 2-HV-P-20C 3 VAR. N/A O O O O N/A N/A d.16 2-12 N2PVR7 Revision 7 November 5, 1993
__.____ _- . _ . _ . - _ - - . ~ . - - - - . , . . . , , - _ - . . . . .- . -a _ _ _ . , _ - , . _ , - , ...._. -_~ . _ -
O o O PUMP INSERVICE TESTING TABLE Relisf Pump ASME System (1) Inlet Differential Flow Lube Bear Request Ident Class Resist Soeed Pressure Pressure Rate Vibration Oil Temo. (P- 1 2-HV-P-22A-3 VAR. N/A O O O O N/A N/A 1.16 2-HV-P-22B 3 VAR. N/A O O O O N/A N/A 1.16 2-HV-P-22C 3 VAR. N/A O O O O N/A N/A 1.16 l
(1) Speed is measured for variable speed pumps. 2-t'W-P-2 is the only variable speed pump in this program.
(2) Pumps 1-CH-P-2C and D have two-speeds; however, they are tested at the high speed and are considered constant speed pumps per this program.
2-13 N2PVR7 Revision 7 November 5, 1993
't. ,
.i 2.2.6~ PUMP INSERVICE TESTING. PROGRAM' RELIEF' REQUESTS-7'N i .. i I.k / Relief.' requests identify those ASME Section XI Code'-
~
requirements considered..to be impractical. .The basis' ;{
for the. relief requeet and the . alternate testing. to be:- ';
performed ~is given. ,
i l
l h
.i i
I l
.i ;
8
)
f
-i I
q i
O.
i
?
1 i
'i i
i
.I i
O 2-14' _ .!
I L
i N2PVR7 Revision 7 I November 5, 1993 ;
44 P
RELIEF REQUEST P-1 O
V' I. IDENTIFICATION OF COMPONENTS ,
Systems: Various t Pump (s): IWP Program Pumps ,
See PUMP INSERVICE TEST TABLE.
Class :
II. IMPRACTICAL CODE REQUIREMENTS Measure pump bearing temperatures and vibration in '
mils.
III. BASIS FOR RELIEF Pump vibration and bearing temperature measurements are used to detect changes in the mechanical characteristics of a pump. Regular testing should detect developing problems, thus repairs can be initiated prior to a pump becoming inoperable. The ,
ASME Section XI minimum standards require measurements '
of the vibration amplitude (displacement) in mils every three months and bearing temperatures once per year.
Our proposed program is based on vibration readings in-velocity units rather than: vibration amplitude in mils displacement. This technique is an industry accepted method which is more sensitive to small changes that are indicative of developing mechanical problems and hence more meaningful. Velocity measurements detect not only high amplitude vibrations that indicate a major mechanical problem, but also the equally harmful low amplitude high frequency vibrations due~to misalignment in balance, or bearing wear that usually go undetected by simple displacement measurements.
In addition, these readings go far beyond the capabilities of a bearing temperature monitoring program. A bearing will be seriously degraded prior to '
the detection of increased heat at the bearing housing. !
Quarterly vibration velocity readings should achieve a much higher probability 1
2-15 N2PVR7 Revision 7 ]
November 5, 1993 l
)
i
t e rx RELIEF REQUEST P-1 (Cont.)
. k ,) of detecting developing problems than the once per-year.
reading of bearing temperatures. Bearing temperature tests present problems-which include the fc".4owing:
- 1. Certain systems have no recirculation test loops and a limited source of water. An enforced thirty minute run time would deplete the source.
- 2. The lubrication fluid for some pumps is taken from the process water, which can change temperature depending on ambient conditions. Data trending for these cases is not meaningful.
The small probability of detection of a bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the measurements. In addition, it is impractical to measure bearing temperatures on many pumps. Therefore, i the detection of possible bearing failure by a yearly temperature measurement is extremely unlikely.
IV. ALTERNATE TESTING Pump vibration measurements will be taken in vibration
()
f- velocity (in/sec). The evaluation of the readings will be per the attached table. The ranges of test parameters given in the attached table were taken from
.i ANSI /ASME OM (Part 6), An American National Standard !
In-Service Testing of Pumps.
b 1
1 i
I
%. l 2-16 l N2PVR7 Revision 7 November 5, 1993 4
p- p ~~ N d V [d RELIEF REQUEST P-1 (cont.)
RANGES OF TEST PARAMETERS f1)
PUMP PUMP TEST ACCEPT /3LE ALERT REQUIRED TYPE SPEED PARAMETER RANGE RANGE ACTION RANGE Centrifugal, 0600 rpm
- V, 52. 5 V,* >2. 5 V, to 6V, >
._6 V, Vertical Line
-Shaft and positive
-displacement but not >0.325 in/sec but not >0.70 in/sec screw pumps m ,
f Note: (1) V, is the vibration reference value in the selected units V, is vibration velocity measured peak, unfiltered (2) There are no pumps in this program that operate below 600 rpm (3) OM-6 does not address positive displacement screw pumps. The Emergency Diesel Generator Fuel Oil pumps are of this type and will be subject to the OM-6 Criteria.
(4) Small values for V, will produce small acceptable ranges for pump operation. Based on a small acceptance range, an adequately and smoothly running pump could be subject to corrective action. To avoid this situation, a minimum value for V, of 0.05 in/sec has been established for velocity measurements. Pumps with a measured reference value below 0.05 in/sec shall have subsequent test results compared to an acceptable range bast.d on 0.05 in/sec.
2-17 N2PVR7 Revision 7 November.5, 1993
, . RELIEF REQUEST P-2
'q]
Relief Request Withdrawn RELIEF REQUEST P-3 Relief Request withdrawn.
RELIEF REQUEST P-4 Relief Request withdrawn.
O 2-18 N2PVR7 Revision 7 November 5, 1993
.. o. -
1 i
e !
i 1,
RELIEF REQUEST P-5 1
'N/
I. IDENTIFICATION OF COMPONENTS System : Residual Heat Removal !
Pump (s): 2-RH-P-1A 2-RH-P-1B Class : 2 II. IMPRACTICAL CODE REQUIREMENTS .
Frequency of Pump. Test.
III. BASIS ."OR RELIEF The low pressure pumps take suction from and discharge to the Reactor Coolant System (RCS)which' operates at 2235 psig. This pressure is well above the operating pressure of the pumps; therefore, testing during normal .
operation is'not possible.
During cold shutdowns of short duration or if the reactor coolant pumps are left running during the cold ;
shutdown, both trains of RHR may be required for decay g
(^s) heat removal and to maintain RCS temperature. Taking one' train of RHR out of service for testing purposes even for a short period could' allow the RCS temperature to increase to the point that the pressurizer power operated relief valve would be challenged. . Therefore, these pumps should only be tested during reactor refuelings. -
IV. ALTERNATE TESTING ,
These pumps will be tested every reactor refueling._ '
t
;f 2-19 N2PVR7 Revision 7 i November 5, 1993 {
j:;
i .-
1 r'N RELIEF REQUEST P-6
.f !.
.% /
1-Relief Request Withdrawn i RELIEF-REQUEST P-7 .;
8 Relief Request Withdrawn !
RELIEF REQUEST P-8 ,
Relief Request withdrawn.
("'T ..
\_sl i
1 I
i
~5 1 1
^s/ 2-20 N2PVR7 Revision 7 November 5, 1993 .]
1
i i
c ,-
RELIEF REQUEST P-9
-l :
' \~, ;
L I. IDENTIFICATION OF COMPONENTS l
System : Service Water l Pump (s): 2-SW-P-1A 2-SW-P-1B .
Class : 3 II. IMPRACTICAL CODE REQUIREMENTS Measure inlet pressure and differential pressure.
l; III. BASIS FOR RELIEF f
These pumps take suction from the Service Water i Reservoir. No inlet pressure instrumentation is installed. The service water reservoir level indicator ('
is located outside and several feet away from the observation point. Also, the measuring stick tends to collect residue from the surface of the reservoir, thus ';
obscuring the markers. Therefore,_ measuring'the ,
reservoir level can be difficult during periods of l geg inclement weather or low light conditions. -
\-) i However, the reservoir level fluctuates very little and can be considered to be constant. The Service Water Reservoir has a minimum level of 313 feet elevation as required by_ Technical Specifications and a maximum recorded level during past testing of 314.9 feet.
Therefore, the expected maximum variation in reservoir '
level is less than 2 feet, which is less than 1 psi.
The discharge pressure gauge has a full scale reading _ ,
of 100 psig and typical discharge pressures range from ~ !
50 to 65 psig. Even the maximum variation, which in i all probability will not occur between successive. ,
tests, is a small percentage of the total head ,
developed by the pump. Therefore, the repeatability of the tests and the ability to detect degradation will not be significantly affected if only discharge ~
t pressure is measured.
I-Applying the Code acceptance criteria to discharge pressure instead of differential pressure is a-conservative application of the acceptance criteria for i deep-draft pumps. For these pumps, the total developed !
head is. calculated by adding the measured discharge pressure to the height from the discharge pressure l
\
2-21 '
N2PVR7 Revision 7 November 5, "993 l
I
F --
i l-l RELIEF REQUEST P-9 (Cont.) ,
[',) ,
\,__/
gauge to the pump impeller, and subtracting the: height ,
from the reservoir-surface to the pump impeller. ;
Therefore, the measured discharge-pressure will always be a smaller number than the actual total head developed by the pump. Applying the Section XI acceptance criteria to just the discharge pressure instead of the total _ developed head for a deep draft pump is a conservative application of the acceptance criteria because the operability band is smaller.
. IV. ALTERNATE TESTING Discharge pressure will be measured in place of differential pressure, ,
P i
I r
2-22 N2PVR7 Revision 7 November 5, 1993 .
E l
RELIEF RdQUEST P-10 e
(~)
.Q.
I. IDENTIFICATION OF COMPONENTS ,
System : Service Water Pump (s): 2-SW-P-4 Class : 3 -
II. IMPRACTICAL CODE REQUIREMENTS j Measure inlet pressure and differential pressure.
III. BASIS FOR RELIEF !
This pump takes suction from Lake Anna. No inlet '
pressure instrumentation is installed. The North' Anna l lake level indicator is located outside and several feet away from the observation point. Also, the measuring stick tends to collect residue from the surface of the lake, thus obscuring the markers. -
Therefore, measuring the lake level can be difficult during periods of inclement weather or low light conditions.
-( ) However, the lake level fluctuates very little from test to test and can be considered to be constant. The lake has a minimum level of 244 feet elevation as required by Technical Specifications, and maximum and minimum recorded levels during past testing of'250.24 feet and 248.16 feet, respectively. Therefore, the expected maximum variation in lake level is about 2 feet, which is less than 1 psi. The discharge pressure i gauge has a full scale reading of 100 psig and the discharge pressures range from 50 to 65 psig.- Even the !
maximum variation, which in all probability will not occur between successive tests, is a small percentage i of the total head' developed by the pump. Therefore, the repeatability of the tests and the ability to detect degradation will not-be significantly affected if only discharge pressure is measured.
Applying the Code acceptance criteria to discharge '
pressure instead of differential pressure is a conservative application of the acceptance criteria for :
the deep draft pump. For this pump, the total l developed head is calculated by adding the measured ;
discharge pressure-to the height from the discharge '
pressure gauge to the pump impeller, and subtracting l
2-23 i N2PVR7 Revision 7 l November 5, 1993 .i
E
!~
RELIEF REQUEST P-10 (Cont.)
5
" y~)
's..
the height from the lake surface to the pump impeller.
Therefore, the measured discharge pressure will-always be a' smaller. number than the actual total head developed by the pump. Applying the Section XI acceptance criteria to just the discharge pressure instead of the total developed head for a deep draft pump is a conservative application of the acceptance criteria because the operability band is smaller.
IV. ALTERNATE TESTING Discharge pressure will be measured in place of differential pressure.
O 2-24 N2PVR7 Revision 7 November 5, 1993
n--
I RELIEF REQUEST P-11 Relief Request withdrawn.
j O
2-25 N2PVR7 Revision 7 November 5, 1993
..,_, RELIEF REQUEST P-12 j V[
l' I. IDENTIFICATION OF' COMPONENTS i System : Component Cooling and Service Water l Pump (s): 2-CC-P-1A 2-SW-P-1A -t 2-CC-P-1B 2-SW-P-1B 2-SW-P-4 Class : 3 II. IMPRACTICAL CODE REQUIREMENTS i
ASME XI, Subarticle IWP-3110 requires reference values ;
to be one or more fixed set of measured values. All i subsequent test results shall be compared to these reference values. -
III. BASIS FOR RELIEF Plant conditions may not be the same as when the reference values' vere established. Many reference points must be established to anticipate future plant a conditions. In the Component Cooling and Service Water ;
Systems, reproducing one of these reference flow points O.
is difficult with the large butterfly valves installed -
and it may not be desirable to alter cooling because of ;
other plant operating parameters.
{
Past vibration data for the subject pumps has been reviewed and it has been determined that pump-vibration does not vary significantly with flow rate over the +
range of the test flow rates.
IV. ALTERNATE TESTING .,
t All subsequent test results will be compared to :
calculated reference values which are determined using the following method. A set of at least five pressure / flow points will be recorded. From these points an equation for the line will be calculated by a '
computer using polynomial regression. The resulting .
polynomial equation describes the reference curve. l f
)
1 O N2PVR7 2-26 1
Revision 7 November 5,.1993
l;
~x. RELIEF REQUEST P-12 -(Cont. ) i
(.)-
Flow points will be taken between the limits of the original data points. The resulting pressure is then compared to the -ASME MI, Table IWP-3100-2 limits. ,
Pumps may then be tested during normal operation ;
without any valve throttling. An example of acceptance criteria based on a reference curve is shown in Figure 1.
L t
I i
i I
+
i
(^~ l
\ 2-27
- N2PVR7 Revision 7 November 5, 1993
i i
i
- ['N .
! )
v 300
-'..* , * . * * ~
- g ,
- ' s,* '
"a..^
95 s . ,
' Alert Rase
- [**.,,:.
s . /
N g A u s ptah *.
- ""a* ;
- s. ,
(Room,eo Aa.n Range)
- 's ~
- s. ::.._
85 s
- s..*.,
s
* . .*** s ' s'.,
*.**, s s
- s s. ,
80
*.., 's, ' .** * . ,
i
=g ,
Aien Range <. .**.,; ?
s.
,..*.*..,*, s s, s n
s '.
s'.,
75 ye -
s
- s. ,
a -
(.s'.
- , . . . . ,s, ,s '..
6 5 s*..
- s. s.*".
y" 70 - -
. . . . ' . s. ~,
- ~.
, s s z..
c - .... s s.s.
f( O 65
~
\s s
t
4 *.,
- Required Action Range) *.., . '* ,
- g. .
g .,
1 60 .
. , . ' ,,s 's s...
s s
s.s .
.*.,.s s 55 . .
. t
.s s s
. s 50 saii,iiii,iiii isli lisi siis ails tili alls till liti lili 6 000 6.500 7.000 7,500 8.000 8,500 9.000 9.500 10.000 10.500 11,000 11,500 12.000 Total F6ow Rate (gpm) * * ' * * '
i Figure 1. Pump Acceptance Criteria Based on a Reference Curve i
1
.i
( !
s 2-28 H2PVR7 a Revision 7 November 5, 1993 !
l 1
y
'l l
RELIEF REQUEST P-13
[Q3)
I. IDENTIFICATION OF COMPONENTS System : Component Cooling :
Chemical and Volume control '
i Pump (s): 2-CH-P-1A 2-CC-P-1A 2-SW-P-1A 2-CH-P-1B 2-CC-P-1B 2-SW-P-1B 2-CH-P-1C 2-SW-P-4 Class : Class 2 for CH and Class 3 for CC and SW II. IMPRACTICAL CODE REQUIREMENTS Instrument Error III. BASIS FOR REQUEST Instruments used to measure certain pump parameters receive their signal at the equipment, which_is transmitted to a process rack and then to a control room indicator. The sensor and rack accuracy can be affected by drift, temperature, and calibration accuracy. The indicator has a limit of accuracy. The total loop accuracy is found by the root sum of the O' squares. The only variables in this formula are the sensor calibration accuracy and the indicator accuracy.
Installing new sensors and indicators to reduce the 1 accuracy by one percent is not warranted by the !
increase in safety obtained.
The following instrument loops exceed the 2% tolerance listed in Table IWP 4110-1.
Instrument Component Parameter Accuracy ,
FI-2122 2-CH-P-1A,B,C Flow 2.34%
FI-CC-200A 2-CC-P-1A Flow 2.69%
FI-CC-200B 2-CC-P-1B Flow 2.69%
PI-SW-201A 2-SW-P-1A Discharge Pressure 3.18%
PI-SW-201B 2-SW-P-1B Discharge Pressure 3.18% l PI-SW-210 2-SW-P-4 Discharge Pressure 2.61% >
t i
IV. ALTERNATE TESTING '
None i 2-29 N2PVR7 Revision 7 >
November 5, 1993 ;
g RELIEF REQUEST P-14 l
+
\
Relief Request withdrawn.
i 4
I f
l
-1 i
4 e
j' a
i 4
d t 4
\
. 2-30 4
N2PVR7 Revision 7 November 5, 1993 P
h
, - ,. m , , . . , . -
4 i.
7 ;. RELIEF REQUEST P-15 1 4
.<J I. IDENTIFICATION OF COMPONENTS System : Boric Acid Transfer ;
Pumpts): 1-CH-P-2C 1-CH-P-2D Class : 3 II. IMPRACTICAL CODE REQUIREMENTS Frequency of pump testing.
III. BASIS FOR RELIEF ,
Permanent flow instrumentation is not installed on the recirculation piping, which is the only test loop available for quarterly testing. To measure flow, flow must be established to the emergency and alternate' boration paths and then to the charging pump suctions.
This flow would increase the reactor coolant system (RCS) boron inventory and cause a reactivity transient during normal operation.
( During cold shutdown, the emergency and alternate.
boration path valves are tested with flow.
i However, this test is short in duration to minimize the amount >
of boric acid injected into the RCS. The pump test requires an extended period of boric acid injection, which would upset the RCS boron balance and possibly '
impact the ability of the plant to restart. . Therefore, this test should only be performed during cold shutdowns on the way to reactor refueling while the RCS l is being borated or during reactor refuelings.
During RCS boration or during reactor refuelings, extended periods of pump operation on high speed can ,
either interfere with the boration process or adversely t affect the boron balance in the RCS. Therefore, to' limit the amount of boric acid injected into the RCS l during the pump tests, the pumps will be run for two ;
minutes with flow to the RCS before the test quantities- i are measured.
)
/~%
k- l 2-31 N2PVR7 Revision 7 November 5, 1993
= . . . , ..
'l F -!
> 1
.1
$#- l RELIEF REQUEST P-15 (Cont.) :
V
!~)
(m /
1 IV. ALTERNATE. TESTING- I l
-These pumps will be tested every.. quarter on the
- recirculation loop. Inlet pressure,. differential pressure and vibration will'be' measured.- Every reactor-refueling,'in1'et-pressure,-differential pressure,' flow: :
I and vibration will-be measured'after the-pumps.have, t been run for two minutes with flow to the RCS. 8 4
i i
L t
- i kw i b
9
.i I
t a
5 L!
(
O 2-32 i
I N2PVR7 Revision 7.
November 5, 1993 ]j 4
J
i.
_ RELIEF REQUEST P-16 LY I. IDENTIFI TION OF COMPONENTS System : vt rious -
Pump (s): IWP Program Pumps ,
See PUMP INSERVICE TEST TABLE. -
Class :
II. IMPRACTICAL CODE REQUIREMENTS Pump inlet pressure shall be measured before starting a pump and during the test (Table IWP-3100-1)
III. BASIS FOR REQUEST '
If the pump being tested is in operation as a result of normal plant or system needs, it is unreasonable to reconfigure system lineups just to provide for the measurement of static inlet pressure. Inlet pressure prior to pump startup is not a significant parameter needed for evaluating pump performance or condition.
^ IV. ALTERNATE TESTING When performing a test on a pump that is already in i operation, inlet pressure will only be measured during pump operation.
i i
P 5
/^
2-33 ;
N2PVR7 Revision 7 November 5, 1993 t
,, 2.2.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS ,
( )
(,/- According to the Minutes of the Public Meeting on Generic Letter 89-04, " Paragraph (g) of 10CFR 50.55a requires the use-of Section XI of the ASME Code for inservice testing of components covered by.the Code.
For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a
' request for relief' to be submitted to the staff.
Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety, but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.
North Anna Power Station has elected to include certain 7g non-Code components in the ASME IST program. Where the
)
( Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability. The alternate testing is described in this section. There may be other deviations from Code provisions that are not described in this section. For these cases, documentation is available at the plant site.
As indicated in the Minutes of the Public Meeting on Generic Letter 89-04, a ' request for relief' need not be submitted for non-Code components. Therefore, the alternative tests described in this section are not
' requests for relief' but are provided for information.
i
/~T k-sl 2-34 N2PVR7 Revision 7 November 5, 1993 1
i I
i NON-CODE ALTERNATIVE TESTING PNC-1
{
I. IDENTIFICATION OF COMPONENTS $
System : Fuel Oil l Pump (s): 2-EG-P-21A 2-EG-P-2JA l 2-EG-P-2HB 2-EG-P-2JB l
Class : NC .
II. IMPRACTICAL CODE REQUIREMENTS :i t
.I Measure test quantities after the pump has been running; :1 for five minutes. i Measure pump bea' ring temperatures and vibration in. ;
mils. '
Measure Inlet and differential pressure. I i
III. BASIS FOR ALTERNATIVE TESTING The pump operating time is limited due to operational restraints.' These pumps start' automatically when fuel.
oil level in'the day tank reaches the low;1evel switch, O, and stop when the level reaches the high f level switch. -
If the pumps are allowed to run for five. minutes prior l to measuring the test quantities, the day tank may fill ;
past the high level switch and cause the pump to-stop. ,
Therefore, the day. tar 9c will. fill'and the pump will ;
stop prior to the gathering _of all of the required- '
Section XI test data..
.)
The basis for. alternative testing for vibration and -l temperature is described in; Relief Request P-1. -i The diesel fuel oil transfer pumps are positive j displacement pumps. One characteristic of. positive i displacement-pumps is that the discharge pressure is. !
independent of-inlet pressure. Therefore, to determine 1 pump degradation, only discharge pressure need be - .j measured. The ASME OM Part 6, Code-1987, with' Addenda' i to OMa-1988, Table'2, which is replacing Section XI, j Subsection IWP, requires that'only discharge pressure ;
need be measured for positive displacement pumps. .
i i
i 2-35 N2PVR7 Revision 7 l November 5, 1993 i 1
f
,- NON-CODE ALTERNATIVE TESTING PNC-1 (Cont.)
(j\
IV. ALTERNATE TESTING The measurement of Section XI quantities will begin when the flow indicat4on stabilizes after the pump is started (i.e., less than five minutes after the pump is started).
The alternative testing for vibration and temperature is described in Relief Request P-1.
Inlet pressure will not be measured. ~ Discharge pressure, flow and vibration will be measured at least once overy three months in accordance with Section XI requirements. The acceptance criteria for flow and discharge pressure will be based on the criteria given in ASME OM Part 6, Code-1987, with Addenda to OMa-1988, Table 2. The acceptance criteria for vibration is addressed in Relief Request P-1.
(3 L
I t
[ ~h ,
2-36 N2PVR7 Revision 7 November 5, 1993
2.3 VALVE INSERVICE TESTING PROGRAM DESCRIPTION V 2.3.1 PROGRAM DEVELOPMENT PHILOSOPHY The North Anna Unit 2-valve Inservice Testing (IST)
Program has been established to meet the requirements >
of the 10CFR50, Section XI of the ASME Boiler and
- Pressure Vessel Code, Subsection IWV and Technical Specifications.
North Anna Unit 2 Technical Specification 4.0.5 states that Inservice Testing of ASME Code. Class 1, 2 and 3 valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10CFR50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10CFR50, Section 50.55a (g) (6) (i) ,
10CFR50, Section 50.55a(g) (4) (iv) states that inservice .
examinations of components, test of pumps and valves, and system pressure tests, may meet the requirements set forth in subsequent editions and addenda of ASME Section XI that have been approved by the NRC, subject to Commission approval. North Anna Unit 2 will test those valves that fall under the scope of ASME Section
()
f~w XI using Subsection IWV of the 1986 Edition of ASME Section XI. The scope of the program includes ASME Section XI Class 1, 2 and 3, and certain non-Code class r valves that are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident.
Subsection IWV of ASME Section XI defines the rules and requirements of inservice testing of Code Class 1 ,2, and 3 valves and states that each specific valve to be tested by the rules of this subsection shall be ;
identified by the owner and listed in the plant '
records.
The purpose of the IST program is to identify the valves that are considered by Virginia' Electric and Power Company as baving a safety function and are therefore subject to the testing requirements of Section XI, Subsection IWV. The intent of the Code is to assess operational readiness and detect potentially adverse changes in the mechanical condition of these valves. The relief requests for the Valve Inservice Test Program identify Code requirements considered to ;
be impractical, provide technical basis for the request '
and propose alternate testing when warranted.
i
\~ 2-37 N2PVR7 (
Revision 7 '
November 5, 1993
l L
i i-i One reason for requesting relief from the ASME Section XI testing requirements for exercising check valves to
[')T
(- the closed position is that the small increase in safety gained by performing these tests does not justify the comp'lications arising from performing such tests. In.some cases, to verify a check valve closes, a leak rate test must be performed. To perform a leak rate test, systems must be removed from service. Many systems are still required during-cold shutdowns and cannut be removed from service. Lines must also be drained or vented. The contents of the lines are often.
radioactive and require processing prior to release.
Draining and venting lines significantly increases the amount of radioactive waste produced by the plant.
An extended containment entry is required to perform leak rate tests. During short cold shutdowns, the concentrations of radioactive isotopes (Iodine-131, ,
Xenon-133, etc.) are high because the isotopes do not have sufficient time to decay. Entering containment under these conditions requires respirators or air packs to be worn. Working under these conditions is difficult and significantly increases the chances of internal contamination.
For the above reasons, all check valves inside
(~%g containment with the exception of those check valves
( / listed in T.S. 4.4.6.2.2 shall be exercised to the closed position each refueling shutdown.
Leak rate testing for containment isolation valves is performed in accordance with 10CFR50, Appendix J, which imposes specific requirements, and in accordance with IWV-3426 and 3427. Appendix J satisfies the testing requirements of Section XI, Paragraphs IWV-3421 to ,
3425.
2.3.2 PROGRAM IMPLEMENTATION The Valve Inservice Testing Program will be executed as part of the normal plant surveillance program which is implemented by periodic tests.
9 k
t 2-38 N2PVR7 Revision 7 November 5, 1993
~
i .
l The Operability Tests will' verify-
- 1) 'The valve responds to control commands.
t
- 2) The valve stroke -time is within specific i limits. ^i lJ
- 3) Remote valve position indication accurately reflects the valve position.: 1 Failsafe valvce vill be tested by observing-valve operation upen ss of actuating power. In most' cases, this can be accemplished using normal ~ control circuits.
i,
. Safety and relief valve setpoints are tested in !
accordance with ANSI /ASME OM-1-1981 as directed by IWV- "
3510. j Valve oxercising during cold shutdown shall commence within 48 hours of achieving cold shutdown,.and continue until all testing is complete or.the plant is ready to r eturn- to power. For extended outages, .;
testing nettd not be commenced'in 48 hours provided all- ;
valves required to be tested during cold shutdown will be tested prior to startup.
Certain valves cannot be full stroke exercised during normal operation ollowing maintenance. These valves are described in the relief requests and cold shutdown justifications. If maintenance _cannot be deferred to a shutdown condition, then an engineering evaluation must ;
be performed prior to the maintenance to determine the effect of the maintenanceLon valve. operability. If the evaluation shows that operability will not be affected, :
then no post maintenance testing will be required. A1 partial stroke test will be performed if possible.
I
'l l
'l i
s O 2-39
)
N2PVR7 Revision 7 November;5, 1993-
-I
; ,3 2.3.3 PROGRAM ADMINISTRATION 1 \
N- / The Engineering staff at North Anna is responsible for the administration of the Valve. Inservice Testing Program. The Operations staff is responsible for performing the periodic tests as required by this program. The Valve Inservice Testing Program is -
implemented by Station ISI Administrative Procedure 2.1 "ASME Section XI Valve Program" and Periodic Test Procedures.
2.3.4 VALVE INSERVICE TESTING TABLE The Valve Inservice Testing Table provides a list of North Anna Unit 2 ASME Section XI valves and their testing requirements. The following is a brief explanation of the table headings and abbreviations.
Valve Number - Each valve has a unique identification number.
Drawina Number - Classification Boundary Drawing Number.
Sheet Number - Classification Boundary Drawing Sheet f- Number.
I Dwa Coor - Drawing Coordinate of valve.
Valve Tyne - The type of valve. Some abbreviations are used for valve type which are explained below.
AO - air operated So - solenoid operated DIA - diaphragm MO - motor operated MAN - manual ,
BFLY - butterfly '
Valve Size - Valve size.
Valve Function - A brief description of the function of the valve.
ASME Class - ASME Code Class of each valve.
Note: NC is for non-class valves. '
i
\-
2-40 N2PVR7 Revision 7 November 5, 1993
P ASME XI IWV Cateaory - Categories as defined by ASME
/, Section XI. Categories determine test requirements.
l (. Valves marked with an "E" are passive valves.
L Test Position --The following abbreviations are used to L describe normal valve positions to which the valves are l tested (including the valve safety position):
0 - open C - closed OC - open and closed Isolation Valve Tvoe - Valves that are assigned a-maximum leakage. The following abbreviations are.used to describe the isolation valve types:
CIV - Containment Isolation Valve subject to Appendix J 1eakage testing PIV - Pressure Isolation Valve which protects low :
pressure safety related piping from RCS pressure C&P - Valves that serve both CIV and PIV functions Test Reauired - Testing requirements identified for the i valves are identified here.
g) i ST - Stroke times shall be measured per Section XI, Subsubarticle IWV-3410 or as modified by a specific relief request.
EV - Exercise Valve for operability at least once every 3 months per Section XI, Subsubarticle IWV-3410 or as modified by a specific relief request or cold shutdown justification.
LT - Leak Test shall be performed per Section XI, Subsubarticle IWV-3420 or as modified by specific relief request.
CV - Check Valves shall be exercised at least once every 3 months per Section XI, subsubarticle IWV-3520 or as modified by a specific relief request or cold-shutdown justification.
l L VP - Valve Position Indication Verification shall be verified per Section XI, Subsubarticle IWV-3300 or as l
modified by a specific relief request.
SP - Set points of safety and relief valves shall be tested per Section XI, Subsubarticle IWV-3510 or as modified by a specific relief request.
2-41 N2PVR7 Revision 7 j November 5, 1993 l
l-
-)
FS - Valves with fail-safe actuators shall be tested by observing the operation of the valves upon loss of the
(')'s
\_ - actuator power at least once every 3 months per Section '
XI, Subsubarticle IWV-3415 or as modified by,a specific relief request or cold shutdown justification.
Relief Recuest - The relief requests corresponding to the numbers in the table are in Section 2.3.5.
Cold Shutdown Justification - The cold shutdown justifications corresponding to the numbers in the table are in Section 2.3.6.
Non-Code Alternative Testino Descrintion - The non-Code alternative testing descriptions corresponding to the numbers in the table are in Section 2.3.7.
9
)
2-42 N2PVR7 Revision 7 November 5, 1993
VIRGINIA POWER COMPANY - PAGE: 1 0F 79 1 NORTH ANEA UNIT 2 REVISION: 07 I SECOND INSPECTION INTERVAL' DATE: 11/05/93.
INSERVICE TESTING PROGRAM - VALVE TABLE .
NC 150- REL CS- All ,
VALVE DRAWING' SHEET DRWG VALVE VALVE ASME ' !WV VALVE TEST - TEST REQ JUS 1 TEST .I NUMBER NUMBER NUMBER C00R TYPE -
SIZE CLASS CAT TYPE TYPE POS V- '
CSV- VCN-2 BD TV-200A 12050-CDM-098A 2 0F 5 C6 A0 GLOBE 3.000 2 A CIV EV. C FS C f
LT C +
ST C w !
x :
"A" STEAM GENERATOR BLOWDOWN, OUTSIDE CON-TAINMENT ISOLATION VALVE 2 BD-TV-200s 12050-CBM-09BA 2 0F 5 C5 Ao CLOBE 3.000 2 A CIV EV C '
FS C f
LT C ST C VP OC >
r
*A" STEAM GENERATOR BLOWDOWN, INSIDE CON-TAINMENT ISOLATION VALVE ;
e 2-BD-TV-200C 12050-CBM-09BA 3 0F 5 C6 A0 GLOBE 3.000 2 A CIV EV C '
FS C LT C '
ST C ,
VP DC '!
"B" STEAM GENERATOR BLOWDOWN, DUTSIDE CON-
-l' TAINMENT ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 2-BD-TV-2000 12050-CBM-098A 3 0F 5 C5 A0 GLOBE 3.000 2 A CIV EV C
^
FS C .
. LT C '
4 ST C
- VP OC "B" STEAM GENERATOR BLOWDOWN, INSIDE CON- e l
TAINMENT ISOLATION VALVE 2 BD-TV-200E 12050-CBM-098A 4 0F 5 t6 A0 GLOBE 3.000 2 A CIV EV C ?!
FS C LT C ST C VP OC t
"C" STEAM GENERATOR BLOWDOWN, CUTSIDE CON-
- TAINMENT ISOLATION VALVE 2-BD TV ?DOF 12050-CBM-D9BA 4 0F 5 C5 A0 GLOBE 3.000 2 A CIV EV C .
FS C LT C ST C ,
VP OC !
"C" STEAM GENERATOR ELOWDOWN, INSIDE CON-y TAlhMENT ISOLATION VALVE '
i i
l 1
sms i
I
VIRGINIA P0bRER COMPANY PAGE: 2 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/D5/93 INSERVICE TESTING PROGRAM - VALVE TABLE l jr-~s ,
\s "O ISO REL CS ALT- .*
VALVE- DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REO JUST TEST
' NUMBER NUMBER NUMBER C00R-TYPE -
SIZE CLASS CAT TYPE TYPE POS - V- CSV- VCN-CC-010 11715-CBM-079A 2 0F 3 E6 CHECK VALVE 18.000 3 C CV C i 0
"A" COMPONENT COOLING PtMP OISCHARGE CHECK VALVE I
2-CC-027 11715-CBM-079A 2 or 3 D6 CHECK VALVE 18.000 3 C CV C o
"B" COMPONENT COOLING PUMP OISCHARGE CHECK VALVE 2-CC-078 12050-CBM-079A 2 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 3 :
LT C CC SUPPLY TO "A" RC PUMP LO, STATOR SHROUD & =
THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV -
2-CC-107 12050-CBM-079A 2 OF 5 C7 CHECK VALVE 3.000 3 C CV C 66 CC SUPPLY TO "A" RC PUMP THERMAL BARRIER COOLER CHECK VALVE 2-CC-115 12050-CBM-079A 3 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 3 LT C ;
CC SUPPLY TO "B" RC PUMP LO, STATOR SHROUD &
THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV '
2-CC 144 12050 CBM-079A 3 0F 5 C7 CHECK VALVE 3.000 3 C CV C 66 ;
CC SUPPLY TO *B" RC PUMP THERMAL BARRIER +
COOLER CHECK VALVE .[
2-CC-152 12050-CBM-079A 4 OF 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 3 .
LT C- +
CC SUPPLY TO "C" RC PUMP LO, STATOR SHROUD &
THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV 2-CC-181 12050 CBM-079A - 4 0F 5 C7 CHECK VALVE 3.000 3 C CV C 66 ,
CC SUPPLY 70 "C" RC PUMP THERMAL BARRIER '
COOLER CHECK VALVE l
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 2-CC 194 12050 CBM 079A 1 0F 5 F 7 ' CHECK VALVE 18.000 2 AC CIV CV C 71 1 0 71 i LT C '
CC SUPPLY TO "A" RHR HEAT EXCHANGER
............................................................. ..... ..... ... ..... ..... . .. ... .... .... _j 2-CC-199 12D50-CBM-079A 1 0F 5 F7 CHECK VALVE 18.000 2 AC CIV CV C 71 ;
O 71 l LT - C CC SUPPLY TO "B" RHR HEAT EXCHANGER !
I 2 CC 276 12050-CBM-0798 3 0F 3 E8 CHECK VALVE 6.000 2 AC CIV CV C 63 LT C ;
i i
8 E
4 l
i I
O.
w .a- p
VIRGINIA POLER COPANY PAGE: 3 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL- DATE: 11/05/93 ,
INSERVICE TESTING PROGRAM - VALVE TABLE J 1
NC l I SO - REL CS ALT !
VALVE DRAWING SHEET DRWG VALVE l VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR M PE -
SIZE CLASS CAT TYPE TYPE POS V- I CSV VCN-CC SUPPLY TO "A" RECIRC AIR COOLING C0!LS, OUTSIDE CONTAINMENT ISOLATION CHECK VALVE 2-CC-289 12050-CBM-079s 3 0F 3 D8 CHECK VALVE 6.000 2 AC CIV CV C 63 i:
LT C CC SUPPLY TO "B" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION CHECK VALW
............................................................. ..... ..... ... ..... ..... .... ... . . , . .... s 2-CC-302 12050 CBM-0798 3 0F 3 C8 CHECK VALVE 6.D00 2 AC Civ CV C 63 i
- LT' C ;
l CC SUPPLY TO "C" RECIRC AIR COOLING COILS, t OUTSIDE CONTAINMENT ISOLATION CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... c;.
2-CC-Mov-200A 12050-CBM-079A 1 OF 5 A3 MO BFLY 18.000 3 8 EV 0 ?
ST C -
VP OC !
COMPONENT COOLING WATER RETURN THROTTLING VALVE FROM "A" RHR HEAT EXCHANGER !
2-CC-Mov-2008 12050-CBM-079A 1 0F 5 83 NO RFLY 18.000 3 B EV 0 j ST 0 !
VP OC s COMPONENT COOLING WATER RETURN THROTTLING VALVE FROM B" RNR HEAT EXCHANGER
{
2-CC-RV-224A 12050 CBM-079A 2 0F 5 F6 RELIEF VALVE 3.000 3 C SP 0 COMPONENT COOLING WATER TO REACTOR SHROUD f HEAT EXCHANGER RELIEF VALVE i
" ~ ~ ' ~ ' ~~~~
$$b$kV2h8 C 2 5
$hb5 bib 8Mb79k"5'bh'$h6"'hE[1kh'hk[hk " " h$bbb 5 ~ b" SP b COMPONENT COOLING WATER TO REACTOR SHRo@
HEAT EXCHANGER RELIEF VALVE E 2-CC-RV-224C 12050-CBM-079A 4 OF 5 F6 RELIEF VALVE 3.000 3 C SP 0
............................................. 'f' COMPONENT COOLING WATER TO REACTOR SNR3UD !
HEAT EXCHANGER RELIEF VALVE 2-CC-RV-225A 12050-CBM-079A 2 0F 5 C6 RELIEF VALVE .750 3 C SP 0 -
CC SUPPLY TO "A" RC PUMP THERMAL BARRIER RELIEF VALVE t
2-CC-RV 2258 12050-CBN-079A 3 of 5 C6 RELIEF VALVE .750 3 C SP O f CC SUPPLT TO "B" RC PUMP THERMAL EARRIER t RELIEF VALVE '
2 CC-RV-225C 12050 CBM-0794 4 0F 5 C6 RELIEF VALVE .750 3 C SP O !
CC SUPPLY TO "C" RC PUMP THERMAL BARRIER RELIEF VALVE 2 CC-RV-22BA 12050-CBM-079A 1 0F 5 E3 RELIEF VALVE - .750 3 C SP 0 l 5
ss .
+)
l l
'i i
~I VIRGINIA P0bER COMPANY PAGE: 4 0F 79 ~'
NORTH ANNA UNIT 2 REVISION: 07 SEDOND INSPECTIDW INTERVAL DATE: 11/05/93' l
. INSERVICE TESTING PROGRAM - VALVE TABLE I WC 150 REL CS ALT '
VALVE DRAWING ENEET ORWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST WUMBER NUMBER WUMBER COOR-TTPE -
SIZE CLASS CAT TYPE TYPE POS V- - CSV- VCN-
"A" RNR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE
.................................................................................... .... ... .... .... )
2-CC RV-228B 12050-CBM-079A 1 0F 5 D3 RELIEF VALVE .750 3 C SP O
............................................. i "B" RHR HEAT EXCHANGER COMPONENT COOLING .
RELIEF VALVE- !
2-CC-TV-200A 12050-CBM-0798 3 0F 3 E3 A0 BFLY 6.000 2 A CIV EV C !
FS C l
LT C ST C !
W K i CC RETURN FROM "A" RECIRC AIR COOLING COILS, l OUTSIDE CONTAINMENT ISOLATION VALVE 5' ~~~ ~~ ~'~~ ~~~'
~
h5bbIhIbbbb'~~~5kbbb5bkkIbkhb T
~~~'bi5"b5~~~ b"BfLk"'~~~~~~' 6$bbb 5"~~~ k" bih ' kh"' C FS C LT C ST C ,
W E CC RETURN FROM "B" RECIRC AIR COOLING COILS, ..
DUTSIDE CONTAINMENT ISOLATION VALVE J!
2-CC-TV-200C 12050-CBM 0798 3 0F 3 C3 A0 SFLY 6.000 2 A CIV EV C [
FS C LT C ST C VP OC CC RETURN FROM "C" RECIRC AIR COOLING C0!LS, !
OUTSIDE CONTAlkMENT ISOLATION VALVE ;
~ ~" ~ ~ ~'~~~'~~ ~~ ~ ~~~ ~~~ ~~~~
h$bb5kV I hbik"~~'ihb5bIbbMI b79I "I'bF 5 bh '"Eb bLbbE d$bbbk'~~~E bih"' bh '~ b ~~~ i ,
FS- C 1 LT C .
ST C 1 VP OC -I
............................................. i CC RETURN FROM REACTOR COOLANT PUMP THERMAL '
BARRIERS, OUTSIDE CONTAINMENT ISOLATION VALVE =
,r 2-CC-TV 2018 12050-CBM-079A 10F 5 D6 A0 CLDBE '4.000 2 A CIV EV C 1
- FS C 1 I LT C ST C -1 .i VP OC '
CC RET 7RN FROM REACTOR COOLANT PUMP THERMAL l i
BARRIERS, INSIDE CONTAINMENT ISOLATION VALVE <
1 2-CC-TV-202A 12050-CBM-079A 4 0F 5 A5 A0 BFLT 8.000 2 A CIV EV C -1 !
FS C 1 l
LT C ST C 1 '
- VP OC l 1
CC RETURN FROM "C" RC PUMP LO, STATOR & SHROUD 1 CCOLERS, CUTSIDE CDNIAINMENT ISOLATION VALVE l
- s. 2-CC-TV-2028 12050-CBM-079A . 4 0F 5 A3 A0 BFLY 8.000 2 A CIV EV C 1 i
- l 1
F l I
- i
- VIRGINIA POWER COMPANY PAGE: 5 0F 79 ;
NORTH ANNA UNIT 2 - REVISION: 07 SECONO INSPECTION INTERVAL DATE: 11/D5/93 INSERVICE TESTING PROGRAM
- VALVE TASLE ,
1 NC ISO REL CS ALT VALVE DkAWING SKEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER IAMBER NUMBER COOR. TYPE -
SIZE CLASS CAT TYPE TYPE POS' V- CSV .VCN- ,
2-CC TV-2028 12050-CBM-079A 4 of 5 A3 A0 BFLY 8.000 2 A CIV FS C 1 1 LT C ST C 1 ,
VP OC CC RETURN FROM "C" RC PUMP LO,$TATOR & SHROUD
-l COOLERS, INSIDE CONTAINMENT ISOLATION VALVE '
2-CC-TV-202C 12D50-CSM-079A 3 0F 5 A5 A0 SFLY 8.000 2 A CIV EV C 1 FS C 1 :
LT C :
ST C 1 i W E CC RETURN FROM "B" RC PUMP LO,$TATOR & SHROUD '
COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CC-TV-202D 12050-CBM-079A 3 0F 5 A3 A0 SFLY 8.000 2 A CIV EV C 1 FS C 1 LT C I' ST C 1 W E ;
CC RETURN FROM "8" RC PUMP LO,$TATOR & SHROUD .
COOLERS, INSIDE CONTAINMENT ISOLAT!DN VALVE ,
2-CC-TV-202E 12050-CaH-079A 2 0F 5 A5 A0 BFLY 8.000 2 A CIV EV C 1 --1
, FS C 1 !
LT C ST C 1 <
VP OC ,
CC RETURN FRON "A" RC PUMP LO, STATOR & SHROUD l COOLERS, DUTSIDE CONTAINMENT ISOLATION VALVE 1
~~~ ~ ~~~'~~~^~ ~~~~ ~~ ~ ~~~ ~~~~
hIbb5hIEbbh'~~'hhbbb$bBMb79E hbh"$k5""~kb'bhth T 5 b$bbbb E~~ bih Eh '~ b""~ l'"~ i FS C 1 LT C ST C 1 VP OC -
CC RETURN FROM "A" RC PUMP LO, STATOR & SHROUD ,
COOLERS, INSIDE CONTAlhMENT ISOLATION VALVE 2 CC-TV 203A 12050-CbM-079A 1 of 5 A7 AD 8 FLY 18.000 2 A Civ EV C 0 '
FS C LT C ST C 0
VP OC CC RETURN FROM "A" RHR HEAT EXCHAkCER, OUT.
$1DE CONTAINMENT ISOLATION VALVE 2 CC-TV 2038 12050-CBM 079A 10F 5 BT A0 BFLY 18.000 2 A CIV EV C 0
FS C LT C ST C 1 0 I W E I I
1
VIRGINIA P0bER COIFANY PAGE '. - 6 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/D5/93 INSERVICE TESTING PROGRAM - VALVE TABLE
(,_,
' NC 150 REL CS ALT' VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NLMBER NUMBER COOR -TYPE -
SIZE . CLASS CAT TYPE TTPE POS V-CSV- VCN-CC RETURN FROM "B" RHR NEAT EXCHANCER, QUT-SIDE CONTAINMENT ISOLATION VALVE 2-CC-TV-204A 12050-CBM-079A 2 OF 5 E8 A0 BFLY 8.000 2 A CIV EV C 1 FS C 1 LT C ST C 1 VP OC CC SUPPLY TO "A" RC PUMP LO, STATOR, SHROLD &
THERM BARRIER COOLERS, OUTSIDE CONT ISOL VLV
[" 2-CC.TV-2048 12D50-CBM-079A 3 0F 5 E8 A0 BFLY 8.000 2 A CIV EV C 1 3 FS C 1 LT C ST C 1 VP OC CC SUPPLY TO "B" RC PUMP LO, STATOR, SHROLD &
THERM BARRIER COOLERS, OUTSIDE CONT ISOL VLV 2-CC-TV-204C 12050-CBM-079A 4 0F 5 E8 A0 SFLY 8.000 2 A CIV EV C 1 FS C 1 LT C ST C 1 VP OC CC SUPPLY TO "C" RC PUMP LO, STATOR, SHROLD &
THERM BARRIER COOLERS, OUTSIDE CONT ISOL VLV 2-CC-TV-205A 12050-CBM-0798 3 0F 3 E4 A0 BFLY 6.000 2 A CIV EV C FS C
- LT C ,
ST C VP OC CC RETURN FROM "A" RECIRC AIR COOLING ColLS, INSIDE CONTAINMENT ISOLATION VALVE -
2-CC-TV 205B 12050-CBM-0798 3 0F 3 D4 A0 BFLY 6.000 2 A CIV EV C FS C LT C l ST C VP DC 1
CC RETURN FROM *B" RECIRC AIR COOLING ColLS, l INSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... . . . . . . . . .... .... i 2-CC-TV-205C -12050-CBM-0798 3 0F 3 B4 A0 BFLY 6.000 2 A CIV EV C -!,
FS C i LT C ST C VP' DC CC RETURN FROM C RECIRC AIR COOLING ColLS, I INS!DE CONTAINMENT ISOLATION VALVE i
I,
i r-I VIRGINIA P0bER COMPANY PAGE: 7 0F 79 l NORTH ANNA UNIT 2 REVISION: 07 l SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE n
I s S
NC !
ISO REL CS ALT [
. VALVE DAAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST RE0 JUST TEST -;
NUMBER - NLMBER NLMBER COOR DPE SIZE CLASS CAT TYPE TYPE POS V- ~i
_. CSV-' VCN-2-CD 163 11715-C88-040C 2 0F 3 E6 CNECK VALVE 3.000 NC C CV 0 '!
' 1 CONTROL ROOM CHILLED WATER STSTEM PUMP ;
DISCHARGE CHECK VALVE -i
............................................................. ..... ..... ... ..... ...... .... ... .... .... j 2-CD-187 11715 CBS 040C 2 0F 3 D6 CHECK VALVE 3.000 NC C CV 0 '!
CONTROL ROOM CHILLED WATER SYSTEM PUMP !
DISCHARGE CHECK VALVE . '
2-CD 211 11715-C88-040C 2 0F 3 C4 CHECK VALVE 3.000 NC C CV 0 7
CONTROL ROOM CHILLED WATER SYSTEM PUMP DISCHARGE CHECK VALVE !
............................................................. ..... ..... ... ..... ..... .... ... .... .... :i i
b k
I t
k
-9 k
\s !
I
- i 5
.. ?;
T f
t i
i r
b
.i
)
i e
t I
s
- z. ,.m,
VIRGINIA poler CCWANY PAGE: 7 0F 79 NORTN ANNA UNIT 2 REVISION: 07 SECOW INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE
( y\'
NC 190 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASSE IW VALVE TEST TEST REG JUST TEST NUMBER NUMBER NLMBER COOR-TYPE -
SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-2-CD-163 11715-Cas-040C 2 OF 3 E6 CHECK VALVE 3.000 3 C CV 0 CONTROL ROOM CHILLED WTER SYSTEM P'MP DISCHARGE CHECK VALVE 2-CD-187 11715-Cas-040C 2 OF 3 D6 CHECK VALVE 3.000 3 C CV 0 CONTROL ROOM CHILLED WTER SYSTEM PUMP DISCHARGE CHECK VALVE 2-CD-211 11715-CBS-040C 2 0F 3 C4 CHECK VALVE 3.000 3 - C: CV 0 CONTROL ROOM CHILLED WTER SYSTEM PUMP DISCHARGE CHECK VALVE O.
I
i I
1 VIRGINIA POWER COMPANY 'PAGE: 8 0F 79- i NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 t
, INSERVICE TESTING PROGRAM - VALVE TABLE -!
NC [
ISO REL CS ALT t VALVE DRAWING SHEET DRWG VALVE VALVE ASE IW VALVE TEST TEST REQ JUST TEST i NUMBER NtMBER WUMBER COOR-MPE -
SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- l
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ........ .... s 1 CH-118 11715-CBM 095A 1 0F 4 C6 CHECK VALVE 2.000 3 C CV 0 3 l
*C" BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE
'1-CH-133 11715 CBM-095A 1 0F 4 C7 CHECK VALVE Z.000 3 C CV 0 3 "D" BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE I 2-CH-153 12050-CBM-0958 1 0F 2 B6 CHECK VALVE 4.000 2 AC cv C 73
- 0 ,
LT C ,
CHARGING PUMP SUPPLY FROM VOLUME CONTROL TAWK f
!$OLATION VALVE 2-CH-155 12050-CBM-095B 1 0F 2 C3 CHECK VALVE 1.000 3 C CV 0 4 !
ALTERNATE EMERGENCY BORATION LINE CHECK VALVE 2-CH-156 a 12050-CBM-095B 1 0F 2 B4 MANUAL GATE 1.000 3 B EV 0 4 .
ALTERNATE EMERGENCY BORATION LINE t*
MANUAL VALVE s 2-CH-157 12050-CBM-095B 1 0F 2 B4 CHECK VALVE 1.000 2 C CV 0 4
............................................. f ALTERNATE EMERGENCY BORATION LINE TO !
CHARGING PUMP SUCTION CHECK VALVE 2-CH-159 12050 CBM 0959 1 0F 2 B5 CHECK VALVE 2.000 2 C CV 0 4 MAIN EMERGENCY BORATION LINE 10 CHARGING i PUMP SUCTION CHECK VALVE 2 CH 176 12050 CBM-095B 2 0F 2 D4 CHECK VALVE 3.000 2 C CV 0 39 "A" CHARGING PLMP DISCHARGE RECIRC LIN2 CHECK a
i VALVE '
1 2-CH 178 12050-CBM-0958 2 0F 2 D4 CHECK VALVE 3.000 2 C CV C 48 0 48 '
............................................. 5 f
"A" CHARGING PUMP DISCHARGE CHECK VALVE '
i
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 2-CH-191 12050-CBM 0958 2 OF 2 D6 CHECK VALVE 3.000 2 C CV 0 39
............................................. [-
"B" CHARGING PUMP DISCHARGE RECIRC LINE CHECK I VALVE 2 CH-193 12050-CBM-095B 2 0F 2 D6 CHECK VALVE 3.000 2 C CV C 48 0 48 >
"B" CHARGlWG PUMP DISCHARGE CHECK VALVE 2-CH-206 12050-CBM 0958 2 0F 2 07 CHECK YALVE 3.000 2 0 C CV 39 "C" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE i
............................................................. ..... ..... ... ..... ..... .... ... .... .... 1 I
a 1
e J
l I
i l
3 5]
h VIRGINIA POWER COMPANY PAGE: 9 0F 79 ' )
NORTH ANNA UNIT 2 REVISION: 07 f SECOND INSPECTION INTERVAL CATE: 11/05/93 !
, INSERVICE TESTING PROGRAM - VALVE TABLE NC \
ISO REL CS ALT i
. VALVE DRAWING SHEET DRWG VALVE VALVE ASME. IWV VALVE TEST TEST REO JUST 1EST .i NUMBER WlMBER NLMBER COOR MPE -
SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN- i 2-CH-208 12D50-CBM-D958 2 0F 2 D7 CHECK VALVE 3.000 2 C CV C 48 !
O 48 i "C" CHARGING PUMP DISCHARGE CHECK VALVE >
2-CH-260 12D50-CBM-095C 2 or 2 B8 CHECK VALVE 2.0D0 1 C CV C 10 'i "A" RC PUMP SEAL WATER SUPPLY, INSIDE I CONTAINMENT ISOLATION CHECK VALVE 2-CH 2S4 12050-CBM-D95C 2 0F 2 BT CHECK VALVE 2.000 1 C CV C 10 "B" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT
- SOLATION CHECK VALVE 2-CH-3D8 12050-CBM-D95C 2 0F 2 B5 CHECK VALVE 2.000 1 C CV C 10 :
"C" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT !$0LAT10N CHECK VALVE
~
2-CH-331 12050-CBM-D95C 2 0F 2 F4 CHECK VALVE .750 2 AC CIV CV C 10 t LT C 59 i-RC PUMP SEAL WATER RETURN, INSIDE CONTAINMENT ISOLATION CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... .j 2-CH-332 12050-CBM-095C 1 0F 2 A5 CHECK VALVE 2.000 1 AC CIV CV C 10
' l LT C l CHARGING SUPPLY To LOOP FILL HEADER, INSIDE CONTAINMENT ISOLATION CHECK VALVE -
2-CH-335 12050-CBM-095C 1 or 2 D4 CHECK VALVE 3.000 2 AC Civ CV C to !
LT C ;
KAIN CHARGING SUPPLY HEADER, INSIDE CONTAIN- I MENT ISOLATION CHECK VALVE I
............................................................. ..... ..... ... ..... ..... .... ... .... .... -f 2-CH-FCV-2113A 12D50-CBM-0958 1 of 2 C3 A0 GATE 1.0D0 3 8 EV 0 i FS 0 ST 0 -i VP OC !
{
ALTEREATE EMERGENCY BORATION LINE ,
FLOW CONTROL VALVE 4~
r
- l 2-CH-FCV-2114A 12D50-CBN-0958 1 0F 2 D4 A0 GLOBE 1.000 3 8 EV C FS C ST c VP DC 6
PRIPARY GRADE WATER FLOW CONTROL VALVE '
i
............................................................. ..... ..... ... ..... ..... .... ... .... .... il t 2-CH FCV-2160 12D50-CBM-095C 1 0F 2 A4 A0 GLOBE 2.000 2 AE CIV LT C W E
............................................. l t CHARGING FLOW CONTROL TO LOOP FILL HEADER, OUTSIDE CONTAINMENT ISOLAfl0N VALVE 2-CH4 CV-2460A 12050-CBM-D95C 1 0F 2 F7 A0 GLOBE 2.000 1 B EV C 5
-(
FS ST C 5 C 5 I
r
<l
. . -. ...-.. ~ = . .
i VIRGINIA PobER CCMPANY PAGE: 10 0F 79 NORTH ANNA UNIT 2. REVISION: 07 SECOND INSPECTION INTERVAL : DATE: 11/05/93 i INSERVICE TESTING PROGRAM - VALVE TABLE ;
.('*%
g- NC ISO REL CS . ALT -r VALVE DRAWING SKEET DRWG VALVE VALVE ABME IWV VALVE TEST TEST. REG JUST- TEST '
NLMBER NLMBER NUMBER C00R TVPE -
$1ZE CLASS CAT TYPE TTPE POS - CSV- VCN--
...... ....... ...... .... ..... ..... ..... ... ..... .... ....'V- ... .... .... ;
2-CH-LCV-2460A 12D50-CBM-D95C 1 0F 2 FT A0 GLOBE 2.000 1 8 VP OC
............................................. r LETDOWN ISOLATION VALVE fr 2 CH-LCV-24608 12050-CBM-095C 1 0F 2 FT A0 GLOBE 2.000 1 B EV C 5 FS C 5- I ST C 5 ,
VP OC '
LETDOWN ISOLATION VALVE P
I kb'IEli55"I5656IEBM I kIbH V b958"'E'bi i B5"'5b'EATE" "'" " $$b56 E" " E" ~~~~' E"'ih"' 5"'
- O 6 -
LT C '
ST C 6- !
O 6 !
W K ,
CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK h
2 CH-MOV-2115C 12050-CBM-0958 1 0F 2 C6 MO GATE 4.000 2 B EV C 6 ST C 6 l
VP OC CHARGlWG PUMP SUPPLY ISOLATION FROM VOLUME CONTROL TANK
{
............................................................. ..... ..... ... ..... ..... .... ... .... .... 1 2-CH MOV-2115D 12050-CBM-095B 2 0F 2 88 M0 CATE 8.000 2 A EV C 6 ?
O 6 i LT C e ST C 6 '
0 6 I VP OC 1 l
CHARGING PUMP SUPPLT ISOLATION VALVE FROM '
REFUELING WATER STORAGE TANK
--~ ~ -~~~ " '--'- ~ ~ ~
I I b9si i bi i Es"'55'EITi"~~~"I'555i i
$IhM5bvIi315E'~ iih56!b5M Eh ~ E"' s'
ST C 6 t VP OC CKARGING PUMP SUPPLY ISOLATION VALVE FROM '
VOLUME CDNTROL TANK 2 CH-MOV-2267A 12050 CBM-0958 2 0F 2 C3 MO GATE 6.000 2 E VP OC I
............................................. +
i "A" CHARGING PUMP SUCTION ISOLATION FROM RWST !
AND VCT
............................................................. ..... ..... ... ..... ..... .... ... .... .... I 2-CH POV-22678 12050-CBN-095B 2 of 2 C3 No GATE 6.000 2 E VP OC
............................................. f o
"A" CHARGING PUMP SUCTION ISOLATION FROM LHS!
............................................................. ..... ..... ... ..... ..... .... ... .... ..... [
2-CH-MOV-2269A 12050-CBM 095B 2 0F 2 C5 MO GATE '
6.000 2 E VP OC i
"B" CnARGING PUMP SUCTION ISOLATION FROM RWST l AMD VCT ,
I
)
2-CH-MOV 22698 12050-CBM-095B 2 0F 2 CS MO GATE 6.000 2 E VP OC l I
i
~l
___n._._... .1
')+
f
+
}
VIRGINIA P0hER COIPANY PAGE: 11 0F 79 i NORTH ANNA UNIT 2 REVISION: 07 !
SECole INSPECTION INTERVAL -
DATE: 11/05/93 i INSERVICE TESTING PROGRAM - VALVE TABLE !
1 NC i ISO . REL CS ALT. i VALVE DRAWING SNEET DRWG VALVE VALVE ASINE IW VALVE TEST TEST REO JUST TEST 1RalBER IAMBER C00R 3#PE
{
NUMBER -
SIZE CLASS CAT TYPE TYPE PDS V- CSV- VCN- t
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... t i
............................................. P CHARGlhG PUMP SUCTION ISOLATION FROM LHSI
."B" -.
2-CH-MOV-227DA 12050-CBM-0955 2 0F 2 C7 No GATE 6.000 2 E VP ' OC ;
............................................. i "C" CHARGING PUMP SUCTION ISOLATION FROM RWST I Als VCT
............................................................. ..... ..... ... ..... ..... .... ... .... .... i CN-Mov-22708 12050-CBM-0955 2 0F 2 C7 No GATE 6.000 2 E- VP OC
},
"C" CHARGING PLMP SUCTION ISOLATION FROM LHS! ;
............................................................. ..... ..... ... ..... ..... .... ... .... .... .[
p 2-CH-MOV-2275A 12050-CBM-0958 2 0F 2 D4 M0 GATE 2.000 2 B EV C .i 0 !
i ST . C ,I O r VP OC - ~!
"A" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE l 2-CH-MOV-2275B 12050-CBM-0955 2 0F 2 D5 M0 GATE 2.000 2 B EV C O i ST C i 0 I VP OC f "B" CHARGING PUMP MINIDAM RECIRCULATION ISO-
-]
LAil0N VALVE i 6
............................................................. ..... ..... ... ..... ..... .... ... .... .... 7 CM MOV 2275C 12050-CBM-0958 2 0F 2 07 MO GATE 2.000 2 B EV C -f 0 t ST C A 0
VP OC I
"C" CHARGING PUMP MINIMLIM RECIRCULATION ISO-
- LATION VALVE l
2 CM-MOV 2286A 12050 CBM-0958 2 0F 2 E4 MO GATE 3.000 2 B EV' C I 0 i j
ST C i 0
VP OC i "A" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2 CH MOV-22868 12050-CBM-0958 2 0F 2 E6 MO GATE 3.000 2 B EV C 0 l ST C 0
VP OC "B" CHARGING PUMP MAIN DISCHARGE ISOLATION ..,
VALVE ~!
2-CH-MOV 2286C 12050-CBM-0958 2 0F 2 ET MO GATE 3.000 2 8 EV -C ~i 0 '
ST C i 0 I W K- i e
L i
d
r -
b d
.i VIRGINIA POWER COIPAlff PAGE: 12 0F 79 {
NORTH ANNA UNIT 2 REYISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE
'- jf NC 150 REL CE ALT
-VALVE DRAWING SHEET DRWG VALVE VALVE ASIE IW VALVE TEST -TEST REG JUST TEST [
NUMBER . NUMBER NUMBER C00R 4YPE - SIZE CLASE CAT TYPE TTPE POS , V- CSV--VCN-
"C" CHARGING PUMP MAIN DISCHARGE ISOLATION
}
VALVE 2 CH-MOV-2287A 12D50-CBM-D958 2 0F 2 D4 M0 GATE 3.000 2 B EV C 0 5 ST C O 6 VP OC 1
"A" CHARGING PW4P ALTERNATE AND LOOP FILL i DISCHARGE ISQLATION VALVE i
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 2-CH MOV-2287B 12D50-CBM-D958 2 OF 2 D6 MO GATE 3.000 2 5 EV C l 0 L t
ST C -,
O VP OC .I "B" CHARGING PUMP ALTERNATE AND LOOP FlLL
~i DISCHARGE ISOLATION VALVE *
............................................................. ..... ..... ... ..... ..... t 2-CH-MOV-2287C 12050 CBM-0958 2 0F 2 D7 M0 GATE 3.000 2 B EV C !
O ST C 0 'i VP OC :
"C" CHARGING PUMP ALTERNATE AND LOOP FILL -
DISCHARGE ISOLATION VALVE f
............................................................. ..... ..... ... ..... ..... ....- .... .... .... j 2-CH-MOV-2289A 12050-CSM-095C 1 0F 2 D4 M0 GATE 3.0D0 2 A CIV EV C 7 i LT C .*
ST C 7 (
VP OC i MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE !
CONTAINMENT ISOLATION VALVE 2-CH-MOV-2289B 12050-CBM-095C 1 of 2 83 M0 GATE 3.000 2 B EV C 7 !
ST C 7. I YP OC .;
-3 MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE :
CONTAINMENT .
............................................................. ..... ..... ... ..... ..... .... ... .... .... l s
2 CH MOV 2350 12D50-tam-D95B 10F 2 B5 - No GATE 2.0D0 2 S EV 0 4 ;
ST 0 4 . ,
r W K i EMERGENCY BORATION TO CHARGING PUMP SUCT10N !
t 2-CH MOV-2373 12050-CBM-D95B 1 0F 2 A8 M3 GATE 3.000 2 E VP DC i
- CHARGING PUMP RECIROULATION HEADER !$3LAT10N L VALVE 2 CH-McV-2380 12D50 cam-095C 2 0F 2 F4 .M0 GATE 3.000 2 A CIV EV C 9
.i LT C 59 !
ST C 9' f
\
VP OC 4 i
0
)
r I
i 2
. - _ _ _ _ . _ . e-
VIRGINIA POWER COMPANY PAGE: 13 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL' CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ. JUST TEST NUMBER NUMBER WUMBER COOR H PE - $1ZE CLASS CAT TYPE TYPE POS V- CSV- VCN-REACTOR COOLANT PLMP SEAL WATER RETURN, INSIDE CONTAINMENT ISOLATION VALVE 2-rN MOV-2381 12050-tam-0955 1 0F 2 C8 M0 GATE 3.000 2 A CIV EV C 9 LT C ST -C 9 VP OC REACTOR COOLANT PUMP SEAL. WATER RETURN, OUT-SIDE CONTAINMENT ISOLATION VALVE 2-CH-RV-2203 12050-CBM-095C 1 0F 2 F3 RELIEF VALVE 2.000 2 C SP 0 LETDOWN RELIEF VLV DOWNSTRLAM OF REGEN HX, RV DISCHARs.E TO PRES $URIZER RELIEF TANC 2-CH-RV-23828 12050-CSM-0958 1 0F 2 C7 RELIEF VALVE 2.000 2 C SP O SEAL WATER HEAT EXCHANGER RELIEF VALVE, RV DISCHARGE TO VOLUME CONTROL TANC 2-CH-TV-2204A 12050-CSM-095C 1 0F 2 E3 A0 GLOBE 2.000 2 A CIV EV C 5 FS C 5 LT C ST C 5 VP OC LETDOWN CONTROL FROM REGEN HX, INSIDE CONTAINMENT ISOLATION VALVE 2-CN-TV-22048 12050-C8M 095A 2 0F 2 C3 A0 CLOBE 3.000 2 A CIV EV C 5 FS C 5 LT C ST C 5 l W E
............................................. {
LETDOWN CONTROL FROM REGEN HX, OUTSIDE CONTAINMENT ISOLAT:0N VALVE 'i t
I t
P t
i h
t t
I h
t h
h I
i l
t
. 1 l
1
)
i i
J
.i VIRGINIA poler CCMPANY PAGE: 14 0F 79' i NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 11/05/93 .
. INSERVICE TESTING PROGRAM - VALVE TABLE ,
1 i
NC i ISO REL CS ALT- '1 VALVE . DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ' JUST TEST ' -{
NUMBER NUMBER NUMBER C00R TYPE -
SIZE CLASS CAT TYPE TTPE POS CSV. VCN-
, ...... ....... ...... .... ..... ..... ..... ... ..... .... ....'V- ... .... .... t t
I 2-CV-004 12050-CBM-092A 2 0F 2 A5 MANUAL GATE 8.000 2 AE CIV LT C
- CONTAINMENT VACULM EJECTOR SUPPLY, OUTSIDE l
CONTAINMENT ISOLATION VALVE i
2-CV-08 12050-cam-092A 2 0F 2 B3 CHECK VALVE 2.000 2 C CV 0 '
CONTAINMENT VACUUM STSTEM ISOLATION CHECK
................ VALVE 2-CV-15 12050-CBM-092A 2 OF 2 C3 CHECK VALVE 2.000 2 C CV 0 CONTAINMENT VACUUM SYSTEM ISOLATION CHECK L VALVE
............................................................. ..... ..... ... ..... ..... .... ... ..... .... :i 2 CV-TV-200 12050-CBM-092A 2 0F 2 A3 A0 BFLY 8.000 2 AE CIV LT C W E !
1 CONTAIEMENT VACLAM EJECTOR, INSIDE CONTAIN- '
MENT ISOLATION VALVE 2-CV-TV-250A 12050-CBM-092A 2 0F 2 B4 A0 GLOBE l
, 2.000 2 A CIV EV C FS C ;
LT C ST C 55 VP OC "A" CONTAINNENT VACUUM PUMP SUCTION ISOLATION G '
f VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE -i 2-CV-TV-250B 12050 CBM-092A 2 0F 2 85 A0 GLOBE 2,000 2 A CIV EV C i FS C LT C ST C 55 VP OC "A" CONTAINMENT VACLUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE !
2-CV-TV-250C 12050-CBM-092A 2 0F 2 C4 A0 CLOBE 2.000 2 A CIV EV C 15 C ,
LT C ST C 55 VP OC "B" CodTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE >
2-CV-TV-2500 12050-CBM 092A 2 0F 2 C5 A0 CLOBE 2.000 2 A CIV EV C- :
FS C LT C 1 ST C 55 W N. j "B" CONTAINMENT VACUUM PUMP SUCTION ISOLATION .
. VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... .l i
?
t E
e h
h o
7
. i.
_._.,.e
I VIRGINIA P0bER COMPANY PAGE: 15 0F 79 l NORTH ANNA UNIT 2 REVISION: 07 3 SECOND INSPECTION INTERVAL DATE: 11/05/93
' INSERVICE TESTING PROGRAM = VALVE TABLE
(
(
NC-150 - R[L CS ALT 1 VALVE- DRAWING , SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST .l wmBER NUMBER NLMBER COOR TTPE -
SIZE CLASS CAT TYPE TYPE POS V. CSV- VCN+ l 2-DA-007 12050-CBM-090A 3 0F 3 D3 MAN DIAPHRAM 2.000 2 AE CIV LT C .1
............................................. 5 VENT LINE FROM PRIMART VENT POT, INSIDE !
CONTAINMENT !$0LATION VALVE '!
2-DA 009 12050-CBM-090A 3 0F 3 E3 MAN DIAPNRAM 2.000 2 AE CIV LT C ,
VENT LINE FROM PRIMARY VENT POT, OLITSIDE CONTAINMENT ISOLATION VALVE 2-DA-TV-200A 12050-CBM-090B 1 0F 1 E7 A0 GLOBE 2.000 2 A CIV EV C FS C-LT C ST C 55 VP OC i
............................................. j REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, OUTSIDE CONTAINMENT ISOLATION VALVE
- 2-DA-TV-2006 12050-CBM-090A 3 0F 3 C3 A0 GLOBE 2.000 2 A CIV EV C l
FS C LT C ST C
............................................. 'I REACTOR CONTAINMENT SUMP PUMPS DISCKARGE, INSIDE CONTAINMENT ISOLATION VALVE f 2-DA-TV-203A 12050-CBM-090A 3 0F 3 87 A0 CLOBE 2. 0' A CIV EV C .
FS C LT C ST C 55 VP OC POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT ISOLATION VALVE 2-DA-TV-203B 12050 CBM-0901. 3 OF 3 88 A0 CLOBE 2.000 2 A CIV EV C ,
FS C LT C ST C 55 VP OC POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTA!NMENT TRIP VALVE i
............................................................. ..... ..... ... ..... ..... .... ... .... .... i k
i t'
4 k
i l
-I
\
VIRGINIA PohER CCBIPANY PAGE: 16 0F 79 NORTH ANNA UNIT 2 ._ REVISION: 07 . .
SECOND INSPECTION INTERVAL . DATE: 11/05/93 l INSERVICE TESTING PROGRAM - VALVE TABLE :
3: [ ' NC ,
ISO REL CS- ALT
. VALVE DRAWING SHEET DRWG VALVE VALVE ASME . iW VALVE TEST TEST RE0 JUST TEST NUMBER NUMBER NUMBER COOR -TYPE -
SIZE CLASS CAT TYPE TYPE POS V- .CSV- VCN-
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... ?
2-DG-TV-200A 12050-CBM 090A 1 0F 3 88 A0 GLOBE 2.000 2 'A CIV EV C i FS C l LT C ST C :
VP OC.
PRIMARY DRAIN TRANSFER PLAIPS DISCHARGE, OUT- ;
SIDE CONTAINMENT ISOLATION VALVE 2-DG-TV-200s 12050-CBM-090A 10F 3 B7 A0 GLOBE 2.000 2 A CIV EV C i FS C i LT C ST C i W K [
PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, i INSIDE CONTAINMENT ISOLATION VALVE
[
i 4
b i
i i
t t
, e
+ l t
--.5 v
, , , . , . .~. . _ . . .-- - , -, , .~
1 i
i i
VIRGINIA POE R COMPANY PAGE: 17 0F 79 l' NORTH ANNA UNIT 2 REVISION: 07 SECOND IhSPECTION INTERVAL DATE: 11/05/93 i INSERVICE TESTING PROGRAM - VALVE TABLE '
i NC o ISO REL CS ALT !
VALVE DRAWING SHEET DRWG VALVE VALVE ASME . IWV VALVE TEST TEST REQ ~JUST TEST i NUMBER NUMBER NUMBER COOR-TTPE -
SIZE CLASS CAT TYPE TYPE POS V- 'CSV- VCN-EB-015 12050-FM -107A 1 0F 4 E6 CHECK VALVE 1.500 NC C CV 0 4 2H DIESEL "NA" AIR RECEIVER TANK DISCHARGE VALVE 2-E8-034 12050-FM -107A 3 0F 4 E6 CHECK VALVE 1.500 NC. C CV 0 4 ;
I 2J DIESEL "JA" AIR RECEIVER TANK DISCHARGE !
VALVE t 2-EB-041 12050-FM -107A 1 0F 4 D6 CHECK VALVE .750 NC AC CV C.
[
2H DIESEL "NA" AIR RECEIVER TANK ISOLATION I VALVE 2-EB-051 12050-FM -107A 3 0F 4 D6 CHECK VALVE .750 WC AC CV C !
LT C t
............................................. l &
t 2J DIESEL "JA" AIR RECEIVER TANK ISOLATION '.
VALVE l 2-EB-061 12D50-FM -107A 2 OF 4 E6 CHECK VALVE 1.500 NC C cv 0 4 2H Di[SEL "HB" AIR RECEIVER TANK DISCHARGE VALVE _
j 2-EB-D68 12050-FM .107A - 2 0F 4 D6 CHECK VALVE .750 NC AC CV '
C LT C I
............................................. I 2H DIESEL "HB" AIR RECEIVER TANK ISOLATION VALVE
............... ............................................. ..... ..... ... ..... ..... .... ... .... .... j 2-EB 078 12050-FM -107A 4 of 4 E6 CHECK VALVE 1.500 NC C CV 0 4 2J DIESEL "JB" AIR RECEIVER TANK DISCKARGE VALVE I 2-EB-085 12050-FM -107A 4 0F 4 D6 CHECK VALVE .750 WC AC CV C .
LT C !
2J DIESEL "JB" AIR RECEIVER TANK ISOLATION VALVE R
?
e L
6 e
7 I
e
VIRGINIA POWER COMPANY NORTH AWEA UNIT 2 PAGE: 18 0F 79 SECOND INSPECTION INTERVAL REVISION: 07 INSERVICE TESTING PROGRAM . VALVE TABLE DATE: 11/05/93 VALVE DRAWING NUMBER
...... WUMBER SHEET DRWG VALVE ISO NC 2-EG-260
....... WUMBER COOR -TYPE
...... .... ..... - VALVE ASME IVV VALVE TEST REL CS ALT SIZE CLASS CAT TY TEST REQ JUST TEST 11715 FB -035A 2 CHECK VA ..... ..... ... ..PE TYPE POS V- CSV. VCN 2H DIESEL 0F 2 C7...................LVE ........
1.500 kt C CV 0 l
DIS *A" EMERGENCY GENERATOR PUMP I
..................... CHARGE CHECK VALVE 2-EG-272 11715-Fs -035A
..................0F 2 2 F7 CHECK VALV ..... ..... ...
2J DIESEL ....................E ...... 1.500 WC C CV O l
D "A" EMERGENCY GENERATOR PUMP I
.. .... . ......... . ..I SCHARGE CHECK VAL VE 2-EG-264 11715-FB -035A
.............. .2 0F 2 76 CHECK ..... .... .....
. C... ..... ....
2J DIESEL "S" Eh . . . . . . . . . . . . . . . . . .VA L VE 1.500 WC CV 0 g DI
....................SCHARGE CHECK 4 ,VEGENCY GENERATOR PUMP l 2-EG-289 11715-F8 -035A.........................................
20 ..... ..... .
....................F 2 C6..................E CHECK VALV 1.500 NC C 2H DIESEL ....... CV 0 [
D "B" EMERGENCY GENERATOR PUMP l
. . . . . . . . . . . . . . . . . . .I S CHAR GE CHECK VAL VE 2-E G-RV-2D4A 11715-FB -035A..........................................
2
..................0F2 C7...................LVE RELIEF VA 1.000 WC
..... C... ..... ..... .... ... .... ....
2N DIESEL ....... SP O g RE
.................... LIEF VALVE,"A" RV DISCHARGE EMER GENERATOR TO PUMPPUMP SUCTION DISCHARGE I 2 EG-RV-2048 11715-FB -035A.........................................
2
..................OF RELIEF VA
.... C... ..... .....
2 C6....................LVE .......
1.000 NC SP O
..................ELIEF R
VALVE, "B"RV EMER DISCHARGE GENERATOR PUMP TODISCHARCE PUMP SUCTION 2H DIESEL l 2-EG-RV-206A 11715-F8 -035A...........................................
2
................. 0F 2 F7. . . . . ..........
RELIEF V
. . . . . 1.000
. . . kC. . . . CAL VE SP .... .. .... ....
2J DIESEL O R
..................ELIEF VALVE, "A" RV EMER GENERATOR PUMP DISCKARGE DISCHARGE TO PUMP SUCTION f 2-E G-R V- 2D6B 11715-F8 -035A...........................................
2O
....................F 2 F6....................E RELIEF VALV 1.000 NC
.... C... ..... ..... .... ... .... ....
..... SP 0
...................ELIEF R
VALVE, "S"RV EMER DISCHARGE GENERATOR PUMP TDDISCHARCE PLMP SUCTION 2J DIESEL l 2-EG RV-702HA 120$0-FM -107A..................................
RELIEF VA ....... ..... ..... ... ..... ..... ....
1
...................OF4 E4...................LVE 2.000 WC C
....... SP O
...................V R
DISCHARGE "A" AIR RECEIVER TO ATMOSPNERE2H TANK REllEF VALVEDIESEL 2-E G-RV-702HB 1205D-FM 107A..........................................,.....
2
..................0F 4 E4 RELIEF VALV
..........-...........E..... 2.000 WC C SP 0
. -. . ....... .... . ..RV
*B" AIR DISCHAR RECEIVER TAhK GE TO RELIEF ATMOSPHERE VALVE 2H DIESEL 2-EG-RV-702J A 12050-FM -107A...........................................,.....
3
. . . . . . . . . . . . . . . . . 0F 4 .........
RELIEF E 4. . .2.000
. . .NC. . . .C . . . . . SP . . .VA ....
L VE ... .... ....
R O
. . . . . . . . .. . . . "A" . . AIR
. . ..V RECEIVER D I SCHAR TANK RELIEF GE 70 VALVE A TMOSPHERE2J DIESEL 2-EG-RV-702JB 12050-FM .107A...-..................n...................,...
4
..................0F4 E4...................LVE RELIEF VA 2,000 ..NC..... C... ..... ..... .... ... .... ....
2J DIESEL ....... SP O
. ... ... . ... .... . ...V D I SCH"B" ARAIR RECEIVER TANK RELIEF VALVE R
GE TO A TMOSPHERE ,
2 EG 50V 700HA 12050 FM -107A..........................................
10F 4 E6 SO GATE 1.500 WC
..... 8... ..... ..... .... ... .... ....
EV O
, ST 0 4
l
_-- _ _ _ - - - - - - - - - - - - - ' __2- ----'"--'- __ _ - - - - ~ ~ -
?
VIRGINIA PohER COWANY . PAGE: . 18 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTl0K INTERVAL DATE: 11/05/93
,,,, INSERVICE TESTING PROGRAM - VALVE TABLE
- NC ' 5f' ISO REL CS ALT VALVE . DRAWING SHEET' DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLMBER - WUMBER COOR -TYPE .
SIZE. CLASS CAT TYPE TYPE POS V- CSV- VCN-
...... ........ ...... .... ..... ..... ..... ... ..... .... .... ... .... .... i 2-EG-260 11715 FB -D35A 2 of 2 C7 CHECK VALVE 1.500 NC 0 6
C CV
]
2H DIESEL *A" EMERGENCY GENERATOR PUMP f
DISCHARGE CHECK VALVE j
............................................................. ..... ..... ... ..... ..... .... ... .... .... g 2-EG-272 11715-FB -035A . 2 0F 2 F7 CHECK VALVE 1.500 NC C CV 0 l f 2J DIESEL "A" EMERGENCY GENERATOR PUMP DISCHARGE CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 2-EG-284 11715-FB -035A 2 0F 2 F6 CHECK VALVE 1.5D0 NC 0 C CV l. >
2J DIESEL "B" EMERGENCY GENERATOR PUMP '
DISCHARGE CHECK VALVE I
............................................................. ..... ..... ... ..... ..... . . . . . ... .... .... g i 2-EG-289 11715-FB -035A 2 OF 2 C6 CHECK VALVE 1.500 NC C CV o l~ f 2H DIESEL "B" EMERGENCY GENERATOR PUMP DISCHARGE CHECK VALVE 2-EG-RV-204A 11715-FB -035A 2 0F 2 C7 RELIEF VALVE 1.000 NC C SP O 1
2H DIESEL "A" EMER GENERATOR PUMP DISCHARGE I RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION .
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 2-EG-RV-2048 11715-FB -D35A 2 0F 2 C6 RELIEF VALVE 1.000 kC- 0 C SP l l 2H DIESEL "B" EMER GENERATOR PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION ' {
2-EG RV-206A 11715 FB 035A 2 0F 2 FT RELIEF VALVE 1.000 NC C SP O ( r I
2J DIESEL "A" EMER GENERATOR PUMP DISCHARGE '
RELIEF VALVE, RV DISCHARGE TO PUNP SUCTION 'I 2 EG RV 2068 11715-TB -035A 2 0F 2 F6 RELIEF VALVE
.i1 1.000 NC C SP O '
2J DIESEL *B" EMER GENERATOR PUMP DISCRARGE f RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION i 2-EG RV-702HA 12D50 FM -107A 10F 4 E4 RELIEF VALVE 2.000 NC C SP O t 2H DIESEL "A" AIR RECEIVER TANK RELIEF VALVE, -
RV DISCKARGE 10 ATMOSPHERE +
............................................................. ..... ..... ... ..... ..... .... ... .... .... '1 2 EG-RV-702HB 12050-FM -107A 2 0F 4 E4 RELIEF VALVE 2.000 NC C SP O
............................................. _j 2H DIESEL "B" AIR RECE!VER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE '
............................................................. ..... ..... ... ..... ..... -L 2-EG-RV 702JA 12050-FM -107A 3 0F 4 E4 EELIEF VALVE 2.000 NC C SP 0 I 2J DIESEL "A" AIR RECEIVER TANK RELIEF VALVE, 4
RV DISCHARGE TO ATMOSPHERE
~~~ ~ ~~ ~ '~~~ ~~~ ~~ '~~~~ '~' ~~~ ~~~~ ~~~~
l iIibIhh!hi38 T iib 56IiM~Ii67k"~~IbiIil'~~iiLiifhthi 2$bbbEb b SP b'~~
2J DIESEL "L" AIR RECEIVER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE I
.... ... .... .... =t 2 EG Sov 700HA 12D50-FM -107A 10F 4 E6 50 GATE 1.500 NC B EV 0 '
ST 0 4-l b
-t i
-5 h
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ ~ . _ . _ _ . - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _
i h
4 h
~ VIRGIN!A poler COMPANY ' PAGE: 19 0F 79 :
NORTH ANNA UNIT 2 REVISION: 07 .
SECOND INSPECTION INTERVAL DATE:.11/05/93 !
INSERVICE TESTING PROGRAM . VALVE' TABLE -
-NC '
ISO REL CS ~ ALT -3 x VALVE DRAWING SHEET 'DRWG VALVE VALVE ASME IWV VALVE TEST TEST req JUST TEST- '
NUMBER NUMBER NUMBER COOR M PE -
SIZE CLASS CAT TYPE TYPE :' POS ~ V. ' CSV.- VCN-(
}
DIESEL' AIR START $0LENCID VALVE !
t 2-EC-SOV-700MB 12050-FM .107A 2 0F 4 E6 SO GATE 1.500 NC B EV O ,
ST 0 4 i
............................................. f. '
DIESEL AIR START SOLEN 0!D VALVE I t
............................................................. ..... ..... ... ..... ..... .... ... .... .... ]
2-EG-SOV-700JA 12050.FM .107A 3 0F 4 E6 So GATE 1.500 NC B EV O l 0
~
' ST 4 ;
............................................. l_
DIESEL AIR START SDLENDID VALVE ,
' 2-EG-$0V.700JB 12050-FM .107A 4 0F 4 E6 SO GATE 1.500 NC B EV 0 ST 0 4 1
.............................................. 1 DIESEL AIR START SOLENDID VALVE l
............................................................. ..... ..... ... ..... ..... .... ... .... .... t 2-EG-SOV.701HA 12050-FM .107A 10F 4 E6 So GATE 1.500 NC B EV O E
ST 0 4. I I
............................................. 'I- ;
's DIESEL AIR START SOLENDID VALVE ,
2-E G-SOV-707J A 12050-FM .107A 3 0F 4 E6 SO GATE 1.500 NC ' B EV O '
-l s ST 0 4 i
............................................. t i
DIESEL AIR START SOLENDID VALVE t f
,i h
'I F
s t
I t
I I
?
I e
I
'I r b
a b
t 1
i e
1
/
^t t
r a
. l i -
![ >
. . . . - _ _ _ _ . ,___ ._m.
?
i i
VIRGINIA POWER COMPANT PAGE: . 20 0F 79 : ;
NORTH ANNA UNIT 2 REVISION: 07 -!
SECOND INSPECTION INTERVAL DATE: 11/05/93 INSERVICE TESTING PROGRAM - VALVE TABLE
! [**%
150 REL CS AT- ,
VALVE DRAWING SHEET DRWG VALVE i VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR -TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV- VCN- ',
..... ..... ... ..... .... .... ... .... .... .l 2-FP 079 120$0-CBB-104A 1 0F 1 A7 CHECK VALVE 4.000 2 AC CIV - CV - C 16' -
I LT C '
FIRE PROTECTION SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CNECK VAAVE 1
2-FP-081 12050-CBB-104A 1 % 1 A6 MANUAL GATE 4.000 2 AE Civ LT C
............................................. j FIRE PROTECTION 'hPPLY TO CONTAlWMENT, ;
OUTSIDE CONTAINriNT ISOLATION VALVE 4 I
?
)
i s
b E
?
I
~
i i
'l
}
t i
)
s f
i.
?
f i
t s
f k
v I
i VIRGINIA POWER COMPANY PAGEi . 21 0F 79 '
NORTH ANNA UNIT 2- REVISION: 07 '
SECOND INSPECT 10N INTERVAL DATE: 11/05/93.
INSERVICE TESTING PROGRAM - VALVE TABLE je-~m; i 1'- y- NC REL CS 150 ALT ;
VALVE DRAWING SHEET , DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER C00R M PE -
SIZE. CLASS CAT TYPE TYPE POS V- CSV- VCN- .
2-FW-062 12050-CBM-074A 1 0F 4 E6 CHECK VALVE 16.000 2 C CV C 12 ;
"A" MAIN FEEDWATER SUPPLY, CONTAINMENT i PENETRATION CHECK VALVE t
............................................................. ........... ... ..... ..... .... . . . . .... .... j 2-FW-063 12050-CBM-074A 1 0F 4 BS CHECK VALVE 3.000 3 C CV 0 30-
............................................. t STANDBY "A" AUXILI ARY FEEDWATER HEADER CHECK i e
VALVE, OUTSIDE OF CONTAINMENT 2-FW-D64 120$0-CBM-074A 1 0F 4 B5 MANUAL GATE 3.000 3 B EV C 40 0 40 '
AUXILIARY TEEDWATER HEADER MANUAL ISOLATION I VALVE FROM MOTOR-DRIVEN PUMP HEADERS 2-FW-065 12050-CBM-074A 10F 4 B6 CHECK VALVE 3.000 3 C CV 0 30 r
STANDBY "A" AUXILIARY FEEDWATER HEADER CHECK VALVE, DUTSIDE OF CONTAINMENT ?
............................................................. ..... ..... ... ..... ..... .... ... .... .... I 2-FW-066 12050-CBM-074A 1 0F 4 B6 MANUAL GATE 3.000 3 B EV C 40 0 40 s
, AUXILI ARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS l}
2-FW 070 12D50-CBM-074A 1 OF 4 D6 CHECK VALVE 3.000 2 C CV 0
............................................. l. [
"A" AUXILI ARY FEEDWATER HEADERCHECK VALVE AT MAIN FEEDWATER HEADER 2-FW-094 12050-CBM-074A 1 0F 4 D6 CHECK VALVE 16.000 2 C CV C 12 "B" MAIN FEEDWATER HEADER SUPPLY, CONTAINMENT PENETRATION CHECK VALVE
.I*
2-FW-095 12050-CBM-074A 1 0F 4 B6 CHECK VALVE 3.000 3 C CV O L "B" AUXILI ARY FEEDWATER HEADER CHECK VALVE, 1
OUTSIDE OF CONTAINMENT '
2-FW 096 12050 CBM-074A 1 0F 4 B6 MANUAL CATE 3.000 3 B EV C 40 ;
O 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR DRIVEN PUMP HEADERS I 2 FW-097 12050-CBM-074A 1 0F 4 C6 CHECK VALVE 3.000 2 .0 C CV 30 "B" AUXILIART FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER {~
............................................................. ..... ..... ... ..... ..... .... ... .... .... i 2-FW-098 12050 CBM-074A 1 0F 4 B6 MANUAL GATE 3.000 3 8 EV C 40 I O 40 'l AUXILI ARY FEEDWATER HEADER MANUAL ISOLATION i VALVE FROM MOTOR-DRIVEN PUMP HEADERS l 2-FW 102 12050-CBM-074A ,
1 0F 4 C6 CHECK VALVE C CV O
............................................. l'-
"B" AUXILARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER
\ ............................................................. ..... ..... ... ..... ..... .... ... .... ....
1 I
VIRGINIA POWER COMPANY PAGE: 22 0F 79 j NORTH ANNA UNIT 2 REVISION: 07 . .!
SECOND INSPECTION INTERVAL DATE: 11/05/93- -[
INSERVICE TESTING PROGRAM
- VALVE TABLE i f<
}
NC'
- ISO .
REL CS . ALT i VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST ;
NUMBER NUMBER NUMBER C00R R PE SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-. t 2 FW-126 12D50-CBM-074A 1 0F 4 b6 CHECK VALVE 16.000 2 C- CV C 12 "C" MAIN FEEDWATER SUPPLY, CONTAIMMENT PENETRATION CHECK VALVE i
............................................................. ..... ..... ... ..... ..... .... ... .... '.... i 2-FW 127 12050-CBM-074A 1 0F 4 B7 CHECK VALVE 3.000 3 C CV 'O 30 i I
STANDBY "C" AUXILIARY TEEDWATER HEADER CHECK
[
VALVE, GUTSIDE OF CONTAINMENT 2-FW 128 12050-CBM-074A 1 0F 4 B7 MANUAL GATE 3.000 3 B EV C 40. !
O 40 q AUXILIARY FEEDWATER HEADER MANUAL !$0LATION i VALVE FROM MOTOR-DRIVEN PUMP HEADERS r-2-FW-129 12050-CBM-074A 1 0F 4 B7 CHECK VALVE 3.000 3 C CV 0 i "C" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT +
2-FW-130 12050-CBM-074A 1 0F 4 B7 MANUAL CATE 3.000 3 B EV C 40 f 0 40 }
3 AUXILIARY FEEDWATER HEADER MANUAL !$0LAT10N '!
VALVE FROM MOTOR-DRIVEN PUMP HEADERS i
..............................~.............................. ..... ..... ... ..... ..... .... ... .... .... :
2 FW-134 12050-CBM-074A 1 0F 4 B7 CHECK VALVE 3.000 2 C CV 0 l
"C" AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 1
2-FW-147 12050-CBM-074A 3 0F 4 BT MANUAL GATE 6.000 3 8 EV O 41 ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS .!
i 2 FW-150 12050-CBM-074A 3 0F 4 D7 CHECK VALVE 1.000 3 C CV O
............................................. l TURBINE DRIVEN AUXILI ARY FEEDWATER PUMP ,
RECIRC LINE CHECK VALVE 2 FW-156 12050-CBM-074A 3 0F 4 D8 CHECK VALVE 6.000 3 0 C CV l 1
TURBINE DRIVEN AUXILI ARY FEEDWATER PUMP )
DISCHARGE CHECK VALVE
,\
s 2-FW-157 12050-CBM 074A 3 0F 4 ET MANUAL GATE 6.000 3 8 EV C 40 O 40 j r
AFW PUMP DISCHARCE HEADER ALIGNMENT / CROSS CONNECT VALVE 2 FW-164 12050-CBM 074A 3 0F 4 B6 MANUAL GATE 6.0D0 3 8 EV O 41 ALTEREATE WATER SUPPLY TO AFW PUMP SUCTIONS
............................................................. ..... ..... ... ..... ..... .... ... .... .... t 2-FW-167 12050-CBM-074A 3 0F 4 D6 CHECK VALVE 1.000 3 0 C CV l !
)
"A" MOTOR DRIVEN AUXILI ARY FEEDWATER PUMP t RECIRC LINE CHECK VALVE ,
2-FW-172 12050 CBM-074A 3 0F 4 D6 CHECK VALVE 4.000 3 C CV 0 l ,
i
1
-l VIRGIN!A POWER COMPANY PAGE: . 23 0F 79- l NORTH ANNA UNIT 2 . REVIS!DN 07 i SECONO INSPECTION INTERVAL DATE: 11/05/93' INSERVICE TESTING PROGRAM - VALVE TABLE l
,u-~e ;
. $' NC 1 ISO REL CS ' . ALT l VALVE DRAWING SHEET DRWG YALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST ')
NUMBER NLMBER NLMBER COOR JYPE ' ,. SIZE CLASS CAT TYPE TYPE POS. V- CSV- VCN- ,
"A" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP DISCH4RGE CnECK YALVE l
............................................................. ..... ..... ... ..... ..... .... ... .... ..... j 2-FW-173 12050-CBM-074A 3 0F 4 E6 MANUAL GATE 6.000 3 8 EV C 40 j 0 40 AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS ,
CONNECT VALVE 2-FW-174 12050-CBM-074A 3 0F 4 E6 MANUAL GATE 6.000 3 8 EV C 40 !
O 40 '
AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS ,
CDNNECT VALVE '!
............................................................. ..... ..... ... ..... ..... .... ... .... ..... .3 2-FW-182 12050-CBM-074A 3 0F 4 B5 MANUAL GATE 6.000 3 8 EV O 41 ;
ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS !
............................................................. ..... ..... ... ..... ..... .... ... .... .... , [
2-FW-185 12050-CBM-074A 3 0F 4 05 CHECK VALVE 1.000 3 C CV O j.
"B" MOTOR DRIVEN AUX!LIARY FEEDWATER PUMP ,
REC!RC LINE CHECK VALVE h
2-FW-192 12050-CBM-074A 3 0F 4 D5 CHECK VALVE 4.000 3 C CV 0 "
............................................. -'+
/'~ '
I
*B" MOTOR DRIVEN AUXILI ART FEEDWATER PUMP g DISCHARGE CHECK VALVE 2-FW-193 12050-CBM-074A 3 0F 4 E5 MANUAL GATE 6.000 3 B EV C 40 0 40 ;
t AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS ;
CONNECT VALVE t
............................................................. ..... ..... ... ..... ..... .... ... .... .... -j 2 FW-194 120$0 CBM-074A 3 0F 4 E5 IW"A GATE 6.000 3 8 EV C 40 '
O 40 '
AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS .i CONNECT VALVE .
2-FW-202 12050-CBM-074A 3 0F 4 A7 MANUAL CATE 6.000 3 8 EV O 41 !
SERVICE WATER SUPPLY TO AFW PUMP SUCTIONS !
t 2 FW-279 12050-CDM-074A 3 0F 4 08 CHECK VALVE 4.000 3 C CV 0 i "A" AUXILI ARY FEEDWATER HEADER CHECK VALVE, 1 OUTSIDE OF CONTAINMENT i 2-FW 317 12050-CBM-074A 3 0F 4 E8 KANUAL GATE 6.000 3 5- EV C 40 -!
O 40 '
h AFW PUMP JISCHARGE HEADER ALIGNMENT / CROSS i CONNECT VALVE ;
2-FW-609 12050 CBM-074A 3 0F 4 CHECK VALVE 1.000 3 C CV 0 '
............................................. l i
- PUMP LUBE DIL COOLER CHECK VALVE 5
............................................................. ..... ..... ... ..... ..... .... ... .... .... [
t I
b
. 1 VIRGINIA poler COWANY 'PAGE: 24 0F 79 !
NORTH ANNA UNIT 2 REVISION: 07 !
SECOND INSPECTION INTERVAL DATE: 11/05/93 . f
. ,ss INSERVICE TESTING PROGRAM - VALVE TABLE !
1 NC ;
t ISO REL CS ALT 4 VALVE DRAWING SHEET DRWG VALVE VALVE ASME- IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER' NUMBER COOR TVPE -
SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-
...... ....... ...... .... ..... ..... ..... ... ..... .... .... ... .... .... l 2-FW-610 12D50-CBM-074A 3 0F 4 CHECK VALVE 1.000 3 C CV 0 l l PUMP LUBE DIL COOLER CHECK VALVE
............................................................. ..... ..... ... ..... ..... .... ... .... .... , j 2 FW 611 12050-CBM-074A 3 0F 4 CHECK VALVE 1.000 3 C CV 0 l -
............................................. i PUMP LUBE DIL COOLER CHECK VALVE I t
2-FW-FCV-2478 12050-CBM-074A 1 0F 4 E4 A0 GLOBE 16.000 WC B EV C 11 I
FS C 11 !
ST C 11 :
W K +
"A" MAIN FEEDWATER REG VALVE t
2-FW-FCV-2479 12050-CBM-074A 1 0F 4 F4 A0 GLOBE 6.000 NC B EV C 11 !
FS C 11 i ST C 11 l "A" BYPASS FEEDWATER REG VALVE l 2 FW-FCV-2488 12050-CBM-074A 1 0F 4 D4 A0 GLOBE 16.000 NC B EV C 11 t FS C 11 i ST C 11 l
[ VP OC l
( .............................................
"B" MAIN FEEDWATER REG VALVE ,
t 2 FW FCV-2489 12050-CBM-074A 1 0F 4 04 A0 GLOBE 6.000 NC B EV C 11 -)
FS C 11 '
ST C 11 ,
p "B" BYPASS FEEDWATER REG VALVE <
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 2-FW-FCV 2498 12050-CBM 074A 1 0F 4 B4 A0 GLOBE 16.000 NC B EV C 11 FS I C 11 ST C 11 i VP OC ;
"C" MAIN FEEDWATER RfC VALVE i f
2-FW FCV-2499 12050-CBM-074A 1 0F 4 C4 A0 GLOBE 6.000 WC B EV . C - 11 FS C 11 ;
ST C 11 "C" BYPASS FEEDWATER REG VALVE l 3
............................................................. ..... ..... ... ..... ..... .... ... .... .... j 2-FW-HCV-2DCA 12050-CBM-074A 1 0F 4 AS A0 GLOBE 3.000 3 B EV 0 32 FS 0 32 >
ST 0 32 i W K [
............................................. r STANDBY AUXILIARY FEEDWATER SUPPLY TO "A" I STEAM CENERATOR (s, 2-FW-HCV-200B 12050-tBM-074A 1 0F 4 A6 A0 GLOBE 3.000 3 B EV O 32 f b
t
1 l
- 1 1
VIRGINIA poler CONDANY - PAGE: 25 0F 79 NORTH ANNA LNili 2 - '
REVISION: 07 .
SECOND INSPECTION INTERVAL DATE: 11/05/93 I INSERVICE TESTING PROGRAM - VALVE TABLE I NC I
~
ISO tEL CS ALT i VALVE DRAWING SHEE! DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST l NUMBER WUMBER NUMBER COOR TYPE . SIZE CLASS CAT TYPE TYPE POS V- CSV- VCN-2-FW-NCV-2008 12050-CBN-074A 1 0F 4 A6 A0 GLOBE 3.000 3 B FS '0 32 I ST 0 32 ll VP OC ,
STANDBY AUXILIARY FEEDWATER SUPPLY TO "B" i STEAM GENERATOR 2-FW-NCV-200C 12050-CBM-074A 10F 4 A7 A0 GLOBE 3.000 3 8 EV 0 32 - l FS 0 32 ST 0 32 VP OC NORMAL AUXILIARY FEEDWATER SUPPLY TO "C" STEAM GENERATOR
.g 2-FW-MOV-200A 12050-CBM-074A 1 0F 4 B5 MO GLOBE 3.000 3 8 EV C 0
ST C O .
W K l STANDBY AUXILIARY FEEDWATER SUPPLY TO "A" '
STEAM GENERATOR 2-FW MOV-2008 '
12050-CBM-074A 1 0F 4 B6 MO GLOBE 3.000 3 B EV C~
0 .
ST C 0
VP OC NORMAL AUXILIARY FEEDWATER SUPPLY To "B" STEAM GENERATOR li 2-FW-MOV-200C 12050-CBM-074A 10F 4 B7 MC GLOBE 3.000 3 B EV C '
.O ST C .;
s 0
- W K ;
.............................................}}