ML20195B569
| ML20195B569 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/14/1999 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20195B544 | List: |
| References | |
| PROC-990514, NUDOCS 9906020020 | |
| Download: ML20195B569 (300) | |
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SUMMARY
OF CHANGES TO THE l NORTH ANNA UNIT 1 L SECOND INTERVAL IST PROGRAM FROM REVISION 7, CHANGE 4 TO I
REVISION 8, CHANGE 2 4 I
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GENERAL COMMENT
S This summary describes changes to the North Anna Unit 1 inservice Testing (IST) Program fmm 1
' Revision 7. Change 4 to Rwision 8. Ghenge 2. With Revision 8 to the North Anna Units 1 and 2 IST Programs, the programs have been ug4ated from the 1986 Edition of ASME Section XI to the 1989 Edition in its entirety and several chsnges to Revision 7 have been combined. The
' 1989 Edition of Section XI invokes ASME/ ANSI OM Part 6, OMa-1988 for pump testing -
ASME/ ANSI OM Part 10, OMa-1988 for valve testing and ANSI OM Part 1 OM-1987 for relief valve testing.
Major portions of the IST programs have already been updated to the newer Code via relief requests and NRC safety evaluations of the IST programs. For example, Relief Request V-66
. committed North Anna to OM Part 10 for valve testing acceptance criteria. Relief Request P-1 '
commits North Anna to the requirements of OM Part 6 for measuring pump vibration. The NRC Safety Evaluation dated September 17,1993 concludes that the requested two year test interval for the inside and outside recirculation spray pumps is consistent with the test interval in OM Part 6 for pumps in dry lay-up. Therefore, relief is not required provided that North Anna complies -l with the provisions of OM Part 6 in its entirety when testing these pumps.
By updating to the 1989 Edition of Section.XI, all pumps and valves will now be using the same Code which improves North Anna's ability to property implement the Code. Also, the need for several valve testing relief requests has been eliminated because the newer Code aliows for exercise testing every reactor refueling.
. The general format of the IST Program Plan has been changed to be consistent with suggestions made in NUREG 1482, entitled " Guidelines for Inservice Testing at Nuclear Power Plants", and with the format of the Surry IST Program Plans. What follows is a section by section summary of changes made to the North Anna Unit 1 IST Program Plan.
1.0 INTRODUCTION
The content was changed to more accurately describe the contents of the program and reference is made to the Federal Register dated 1992 which endorses the 1989 Edition
. of Section XI.
2.0 GENERAL PROGRAM DEVELOPMENT in a NRC Safety Evaluation Report for Suny dated October 20,1994, the NRC wanted a description of how the IST program was developed, how scope was determined and how the program is updated. This description was included in the Surry IST program and is now being included in the North Anna IST program. Section 2 describes the IST program administrative process as it is now and does not commit North Anna to imposing additional requirements.
3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION Reference is made to the 1989 Code Edition of Section XI and OM Part 6, OMa-1988 for
, pump testing. Also, vert >iage was borrowed from the Surry IST program to more accurately describe the North Anna IST pump program philosophy, implementation and administration. Again, Section 3 describes the IST program for pumps as it is now and does not commit North Anna to imposing additional requirements.
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m 3.5 PUMP INSERVICE TEST TABLES r0
('~') Unit 1 Pump Number Prooram Chance 1-CC-P 1 A Relief Request P-16 was withdrawn for these pumps. P-16 requests 1-CC-P-1 B relief from measuring static inlet pressure for a pump that is already in 1-CH-P-1 A operation prior to testing. OM Part 6 does not require the measurement 1-CH-P-1 B of static intet pressure, therefore, the relief is no longer necessary.
1-CH-P-1 C 1-CH-P-2A 1-CH-P-2B 1-FW-P-2 1-FW-P-3A 1-FW-P-3B 1-QS-P 1 A 1-OS-P-1 B 1-RH-P-1 A 1-RH-P-1 B 1-RS-P-3A 1-RS-P-3B 1-HV-P-20A 1-HV-P-20B 1-HV-P-200 1 HV-P-22A l 1-HV-P-228 l 1-HV-P-22C g (Rev. 8)
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3.6 PUMP TEST PROGRAM RELIEF REQUESTS l Unit 1 Pump l Relief Reouest Prooram Chance P-1 Requests for relief from measuring pump bearing temperature end (Rev. 8) vibration displacement in mils were witharawn from P-1, along with the description of using vibration velocity in inches per second. OM Part 6 l requires that vibration velocity be measured instead of bearing temperature and vibration displacement.
I P-1 also establishes a minimum reference value for vibration of 0.05 in/sec. The minimum reference value avoids subjecting smooth running pumps to unnecessary corrective action by maintaining a small but reasonable acceptable operating range. This portion of P-1 was ,
retained in the revised relief request. l P-12 Figure 1 was removed from P-12. Figure 1 gave a graphical (Rev. 8) representation of the pump acceptance criteria based on a reference curve. The figure provided no more information than that provided in the attemate testing discussion of P-12. Therefore, the figure is not necessary.
(N P-16 Relief request was withdrawn. The relief requested that static inlet
() (Rev. 8) pressure not be measured for pumps already operating prior to the 2
l inservice test. OM Part 6 does no.t required that static inlet pressure be measured. Therefore, the relief request is no longer necessary.'
3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS l
Unit 1 Pump Non-Code Attemative Testing Description l
Proaram Chanae PNC-1 Reference to running the diesel fuel oil transfer pumps five minutes prior
- (Rev. 8) to measuring the test quantities was changed to two minutes as required by OM Part 6. The reason for not waiting before measuring the test
, quantities has not changed. Also, the discharge pressure gauges were l identified as having a full scale of 0 to 30 psig, and reference values J
ranging from 7.5 to 8.5 psig which does not meet the one third scale l requirernent of OM Part 6, paragraph 4.6.1.2 for reference values.
l However, test results show the data is repeatable. Therefore, the l accuracy of the instruments provides acceptable results.
, A note was added to enhance clarity. The note reads,"The diesel oil l transfer pumps are positive displacement pumps. According to OM Part l 6, Table 2, discharge pressure, flow and vibration need to be measured l for positive displacement pumps. Differential pressure does not have to I
i be measured.'
4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION Verbiage was borrowed from the Surry IST program to more accurately describe the North Anna IST pump program philosophy, implementation and administration. Section 4 describes the IST program for valves as it is now and does not commit North Anna to imposing more requirements.
4.4 VALVE INSERVICE TEST TABLES The valve table column heading explanations were revised to provide more complete and accurate descriptions. Also, the test frequency for each test was added to the table per the suggestions in NUREG-1482, Section 2.4.2.
In cases where a valve is subject to a test to the partially open position as described in a relief request, cold shutdown justification or reactor refueling justification, the partially open test (PO) designation was added to the table.
This addition of the PO test to the table is not an increase in the commitments to test, but is an enhancement to the table to provide a clearer description of existing test commitments.
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Unit 1 nf Valve Number Proaram Chanae 1-CC-84 Program change: Relief Request V-3 was replaced by Reactor 1-CC-119 Refueling Justification RRV-1. According to OM Part 10, paragraphs l 1-CC-154 4.2.1.2 (e) and 4.3.2.2(e), *1f exercising is not practicable during plant I (Rev. 8) operation or cold shutdown, it may be limited to full-stroke during l refueling outages." Therefore, relief is no longer required to defer testing until refueling outages, however, the justification for the deferral
[ should be described in the IST Program Plan per NUREG 1482, j Section 2.4.5. The technical basis for the deferral has not changed.
1-CC-111 Program change: Relief Request V-65 was replaced by Reactor 1-CC-146 Refueling Justification RRV-20. The technical basis for the deferral 1-CC-181 has not changed.
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l l 1-CC-193 Program change: Relief Request V-70 was replaced by Reactor 1
1-CC-198 Refueling Justification RRV-22. The technical basis for the defermi has not changed. The test to the partially open position (PO) was
! (Rev' 8) added to the valve table to enhance clarity. This partially open test is ,
described in Reactor Refueling Justifica; ion RRV-22 and is not a new I l test commitment.
! 1-CC-546 Relief Request V 62 was replaced by Reactor Refueling Justification 1-CC-559 RRV-18. Also, reference to NUREG 1482, Section 4.1.4, entitled 1-CC-572 " Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing"was added to provide additional (Rev. 8) Justification to the basis. The remaining technicaljustification for i d deferral was expanded to enhance clarity.
Program change: Relief Request V-62 was replaced by Reactor l Refueling Justification RRV-18.
l 1 CC-RV-104A Credit is taken for these relief valves protecting penetrations 9,10 and 1-CC-RV-104 B 11 in a memorandum from E. W. May entitled " OVERPRESSURE 1-CC-RV-104C PROTECTION OF CONTAINMENT PENETRATIONS, GENERIC (Rev. 8) LETTER 96-06, NORTH ANNA UNITS 1& 2" dated June 25,1997.
Program change: The valves were added to the program.
l 1-CC-RV-126 Credit is taken for this relief valve protecting penetration 1 in a (Rev 8) memorandum from E. W. May entitled ' OVERPRESSURE PROTECTION OF CONTAINMENT PENETRATIONS, GENERIC LETTER 96-06, NORTH ANNA UNITS 1& 2" dated June 25,1997.
Program change: The valve was added to the program.
1-CC-RV-131 A These relief valves protect the RHR Seal Coolers from over pressure ,
1-CC-RV-131B as a result of thermal expansion when a cooler is isolated. If a cooleris !
(Rev. 8) locally isolated the associated pump would be considered inoperable. !
However, the ASME Subcommittee on Valves has interpreted this thermal relief protection function as being within the scope of OM Part l 10 if the equipment being protected is required for accident mitigation l (refer to ASME Interpretation: 95-9).
Program change: The valves were added to the program.
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' Valve Number Prooram Channe 1-CH-84 Program change: .The test to the partially open position (PO) was 1-CH-102 added to the valve table to enhance clarity. This partially open test is I (Rev. 8)- described in Cold Shutdown Justification CSV 3 and is not a new test I commitment.
1-CH-215 . Relief Request V-72 was esplaced by Reactor Refueling Justification 1-CH-64g RRV-23. Also, reference to NUREG 1482, Section 4.1.4, entitled
" Extension of Test interval to Refueling Outage for Check Valves (Rev* 8) Verified Closed by Leak Testing" was added to provide additional justification to the basis. The remaining technical justification for
. deferral was expanded to enhance clarny, 1
l Program change: Relief Request V-72 was replaced by Reactor Refueling Justification RRV-23.
1-CH-254 Program chanoe: Relief Request V-47 was replaced by Reactor
!- 1-CH-267 Refueling Justification RRV-16. The technical basis for the deferral
! 1-CH-279 has not changed.
l (Rev. 8) l i' 1-CH-322 Program change: Relief Re i 1 CH-330 Refueling Justification RRV quest
- 2. The V 10basis technical wasforreplaced by has the deferral Reactor 1-CH 336 not changed.
l 1-CH-358 1-CH-380 l 1-CH-402 (Rev. 8) 1-CH-402 Relief Request V-59 was withdrawn. V-59 requested relief from the
! '1-CH-MOV-1380 IWV requirement to individually leak test valves. Certain valves l cannot be individually tested, but must be tested as a group or (Rev' 8) combination. OM Part 10, paragraph 4.2.2.3(c)(2) allows for testing a combination of valves at the same time. Therefore, relief is no longer necessary for these valves.
Program change: Relief Request V 59 was withdrawn.
1 CH-MOV-1380 Program change: Relief Request V 9 was replaced by Cold Shutdown 1-CH-MOV-1381 Justification CSV-48. The technical basis for the deferral has not changed.
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- l. 1 CH-RV-1382A This valve protects the seal water leakoff piping from over-pressure l (Rev. 8) during an accident when the associated piping segment is isoiated and l may be subjected to heating or seal failure. Credit is taken for this
- l. relief valve protecting penetration 19 in a memorandum from E. W. j l May entitled " OVERPRESSURE PROTECTION OF CONTAINMENT I: PENETRATIONS, GENERIC LETTER 96-06, NORTH ANNA UNITS 1& 2' dated June 25,1997.
Program change: The valve was added to the program.
1-CV-8 Valves 1-CV-8 and 14 were added to RRV-4. To test these valves full 1 CV 14 open requires a significant manipulation and operation of the hydrogen O 1 HC-14 1-HC recombiner system. In addition, should a containment pressurization event occur while the recombiner system is operating, the design l
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Unit 1 Valve Number Prooram Channe (Rev. 8) pressure of the low pressure hydrogen recombiner system could be -
exceeded.
These valves will be verified open at least once every 18 months during the surveillance testing of the hydrogen recombiner system as required by Technical Specification Section 4.8.4.2. The small increase in safety gained by testing during normal operation or cold l shutdown does not justify the potential risk of overpressurtzing the hydrogen recombiner system, or the added burden of disrupting normal plant operations to manipulate the recombiner system and performing the test on the more frequent basis. Valves 1-CV-8 and 14 can be tested to the partially open position every three months using the containment vacuum pumps while maintaining the recombiner system {
isolated from the containment atmosphere.
l l Reference to using a locally installed rotameter was deleted from the original technical basis for valves 1-HC-14 and 18. The remaining portion of the technical basis was used in RRV-4. Also, for closure testing, r6ference to NUREG 1482, Section 4.1.4, entitled Extension of i Test interval to Refueling Outage for Check Valves Verified Closed by
! Leak Testing" was added to provide additional justification to the basis.
Program change: Valves 1 CV-8 and 14 were added to RRV-4 to be full now tested on a 18 month frequency and tested to the partially open position once every three months. Relief Request V-20, which deferred testing for valves 1-HC-14 and 18, was replaced by Reactor Refueling Justification RRV-4, 1-FP-272 Program change: Relief Request V-16 was replaced by Reactor (Rev. 8) Refueling Jushfication RRV-3. Also, reference to NUREG 1482, Section 4.1.4, entitled " Extension of Test interval to Refueling Outage for Check Valves Verified Closed by Leak Testing" was added to xovide additional justification to the basis. The remaining technical' ustification for deferral has not changed.
1-FW-FCV-1478 The requirement to perform a partial open exercise test every three l 1-FW-FCV-1488 months was deleted for the main feedwater regulating valves 1-FW- j 1-FW-FCV-1498 FCV-1478,1488 and 1498, in order to perform a partial stroke test ,
! during normal operation, the plant has to reduce power to cause the '
l (Rev 8) valve disks to move. Reducing power for the purpose of performing an exercise test is considered impractical according to the NRC response to Comment 2.4.5-1 in NUREG-1482, Appendix G.
l Program change: The three month partial stroke test was deleted. !
l J 1-FW-HCV-100A Per OM Part 10, paragraph 4.2.1.2(b) if full-stroke exercising during l l
1-FW-HCV-1008 plant operation is not practicable, it may be limited to part stroke during i 1-FW-HCV 100C plant operation and full-stroke during cold shutdowns. These valves can be part-stroke exercised during normal operation. Note that the (Rev* 8I valve stroke time need not be measured during a part stroke test.
Program change: The three month partial stroke test was added.
1-FW-PCV-159A Per OM Part 10, paragraph 4.2.1.2(b) if full-stroke exercising during 1-FW-PCV-159B plant operation is slot practicable, it may be limited to part stroke during Plant operation and full-stroke during cold shutdowns. These valves (Rev. 8)
'O can be part-stroke exercised during normal operation. Note that the valve stroke time need not be measured during a part-stroke test.
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/^ Valve Number Proaram Chance Program change: The three month partial stroke test was added.
1-HV-MOV-100B Relief Request V-59 was withdrawn. V-59 requested ralief from the 1-HV-MOV-100D IWV requirement to individually leak test valves. Certain valves 1-HV MOV 101 cannot be individually tested, but must be tested as a group or combination. OM Part 10, paragraph 4.2.2.3(c)(2) allows for testing a 1 HV-MOV-102 combination of valves at the same time. Therefore, relief is no longer (Rev. 8) necessary for these valves.
Program change: Relief Request V-59 was withdrawn.
1-IA-55 Program change: Relief Request V 21 was replaced by Reactor 1-IA-149 Refueling Justification RRV-5. Also, reference to NUREG 1482, Section 4.1.4, entitled
- Extension of Test Interval to Refueling Outage (Rev* 8) for Check Valves Verified Closed by Leak Testing" was added to 3rovide additional justification to the basis. The remaining technical ustification for deferral has not changed.
1-IA-RV-110 These relief valves protect instrument air supply piping to the PORVs.
1-IA-RV-111 This piping must remain intact so that the safety related bottled air can (Rev. 8) supply the pressurizer PORVs (1-RC-PCV-1455C and 1456).
Program change: The valves were added to the program.
1 MS-NRV-101 A Program change: The method of testing described in Cold Shutdown 1-MS-NRV 101B Justification CSV-13 was changed to incorporate the use of motor
/S 1-MS-NRV-101C current instead of yoke strain to detect changes in running force. Motor current is more sensitive to changes in stem load.
h (Rev. 7, Chg. 4) 1-QS-11 Relief Request V-67 was replaced by Reactor Refueling Justification 1-QS-19 RRV-21. Also, reference to NUREG 1482, Section 4.1.4, entitled 1-RS-18 "F.xtension of Test interval to Refueling Outage for Check Valves Verified Closed by Leak Testing" was added to provide additional 1-RS-27 justification to the basis. The remaining technical justification for (Rev. 8) deferral was expanded to enhance clarity.
Program change: Relief Request V-67 was replaced by Reactor Refueling Justification RRV 21.
1-RC-149 Program change: Relief Request V 28 was replaced by Reactor (Rev. 8) Refueling Justification RRV-6. Also, reference to NUREG 1482, Section 4.1.4, entitled
- Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing" was added to 3rovide additional justification to the basis. The remaining technical ustification for deferral has not changed.
1-RC-SOV-101 A-1 Relief Request V 57 was replaced by Cold Shutdown Justification CSV- !
1-RC-SOV-101 A-2 49. V 57 was originally a cold shutdown justification but with 1-RC-SOV-1018-1 provisions. Therefore, there could be cold shutdowns where the testing w uld be impracticable and a relief request was the appropriate means 1 RC~SOV-101B-2 of addressing the testing interval. With OM Part 10 allowing deferral to ;
(Rev. 8) reactor refueling, the appropriate means for addressing this testing is a i cold shutdown justification. l l
Program change: Relief Request V 57 was by Cold Shutdown i Justification CSV-49. The technicaljustification for deferral has not I changed.
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1-SI-4 Program change: Relief Request V 53 was replaced by Reactor 1 SI-21 Refueling Justification RRV-17. Also, reference to NUREG 1482, (Rev' 8) Section 4.1.4, entitled " Extension of Test interval to Refueling Outage for Check Valves Verified Closed by Leak Testing" was added to
'>rovide additional justification to the basis. The remainir'g technical ustification for deferral has not changed.
1 SI-9 Program change: Relief Request V 38 was replaced by Reactor 1 SI-18 Refueling Justification RRV-7. The technical justification for deferral 1-SI-26 has not changed. The test to the partially open position (PO) was added to the valve table to enhance clarity for valve 1-SI-18. This (Rev. 8) partially open test is described in Reactor Refueling Justification RRV-7 and is not a new test commitment.
1 SI-47 Program change: Relief Request V-39 was replaced by Reactor (Rev. 8) Refueling Justification RRV-8. Also, reference to NUREG 1482, Section 4.1.4, entitled ' Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing" was added to provide additional justification to the basis. The remaining technical justification for deferral has not changed. The test to the partially open position (PO) was added to the valve table to enhance clarity. This partially open test is described in Reactor Refueling Justification RRV-8 and is ..)t a new test commitment.
1-SI-66 Tests have revealed that when either 1-SI-MOV-1867A or B is opened 1-SI-MOV-1867A using the normal valve actuator, the BIT and the associated piping 1-SI-MOV-18678 experience a significant hydraulic transient. This hydraulic transient also perturbs the reactor coolant pumps (RCPs) seal injection flow O)
V (Rev 8) because the RCP seal flow comes off the same header as the BIT flow.
When the BIT inlet isolation velve is opened, flow to the RCP seals decreases until the BIT volume becomes pressurized. While this is happening the charging pump discharge header flow increases because of the newly opened flow path to the BIT. Once the BIT volume is pressurized, the increased charging pump discharge header flow is diverted to the RCP seal injection paths which momentarily causes a high flow condition in the RCP seals. During one test, the reactor coolant system controlled leakage limit of 30 gpm (T.S.
Paragraph 3.4.6.2.e) for total seal injection flow was exceeded.
During cold shutdowns the charging system is still in use. Therefore, a high differential pressure exists across the BIT inlet isolation valves even during cold shutdowns. The hydraulic transient caused by opening the BIT inlet isolation valves with a high differential pressure across the valves places stress on the BIT and the associated piping.
Also, the oscillating RCP seal injection flow may have a degrading effect on the RCP seals when the RCPs are operating. To eliminate these concems, the exercise tests will be performed during reactor refueling when the charging system is secured.
The preferred method for backseat testing check valve 1-SI-66 is during reactor refuelings when the charging system is secured and a local backseat / leak test can be performed. According to NUREG-1482, Section 4.1.4, "The NRC has determined that the need to set up test i
equipment is adequate justification to defer back flow testing of a check valve until a refueling outage."
Program change: These valves will be exercised every reactor refueling. Referto Reactor Refueling Justification RRV-25.
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d 1-St.79 The technicaljustification for deferring the testing of the hot and cold 8
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1-SI-90 legs Si check valves to refueling outages was moved from Relief 1 SI-95 Request V-43 to Reactor Refueling Justification RRV-12. The technical
$'3;'gg justification has not changed. The remaining portion of V-43 addresses 1-SI 103 the non-intrusive techniques used to test the hot leg Si check valves 1 SI-95,99,103,209,211 and 213, along with a sampling plan for 1-SI-185 Instrumenting the valves. This portion remains in V-43 and has been 1-SI 201 editorially changed to enhance clarity. Also, per NUREG 1482, to use l 1-SI-206 the sampling plan the check valves must be grouped based on valve '
1-SI-207 design and service conditions. A description of the grouping was 1-SI-209 added to V-43.with valves 1-SI-95,99 and 103 in one group and valves i 1 Sl 211 1-SI-209,211 and 213 in the other group. No new commitments have 1-Si 213 been made by the changes described above.
(Rev. 8) Program change: The deferral to test every reactor refueling was moved to Refueling Justification RRV-12. )
1-SI-83 The technical justification for deferring the testing of the RCS cold leg 1-SI-86 Si admission check valves to refueling outages was rnoved from Relief 1 SI-89 Request V-41 to Reactor Refueling Justification RRV-10. The technical 1-SI-19#
- justification has not changed. The remaining portion of V-41 addresses the non-intrusive techniques used to test the check valves along with a 1-SI-197 sampling plan for instrumenting the valves. This portion remains in V-1-SI-199 41 and has been editorially changed to enhance clarity. However, no (Rev. 8) new commitments have been made.
Prsgram change: The deferral to test every reactor refueling was moved to Refueling Justification RRV-10.
1-SI-106 Program change: Relief Request V-40 was replaced by Reactor
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1-SI-110 (Rev* 8)
Refueling Justification RRV-9. Also, reference to NUREG 1482, Section 4.1.4, entitled " Extension of Test interval to Refueling Outage i
for Check Valves Verified Closed by 1.eak Testing" was added to l 3rovide additional justification to the basis. The remaining technical I ustification for deferral has not changed.
1-SI-125 The technical justification for deferring the testing of the Si accumulator 1 SI-127 discharge check valves to refueling outages was moved to Reactor 1-SI 142 Refueling Justification RRV-11. The technicaljustification has not 1-SI 144 changed. The remaining portion of V-42 addresses the non-intrusive techniques used to test the check valves along with a sempling plan for 1 SI-159 instrumenting the valves. This portion remains in V-42. References in 1-SI 161 V-42 to evaluating non-intrusive monitoring techniques and using (Rev. 8) disassembly and inspection as an attemative were deleted and the description of the test method revised to enhance clarity. The evaluation has been completed and the use of non-intrusive techniques has been accepted as the test of choice.
Program change: The deferral to test every reactor refueling was moved to Refueling Justification RRV-11. Also, the use of non-intrusive techniques has been accepted as the test of choice as described in Relief Request V-42.
1 SI-190 Program change: Relief Request V-44 was replaced by Reactor 1 SI-192 Refueling Justification RRV 13. The technicaljustification for deferral
! 1-SI-194 has not changed.
(Rev. 8) l 1
1 SI-MOV-1867C Relief Request V 59 was withdrawn. V-59 requested relief from the !
h (d 1-SI-MOV 1867D IWV requirement to individually leak test valves. Certain valves cannot be individually tested, but must be tested as a group or i
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1-SI-MOV-18900 combination. OM Part 10, paragraph 4.2.2.3(c)(2) allows for testing a 1 SI-MOV-1890D combination of valves at the same time. Therefore, relief is no longer necessary for these valves.
(Rev. 8)
Program change: Relief Request V-59 was withdrawn.
1 SI-RV-104 This recently installed valve protects the Si accumulator test line (Rev. 8) containment penetrations from overpressure when samples are being drawn and there is back leakage through the Si accumulator isolation check valves.
Program change: The valve was added to the program. 1 1 SI-RV-1857 This valve protects the HHSI injection line downstream of the BIT from (Rev. 8) over-pressure. This is primarily a thermal relief function to protect from pressure developed by the heat tracing in the isolated portion of the q piping and BIT. The ASME Subcommittee on Valves has interpreted 4' this thermal relief protection function as being within the scope of OM Part 10 if the equipment being protected is required for accident mitigation (refer to ASME Interpretation: 95-9).
1 Program change: The valve was added to the program.
1-SI-RV-1858A According to FSAR Section 6.3.2.1.4.5, these Si accumulator tank 1-SI-RV-1858B relief valves are sized to pass nitmgen at a rate in excess of the A 1 SI-RV-1858C accumulator gas fill line delivery rate. Therefore, they protect the
('j (Rev. 8) accumulators from an uncontrolled release from the gas delivery system.
Program change: The valves were added to the program.
1 SW-3 Program change: Relief Request V-63 was replaced by Reactor 1-SW-10 Refueling Justification RRV-19. The technical justification for deferral has not changed. The test to the partially open position (PO) was (Rev' 8) added to the valve table to enhance clarity. This partially open test is described in Reactor Refueling Justification RRV-19 and is not a new test commitment.
1-SW-22 Program change: Relief Request V-73 was replaced by Reactor (Rev. 8) Refueling Justification RRV-24. The technical justification for deferral has not changed. The test to the partially open position (PO) was added to the valve table to enhance clarity. This partially open test is described in Reactor Refueling Justification RRV-24 and is not a new test commitment. I 1-SW-114 Program change: Relief Request V-45 was replaced by Reactor ,
1-SW-116 Refueling Justification RRV-14. The technical justification for deferral i 1 SW-120 has not changed. '
1 SW 130 1-SW-140 1-SW-150 (Rev. 8) i
! 1-SW-251 These service water header supply and retum manual isolation valves
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1-SW-254 were added to the IST program in response to a Level IV violation 10 l
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1-SW-285 : received in 1990 for not testing the service water header isolation 1-SW-286 capabilities, it was assumed at the time that credit could be taken for 1-SW478 operator action to manually isolate the header in the event of a passive 1-SW479. failure (i.e., pipe rupture). An active failure that could lead to a 1-SW481 ' depressuized header was not considered.
1-SW494 (Rev. 7, Chg. 4) - The failure of a service water pump to sta 1 with one pump out-of-service and the remaining two pumps lined up to the same header would result in a depressurized header. In this case, no credit can be I taken for operator action to manually isolate a depressurized header.
To ensure automatic isolation of the headers, closure tests for check valves that are required to close to allow adequate cooling water for the
- service water to charging pump coolers are being added to the IST program. Therefore, there is no need to continue testing the manual valves.
Program change: The valves were removed from the IST program.
, 1 SW-364 The intemals to these service water supply to control room condenser l 1-SW-386 check valves were removed.
l 1-SW-420 (Rev. 7. Chg. 4) Program change: The valves were removed from the IST program.
1 SW430 The failure of a service water pump to start with one pump out of.
1 SW431 service and the remaining two pumps lined up to the same header h 1 SW441
.1-SW444 would result in a depressurized header. In this case, no credit can be taken for operator action to manually isolate a depressurtzed header.
1 SW447 To ensure automatic isolation of the headers, closure tests for check 1 SW448 valves that are required to close to allow adequate cooling water for the L
1 SW-658 service water to charging pump coolers were added to the IST 1-SW461 program.
1-SW464 1 SW-665 These check valves were tested to the full open position using 1 SW486 temporary ultrasonic flow instrumentation. Because the use of this 1 SW489 equipment is very labor intensive, testing was deferred to every cold (Rev. 7, Chg. 4) shutdown. This test method was replaced by disassembly and inspection that will ve;ify the capability of the check valves to open and close.
Program change: Closure tests were added to the IST program and l_ the full flow open test method using ultrasonic flow instrumentation was l replaced with dbassembly and inspection. The capability of these check valves to ciosed will be verified by disassembly and inspection l as described in Relief Request V 76, I i 1 SW-1067 The test frequency for these manual valves was changed from a cold l 1-SW-1070 shutdown frequency to a reactor refueling frequency. The burden of j 1-SW-1139 testing these valves justifies extending the frequency. The valves are
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l (Rev. 8, Chg. 2) simple manual valves and are not subject to the degradation mechanistr,s experienced by power operated valves. Because the valves are normally open and not exercised frequently, they experience little wear.
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p Unit i Valve Number Prooram Chance f]-
V l
Program change: The test frequency was changed from cold shutdown to reactor refueling. Cold shutdown Justification CSV-45 was replaced by Reactor refueling Justification RRV 26. I l . .
l 7 1-SW-RV-101 A These valves open to provide over-pressure protection for an isolated
' 1-SW-RV 101B component cooling heat exchangerif the heat exchanger is manually (Rev. 8) isolated for maintenance and subjected to thermal loads. The component cooling heat exchangers are required to bring the plant to l cold shutdown following an accident. The ASME Subcommittee on Valves has Interpreted this thermal relief protection function as being within the scope of OM Part 10 (refer to ASME Interpretation: 95-9).
Program change: The valves were added to the program.
1-VP-12 Program change: Relief Request V-46 was replaced by Reactor (Rev. 8) . Refueling Justification RRV 15. Also, reference to NUREG 1482, Section 4.1.4, entitled " Extension of Test interval to Refueling Outage for Check Valves Verified Closed by Leak Testing" was added to l rovide additional justification to the basis. The remaining technical ustification for deferral has not changed.
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l 4.5 VALVE TEST PROGRAM RELIEF REQUESTS i Unit i Valve L Relief Reauest Prooram Channe V-3 Replaced by Reactor Refueling Justification RRV-1. According to OM (Rev. 8) Part 10, paragraphs 4.2.1.2 (e) and 4.3.2.2(e), "If exercising is not practicable during plant operation or cold shutdown, it may be limited to full-stroke during refueling outages." Therefore, relief is no longer required to defer testing until refueling outages, however, the justification for the deferral should be described in the IST Program Plan per NUREG 1482, Section 2.4.5. The technical basis for the deferral has not changed.
l V-9 Replaced by Cold Shutdown Justification CSV-48. V 9 was originally a l (Rev. 8) cold shutdown justification but with provisions. Therefore, there could
, be cold shutdowns where the testing would be impracticable and a relief L
request was the appropriate means of addressing the testing interval.
With OM Part 10 allowing deferral to reactor refueling, the appropriate means for addressing this testing is a cold shutdown justification.
V-10 - Replaced by Reactor Refueling Justification RRV 2. The technical basis (Rev. 8) for the deferral has not changed. l V-16 Replaced by Reactor Refueling Justification RRV-3. The technical basis (Rev. 8) for the deferral has not changed.
V-20 Replaced by Reactor Refueling Justification RRV-4. Reference to using (Rev. 8) a locally installed rotameter was deleted from the original technical basis !
for the deferral for valves 1-HC-14 and 18. The remaining portion of the technical basis was used in RRV-4.
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Unit i Valve
/'T Relief Reouest Prooram Chance t i I V V-21 Replaced by Reactor Refueling Justification RRV-5. The technical basis (Rev. 8) for the deferral has not changed.
V-28 Replaced by Reactor Refueling Justification RRV-6. The technical basis (Rev. 8) for the deferral has not changed.
V-38 Replaced by Reactor Refueling Justification RRV 7. The technical basis (Rev. 8) for the deferral has not changed.
i V-39 Replaced by Reactor Refueling Justification RRV-8. The technical basis (Rev. 8) for the deferral has not changed.
V-40 Replaced by Reactor Refueling Justification RRV-9. The technical basis (Rev. 8) for the deferral has not changed.
V-41 The technicaljustification for deferring the testing of the RCS cold leg Si (Rev. 8) admission check valves to refueling outages was moved to Reactor Refueling Justification RRV-10. The technicaljustification has not changed. The remaining portion of V-41 addresses the non-intrusive techniques used to test the check valves along with a sampling plan for instrumenting the valves. This portion remains in V-41 and has been editorially changed to enhance clarity. However, no new commitments have been made.
V-42 The technicaljustification for deferring the testing of the Sl accumulator (Rev. 8) discherge check valves to refueling outages was moved to Reactor Refeeling Justification RRV-11. The technicaljustification has not changed. The remaining portion of V-42 addresses the non-intrusive
- n. techniques used to test the check valves alcng with a sampling plan for V)
I instrumenting the valves. This portion remains in V-42. References in V-42 to evaluating non-intrusive monitoring techniques and using disassembly and mspection as an attemative were deleted and the description of the test method revised to enhance clarity. The evaluation has been completed and the use of non-intrusive techniques has been accepted as the test of choice.
l V-43 The technicaljustification for deferring the testing of the hot and cold (Rev. 8) legs Si check valves to refueling outages was moved to Reactor Refueling Justification RRV-12. The technicaljustification has not changed. The remaining portion of V-43 addresses the non-intrusive techniques used to test the hot leg SI check valves 1-SI-95,99,103, 209,211 and 213, along with a sampling plan for instrumenting the valves. This portion remains in V-43 and has not unchanged.
V-44 Replaced by Reactor Refueling Justification RRV-13. The technical (Rev. 8) basis for the deferral has not changed. !
j V-45 Replaced by Reactor Refueling Justification RRV-14. The technical (Rev. 8) basis for the deferral has not changed.
V-46 Replaced by Reactor Refueling Justification RRV-15. The technical (Rev. 8) basis for the deferral has not changed.
l V-47 Replaced by Reactor Refucling Justification RRV-16. The technical basis for the deferral has not changed.
( (Rev. 8)
V-53 Replaced by Reactor Refueling Justification RRV-17. The technical (Rev. 8) basis for the deferral has not changed.
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Unit i Valve O Relief Reauest Proaram Chance V-54 Relief request was withdrawn. V 54 deferred the corTective action (Rev. 8) requirements of IWV-3417(a) for rapid acting valves with stroke times less than 2 seconds. IWV 3417(a) regiaired that the test frequency be increased if the stroke time exceeded the previous stroke time by a certain percentage. OM Part 10, paragraph 4.2.1.8(e) addresses rapid acting valves. Therefore, relief is no longer necessary.
l V-57 Replaced by Cold Shutdown Justification CSV-49. V-57 was originally a
! (Rev. 8) cold shutdown justification but with provisions. Therefore, there could
! be cold shutdowns where the testing would be impracticable and a relief request was the appropriate means of addressing the testing interval.
With OM Part 10 allowing deferral to reactor refueling, the appropriate means for addressing this testing is a cold shutdown justification.
I V-59 Relief request was withdrawn. V 59 requested relief from the IWV l (Rev. 8) requirement to individually leak test valves. Certain valves cannot be individually tested, but must be tested as a group or combination. OM Part 10, paragraph 4.2.2.3(c)(2) allows for testing a combination of I
valves at the same time. Therefore, relief is no longer necessary for these valves.
I V-60 Relief request was withdrawn. V-60 requested relief from the l (Rev. 8) requirements of IWV-3427(b) to compare the current leakage rate to the previous measured leakage rate and increase the test frequency if there is an increase of 50% or greater. OM Part 10 does not have this requirement. Therefore, relief is no longer necessary, i
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G V-62 (Rev. 8)
Replaced by Reactor Refueling Justification RRV-18. The technical basis for the deferral has not changed.
V-63 Replaced by Reactor Refueling Justification RRV-19. The technical (Rev. 8) basis for the deferral has not changed.
V-65 Replaced by Reactor Refueling Justification RRV 20. The technical (Rev. 8) basis for the deferral has not changed.
V-66 Relief request was withdrawn. V-66 requested relief from the (Rev. 8) requirements of IWV 3417(a) to compare the current stroke time to the i
previous measured stroke time and increase the test frequency if there is an increase by a certain percentage. V-66 used OM Part 10 paragraphs 4.2.1.8 and 4.2.1.9 as the attematives.to IWV-3417(a).
After committing to OM Part 10 in its entirety relief is no longer necessary.
V-67 Replaced by Reactor Refueling Justification RRV-21. The technical (Rev. 8) basis for the deferral has not changed.
l V-70 Replaced by Reactor Refueling Justification RRV-22. The technical (Rev. 8) basis for the deferral has not changed.
V-72 Replaced by Reactor Refueling Justification RRV 23. The technical (Rev. 8) basis for the deferral has not changed.
V-73 Replaced by Reactor Refueling Justification RRV 24. The technical (Rev. 8) basis for the deferral has not changed.
V-76 This relief request was added to the IST program to describe the testing m (Rev. 7, Chg. 4) method for the service water to charging pump coolers check valves.
These valves will be verified to the full open position and to the closed position using disassembly and inspection as the test method on a l
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Relief Realms Pmoram Channe
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reactor refueling frequency. ,The valves will be stroked to the partially
. open position every three months using flow.
l There is no permanently installed instrumentation to measure flow
- through the valves for testing to the full open position. Due to the l
system configuration, it is not practical to perform a backpressure / backseat test on these valves every quarter for testing to the closed position.' Both service water headers are pressurized during i
normal operation and are shared between the two units. Therefore, header pressure cannot be used to create a pressure differential across the check valves without putting the plant through a major evolution to depressurize one header.
The valves can be disassembled and inspected while the plant is operating. To allow for flexibility in planning for refueling outages and i still meet the intent of OM Part 10, the valves will be disassembled on a I
reactor refueling frequency (not to exceed 24 months) but not
. necessarily during refueling outages. The valves will be placed in groups of two, two groups per pump, according to valve manufacturer, type, size and service conditions. One valve from each group will be disassembled and inspected on a refueling frequency (not to exceed 24 months). The second valve in the group will be disassembled during the next inspection and the cycle will continue on a rotating basis. The valves will be stroked to the partially open position every three months.
The test method, frequency and sampling plan are in accordance with Generic Letter 89-04, Position 2. Therefore, prior approval by the NRC to use this test method, frequency and sampling plan is not required.
These check valves were tested to the full open position using temporary ultrasonic flow instrumentation. Because the use of this equipment is very labor intensive, testing was deferred to every cold shutdown. This test method was replaced by disassembly and inspection that will verify the capability of the check valves to open and close, a 4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS I
Unit i Valve Cold Shutdown Justification Prooram Chanoe CSV 11 The requirement to perform a partial open exercise test every three
! (Rev,8) months was deleted for the main feedwater regulating valves 1 FW-1 FCV 1478,1488 and 1498. In order to perform a partial stroke test during normal operation, the plant would have to reduce power to cause the valve disks to move. Reducing power for the purpose of performing an exercise test is considered im actical according to the NRC response to Comment 2.4.5-1 in UREG-1482, Appendix G.
CSV-13 The method of testing for the main steam non-retum valves was
_ (Rev. 7, Chg. 4) changed to incorporate the use of motor current instead of yoke strain to detect changes in running force. Motor current is more sensitive to 15
D Unit i Valve s Cold Shutdown Justification Program Chanoe changes in stem load.
CSV-33 This cold shutdown Justification was revised to indicate that the main (Rev. 8) - steam trip bypass valves 1-MS-TV-113A, B and C are passive in the closed position during normal operation and do not require quarterly l testing.. These trip valves are opened only during plant startup to j
provide flowpaths for steam from each of the steam generators to equalize pressure across the main steam trip valves. They remain closed during normal operation to prevent the unrestricted release of steam from multiple steam generators in the event of a downstream steamline rupture and to isolate the steam generators (automatically close on steamline or IHH isolation) in the event of a LOCA or steam generator tube rupture. When closed, they provide isolation of the unaffected steam generators thus ensuring an adequate supply of steam
. for AFW pump turbine operation. They are designated as containment
' isolation valves (non-leak tested). There is a remote possibility that these valves would have to close during plant startup; therefore, they are considered active to the closed position only during plant startup.
During normal operation they are passive in the closed position and do
, not require quarterly testing. They will be tested prior to startup to I ensure nperability.
CSV-35 This cold shutdown justification was replaced by Relief Request V-76.
/' (Rev. 7, Chg. 4) The service water to charging Pump cooler check valves were tested to the full open position using temporary ultrasonic flow instrumentation.
l Because the use of this equipment is very labor intensive, testing was l
deferTed to evety cold shutdown. This test method was replaced by disassembly and inspection that will verify the capability of the check valves to open and close.
The increase in safety provided by the full open flow test does not justify l the burden of using the ultrasonic flow instrumentation given that en allemative test method will be used to verify the full open position. The valves will be tested to the partially open position using flow every three months.
CSV-45 Replaced by Reactor Refueling Justification RRV-26 (Rev. 8, Chg. 2)
CSV-47 Replaced by Reactor Refueling Justification RRV-25 (Rev. 8)
CSV 48 Replaces Relief Request V-9 (Rev,8)
CSV-49 Replaces Relief Request V-57 !
(Rev. 8) 4.7 - VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS j L
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Unit i Valve Cs Reactor Refueling Q Justification Prooram Chance RRV-1 Replaces Relief Request V-3 (Rev. 8)
RRV-2 Replaces Relief Request V-10 (Rev. 8)
RRV-3 Replaces Relief Request V-16 (Rev. 8)
RRV.4 Replaces Relief Request V 20. Valves 1-CV-8 and 14 were added to (Rev. 8) RRV-4. Full flow testing these valves requires that the hydrogen recombiner system be operated. Should a containment pressurization event occur while the recombiner system is operating, the design pressure of the low pressure hydmgen recombiner could be exceeded.
valves 1-CV-8 and 14 can be tested to the partially open position every three months using the containment vacuum pumps while maintaining the recombiner system isolated from the containment atmosphere.
Reference to using a locally installed rotameter was deleted from the original technical basis for the deferral for valves 1 HC-14 and 18. The remaining portion of the technical basis was used in RRV-4.
RRV-5 Replaces Relief Request V 21 (Rev. 8)
RRV-6 Replaces Relief Request V-28 (Rev. 8)
RRV 7 Replaces Relief Request V-38 (Rev. 8)
RRV-8 Replaces Relief Request V-39 (Rev. 8)
RRV-9 Replaces Relief Request V-40 (Rev. 8)
RRV-10 The portion of Relief Request V-41 that addresses deferral of testing to (Rev. 8) reactor refueling outages was moved to this reactor refueling justification.
RRV-11 The portion of Relief Request V-42 that addresses deferral of testing to (Rev. 8) reactor refueling outages was moved to this reactor refueling justification.
RRV-12 The portion of Relief Request V-43 that addresses deferral of testing to (Rev. 8) reactor refueling outages was moved to this reactor refueling justification.-
RRV-13 Replaces Relief Request V-44 (Rev. 8)
RRV 14 Replaces Relief Request V-45 (Rev. 8)
RRV-15 Replaces Relief Request V-46 17 t
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/" Reactor Refueling Justification Prooram Chanoe
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(Rev. 8)
PRV-16 Replaces Relief Request V-47 (Rev. S) l RRV-17 Replaces Relief Request V 53 (Rev. 8)
RRV-18 Replaces Relief Request V42 (Rev. 8) 6 RRV-19 Replaces Relief Request V43 (Rev. 8)
RRV-20 Replaces Relief Request V45 l (Rev. 8)
RRV-21 Replaces Relief Request V47 (Rev. 8) -
RRV-22 Replaces Relief Request V-70 (Rev. 8) l RRV-23 Replaces Relief Request V-72 (Rev. 8)
RRV-24 Replaces Relief Request V-73 (Rev. 8)
RRV-25 Replaces Cold Shutdown Justification CSV 47. Refer to the discussion (Rev. 8) for valves 1 Sl46,1-SI-MOV-1867A and 1-SI-MOV-18678.
RRV-26 Replaces Cold Shutdown Justification CSV-45. Refer to the discussion (Rev. 8, Chg. 2) for valves 1-SW-1067,1070 and 1139.
5.0 REPORTING OF INSERVICE TEST RESULTS Section 5 was changed to reference the reporting requirements of OM Part 6, Section 7, and OM Part 10, Section 6.
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VIRGINIA ELECTRIC AND POWER = COMPANY-
-NORTH ANNA POWER STATION UNIT 1 INSERVICE TESTING PROGRAM PLAN FOR PdMPS AND VALVES SECOND INSPECTION INTERVAL DECEMBER 14, 1990 - DECEMBER 14, 2000 REVISION 8 I
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TABLE OF CONTENTS-p .,
V INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES
1.0 INTRODUCTION
2.0 GENERAL PROGRAM DEVELOPMENT 2.1-~ Program Scope 2.2 Program Update.
3.0 PUMP. INSERVICE TEST PROGRAM DESCRIPTION 3.1. Program Development Philosophy.
' 3. 2 Program Implementation 3.3 Program Administration 3.4- Pump Reference List
' 3. 5' Pump InserviceLTest Tables 3.6 Pump Test Program Relief Requests 3.7 Alternative Testing for Non-Code Pumps 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION
.4.1 Program Development Philosophy 4.2- Program' Implementation:
~4. 3 Program Administration
.4.4 ' Valve Inservice Test Table 4.5 Valve Test Program Relief ~ Requests 4.6 -ValveLTest Program Cold Shutdown Justifications 4.7 Valve Test Program Reactor Refueling Justifications 4.8 Alternative T. sting for Non-Code Valves 15 , 0 REPORTING OF INSERVICE TEST RESULTS 5.1 - Pump Inservice Test Program 5.2. Valve Inservice Test Program 6.0 QUALITY' ASSURANCE PROGRAM O 11 l N1PVI2R8 .' ,
Revision 8 August 17, 1998 i
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m INSERVICE TESTING. PROGRAM FOR PUMPS AND VALVES -
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( 1.0' INTRODUCTION This Pbmp and' Valve Inservice Test'(IST) Program Plan is-applicable'to the North Anna Power Station Unit 1 which-received its construction permit on February 19,-1971 and began 1 commercial operation ~in June 1978. North Anna Power Station. Unit 1 is a Pressurized Water Reactor located on Lake Anha in Louisa County, Virginia. The plant employs a Westinghouse Electric Corp. Nuclear Steam System.
The IST Program Plan is comprised of-two independent subprograms - the Pump Inservice Test Program and the Valve Inservice Test Program. The development, implementation and administration of these two programs are detailed in subsequent sections. This IST Program Plan applies to the second 10-year IST interval for North Anna Power Station-Unit 1 which started on December 14, 1990 and ends on December 14, 2000. The end of the first inspection interval for IST was extended from June 6, 1988 to December 14, 1990 to coincide with the end of the first inspection interval for North Anna Unit 2. This extension was granted in the form of an exemption to 10CFR50.55a(g) (4) per NRC letter (Serial Number 88-242), dated April 26, 1988.
For IST, 10CFR50.55a(g) was replaced by 10CFR50.55a (f) which was approved for use by the Federal Register, Vol. 57, No.
152, dated AugustJ6, 1992. As described in paragraph (b) (2) of 10 CFR 50.55a, " references to Section XI of the ASME Boiler and Pressure Vessel Code refer to Section XI, Division 1, and include addenda through the 1988 Addenda and editions through the 1989 Edition." The IST Program Plan for the second 10-year interval for North Anna Unit 1 complies with these addenda and edition.
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N1PVI2R8 Revision 8 August 17, 1998 L
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l 2.0 GENERAL-PROGRAM DEVELOPMENT.
ASME'B&P Code,Section XI (hereby referred to as 'the Code')
requires that the' owner of each nuclear power plant prepare and submit a " plan" for testing and inspection of systems and components under the jurisdiction of the Code and in compliance with Title 10, Part'50 of the Code of Federal I Regulations (Para. 50.55a). With respect to the elements of L
that plan related to the testing of pumps and valves,Section XI, Subsections IWP and IWV dire <st each licensee to comply-with the applicable portions of ASME/ ANSI OM Parts 6 and 10. The NRC directed via the Federal Register, Vol. 57, No. 152 dated August 6, 1992 that pump and valve testing should be performed in accordance with ASME/ ANSI OM-1987 including OMa-1988 Addenda. Specifically, . Part 1 of OM-1987 and Paragraphs 1.1 of OMa-1988 Addenda, Parts 6 and 10, ,
establish the IST program scope with the provision that the 1
. rules apply only o ISI Classes 1, 2 and 3 as stated by the NRC in the Federal Register, Vol. 56, No. 21 dated January 31, 1991. I In accordance with ASME/ ANSI OM-1987 and OMa-1988 Addenda, the following are required to be included in the testing program:
("N 1) Centrifugal and positive displacement pumps that are ]
provided with an emergency power source and required to perform a specific function in shutting down the reactor to the cold shutdown condition ~, maintaining the cold shutdown !
condition or mitigating the consequences of an accident.
- 2) Active or passive valves (and their actuating and
! position indicating systems) which are required to perform a specific function in shutting'down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or mitigating the consequences of an accident.
- 3) Pressure relief devices that protect systems or portions of systems which perform a required function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or mitigating the consequences of an accident.
In addition to the general Code requirements outlined above, there are other interpretations and positions that have come about as a result of past regulatory and licensee actions including Generic Letter 89-04 and NUREG-1482. Other than these guides, there is no specific guidance for developing the IST Program scope of testing. Therefore, a set of rules was established by which the scope of the North Anna ASME 2-1 Revision 8 l l N1PVI2R8 August 17, 1998 i l
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Section XI IST Program is determined including components that are to be included and the extent and type of testing required for each. Based on these rules, the philosophy and assumptions used in determining the test' requirements for selected pumps and valves were docnmented.
2.1 PROGRAM SCOPE In the course of developing the Program scope, each of the significant safety systems included within the ISI Class boundaries and certain safety systems outside of the ISI Class boundaries (such as the emergency diesel fuel oil transfer system) were evaluated with respect to the function of each component and the need for its operability as it relates to the scope of Section XI.
Supporting documents used include, Final Safety Analysis Report (FSAR),
Technical Specifications, Past program correspondence, Operating Procedures (normal, emergency and abnormal) and Plant' System Descriptions.
The sequence followed during the development effort was as follows:
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- 1) Each of the plant systems was subjected to an overview to determine any potential active safety function as described in the scope statement. Those systems with no obvious safety functions were then excluded from further consideration. Plant documents as well as operating staff comments were utilized in this phase.
- 2) For the remaining systems, flow diagrams were studied and any component that could possibly have an active or passive safety function (other than simply maintaining the pressure boundary) were identified for further evaluation.
- 3) The function of each component identified from the flow diagrams was determined based on available documentation, staff review or general experience of the evaluator. Testing requirements were derived based on the component function (s) and the applicable rule (s).
A U 2-2 Revision 8 N1PVI2R8 August 17, 1998
- 4) Available documents were reviewed and specific or O implied component operational requirements were compared to the component functions.
- 5) The results of the steps described above were reviewed by several knowledgeable members of the plant staff and evaluated for accuracy and consistency, and compiled in an IST basis document. Based on this review, the final program scope was derived and the IST Program Plan developed.
2.2 PROGRAM UPDAT.h During the third 10-year interval it is expected that the scope of the Program will occasionally be modified in response to unrelated activities including, but not limited to:
- 1) Plant design changes,
- 2) Changes in operating conditions (e.g. normal valve lineup) and
- 3) Changes in accident mitigating procedures philosophy.
As a result, it is expected that the IST Program may be revised to ensure continued compliance with the Code
-requirements relating to the scope of the test program.
The supervisor responsible for maintaining the IST Program is provided copies of all plant modifications that are designated by Engineering to have a potential IST/ISI impact. Should a change require a Program revision, the IST Coordinator would then implement the change to the Program Plan and the appropriate test procedure (s) in a timely manner.
2-3 Revision 8 N1PVI2R8 August 17, 1998 L. .. . . . .
3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION
(N N ,)
s 3.1 PROGRAM DEVELOPMENT PHILOSOPHY The North Anna Unit 1 Pump 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 that Inservice Testing of ASME Code Class 1, 2 and 3 pumps 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 (f) , except where specific written relief has been granted by the Commission pursuant to 10CFR50, Section 50.55a (f) (6) (1) .
10CFR50, Section 50.55a (f) (4) (iv) stLtes 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 pumps that fall under the scope of ASME Section
\s,}/ XI using Subsection IWP of the 1989 Edition. The 1989 Edition of Subsection IWP references OM Part 6, Edition OM-87, ASME/ ANSI, Operation and Maintenance of Nuclear Power Plants, Addenda OMa-1988. 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.
OM Part 6 defines the rules and requirements of inservice testing of Code Class 1 ,2, and 3 pumps and states that each specific pump 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 pumps that are considered by Virginia Electric and Power Company as having a safety function and are therefore subject to the testing requirements of OM Part 6. The intent of the Code is to assess operational readiness and detect potentially adverse changes in the mechanical condition of these pumps. The relief
/~' requests for the Pump Inservice Test Program identify V) 3-1 Revision 8 N1PVI2R8 August 17, 1998 I- -
y Code requirements considered to be impractical, provide T technical basis for the request and propose alternate l s testing when warranted.
l l 3.2 PROGRAM IMPLEMENTATION Surveillance testing is performed to detect equipment malfunction or degradation and to initiate corrective l
action. Since the safeguards pumps are normally in l standby mode, periodic testing of this equipment is
- especially important. The North Anna Power Station i Unit 1. Inservice Test Program provides a schedule for testing safety-grade pumps and is implemented as part of normal periodic surveillance testing.
Reference data is gathered during initial surveillance tests. In most cases, test parameters are measured with normal plant instrumentation. This approach simplifies the test program and promotes timely completion of periodic surveillance testing. When permanently installed instrumentation is not available, portable instrumentation is used to record the required parameters.
During subsequent surveillance tests, flow rate is normally selected as the independent test parameter and O- is set to match the reference flow rate. Other hydraulic and mechanical performance parameters are measured and evaluated against the appropriate reference values. The results of such evaluations determine whether or not corrective action is warranted.
Each pump in the Pump Inservice Test Program is tested according to a detailed test procedure. The procedure include, as minimum:
- 1)
References:
This section identifies references !
applicable to Technical Specifications and other necessary material as drawings. l 2)
Purpose:
This section identifies test objectives. I
- 3) Initial Conditions: Each procedure should identify those independent actions or procedures which shall be completed and station conditions which shall exist prior to use.
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- 4) Precautions: Precautions should be established to ;
alert the individual performing the task to those-
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3-2 I Revision 8 N1PVI2R8 August 17, 1998
situations in which important measures should be taken O early or.where extreme care should be used to protect-equipment and personnel. Cautionary notes applicable to specific steps in the procedure should be included
.in the main body of the procedure as appropriate and should be identified as such.
- 5) Instructions: The main body of a procedure should contain step by step instructions in the degree of detail necessary for performing'a required test.
- 6) Acceptance Criteria: The ranges within which test data are considered acceptable are established and included in the test procedure. In the event that data fall outside the acceptable range, operator action is ;
governed by approved station procedures.
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Finally, it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements.
{
Additional testing is performed, as required, after I pump maintenance or as determined necessary by personnel at North Anna Power Station.
3.3 PROGRAM ADMINISTRATION R" The Engineering staff at North Anna is responsible for k)? -
m the administration of the Pump Inservice Testing Program. The Operations staff is responsible for performing the periodic tests as required by this program. The Pump Inservice Testing Program is implemented by Station Periodic Test Procedures.
3.4 PUMP REFERENCE LIST This list gives a brief description of each pump identified in the Pump Inservice Test Program.
1 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. j
() 3-3 -
i Revision 8 l I
N1PVI2R8 August 17, 1998
1-CH-P-1A High Head Safety Injection / Charging Pumps
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1-CH-P-1B 1-CH-P-1C Drawing: 11715-CBM-95B, Sh 2 of 2 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.
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 l 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.
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1-FW-P-2 Auxiliary Feedwater Pumps 1- FW-P-3 A 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-OS-P-1A Quench Spray Pumps 1-OS-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 I i
Depressurization Actuation signal.
1-RH-P-1A Residual Heat Removal Pumps 1-RH-P-1B Drawing: 11715-CBM-94A, Sh 1 of 2 ,
Function: Remove decay heat from the reactor core and !
/~') the Reactor Coolant System during plant cooldown.
V 3-4 Revision 8 N1PVI2R8 August 17, 1998
O
\s ,/- 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 an accident.
1-RS-P-2A; Outside Recirculation Spray Pumps 1-RS-P-2B' Drawing: 11715-CBM-91A, Sh 4 o'f 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.
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.
i O 3-5 Revision 8 N1PVI2R8 August 17, 1998
1-SW-P-4 Auxiliary Service Water Pump Drawing: 11715-CBM-78A, Sh 1 of 4
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Function: Provide make up to the Service Water 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.
1-HV-P-22A Control 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.
3.5 PUMP INSERVICE TEST TABLES
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This tabulation identifies the pumps to be tested, code classes, required test quantities and frequencies.
Relief from test requirements is requested in cases where test requirements have been determined to be impractical. Where relief is requested, technical. 1 justification is provided along with alternative test i methods when applicable.
For non-Code pumps, a request for relief is not I necessary when provisions of the Code cannot be met.
Section 3.7 contains a discussion of the testing requirements for non-Code pumps and descriptions of alternative testing in cases where the provisions of the Code cannot be met.
To aid the reader in interpreting the Pump Inservice Test Table, brief explanations of the table headings i and abbreviations are provided below.
- 1) Pump Number - Each pump in the plant has a unique
" mark" number which identifies the system to which the pump belongs.
- 2) Code Class - ASME Code Class of each pump as per O 10CFR50.55a and Regulatory Guide 1.26. !
3-6 Revision 8 N1PVI2R8 August 17, 1998 m
(~} Note: NC is for non-Code pumps. These pumps are
(_/ important to safety but are not in systems that are classified ASME Class 1, 2 or 3.
- 3) System Resist - Either FIX for a test loop with a fixed system resistance or VAR for a test loop with a system resistance that can be varied.
- 4) The required Section XI test quantities of Inlet Pressure, Differential Pressure (Discharge Pressure is not a required test quantity but is listed for clarity), Flow Rate, Vibration, Pump Speed and Lubrication Level / Pressure are given as column headings. The following abbreviations are used to describe the test status:
0 - the test will be performed on a quarterly basis CSD - the test will be performed every cold shutdown. A relief request explains the need for deviating from Section XI test frequency requirements
/~h NA - the test is not applicable, see corresponding (s) relief request j RR - the test will be performed every reactor refueling. A relief request explains the need for deviating from Section XI test frequency requirements.
2Y - the test will be performed every 24 months Under pump speed, NA applies to constant speed pumps which do not require the measurement of speed. Therefore, no relief is necessary. I Under Lubrication Level / Pressure, NA applies to pumps that have a lubrication system with no level or pressure indication. No relief is necessary.
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O 3-7 Revision 8 N1PVI2R8 August 17, 1998 l
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3.6 PUMP TEST PROGRAM RELIEF REQUESTS l
Relief requests identify those ASME OM Part 6 Code requirements considered to be impractical. The basis for the relief request and the alternate testing to be l performed is given.
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3-12 N1PVI2R8 Revision 8 August 17, 1998 L_
f'T RELIEF REQUEST P-1
. \v' Systems: Various Pump (s): IWP Program Pumps. See PUMP INSERVICE TEST TABLE.
Class :
OM Part 6 Code Requirements For Which Relief Is Requested OM Part 6, Paragraph 4.3, requires that reference values be determined.from the results of preservice testing or from the results of-the first inservice test.
This request applies only to. vibration testing.
Basis For Request Small reference values for vibration (Vr) will produce small acceptable ranges for pump operation. Based on a small acceptable range, an adequately and smoothly running pump could be subject to corrective action. To avoid this situation, a
/~N minimum value for Vy of 0.05 in/see has been established for
-d velocity measurements.
Alternate Testing Proposed Pumps with a measured reference value below 0.05 in/sec shall have subsequent test results compared to an acceptable range based on 0.05 in/sec.
l O 3-13 N1PVI2R8 Revision 8 August 17, 1998
RELIEF REQUEST P-2
{ Relief Request Withdrawn I RELIEF REQUEST P-3 Relief Request withdrawn.
RELIEF REQUEST P-4 Relief Request withdrawn.
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O 3-14 N1PVI2R8 Revision 8 August 17, 1998
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RELIEF REQUEST.P-5
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Systems: Residual Heat Removal Pump (s) : 1-RH-P-1A 1-RH-P-1B
. Class : -OM;Part.6' Code. Requirements For Which Relief-Is Requested OM-Part 6, Paragraph 5.1 requires an inservice test be run on i
. ;- each pump nominally every 3 months.
Basis'For Request The low pressure pumps take suction from and discharge to the i 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.
Also, the pumps are' located'inside containment and are inaccessible during normal operation.
( As a ressltLof industry experience and NRC guidance (Generic Letter.88-17) concerning the loss of decay heat removal capability, North Anna Power Station practices a policy of minimizing perturbations to RHR pump flow and system configuration when' decay heat must be removed during cold shutdowns and reactor-refueling outages.
.Therefore, to permit RHR pump testing and to minimize system'
, perturbations during cold shutdown testing, the RHR pumps will be tested in a range of flows from approximately 2500 gpm to 4000 gpm'(depending on-the system flow at.the time of the test), and the results will-be compared to acceptance criteria based on that
' portion of the pump.' curve described above and the hydraulic
' acceptance criteria given in OM Part 6. The guidelines set forth 1 in NUREG 1482, Section 5.2, "Use of Variable Reference Values for Flow; Rate and Differential Pressure During Pump Testing," will be
.followed.
I 3-15
! 1 N1PVI2R8 Revision 8
- ' August 17, 1998 iT
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RELIEF REQUEST P-5 (Cont.)
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If vibration is found to vary significantly over the range of flow rates, flow rate versus vibration velocity data for at least five points will be taken, and a curve fit for these data points will be determined. Using the fitted curve and the acceptance criteria'for vibration' testing in OM Part 6, acceptance criteria dependent on flow rate will be determined.
Alternate Testing Proposed These pumps _will be tested every cold shutdown but not more frequently than-once every three months. Acceptance criteria will be' based on a portion of the pump curve and not on discreet reference values.
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U 3 N1PVI2R8 Revision 8 August 17, 1998
r O RELIEF REQUEST P-6 Relief Request Withdrawn l
RELIEF REQUEST P-7 Relief Request Withdrawn l
l RELIEF REQUEST P-8 Relief Request withdrewn.
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l N1PVI2R8 Revision 8 August 17, 1998 i
(~ RELIEF REQUEST P-9 V}
Systems: Service Water Pump (s) : 1-SW-P-1A 1-SW-P-1B Class : 3 OM Part 6 Code Requirements For Which Relief Is Requested OM Part 6, Section 5, Table 2 (Inservice Test Parameters) requires the measurement of differential pressure.
Basis For Request These pumps take suction from the Service Water 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 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. 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 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 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 gauge
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3-18 N1PVI2R8 Revision 8 August 17, 1998
1 RELIEF REQUEST P-9 (Cont.)
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 i the operability band is smaller.
Alternate Testing Proposed l
Discharge pressure will be measured in place of differential pressure.
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3-19 N1PVI2R8 Revision 8 August 17, 1998
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RELIEF REQUEST P-10
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- Systems: Service Water Pump (s): 1-SW-P Class : 3 OM Part 6 Code Requirements
.For Which Relief Is Requested OM Part-6, Section 5, Table 2 (Inservice Test Parameters) requires the measurement of differential pressure.
, Basis-For Request 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 required by Technical l Specifications, and maximum and minimum recorded levels during I 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 l pressure is measured. l
' 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 l discharge pressure to the height from the discharge pressure gauge j o
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). 3-20 l N1PVI2R8 Revision 8 August 17, 1998
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RELIEF ' REQUEST P-lb' (Cont. )
to.the pump impeller, subtracting the height from the lake surface to-the pump-impeller.
i 'Therefore,.the measured discharge pressure will always be a
- l. smaller number than the actual total head developed by.the pump.
l- Applying the Section XI acceptance criteria to'just the discharge l . pressure instead-of the total developed head for a deep draft pump is a conservative application.of the acceptance criteria'because l the operability band is smaller.
Alternate Testing Proposed ~
Dis' charge pressure will be measured in place of differential
. pressure.
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3-21 -
l N1PVI2R8 Revision 8 August 17, 1998
RELIEF REQUEST P-11 Relief Request withdrawn.
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l 3-22 N1PVI2R8 Revision 8 August 17, 1998 1
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, RELIEF. REQUEST P-12 l
Systems: Component Cooling a'nd Service' Water l HPump (s) : 1-CC-P-1A 1-SW-P-1A 1-CC-P-1B l-SW-P-1B 1-SW-P-4
~ Class ~ : 3 OM Part 6 Code Requirements For Which Relief Is; Requested
'OM Part 6, Paragraph 4.3 requires reference values to be points of operation readily duplicated during subsequent tests. All subsequent. test results shall~be compared to these initial reference values.
Basis'For-Request 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
N Service Water Systems, reproducing one of these reference flow points-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 _i significantly with flow rate over the range of the test flow l rates. l Alternate Testing' Proposed All subsequent test results will be compared to calculated .
reference values which are determined using the following method. j A set of at least five pressure / flow points will be recorded. l From these points an equation for the line will be calculated by a computer using polynomial regression. The resulting polynomial i equation describes the reference curve. i l
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3-23 N1PVI2R8 Revision 8 August 17, 1998
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'(y,/) 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, OM Part 6, Table 3b limits. Pumps may then be tested during normal operation without any valve throttling.
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(D LJ 3-24 N1PVI2R8 Revision 8 August 17, 1998 l 1
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"'T RELIEF REQUEST P-13
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' Systems: Component-Cooling-Chemi' cal and Volume Control Service. Water Pump'(s) : 1-CH-P-1A- 'l-CC-P-1A 1-CH-P-1B 'l-CC-P-1B 1-CH-P-1C' 1-SW-P-4 Class : 3 OM'Part 6 Code Requirements For'Which Relief Is Requested OM Part 6,'Section 4.6,1Tabl.e 1 (Acceptable Instrument Accuracy) requires that pressure and flow instruments be accurate to 1 2%.
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 faccuracy is found by the root sum of the squares.
The only i 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 12% tolerance listed in Table 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-110 1-SW-P-4 Discharge Pressure 2.61%
Alternate Testing Proposed None.
O' 3-25 N1PVI2R8: Revision 8 ;
August 17, 1998 i
RELIEF REQUEST P-14 Relief Request withdrawn.
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O 3-26 N1PVI2R8 Revision 8 August 17, 1998
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v RELIEF' REQUEST P-15 Systems: Boric Acid Transfer Pump (s): 1-CH-P-2A 1-CH-P-2B Class : 3
- OM Part 6 Code. Requirements For Which Relief Is Requested OM Part 6, Paragraph 5.1-requires an inservice test be run on each pump nominally every 3 months.
Basis For Request 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. 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 inje:cted into the RCS during the. pump tests, the pumps will be run for two minutes with flow to the RCS before the test quantities are measured.
3-27 -
N1PVI2R8 Revision 8
' August 17, 1998
) RELIEF REQUEST P-15 (Cont.)
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Alternate Testing Proposed 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.
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O 3-28 N1PVI2R8 Revision 8 August 17, 1998 L
RELIEF REQUEST P-16 Relief Request withdrawn.
O O 3-29 N1PVI2R8 Revision 8 August 17, 1998
p 3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS v
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. I 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 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.
l l
3-30 N1PVI2R8 Revision 8 August 17, 1998
P?
NON-CODE ALTERNATIVE TESTING PNC System : Puel Oil
. Pump ( s') : 1-EG-P-1HA' 1-EG-P-1JA' J EG-P-1HB' 1-EG-P-lJB Class. : NC 1 OM Part 6 Code Requirements Which Will Not Be Met OM Part 6, Paragraph 5.6. requires that test quantities be measured' after the pump has been running for at-least two minutes.
OM Part'6, Paragraph 4.6.1.2.' requires that the full-scale range
~
-of'each analog instrument shall-be.not greater-than three times the reference value.
Basis For Alternate Testing The pump operating time is limited due to operational restraints.
While the diesels'are running, these pumps start automatically O when the fuel-oil level in the day tank reaches the low level switch, and stop when the level reaches the high level switch.
The pump run-time can vary depending upon the diesel load and the resulting fuel consumption rate.- If the pumps are' allowed to run for two minutes prior to measuring the test quantities'and the fuel consumption rate is low, not enough time is available to gather all-of the required.Section XI test data.
The discharge pressure gauges have a full-scale. range of 0 to 30 psig. Discharge pressure reference values range from 7.5 to B.5 psig, less than the required 1/3 of full-scale or 10 psig. Test results show that the data is repeatable. Therefore, even though the reference values are less than 1/3 full-scale, the accuracy
-of-the instruments provides acceptable results.
O 3-31
'N1PVI2R8 Revision 8 August 17,"1998
i
.NON-CODE' ALTERNATIVE TESTING PNC-1 (Cont.)
Alternate Testing
'The measurement of Section XI quantities'will begin when the pump-automatically _ starts'on a low tank level signal.
Discharge pressure l measurements will be performed with reference
. values slighty-below1the 1/3 full-scale requirement.
Note: The diesel oil transfer pumps are positive displacement pumps. . According to OM Part 6, Table 2, discharge pressure, flow and vibration must be measured-for positive displacement pumps.
Differential. pressure does not have to be measured.
t O
O 3-32 N1PVI2R8- Revision 8 August 17, 1998
r l
4.0 VALVE INSERVICE TESTING PROGRAM DhSCRIPTION 4.1 PROGRAM DEVELOPMENT PHILOSOPHY North Anna Power Station Unit 1 is a Pressurized Water Reactor being operated in compliance with the ASME Boiler and Pressure Vessel Code. The Code requires periodic testing of certain safety related valves in order to verify their operability and physical integrity. The North Anna Unit 1 Valve Inservice Test Program satisfies these requirements.
The program will detect potentially adverse changes in the mechanical condition of valves within the scope of Section XI, Subsection IWV of the Code. Subsection IWV, addenda through the 1988 Addenda and editions through the 1989 Edition, references Part 10, Edition OM-87, ASME/ ANSI, Operation and Maintenance of Nuclear Power Plants, Addenda OMa-1988. Therefore, the Program is based on the requirements of Part 10, along with NRC Staff guidelines provided in Generic Letter 89-04 for complying with certain provisions of 10.CFR 50.55a (f) .
This program includes valves "which are required to O perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident." It is important to note that the scope of ASME Section XI and the North Anna J Inservice Testing Program for its implementation includes many valves which are not required to operate to meet FSAR license condition of hot shutdown nor limiting conditions in the plant Technical Specifications. In these cases, the requirements of Section XI, OM Part 10 shall be met except where relief has been granted.
To generate the North Anna Unit 1 Valve Program, ASME Class 1, 2 and 3 valves were analyzed to determine their required type and frequency of testing. The valves to be tested under OM Part 10 commitments are listed by system and drawing in the Valve Test Tables.
North Anna Unit 1 is committed to meeting the leak rate testing requirements of:
- 1) 10CFR50, Appendix J for containment isolation valves and 4_ ,
N1PVI2R8 Revision 8 August 17, 1998
/N 2) OM Part 10 for other valves for which seat ksl m leakage is limited to a specific maximum amount (i.e. pressure isolation valves) unless relief is specifically requested from OM Part 10 requirements.
Valves subject to leak testing per Appendix J will be tested to the requirements of OM Part 10, Paragraphs
- 4. 2. 2. 3 (e) and 4.2.2.3 (f) as required by 10 CFR 50.55a (b) (2) (vii) . Appendix J satisfies the testing requirements of OM Part 10, Paragraph 4.2.2.2.
The Code recognizes that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.
The relief requests for the Valve Inservice Test Program identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted (refer to Section 4.5).
The North Anna Unit 1 Valve Inservice Test Program complies with the intent of the applicable codes,
("'N
(_,)
regulations and guidelines and makes a positive contribution to the safe operation of the plant.
4.2 PROGRAM IMPLEMENTATION The Valve Inservice Test Program is executed as part of the normal plant surveillance routine. Three types of tests are conducted as part of the Valve Test Program:
- 1) Valve Exercise Tests,
- 2) Valve Leakage Tests and
- 3) Safety Valve Tests The Exercise Tests verify that:
- 1) the valve strokes properly,
- 2) the valve responds to control commands,
- 3) the valve stroke time is within specific limits and
- 4) remote position indication accurately reflects the observed valve position. Remote valve position indication will be verified every two years.
Fail safe valves are tested by observing the valve operation upon loss of actuating power. In most cases, i
this can be accomplished using normal control circuits.
4-2 N1PVI2R8 Revision 8 August 17, 1998
l C\ #
E u/ Those valves which are scheduled to be exercised during cold shutdown are subject to the requirements of OM Part 10, Paragraph 4.2.1.2 (g) ' which states that:
" valve exercising during cold shutdown shall commence within 48 hr of achieving cold shutdown, and continue until all testing is I complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hr provided all valves required to be tested during cold shutdown will be tested prior to plant startup.
However, it is not the intent of this Part to )
keep the plant in cold shutdown in order to
]
complete cold shutdown testing." J Valve Leakage Tests verify that valves are leak tight in accordance with Appendix J or ASME Section XI.
Relief and Safety valves are required to be tested to the requirements of OM Part 1.
Certain valves cannot be full stroke exercised during normal operation following maintenance. These valves
N are described in the cold shutdown justifications
- (refer to Section 4.6) and reactor refueling justifications (refer to Section 4.7). 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 performance. If the evaluation shows that performance will not be affected, then no post maintenance testing is required. A partial stroke test will be performed if practicable.
To test check valves to the full open position, the maximum requiled accident condition flow must be measured th ough the valve. In certain cases, this flow cannot be practically established or verified.
According to Generic Letter 89-04, disassembly and inspection of the check valves on a sampling basis is an acceptable alternative testing method.
As described in Generic Letter 89-04, the sample disassembly and inspection program involves grouping similar valves and testing one valve in each group during each refueling outage. The sampling technique 7_,
requires that each valve in the group be the same I e design (manufacturer, size, model number, and materials I
I
(_-) 4-3 N1PVI2R8 Revision 8 August 17, 1998
of construction) and have the same service conditions including valve orientation. The group size cannot
, exceed'four valves.
Additionally, at each 'isassembly d it must be verified that the disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound. Also, to verify the full stroke capability of the valve, the disk should be manually exercised.
A different valve of each group is required to be disassembled, inspected, and manually full stroked exercised'at each successive refueling outage, until the entire group has been tested. If the disassembled valve is not capable of being full stroked exercised or there is binding or failure of valve internals, the remaining valves in that~ group must be disassembled, inspected, and manually full stroked exercised during the same outage.
- 4.3 PROGRAM ADMINISTRATION
! The Engineering staff at North Anna is responsible I for the administration of the Valve Inservice
! Testing Program. The Operations staff-is l
responsible for' performing the periodic tests as required by this program. The Valve Inservice
! Testing Program is implemented by Station Periodic
_ Test Procedures.
4.4 VALVE INSERVICE TEST TABLE The Valve Inservice Test Tables are the essence of the Valve Program to meet OM Part 10 requirements. The tables reflect the positions taken in support of the relief requests. . To aid the reader in the interpretation of the tables, brief explanations of the table headings and abbreviations are provided.
For non-Code valves, a request for relief is not necessary when provisions of the Code cannot be met.
Section 4.8 contains a discussion of the testing requirements for non-Code valves and descriptions of alternative testing in cases where the provisions of the Code cannot be met.
- 1) Valve Number - Each valve in the plant has a unique
" mark" number which identifies the system to which
/ the equipment belongs and type of equipment.
4-4 N1PVI2R8- Revision 8 August 17, 1998
r .-
. f3 (s,/ 2) Drawing and Sheet Number, Coordinate - The specific coordf. nates of each valve are supplied to facilitate location of the valves on the flow diagrams provided.
- 3) Valve Type - A brief description of the actuator and valve type.
The following abbreviations are used to describe actuator types. Valves may be actuated in more than one way.
MO - Motor Operated AO - Pneumatic (Air Operated)
MAN - Manually Operated SO - Electronic solenoid Operated Valves
- 4) Size - Nominal pipe diameter to which valve connects is given in inches.
- 5) Code Class - ASME Code Class of each valve as per 10 CFR 50.55a and Regulatory Guide 1.26.
(-] NOTE: NC is for non-Code valves. These valves are
\s ,/ important to safety but are not in systems or l
portions of systems that are classified ASME Class 1, 2 or 3.
l l 6) Category - Categories are defined by OM Part 10, j
! Section 1.4. Each valve has specific testing )
l requirements which are determined by the category J l to which it belongs. Valves marked with an "E" are l l passive valves.
l
- 7) Isolation Valve Type - Valves that are assigned a maximum leakage. The following abbreviations are used to describe the main isolation valve types:
l CIV - Containment Isolation Valve subject to Appendix J, Option B leakage testing as described in Technical Specification Section 4.6.1.2.
PIV - Pressure Isolation Valve which protects low pressure safety related piping from RCS pressure.
Technical Specification Section 3.1.C specifies the pressure isolation valves that are tested in accordance with this program.
/~'T 4-5 N1PVI2R8 Revision 8 August 17, 1998
b
\ C&P - Valves that serve both CIV and PIV functions
- 8) Test Required - Testing requirements identified for the valves are identified here.
ST - Stroke times shall be measured per OM Part 10, Paragraph 4.2.1.4 or as modified by a specific relief request.
EV - Exercise valve for operability at least once .
every 3 months per OM Part 10, Paragraph 4.2.1.4 or I as modified by a specific cold shutdown or reactor refueling justification which is allowed by OM Part 10, Section 4.2.1.2.
LT - Leak test shall be performed per OM Part 10, Section 4.2.2 or as modified by specific relief request.
CV - Check valves shall be exercised at least once every 3 months per OM Part 10, Paragraph 4.3.2.1 or as modified by a specific cold shutdown or reactor refueling justification which is allowed by OM Part
("'}
(_s 10, Section 4.2.2.2.
VP - Valve position indication shall be verified l per OM Part 10, Paragraph 4.1 or as modified by a l specific relief request. l SP - Set points of safety and relief valves shall )
be tested per OM Part 1, 1987 Edition or as l modified by a specific relief request. In the case of power actuated relief valves, testing consists of determining the operability of the pressure sensing and valve actuation equipment per the requirements of OM Part 1, Section 7.3.1.2.
FS - Valves with fail-safe actuators shall be ;
tested by observing the operation of the valves upon loss of the actuator power at least once every 3 months per OM Part 10, Paragraph 4.2.1.6 or as modified by a specific cold shutdown or reactor refueling justification which is allowed by OM Part 10, Section 4.2.1.2.
- 9) Test Position - The following abbreviations are
(~'s used to describe normal valve positions to which 4-6 N1PVI2R8 Revision 8 August 17, 1998
1
(~~'} the valves are tested (including the valve" safety
'N s position):
0 - Open C - Closed OC - Open and Closed PO - Partially Open PS - Partially Stroked
- 10) Test Frequency - The following abbreviations are used to describe the test frequency:
03 - Nominally every three months 18 - Nominally every 18 months 24 - Every 24 months 60 - Every 60 months 120 - Every 120 months CS - Every cold shutdown but not more often then every three months
,O (m) RR - Every reactor refueling outage l OPB - Per the test frequency determined by the Appendix J, Option B program for leak testing containment isolation valves
- 11) Relief Request Reference
- 12) Cold Shutdown Justification Reference
- 13) Reactor Refueling Justification Reference
- 14) Non-Code Alternative Test Reference
- 15) Function - A brief description of the function of the valve.
1"h b) 4-7 -
N1PVI2R8 Revision 8 August 17, 1998
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VIRGINIA POWER COMPANY PAGE: 1 0F 82 NORTH ANNA UNIT 1 REVIsl0N: 8 I
( SECONO INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV- RRV VCN-1 BD.TV.100A 11715 CBM 098A 2 0F 5 C5 A0 GLOBE 3.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 i VP OC 24 "A" STEAM GENERATOR BLO@0WN, OUTSIDE CON-TAINMENT ISOLATION VALVE 1 BO-TV-1008 11715 CBM-093A 2 0F 5 C6 A0 GLOBE 3.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VF OC 24 "A" $ TEAM GENERATOR BLOW OWN, INSIDE CON-TAINMENT ISOLATION VALVE 1 BD-TV 100C 11715 CBM 098A 3 0F 5 C5 A0 GLOBE 3.000 2 A CIV EV C 03 j FS C 03 LT C OPB {
"B" STEAM GENERATOR BLO W OWW, OUTSIDE CON-TAINNENT ISOLATION VALVE
,<-~sg ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
6 i 1 BD TV.1000 11715 CBM-D98A 3 0F 5 C6 A0 GLOBE 3.000 2 A CIV EV C 03
(/ FS C 03 LT C DPB ST C 03 VP DC 24 "B" STEAM GENERATOR BLOWDOWW, INSIDE CON-TAINMENT ISOLATION VALVE l 1 BO TV 100E 11715 CBM 09BA 4 0F 5 C5 A0 GLOBE 3.000 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 VP DC 24 "C" STEAM GENERATOR BLOWDOWN, OUTSIDE CON-TAINMENT ISOLATION VALVE 1 BD.TV-100F 11715 CBM-09&A 4 0F 5 C6 A0 GLOBE 3.000 2 A CIV EV C 03 FS C 03 LT C DPS ST C 03 l VP OC 24 i
{
"C" STEAM GENERATOR BLOWOOWW, INSIDE CON- ;
TAINMENT ISOLAfl0N VALVE
'(\
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VIRGINIA POWER COMPANY PAGE: 2 0F 82 NORTH ANNA UNIT 1 REVISION: 8
[ \ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
( ,) INSERVICE TESTING PROGRAM VALVE TABLE WC
!$0 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST EEQ JUST JUST TEST NUMBER NUMBER WUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRED V-CSV RRV VCN-1 CC-024 11715-CDM 079A 1 0F 3 C5 CHECK VALVE 18.000 3 C CV C 03 0 03 "A" COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 1 CC 047 11715 CDM 079A 1 0F 3 B5 CHECK VALVE 18.J00 3 C CV C 03 0 03 "B" COMPONENT COOLING PUMP DISCHARGE CHECr VALVE 1 CC 064 11715 CDM 0798 2 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C RR 1 LT C OPB CC SUPPLY TO "A" RC PUNP LO, STATOR SHROUD & ;
THERN BARRIER CDOLERS, IN CONT ISOL CHECK VLV l 1-CC 111 11715 CBM 0798 2 0F 5 C7 CHECK VALVE 3.000 3 C CV C RR 20 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 RR 1 LT C OPG
(%
N
/
CC SUPPLY TO "B" RC PUMP LO, STATOR SHROUD &
THERM BARRIER Co0LERS, IN CONT ISOL CHECK VLV 1-CC 146 11715-CBM 0798 3 or 5 C7 CHECK VALVE 3.000 3 C CV C RR 20 1 CC SUPPLY TO "B" RC PUMP THERMAL BARRIER COOLER CHECK VALVE 1 CC 154 11715 CBM-0798 4 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C RR 1 LT C OPS CC SUPPLY TO "C" RC PUMP LO, STATOR SHROUD &
THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV 1 CC-181 11715 CBM 079s 4 0F 5 C7 CHECK VALVE 3.000 3 C CV C RR 20 CC SUPPLY 70 "C" RC PUMP THERMAL SARRIER COOLER CHF.CK VALVE i
1 CC 193 11715-CBM-079B 1 CF 5 F7 CHECK VALVE 15.000 2 AC CIV CV C RR 22 l 0 RR 22 i PO 03 LT C DPB CC SUPPLY TO "A" RWP MEAT EXCHANGER 1 CC 198 11715 CBM 079s 1 0F 5 F7 CHECK VALVE 18.000 2 AC CIV CV C RR 22 0 RR 22 PO 03 l LT C OPB l
l CC SUPPLY TO "B" RNR HEAT EXCHANGER I
\g w
s- -
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i VIRGINIA POWER COMPANY PAGE: 3 0F 82 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 v INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER C004 TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV RRV- VCN-1 CC 546 11715 COM 079D 4 0F 5 E8 CHECK VALVE 6.000 2 AC CIV CV C RR 18 LT C OPB CC SUPPLY TO "A" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION CHECK VALVE 1 CC 559 11715 cam 0790 4 0F 5 D8 CHECK VALVE 6.000 2 AC CIV CV C RR 18 LT C DPS l
CC SUPPLY TO "O" RECIRC AIR COOLING COILS, QUTSIDE CONTAINMENT ISOLATION CHECK VALVE 1 CC-572 11715 CBM-0790 4 0F 5 C8 CHECK VALVE 6.000 2 AC Civ CV C RR 18 LT C OPB CC SUPPLY TO "C" RECIRC AIR COOLING C0!LS, OUTSIDE CONTAINMENT ISOLATION CHECK VALVE J
1-CC MOV.100A 11715-CeM-0796 1 0F 5 A3 MO BFLY 18.000 3 B EV 0 03 ST 0 03 VP OC 24 COMPONENT COOLING WATER RETURN THROTTLING VALVE FROM A RHR HEAT EXCHANGER 1-CC MOV-100s 11715 Cam 0798 1 0F 5 B3 MO BFLY 18.000 3 B EV O 03 ST C 03
' VP OC 24 COMPONENT COOLING WATER RETURN THROTTLING VALVE FROM B RHR HEAT EXCHANGER 1 CC-RV 104A 11715 CBM 0790 4 0F 5 E5 RELIEF VALVE .750 NC C SP O 120 CONTAINMENT PENETRATION 11 RELIEF VALVE -
CC SUPPLY TO RECIRC AIR COOLERS 1-CC RV 1048 11715-cam-079D 4 0F 5 D5 RELIEF VALVE .750 NC C SP O 120 CONTAINMENT PENETRATION 10 PELIEF VALVE -
CC SUPPLY TO RECIRC Allt COOLER 1 CC RV-104C 11715-CBM-0790 4 0F 5 C5 RELIEF VALVE .750 WC C SP O 120 CONTAIMMENT PENETRATION 9 RELIEF VALVE -
CC SUPPLY TO RECIRC AIR COOLER 1 CC RV 124A 11715 CBM-0798 2 0F 5 F6 RELIEF VALVE 3.000 3 C SP 0 120 COMPONENT COOLING WATER TO REACTOR SHROUD HEAT EXCHANGER RELIEF VALVE 1 CC-RV 124B 11715 CBM-0798 3 0F 5 F6 RELIEF VALVE 3.000 3 C SP O 120
..................e..........................
i COMPONENT COOLING WATER TO REACTOR SHROUD l
HEAT EXCMANGER RELi[F VALVE 1-CC RV 124C 11715 CBM-079B 4 0F 5 F6 RELIEF VALVE 3.000 3 C $P 0 120 N
N l
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VIRGINIA POWER COMPANT PAGE: 4 0F B2 gi NORTH ANNA UNIT 1 REVIS10W: 8
/ \
\
v) SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DATE: D8/17/98 NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER WUMBER Coot TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV* RRV VCN-COMPONENT COOLING WATER TO REACTOR SHROUD MEAT EXCHANGER RELIEF VALVE 1 CC RV 125A 11715-CBM 0790 2 0F 5 C6 RELIEF VALVE .750 3 C SP O 120 .
CC SUPPLY TO "A" RC PUMP THERMAL BARRIER
)
RELIEF VALVE 1 CC-RV 1258 11715-CBM-0796 3 0F 5 C6 RELIEF VALVE .750 3 C SP O 120 t
CC SUPPLY TO "B" RC PUMP THERMAL BARRIER i RELIEF VALVE
'1 CC RV 125C 11715 CBM 0798 4 0F 5 C6 RELIEF VALVE .750 3 C SP O 120 CC SUPPLY TO "C" RC PUMP THERMAL BARRIER RELIEF VALVE l i
1 l
1-CC RV 126 11715 CBM 079s 5 0F 5 C6 RELIEF VALVE 1.000 3 C SP 0 120 EXCESS LETDOWN HEAT EXCHANGER COMPONENT COOLING WATER PENETRATION 1 RELIEF VALVE 1-CC-RV 12BA 11715-CbM-0798 1 0F 5 E3 RELIEF VALVE .750 3 C SP O 120
\
"A" RNR HEAT EXCHANGER COMPONENT COOLING l RELIEF VALVE j
l 1 CC RV 1288 11715 CBM 0798 1 0F 5 D3 RELIEF VALVE .750 3 C SP O 120 l
"B" RHR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 1 CC RV-131A 11715 CBM 0798 5 0F 5 C4 RELIEF VALVE .750 3 C SP 0 120 i RHR PUMP SEAL COOLER RELIEF VALVE 1 CC RV 131B 11715 CBM 0798 5 0F 5 C4 RELIEF VALVE .750 3 C SP O 120 RHR PUMP SEAL COOLER RELIEF VALVE 1 CC TV 100A 11715 CBN 0790 4 0F 5 E4 A0 BFLT 6.000 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 VP DC 24 CC RETURN FROM "A" RECIRC AIR COOLING ColLS, OUTSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... .... ... .... ..~. .... .... ... .... .... ....
1 CC TV-1008 11715-CBM 079D 4 0F 5 D4 A0 BF!Y 6.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24
\
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s
l l VIRGINIA POWER COMPANY PAGE: 5 0F 82
- ~'\ NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 k~ INSERVICE TESTING PROGRAM - VALVE TABLE l
1 NC ISO REL C5 RR ALT l VALVE DRAWING SMEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $!ZE CLAS CAT TYPE TYPE POS FREQ V-CSV RRV VCN-CC RETURN FROM "B" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT !$0LAll0N VALVE 1 CC TV 100C 11715 CBM 0790 4 of 5 C4 A0 SFLY 6.000 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 VP OC 24 CC RETURN FROM "C" RECIRC AIR COOLING ColLS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CC TV 101A 11715 CBM 0799 10F 5 D7 A0 GLOBE 4.000 2 A CIV EV C CS 1 FS C CS 1 LT C OPB ST C CS 1 VP OC 26 CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIERS, QUTSIDE CONTAINMENT ISOLATION VALVE 1 CC-TV 1015 11715 CbM 0795 1 0F 5 D6 A0 GLOBE 4.000 2 A CIV EV C CS 1 FS C CS 1 LT C DPB
\s CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIERS, ItstIDE CONTAINMENT ISOLAfl0N VALVE 1 CC TV-102A 11715-CBM-0795 4 0F 5 A5 A0 BFLY 8.000 2 A Civ EV C CS 1 FS C CS 1 LT C OPB ST C CS 1 VP OC 24 i
............................................. I CC RETURN FROM "C" RC PUMP LO, STATOR & SMROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CC TV-102B 11715 CBM-0798 4 0F 5 A3 A0 BFLY 8.000 2 A CIV EV- C CS 1 FS C CS 1 LT C OPB ST C CS 1 VP OC 24 CC RETURN FROM "C" RC PUMP LO, STATOR & SHROUD COOLERS, INSIDE CONTAlWMENT ISOLATION VALVE 1 CC TV 102C 11715-CBM 0798 3 0F 5 A5 A0 SFLY 8,000 2 A CIV EV C CS 1 FS C CS 1 LT C OPB ST C CS 1 VP OC 24 CC RETURN FROM "B" RC PUMP LO, STATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1 CC-TV-102D 11715 CBM-0795 3 0F 5 A3 A0 BFLY 8.000 2 A CIV EV C CS 1 s FS C CS 1
) LT C OPB J
1
)
i VIRGINIA POWER COMPANY PAGE: 6 0F 82 NORTH ANNA TWIT 1 - REVISION: 8
[ SECOND INSERVICE TESTING INTERVAL
(, INSERVICE TESTING PROGRAM VALVE TABLE DATE: D8/17/96 l
1 i
NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST l NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-
...... .r..... ...... .... ..... ..... .... ... .... .... .... .... ... .... .... ....
1 CC-TV 102D 11715-CBM 079B 3 0F 5 A3 A0 SFLY 8.000 2 A CIV ST C CS 1 VP OC 24 CC RETURN FROM "B" RC PUMP Lo, STATOR & SHROUD COOLERS, INSIDE CONTAINMENT ISO,LATION VALVE j 1-CC TV 102E 11715 C9M-079B 2 0F 5 A5 A0 BFLY 8.000 2 A CIV EV C CS 1 FS C CS 1 LT C OPS ST C CS 1 VP OC 24 CC RETURN FROM "A" RC PUMP LO,$TATOR & 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 CS 1 FS C CS 1 LT C OPB ST C CS 1 VP OC 24 CC RETURN FROM "A" RC PUMP Lo, STATOR & SHROUD COOLERS, INSIDE CONTAINMENT ISOLAfl0N VALVE 1-CC-TV 103A 11715 CBM 079B 10F 5 A7 A0 SFLY 18.000 2 A CIV EV C 03
.f. g 0 03 ;
i
" FS C 23 l
%. LT C OPB ST C 03 0 03 VP OC 24 CC RETURN FROM "A" RHR HEAT EXCHANGER, DUT-
$1DE CONTAINMENT ISOLATION VALVE 1 CC TV-1038 11715 CBM 0798 1 0F 5 B7 A0 BFLY 18.000 2 A CIV EV C 03 0 03 FS C 03 LT C DPS ST C 03 0 03 VP OC 24 CC RETURN FROM "B" RHR HEAT EXCHANGER, DUT.
SIDE CONTAINMENT ISOLATION VALVE 1 CC TV 104A 11715 CBM 0798 2 0F 5 E8 A0 BFLY 8.000 2 A CIV EV C CS 1 FS C CS 1 LT C OPB ST C CS 1 VP OC 24 CC SUPPLY TO "A" RC PUMP LO, STATOR, SHROUD &
THERM BARRIER COOLERS, OUTSIDE CONT ISOL VLV 1-CC TV-104B 11715 CBM 079B 3 0F 5 E8 A0 BFLY 8.000 2 A CIV EV C CS 1 FS C CS 1 LT C DPB ST C CS 1 VP OC 24
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VIRGINIA POWER COMPANY PAGE: 7 0F B2
.s NORTH ANNA UNIT 1 REVISION: 8
[' SEDOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DATE: D8/17/98 WC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-CC SUPPLY TO "B" RC PUMP LO, STATOR, $NROUD &
THERM BARRIER COOLERS, OUTSIDE CONT ISOL VLV 1-CC TV 104C 11715-CBM-0798 4 0F 5 E8 A0 SFLY 8.000 2 A Civ EV C CS 1 FS C CS 1 LT C OPB ST C CS 1 VP DC 24 CC SUPPLY TD "C" RC PUMP LO, STATOR, SHROLD &
THERM BARRIER COOLERS, OUTSIDE CONT ISOL VLV 1-CC TV 105A 11715 CBM-0790 4 DF 5 E4 A0 BFLY 6.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 CC RETURN FROM "A" RECIRC AIR COOLING 00!LS, INSIDE CONTAINMENT ISOLATION VALVE 1 CC-TV 1058 11715-CBM-0790 4 0F 5 D4 A0 BFLY 6.000 2 A CIV EV C 03 FS C 03 LT C OPB
$7 C 03 VP OC 24 g, .............................................
CC RETURN FROM "B" RECIRC AIR COOLING C0!LS, INSIDE CONTAINMENT ISOLATION VALVE 1-CC TV 105C 11T15-CEM-0790 4 0F 5 C4 A0 BFLY 6.000 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 VP OC 24 CC RETURN FROM "C" RECIRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATIDN VALVE I
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l VjkGINIA POWER COMPANY PAGE: 8 0F 82 l 100RTH ANNA UNIT 1 REVISION: 8 t l SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
' kj INSERVICE TESTING PROGRAM - VALVE TABLE NC l l 150 REL CS RR ALT f VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST {
NLMBER NUMBER NUMBER COOR TYPE $1ZE CLAS CAT TYPE TYPE POS FRED V- CSV RRV VCN-l ...... ....... ...... .... ..... ..... .... ... .... .... .... .... ... .... .... ....
! 1 CD 161 11715 Cas 040C 1 0F 3 E6 CHECK VALVE 3.000 3 C CV 0 03 l .............................................
CONTROL ROOM CHILLED WATER SYSTEM FUMP DISCNARGE CHECK VALVE ,
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j 1-CD ' .82 11715-Cas-040C 1 0F 3 D6 CHECK VALVE 3.000 3 C CV 0 03 1
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CONTROL ROOM CHILLED WATER SYSTEM PUMP DISCHARGE CHECK VALVE 1-CD 209 11715 Cas-040C 1 0F 3 C6 CHECK VALVE 3.000 3 C CV 0 03
............................................. 1 CONTROL ROOM CHILLED WATER SYSTEM PUMP DISCHARGE CHECK VALVE I
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i VIRGIN!A POWER COMPANY PAGE: 9 of 82
..s, WORTH ANNA UNIT 1 REVISION: 8 SEDONO INSERVICE TESTING INTERVAL DATE: 08/17/96 s INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ABME DM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER C00R TTPE SIZE CLAS CAT TYPE TYPE PDS FRE0 V*
CSV- RRV VCN-1 CN 004 11715 CBM 095A 1 0F 4 C4 CHECK '/ALVE 2.000 3 C CV 0 CS 3 i P0 03 "A" BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE 1 CH 102 11715-CBM-D95A 1 of 4 c5 CHECK VALVE 2.000 3 C cv 0 CS 3 P0 03 "B" BORIC ACID TRANSFER PUMP D!$ CHARGE CHECK VALVE 1 CH-215 11715-CBM-0955 1 0F 2 B6 CHECK VALVE 4.000 2 AC CV C RR 23 0 03 LT C 24 CHARGING PUMP SUPPLY FROM VOLUME CONTROL TANK ISOLATION VALVE 1 CH 238 11715-CBM-0955 1 0F 2 B5 CHECK VALVE 2.000 2 C CV 0 CS 4 MAIN EMERGENCY BORATION LINE TO CHARGlWG PUMP SUCTION CHECK VALVE
.......................................................~..... ..... .... ... .... .... .... .... ... .... .... ....
1 CH-240 11715 CBM-0958 1 0F 2 C3 CHECK VALVE 1.000 3 C CV 0 CS 4
[( ALTERNATE EMERGENCY BORATION LINE CHECK VALVE I
1-CH-241 11715-CBM D955 1 0F 2 B4 MANUAL GATE 1.000 3 B EV 0 CS 4 ALTERNATE EMERGENCY BORATION LINE MANUAL VALVE I 1 CH-242 11715 CBM-095B 1 0F 2 05 CHECK VALVE 1.000 2 C CV 0 CS 4 ALTERNATE EMERGENCY BORATION LINE TO CHARGING PUMP SUCTION CHECK VALVE 1 CH 252 11715 CBM D955 2 0F 2 D7 CHECK VALVE 3.000 2 C CV 0 CS 38 "A" CHARGlWG PUMP DISCHARGE RECIRC LINE CHECK VALVE 1 CH 254 11715 CBM 0955 2 0F 2 D7 CHECK VALVE 3.000 2 C CV C 03 0 RR 16 "A" CHARGING PUMP DISCHARGE CHECK VALVE 1 CH 264 11715-CBM-0955 2 0F 2 D6 CHECK VALVE 3.000 2 C CV O CS 38 "B" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 1-CH-267 11715 CBM-0958 2 OF 2 D6 CHECK VALVE 3.000 C CV C 03 0 RR 16 "B" CHARGING PUMP DISCHARGE CHECK VALVE l
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h VIRGINIA POWER COMPANY PAGE: 10 0F 82 NORTH ANNA UNIT 1 REVISION: 8
[\ '\f SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
%./ INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER WUMBER NUMBER COOR TYPE $12E CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV- VCN-1 CH-277 11715 CBM 0958 2 0F 2 04 CHECK VALVE 3.000 2 C CV o CS 38 "C" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 1 CH 279 11715-CBM D95B 2 0F 2 06 CHECK VALVE 3.000 2 C CV C 03 0 RR 16 "C" CHARGING PUMP DISCHARGE CHECK VALVE 1 CH 322 11715 CDM 09SC 1 0F 2 D4 CHECK VALVE 3.000 2 AC CIV CV C RR 2 LT C DPB 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 RR 2 LT C DPB -
............................................. l CHARGING SUPPLY TO LOOP FILL HEADER, INSIDE -
CONTAINMENT ISOLATION CHECK VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 1 CH-336 11715-CBM 095C 2 0F 2 E8 CHECK VALVE 2.000 1 C CV C RR 2 !
l "A" RC PUMP SEAL WATER SUPPLY, INSIDE
!-s CONTAINMENT ISOLAfl0N CHECK VALVE
\ ,,)\ ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1 CH-358 11715 CBM-095C 2 0F 2 BT CHECK VALVE 2.000 1 C CV C RR 2 "B" RC PUMP SEAL WATER SUPPLT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CH-380 11715-CBM D95C 2 0F 2 B5 CHECK VALVE 2.000 1 C CV C RR 2 "C" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1 CH 402 11715 CBM 095C 2 0F 2 F4 CHECK VALVE .750 2 AC Civ CV C RR 2 LT C OPB RC PUMP SEAL WATER RETURN, INSIDE CONTAIMMENT ISOLATION CHECK VALVE 1 CH 649 11715 CBM 095B 1 0F 2 B6 CHECK VALVE 2.000 2 AC CV C RR 23 0 CS 38 LT C 24 j CHARGlWG PUMP RECIRC AND RCP SEAL WATER '
RETURN LINE ISOLATION CHECK VALVE 1 CH FCV 1113A 11715-CBM-0958 1 0F 2 C3 A0 GATE 1.000 3 B EV 0 03 FS 0 03 ST C 03 VP OC 24 ALTERNATE EMERGENCY BORAfl0N LINE FLOW CONTROL VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 1
, ~~s 1-CH FCV-1114A 11715-CBM-095B 1 of 2 04 A0 GLOBE 1.000 3 8 EV C 03
( FS C 03
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VIRGINIA POWER COMPANT PAGE: 11 0F 82 WORTH ANNA UNIT 1 REVISION: 8
/,,,% SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 f f V INSERVICE TESTING PROGRAM VALVE TABLE NC
, ISO REL CS RR ALT l VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV VCN-l 1-CH FCV 1114A 11715 CBN-0955 1 0F 2 D4 A0 GLOBE 1.000 3 B ST C 03 VP OC 24 PRIMARY GRADE WATER FLOW CONTROL VALVE l
1 CH-FCV 1160 11715-CBM-095C 1 0F 2 A4 A0 GLOBE 2.000 2 AE CIV LT C OPB VP OC 24 CHARGING FLOW CONTROL TO LOOP FILL HEADER, OUTSIDE CONTAINMENT !$0LATION VALVE 1 CH LCV.1460A 11715-CBM 095C 1 or 2 F7 A0 GLOBE 2.000 1 B EV C Cs 5 FS C CS 5 ST C CS 5 VP OC 24 LETDOWN ISOLATION VALVE
\ ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1 CH LCV 14608 11715-CBM 095C 1 0F 2 F7 A0 GLOBE 2.000 1 B EV C CS 5 FS C CS 5 ST C CS 5 VP OC 24 l
LLTDOWN ISOLATION VALVE
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, 1 CH-MOV-1115B 11715-CBM-095B 2 0F 2 B8 M0 GATE 8.000 2 A EV C CS 6 O CS 6 LT C 24 75 ST C CS 6 0 CS 6 VP OC 24 CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 1 CH-MOV 1115C 11715-CBM 095B 1 0F 2 C6 MO GATE 4.000 2 8 EV C CS 6 ST C CS 6 VP- DC 24 CHARGING PUMP SUPPLY ISOLAT10N FROM VOLUME CONTROL TANK 1 CH-MOV 1115D 11715-CBM 0958 2 0F 2 B8 M0 GATE 8.000 2 A EV C CS 6 0 CS 6 LT C 24 75 ST C CS 6 0 CS 6 VP OC 24 CHARGING PUMP SUPPLY ISOLATION VALVE FROM I REFUELING WATER STORAGE TANK l 1 CH-MOV 1115E 11715-CBM-095B 1 or 2 C6 MO GATE 4.000 2 B EV C CS 6 ST C CS 6 VP OC 24
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r-I VIRGINIA POWER COMPANT PAGE: 12 0F 82 f
es MORTH ANNA
- UNIT 1 .
REVISION: 8 SECONO INSERVICE TESTING INTERVAL DATE: 08/17/98 kg INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEsf TEST REO JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-i CHARGING PUMP SUPPLY ISOLATION VALVE FROM
! VOLUE CONTROL TANK 1
1 CH-MOV 1267A 11715 CDM 0958 2 Of 2 C7 No GATE 6.000 2 E VP OC 24 "A" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 1 CH MOV 12678 11715 CDM 0958 2 0F 2 C7 MO GATE 6.0D0 2 E VP OC 24 l
l "A" CHARGING PUMP SUCTION ISOLATION FROM LMSI l
1 CH-MOV 1269A 11715 CBM-0958 2 0F 2 C5 M0 GATE 6.000 2 E VP DC 24 1
"B" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1*CH-MOV 1269s 11715-CBM-0958 2 0F 2 C5 M0 CATE 6.000 2 E VP OC 24 "B" CHARGING PUMP SUCTION ISOLATION FROM LHSI 1 CH-MOV-1270A 11715 CBM-0958 2 0F 2 C3 M0 GATE 6.000 2 E VP OC 24
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4 "C" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 1 CH-MOV 127De 11715 CBM-D95B 2 0F 2 C3 Mc GATE 6.000 2 E VP OC 24 "C" CHARGING PUMP SUCTION ISOLATION FROM LHSI 1 CH-MOV-1275A 11715 CBM-0958 2 0F 2 D7 MO GATE 2.000 2 8 EV C 03 0 03 ST C 03 0 03 VP OC 24 z
"A" CKARGING PUNP MINIMUM RECIRCULATION !$0- -
LATION VALVE 1 CH MOV 1275B 11715-CBM 0958 2 0F 2 05 MO GATE 2.000 2 B EV C 03 I O 03 ST C 03 0 03 VP OC 24 "B" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE 1-CH MOV 1275C 11715 CBM-095B 2 0F 2 D4 MO GATE 2.000 2 B EV C 03 0 03 ST C 03 0 03 VP OC 24 "C" CHARGING PUMP MINIMUM RECIRCULAfl0N 150-('s LATION VALVE f ............................................................. ..... .... ... .... ....
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VIRGINIA POWER COMPANY PAGE: 13 0F 82 NORTH ANNA UNIT 1
[\
SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE REVISION: 8 DATE: 08/17/98 NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER MUMBER MUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE PDS FREQ V- CSV RRV VCN-1 CH MOV-1266A 11715 CBM-0958 2 0F 2 E7 M0 GATE 3.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 "A" CHARGING PUMP MAIN DISCHARGE. ISOLA?!ON VALVE 1 CH-MOV 12668 11715 CBM-0958 2 0F 2 E6 M0 GATE 3.000 2 B EV C 03 0 03 ST C 03 0 03 VP OC 24 )
"S" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV 1286C 11715-CBM 0958 2 0F 2 E4 M0 GATE 3.000 2 B EV C 03 8 0 03 ST C 03 0 03 VP OC 24 "C" CHARGING PUMP MAIN DISCHARGE ISOLAfl0N VALVE A ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
(' 1 CH MOV 1287A 11715 CBM-095B 2 0F 2 D7 MO GATE 3.000 2 B EV C 03 O 03 ST C 03 0 03 VP DC 24 "A" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 1 CH-MOV 12875 11715-CBM-095B 2 0F 2 D6 M0 GATE 3.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 ,
............................................. l "B" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 1-CH-MOV 1287C 11715 CBM-095B 2 0F 2 D4 No GATE 3.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 "C" CHARGlWG PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 1-CH MOV 1289A 11715-CBM 095C 1 0F 2 D4 M0 GATE 3.000 2 A CIV EV C CS 7 LT C OPB ST C CS T VP DC 24 fn f \
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VIRGIN!A POWER COMPANY PAGE: 14 0F 82 I
NORTH ANNA WNIT 1 REVI5!DNi 8
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BECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 s INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 CH MOV-12898 11715-CBM 095C 10F 2 83 M0 GATE 3.000 2 8 EV C CS 7 ST C CS 7 VP OC 24 MAIN CHARGING HEADER 160LATION VALVE, OUTSIDE CONTAINMENT 1-CH MOV 1350 11715 CBM-D958 1 0F 2 B5 M0 GATE 2.000 2 B EV 0 CS 4 ST 0 CS 4 i VP OC 24 i EMERGENCY BORATION TO CHARGING PUMP SUCTION 1 CH-Mov-1373 11715 CBM 0955 1 0F 2 A8 MO GATE 3.000 2 E VP OC 24 CHARGING PUMP RECIRCULATION HEADER ISOLATION VALVE 1-CH-MOV 1380 11715 CBM 095C 2 0F 2 F4 NO GATE 3.000 2 A CIV EV C CS 48 LT C DPB p ST C CS 48
( VP OC 24
(~~ .............................................
REACTOR COOLANT PUMP SEAL WATER RETURN, INSIDE CONTAINMENT ISOLATION VALVE 1-CH-MOV-1381 11715-CBM 0958 1 0F 2 C8 MO GATE 3.000 2 A CIV EV C CS 48 LT C OPB ST C CS 48 VP OC 24 REACTOR COOLANT PUMP SEAL WATER RETURN, OUT*
SIDE CONTAINMENT ISOLATION VALVE i CH-RV-1203 11715 CBM-095C 1 0F 2 F4 RELIEF VALVE 2.000 2 C SP 0 120 LETDOWN RELIEF VLV DOWNSTREAM OF REGEN HX, RV DISCHARGE TO PRESSURIZER RELIEF TANK 1 CH RV 1382A 11715 CBM-095C 2 0F 2 F5 RELIEF VALVE 2.000 2 C SP 0 120 CONTAINMENT PENETRATION 19 RELIEF VALVE -
RCP SEAL WATER RETURN PIPING 1 CH-RV-1382B 11715 CBM-095B 10F 2 C7 RELIEF VALVE 2.000 2 C SP O 120 SEAL WATER HEAT EXCHANGER RELIEF VALVE, RV DISCHARGE TO VOLUME CONTROL TANK 1-CH-TV-1204A 11715 CBM-095C 1 0F 2 E3 A0 GLOBE 2.000 2 A CIV EV C CS 5 FS C CS 5 LT C OPB ST C CS 5 l VP OC 24
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VIRGINIA POWER COMPANY PAGE: 15 0F 82 NORTH AWMA UNIT 1 REVisl0N: 8 l SECOND INSERVICE TESTING INTERVAL DATE: 08/1T/98
( INSERVICE TESTING PROGRAM VALVE TABLE WC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST l.
t NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV- VCN-LETDOWN CONTROL FRON REGEN HM, INSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j l 1 CH TV 12048 11715-CBM 095A 4 0F 4 C3 A0 GLOBE 3.000 2 A CIV EV C CS 5 l
! FS C CS 5 j
( LT C OPB i ST C CS 5 VP OC 24 LETDOWN CONTROL FROM REGEN HM, OUTSIDE l CONTAINMENT ISOLATION VALVE i
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VIRGINIA POWER COMPANY PAGE: 16 0F 82
/m NORTH ANNA UNIT 1 REVISION: 8 i I SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
(/ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $12E CLAS CAT TYPE TYPE POS FREQ V- CSV RRV* VCN-1-CV-004 11715-CBM-092A 2 of 2 AS MANUAL CATE 8.000 2 AE CIV LT C OPB CONTAINMENT VACUUM EJECTOR SUPPLY, OUTS!DE CONTAINMENT ISOLATION VALVE 1 CV 08 11715 CBM-092A 2 Ef 2 B3 CHECK VALVE 2.000 2 C CV 0 18 4 PO 03 CONTAINMENT VACUUM SYSTEM ISOLATION CHECK VALVE 1 CV-14 ti/15-CBM-092A 2 0F 2 C3 CHECK VALVE 2.000 2 C CV 0 18 4 PO 03 CONTAINMENT VACUUM SYSTEM ISOLATION CHECK VALVE 1-CV-TV-100 11715-CBM-092A 2 0F 2 A3 A0 BFLY 8.000 2 AE CIV LT C OPB VP OC 24 CONTA!NMENT VACUUM EJECTOR, INSIDE CONTAIN-MENT ISOLATION VALVE 1-CV TV 150A 11715-CBM-092A 2 0F 2 84 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03
/7 LT C OPB I
\ ST C 03
( VP OC 24 "A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CV-TV 1508 11715-CBM-092A 2 0F 2 85 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 2f.
"A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT !$0LATION VALVE 1-CV-TV 150C 11715 CRM 092A 2 0F 2 C4 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 "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 03 FS C 03 LT C OPB ST C 03 VP OC 24 "B" CONTAINMENT VACUUM PUMP SUCTION ISOLAT!DN VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE J
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t VIRGIN!A POWER COMPANY PAGE: 17 0F 82 m '
NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMSER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV- RRV VCN-l 1 DA-039 11715 Cam-090C 3 0F 3 03 MAN DIAPHRAM 2.000 2 AE Civ LT C OPS l VENT LINE FROM PRIMARY VENT POT, INSIDE CONTAINMENT ISOLATION VALVE 1 DA-041 11715-CBM-090C 3 0F 3 E3 MAN DIAPHRAM 2.000 2 AE CIV LT C OPB VENT LINE FROM PRIMARY VENT POT, OUTSIDE CONTAINMENT ISOLATION VALVE 1-DA-TV-100A 11715-CBM-0904 1 0F 2 E7 A0 GLOSE 2.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24 RF. ACTOR CONTAINMENT SUMP PUMPS DISCHARGE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 DA-TV-1000 11715-CBM-090C 3 0F 3 C3 A0 GLOSE 2.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24
,, REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, INSIDE CONTAINMENT ISOLATION VALVE 1-DA-TV 103A 11715 CBM-090C 3 0F 3 B7 A0 GLOSE 2.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAIMMENT !$0LATION VALVE 1-DA-TV.1038 11715-CBM-090C 3 0F 3 B8 A0 GLOBE 2.000 2 A Civ EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDF CONTAINMENT TRIP VALVE C'
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VIRGINIA POWER COMPANY PAGE: 18 0F 82 NORTH ANNA'tm!T 1 -
REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C002 TTPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV* RRV VCN-1.DG-TV 10GA 11715 CBM 090C 1 0F 3 B8 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 LT C DPS ST C 03 VP DC 24 PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, OUTa SIDE CONTAINMENT ISOLATION VALVE 1 DG TV 100s 11715 CeM-090C 1 0F 3 37 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24 PRIMARY DRAIN TRANSFER PUMPS DISCRARGE, INSIDE CONTAlWMENT ISOLATION VALVE
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VIRGIW!A POWER COMPANY PAGE: 19 0F 82
,, WORTH ANNA UNIT 1 REvlsl0N: 8
/\ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\v ) INSERVICE TESTING PROGRAM - VALVE TABLE l NC
!$0 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV- VCN-1-EB-015 11715-FM -107A 1 0F 4 E6 CHECK VALVE 1.500 NC C CV 0 18 4 1H DIESEL "MA" AIR RECEIVER TANK DISCHARGE VALVE 1 EB 034 11715 FM 107A 3 0F 4 E6 CHECK VALVE 1.500 NC C CV 0 18 4 1J DIESEL "JA" AIR RECEIVER TANK DISCHARGE VALVE 1 EB 041 11715-FM 107A 1 0F 4 D6 CHECK VALVE .750 NC AC CV C 03 LT C 24 1H DIESEL "MA" AIR RECEIVER TANK ISOLATION VALVE 1-EB-053 11715 FM -107A 3 0F 4 D6 CHECK VALVE .750 NC AC CV C 03 LT C 24 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 18 4 1H DIESEL "B" AIR RECEIVER TANK DISCHARGE VALVE
/'~ ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
k 1 EB-072 11715 FM -107A 2 0F 4 D6 CHECK VALVE .750 NC AC CV C 03 LT C 24 1H DIESEL "B" AIR RECEIVER TANK ISOLATION VALVE 1-EB 084 11715-FM 107A 4 0F 4 E6 CHECK VALVE 1.500 NC C CV 0 18 4 1J DIESEL "B" AIR RECEIVER TANK DISCHARGE VALVE 1 EB 091 11715-FM 107A 4 0F 4 D6 CHECK VALVE .750 NC AC CV C 03 LT C 24 1J DIESEL "B" AIR RECEIVER TAWK ISOLAfl0N VALVE I
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VIRGIN!A POWER COMPANY PAGE: 20 0F 82 f ~g NORTH ANNA UNIT 1 REVISION: 8 i SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST I WUMBER WUMBER WUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-l 1-EG-254 11715-FB -035A 2 0F 2 B7 CHECK VALVE 1.500 NC C CV o 03 i 1H DIESEL "A" EMERGENCY GENERATOR PUMP l
1 DISCHARGE CHECK VALVE l 1 EG-266 11715 FB -035A 2 0F 2 B6 CHECK VALVE 1.500 NC C CV O 03 1J DIESEL "A" EMERGENCY GENERATOR PUMP DISCHARGE CHECK VALVE I 1 EG 278 11715 FB -035A 2 0F 2 56 CHECK VALVE 1.500 NC C CV O 03 1H DIESEL "B" EMERGENCY GENERATOR PUMP DISCHARGE CHECK VALVE l
1-EG 295 11715 FB -035A 2 0F 2 D6 CHECK VALVE 1.500 NC C CV 0 03 1J DIESEL "B" EMERGENCY GENERATOR PUMP DISCHARGE CHECK VALVE 1 EG-RV 103A 11715 FB -035A 2 0F 2 B7 RELIEF VALVE 1.000 NC C SP O 120 1H DIESEL "A" EMER GENERATOR PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION
/-x 1 EG RV 1038 11715 FB -035A 2 0F 2 B6 RELIEF VALVE 1.000 NC C SP 0 120
( ) .............................................
1H DIESEL "B" EMER GENERATOR PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION 1-EG RV-1054 11715 FB 035A 2 0F 2 E7 RELIEF VALVE 1.000 NC C SP O 120 1J DIESEL "A" EMER GENERATOR PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO PUMP SUCT!0N 1 EG RV 105B 11715-FB -035A 2 OF 2 E6 RELIEF VALVE 1.000 NC C SP o 120 1J DIESEL "B" EMER GENERATOR PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION 1-EG-RV-602HA 11715-FM -107A 1 0F 4 E4 RELIEF VALVE 2.000 NC C SP O 120 1H DIESEL "A" AIR RECEIVER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE 1 EG RV-602MB 11715 FM -107A 2 0F 4 E4 RELIEF VALVE 2.000 NC C SP O 120 1H DIESEL "B" AIR RECEIVER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE 1 EG-RV-602JA 11715-FM -107A 3 of 4 E4 RELIEF VALVE 2.000 NC C SP 0 120 1J DIESEL "A" AIR RECEIVER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE 1-EG RV 602JB 11715 FM -107A 4 0F 4 E4 RELIEF VALVE 2.000 NC C SP O 120 1J DIESEL "B" AIR RECE!VER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE
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VIRGINIA POWER COMPANY PAGE: 21 0F 82 s NORTN ANNA UNIT 1 REVISION: 8
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SECOND INSERVICE TESTlWG INTERVAL DATE: 08/17/98 s ,,I INSERVICE TESTING PROGRAM - VALVE TABLE WC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NLMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TTPE POS FREQ V- CSV- RRV VCN-1-EG 80V 600HA 11715-FM 107A 1 0F 4 E6 50 GATE 1.500 NC B ST C 03 4
' DIESEL AIR START SOLEN 0ID VALVE 1-EG-SOV-600HB 11715 FM 107A 2 0F 4 E6 50 GATE 1.500 NC B EV 0 03 ST C 03 4 DIESEL AIR START SOLEN 0ID VALVE 1 EG-50V-600JA 11715-FM -107A 3 0F 4 E6 50 GATE 1.500 NC B EV 0 03 ST 0 03 4 DIESEL AIR START SOLEN 0ID VALVE 1-EG SOV 600JB 11715 FM 107A 4 0F 4 E6 SO GATE 1.500 WC B EV O 03 ST 0 03 4 DIESEL AIR START SOLEN 0!D VALVE 1 EG 80V-601HA 11715-FM -107A 1 0F 4 E6 So GATE 1.500 NC B EV 0 03 ST C 03 4 1
DIESEL AIR START SOLEN 0ID VALVE
%-.s 1 EG SOV-607JA 11715 FM -107A 3 0F 4 E6 SO GATE 1.500 NC B EV 0 03 ST C 03 4 DIESEL AIR START SOLEN 0ID VALVE i
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VIRGINIA POWER COMPANY PAGE: 22 0F 82 NORTH ANNA UNIT 1 REVISIOW: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT l VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST
- NUMBER NUMBER NUMBER COOR TYPE SI2E CLAS CAT TYPE TYPE POS FREO V- CSV RRV VCN-1 FP 272 11715 Ces 1028 1 0F 1 C6 CHECK VALVE 4.000 2 AC Civ CV C RR 3 LT C OPB FIRE PROTECTION SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1 FP 274 11715-Cas 1028 10F 1 C7 MANUAL GATE 4.000 2 AE CIV LT C OPS FIRE PROTECTION SUPPLY TO CONTAINMENT, OUTS!DE CONTAINMENT ISOLATION VALVE 1 ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
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[s SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 v INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBLR WUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRED V- CSV- RRV VCN-1-FW-047 11715 CBN-074A 1 0F 4 E6 CHECK VALVE 16.000 2 C CV C CS 12 "A" MAIN FEEDWATER SUPPLY, CONTAINMENT PENETRATION CHECK VALVE 1 FW-061 11715 CBM-074A 1 0F 4 B5 CHECK VALVE 3.000 3 C CV 0 CS 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 CS 40 0 CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1-FW-D63 11715 CBM 074A 1 0F 4 B6 CHECK VALVE 3.000 3 C CV o CS 29 STANDBY "A" AUX!LI ARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT q
1 FW-064 11715 CBM 074A 1 0F 4 85 MANUAL GATE 3.000 3 B EV C CS 40 0 CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION s VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1 FW-068 11715 CBM-074A 10F 4 D6 CHECK VALVE 3.000 2 C CV 0 03 "A" AUXILI ARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 1 FW-079 11715-CBM-074A 10F 4 D6 CHECK VALVE 16.000 2 C CV C CS 12 "B" MAIN FEEDWATER HEADER SUPPLY, CONTAINMENT PENETRATION CHECK VALVE 1 FW-093 11715 CBM-074A 1 0F 4 B6 CHECK VALVE 3.000 3 C CV O 03
............................................. I "B" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT -
1-FW-094 11715 CBM-074A 1 0F 4 B6 MANUAL GATE 3.000 3 8 EV C CS 40 0 CS 40 1 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR DRIVEN PUMP HEADERS 1 FW-095 11715 CBN-074A 1 0F 4 B6 CHECK VALVE 3.000 3 C CV o CS 29 STANDBY "B" AUXILI ARY FEEDWATER HEADER CHECK VALVE, DUTSIDE OF CONTAINMENT 1 FW-096 11715-CBM-074A 1 0F 4 B6 MANUAL GATE 3.000 3 B EV C CS 40 O CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 1 1 FW-100 11715 CBM-074A 1 0F 4 C6 CHECK VALVE 3.000 2 O 03
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VIRGINIA POWER COMPANY PAGE: 24 0F 82 (q NORTH ANNA VNIT 1 SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE REVISION: 8 DATE: 08/17/98 NC ISO REL CS RR ALT VALVE DRAWING SHEET DAWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEET NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV RRV- VCN-
"B" AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 1 FW-111 11715 CBM 074A 1 0F 4 56 CHECK VALVE 16.000 2 C CV C CS 12 "C" MAIN FEEDWATER SUPPLY, CONTAINMENT PENETRATION CHECK VALVE 1-FW-125 117tS CBM-074A 1 0F 4 B7 CHECK VALVE 3.000 3 C CV 0 CS 29 STANDBY "C" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 1 FW 126 11715 CBM-074A 1 0F 4 57 MANUAL GATE 3.000 3 B EV C CS 40 0 CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1 FW-127 11715-CBM 074A 1 0F 4 57 CHECK VALVE 3.000 3 C CV 0 03 "C" AUXILIARY FEE 0 WATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 14W-128 11715 CBM 074A 1 0F 4 87 MANUAL GATE 3.000 3 B EV C Ct 40 0 CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS 1 FW-132 11715 CBM-074A 10F 4 B7 CHECK VALVE 3.000 2 C CV 0 03 "C" AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 1 FW 145 11715 CBM-074A 3 0F 4 87 MANUAL GATE 6.000 3 B EV 0 CS 41 ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS 1 FW 148 11715 CBM 074A 3 0F 4 D8 CHECK VALVE 6.000 3 C CV 0 03 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 1 FW-149 11715-CBM-074A 3 0F 4 E8 MANUAL GATE 6.000 3 B EV C CS 40 0 CS 40 AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS CONNECT VALVE 1 FW-150 11715 CBM-074A 3 0F 4 D7 CHECK VALVE 1.000 3 C CV 0 03 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE 1 FW-155 11715-CBM 074A 3 0F 4 E7 MANUAL GATE 6.000 3 B EV C CS 40 0 CS 40 a
VIRGINIA POWER COMPANY PAGE: 25 0F 82
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\v) INSERVICE TESTING PROGRAM VALVE TABLE DATE: 08/17/98 NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-AFW PUMP DISCHARGE HEADER ALIGNMFNT/ CROSS CONNECT VALVE 1 FW 162 11715-CBM 074A 3 0F 4 B6 MANUAL GAT 2 6.000 3 8 EV O CS 41 ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS 1-FW-165 11715 CBM 074A 3 OF 4 D6 CHECK VALVE 4.000 3 C CV 0 03 "A" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP I 1
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............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 1 FW 166 11715-CBM-074A 3 0F 4 E6 MANUAL GATE 6.000 3 B EV C CS 40 0 CS 40 AFW PUMP DISCHARGE HEADER ALICMMENT/ CROSS CONNECT VALVE 1 FW 167 11715-CBM 074A 3 0F 4 D6 CHECK VALVE 1.000 3 C CV 0 03 "A" MOTOR DRIVEN AUMILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE 1 FW 172 11715 CBM-074A 3 0F 4 E6 MANUAL GATE 6.000 3 8 EV C CS 40 0 CS 40 y .............................................
AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS CONNECT VALVE 1 FW 180 11715 CBM 074A 3 0F 4 85 MANUAL GATE 6.000 3 8 EV O CS 41 ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS 1 FW 183 11715 CBM 074A 3 0F 4 05 CHECK VALVE 4.000 3 C CV 0 03 "B" MOTOR DRIVEN AUXILLARY FEEDWATER PUMP DISCHARGE CHECK VALVE 1 FW-184 11715 CBM-074A 3 0F 4 E5 MANUAL CATE 6.000 3 8 EV C CS 40 0 CS 40 AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS CONNECT VALVE 1 FW 185 11715-CBM-074A 3 0F 4 D5 CHECK VALVE 1.000 3 C CV 0 03 "B" MOTOR DRIVEN AUX!LIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE I 1*FW 190 11715-CBM 074A 3 0F 4 E5 MANUAL GATE 6.000 3 B EV C CS 40 1
0 CS 40 l AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS CONNECT VALVE 1 FW 227 11715-CBM-074A 3 0F 4 A7 MANUAL GATE 6.000 3 B EV 0 CS 41 O
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VIRGINIA POWER COMPANY PAGE: 26 0F 82
, ,-wg NORTH ANNA UNIT 1 REVISION: 8
[ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE 1
l 1 NC ISO REL CS RR ALT l VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST RE0 JUST JUST TEST l
NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-l SERVICE WATER SUPPLY TO AFW PUMP SUCTIONS i
1 1 FW-279 11715 CBM-074A 3 0F 4 D8 CHECK VALVE 4.000 3 C CV 0 03 "A" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 1
! 1 FW-526 11715 CBM 074A 3 0F 4 D7 CHECK VALVE 1.000 3 C CV 0 03 1
i PUMP LUBE 0!L COOLER CHECK VALVE 1 FW-527 11715 CBM 074A 3 0F 4 E6 CHECK VALVE 1.000 3 C CV 0 03 4 l
PUMP LUBE OIL COOLER CHECK VALVE 1 FW-528 11715 CBM-074A 3 0F 4 E4 CHECK VALVE 1.000 3 C CV 0 03 PUMP LUBE Cll COOLER CHECK VALVE 1-FW-FCV 1478 11715 CBM-074A 10F 4 E3 A0 GLOBE 16.000 NC B EV C CS 11
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1 FW FCV-1479 11715-CBM 074A 1 0F 4 F4 A0 CLOBE 6.000 NC B EV C CS 11 FS C CS 11 ST C CS 11 "A" BYPASS FEEDWATER REG VALVE l 1-FW FCV 1488 11715 CBM-074A 1 0F 4 04 A GLOBE 16.000 NC B EV C CS 11 l FS C CS 11 1
l "B" MAIN FEEDWATER REG VALVE 1 FW FCV 1489 11715 CBM-074A 1 0F 4 D4 A0 GLOBE 6.000 NC B EV C CS 11 FS C CS 11 ST C CS 11 "B" BYPASS FEEDWATER REG VALVE 1-FW FCV-1498 11715 CBM-074A 1 0F 4 B4 A0 GLOBE 16.000 NC B EV C CS 11 FS C CS 11 ST C CS 11 VP OC 24 i
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"C" MAIN FEEDWATER REG VALVE 1-FW-FCV-1499 11715 CBM 074A 1 0F 4 C4 A0 GLOBE 6.000 NC B EV C CS 11 FS C CS 11 ST C CS 11 l "C" BYPASS FEEDWATER REG VALVE I 1-FW-NCV-100A 11715-CBM-074A 1 0F 4 B5 A0 GLOBE 3.000 3 B EV O CS 31 P 03 31 FS 0 CS 31 ST o CS 31 VP DC 24 STANDBY AUXILIARY FEEDWATER SUPPLY To "A" STEAM GENERATOR 1 FW-HCV 1008 11715-CBM 074A 1 0F 4 B6 A0 GLOBE 3.000 3 B EV 0 CS 31 P 03 31 FS 0 CS 31 ST 0 CS 31 VP OC 24
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g STANDBY AUXILIARY FEEDWATER SUPPLY To "B" Q STEAM GENERATOR 1-FW-NCV 100C 11715 CBM-074A 1 0F 4 A7 A0 GLOBE 3.000 3 B EV 0 CS 31 P 03 31 FS 0 CS 31 ST 0 CS 31 VP OC 24 NORMAL AUXILIARY FEEDWATER SUPPLY 10 "C" STEAM GENERATOR 1-FW-MOV-100A 11715-CBM-074A 1 0F 4 B5 M0 GLOBE 3.000 3 B EV C 03 0 03 ST C 03 j 0 03 VP OC 24 ?
STANDBY AUXILIARY FEEDWATER SUPPLY TO "A" STEAM GENERATOR 1 FW-MOV-100B 11715 CBM-074A 1 0F 4 A6 MO GLOBE 3.000 3 5 EV C 03 0 03 ST C 03 0 03 VP OC 24 NORMAL AUXILIARY FEEDWATER SUPPLY TO "B" STEAM GENERATOR 1 FW-Mov-1 DOC 11715 CBM-074A 1 0F 4 B7 M0 GLOBE 3.000 3 B EV C 03 0 03 ST C 03 es 0 03
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(%s ,,s/ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-STANDBY AUXILIARY FEEDWATER SUPPLY 70 "C" STEAM GENERATOR 1 FW-Mov-1000 11715 CBM 074A 3 0F 4 EB N0 GLOBE 3.000 3 8 EV C 03 0 03 ST C 03 0 03 VP OC 24 NORMAL AUXILIARY FEEDWATER SUPPLY TO "A" STEAM GENERATOR 1 FW-MOV 154A 11715-CBM 074A 10F 4 E3 M0 GATE 16.000 NC B EV C CS 11 ST C CS 11 VP OC 24 "A" MAIN FEEDWATER SUPPLY ISOLATION VALVE 1.FW-MOV 154B 11715-CBN-074A 1 CF 4 D3 MO GATE 16.000 NC B EV C CS 11 ST C CS 11 VP OC 24
] *B" MAIN FEEDWATER SUPPLY ISOLATION VALVE
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1 FW-MOV-154C 11715-CBM-074A 1 0F 4 B3 M0 GATC 16.000 NC B EV C CS 11 ST C CS 11 VP OC 24 "C" MAIN FEEDWATER SUPPLY ISOLATION VALVE 1 FW-PCV 159A 11715-CBM-074A 3 0F 4 F8 A0 GLOBE 4.000 3 B EV 0 CS 32 P 03 32 FS 0 CS 32 ST o CS 32 i
VP OC 24 1 .............................................
AUXILIARY FEEDWATER PRESSURE CONTROL VALVE l 1 FW PCV 1598 11715 CBM-074A 3 0F 4 E8 A0 GLOBE 4.000 3 B EV O CS 32 P 03 32 FS 0 CS 32 l ST 0 CS 32 VP OC 24 AUXILIARY FEEDWATER PRESSURE CONTROL VALVE 1 FW-RV 100 11715 CBM-074A 3 0F 4 D8 RELIEF VALVE 3.000 3 C SP O 120 TURBINE DRIVEN AUXILIARY FEED PUMP FEEDWATER DISCHARGE RELIEF VALVE I
VIRGINIA POWER COMPANY PAGE: 29 0F 82 NORTH ANNA UNIT 1 REVISION: 8
[D SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\ INSERVICE TESTING PROGRAM - VALVE TABLE 1 NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV- VCN-1 GN 225 '11715 FM .105A 10F 3 E4 CHECK VALVE .500 NC AC CV C RR 1 LT C 24 BOTTLED N!TROGEN SUPPLY TO PORV ISOLATION CNECK VALVE 1 GN 229 11715-FM .105A 1 0F 3 E6 CHECK VALVE .500 NC AC CV C RR 1 LT C 24 l BOTTLED N!TROGEN SUPPLY TO PORY ISOLATION !
I CHECK VALVE l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
l 1 GN-RV-108A 1 11715-FM -105A 1 0F 3 ET RELIEF VALVE .750 NC C SP O 120 BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE 1 GN-RV 108A 2 11715-FM -105A 10F 3 F6 RELIEF VALVE .750 NC C SP O 120
............................................. I BOTTLED N!TROGEN SUPPLY TO PORV RELIEF VALVE l
1-GN RV 108A 3 11715-FM 105A 10F 3 E6 RELIEF VALVE .750 NC C SP O 120 BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE
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i s 1 GN RV.1088 1 11715-FM 105A 10F 3 E3 RELIEF VALVE .750 NC C SP 0 120 BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE 1-GN-RV 1088 2 11715 FM 105A 1 0F 3 F5 RELIEF VALVE .750 NC C SP O 120 I BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE 1
1 1 GN RV 1088 3 11715 FM -105A 1 0F 3 E5 RELIEF VALVE .750 NC C SP O 120 l
1 BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE 4
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/ SECOND INSERVICE TESTING INTERVAL DATE: 08/1T/98 k
v INSERVICE TESTING PROGRAM - VALVE TABLE WC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER WUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-1-HC 014 11715 CBM-106A 1 0F 4 E8 CHECK VALVE 2.000 2 AC CIV CV C RR 4 0 18 4 LT C OPB UNIT 1 RETURN LINE FROM UNIT 1 HYDROGEN ANA-
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LYZERS & RECOMB, INSIDE CONT ISOL CHECK VALVE 1 HC-018 11715 CBM 1D6A 2 0F 4 E6 CHECK VALVE 2.000 2 AC CIV CV C RR 4 0 18 4 LT C DPB UNIT 1 RETURN LINE FROM UNIT 2 HYDROGEN ANA-LYZERS & RECOMB, INSIDE CONT ISOL CHECK VALVE 1-HC-063 11715-CBM-106A 1 0F 4 C7 CHECK VALVE .375 NC C CV 0 03 HYDROGEN ANALYZER DISCHARGE CHECK VALVE 1-HC TV 100A 11715 CBN 106A 10F 4 E8 SO GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 0 03 VP OC 24
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Q UNIT 1 SAMPLE LINE TO UNIT 1 HYDROGEN ANA-LYZERS, INSIDE CONTAINMENT ISOLATION VALVE 1-HC-TV-1000 11715-CBM-106A 1 0F 4 E7 SO GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 0 03 VP OC 24 UNIT 1 SAMPLE LINE TO UNIT 1 HYDROGEN ANA-LYZERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-HC TV-101A 11715 CBM-1D6A 10F 4 D7 SO GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 0 03 VP OC 24 RETURN ISOLATION FROM UNIT 1 HYDROGEM ANA*
LYZERS TO UNIT 1 CONT,0UTSIDE CONT ISOL VALVE 1 HC TV-1018 11715 CBM-106A 10F 4 D7 SO GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C OPB <
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VIRGINIA POWER COMPANY PAGE: 31 0F 82
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SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV- VCN-RETURN ISOLATION FROM UNIT 1 HYDROGEN ANA-LYZERS TO UNIT 1 CONT,0UTSIDE CONT ISOL VALVE 1.HC-TV 102A 11715-CBM-106A 2 0F 4 E6 $0 GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 0 03 VP DC 24 UNIT 1 SAMPLE LINE TO UNIT 2 HYDROGEN ANA.
LYZERS, INSIDE CONTAINMENT ISCLATION VALVE 1-HC TV-102B 11715-CBM 106A 2 0F 4 E7 $0 GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C DPB ST C 03 0 03 VP OC 24 UNIT 1 SAMPLE LINE TO UNIT 2 HYDROGEN ANA-LYZERS, OUTSIDE CONTAINMENT ISOLATION VALVE
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0 03 FS C 03 LT C OPB ST C 03 0 03 VP OC 24 RETURN ISOLATION FROM UNIT 2 HYDROGEN ANA-LYZERS TO UNIT 1 CONT,0UTSIDE CONT ISOL VALVE 1 HC-TV-1038 11715 CBM-106A 2 0F 4 D7 SO GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 0 03 VP OC 24 RETURN ISOLATION IROM UNIT 2 NYDR0 GEN ANA-LYZERS To UNIT 1 DNT,0UTSIDE CONT ISOL VALVE 1 HC-TV 104A 11715-CBM-106A l. OF 4 F6 A0 GLOBE 2.500 2 A CIV EV C 03 0 03 I FS C 03 LT C OPB ST C 03 0 03 VP OC 24 SUPPLY ISOL FROM UNIT 1 CONT TO N1 HYDRO RE-COMB & N2 CONT BLOWER,0UTSIDE CONT ISOL VALVE
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I 1 NC TV-105A 11715-CBM-106A 10F 4 E6 A0 GLOBE 2.500 2 A CIV EV C 03 0 03 FS C 03 LT C DPB ST C 03 0 03 VP DC 24 i RETURN ISOLATION FROM UNIT 1 HYDROGEN RECOMB
& ANAL TO UNIT 1 CONT, OUTSIDE CONT ISOL VALVE 1 NC-TV 105B 11715-CBM-106A 10F 4 E6 A0 GLOBE 2.500 2 A CIV EV C 03 l 0 03 l FS C 03 LT C OPB ST C 03 l O 03 VP OC 24 s .............................................
RETURN ISOLATION FROM UNIT 1 HYDROGEN RECOMB
& ANAL TO UNIT 1 CONT, OUTSIDE CONT ISOL VALVE l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1-HC TV 106A 11715-CBM-106A 4 0F 4 F8 A0 GLOBE 2.500 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 0 03 VP OC 24 l .............................................
l UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE BLOW & N2 HYDRO RECOMB, OUTSIDE CONT ISOL VLV 1-HC-TV 1068 11715-CBM-106A 4 0F 4 F8 A0 GLOBE 2.500 2 A CIV EV C 03 0 03 l FS C 03 i LT C DPS ST C 03 0 0'J VP OC 24 i
( UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE l BLOW & N2 HYDRO RECOMB, OUTSIDE CONT ISOL VLV 1 HC TV 107A 11715-CSM-1D6A 2 0F 4 E7 A0 GLOBE 2.500 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 0 03
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VIRGINIA POWER COMPANT PAGE: 33 0F 82 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
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INSERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-RETURN ISOLATION FROM UNIT 2 HYDROGEN RECOMS ]i
& ANAL TO UNIT 1 CONT, QUTSIDE CONT ISOL VALVE 1-NC TV 107B 11715-CeM 106A 2 0F 4 E8 A0 GLOBE 2.500 2 A CIV EV C 03 ;
o 03 FS C 03 LT C OPB ST C 03 0 03 VP OC 24 !
RETURN ISOLATION FROM UNIT 2 HYDROGEN RECOM8
& ANAL TO UNIT 1 CONT, OUTSIDE CONT ISOL VALVE 1 HC TV 108A 11715-CBM-106A 3 0F 4 E8 So GLOSE .375 2 A CIV EV C 03 .
FS C 03 LT C OPS ST C 03 VP OC 24 UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, INSIDE CONTAINMENT ISOLATION VALVE 1 NC-TV-1088 11715-CSM-106A 3 0F 4 E7 $0 GLOBE .375 2 A Civ EV C 03 p FS LT C
C 03 OP8 g
ST C 03 vP OC 24 UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, DUTSIDE CONTAINMENT ISOLAfl0N VALVE
VIRGINIA POWER COMPANY PAGE: 34 0F 82
-~s WORTH ANNA UNIT 1 REVISION: 8
[\s,,/l SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DATE: D8/17/98 NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-1 HV-MOV 100A 11715 CBB D06A 1 0F 3 D7 M0 BFLY 36.000 2 AE CIV LT C OPB VP OC 24 CONTAINMENT PURGE SUPPLY, INSIDE CONTAINMENT ISOLATION VALVE 1 HV-MOV 1008 11715-CBB 006A 1 0F 3 D7 M0 BFLY 36.000 2 AE Civ LT C OPB VP OC 24 CONTAINMENT PURGE SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1-HV-MOV-100C 11715-CBB DD6A 1 0F 3 C7 M0 BFLY 36.000 2 AE CIV LT C OPB VP OC 24 CONTAINMENT PURGE EXHAUST, INSIDE CONTAINMENT ISOLATION VALVE 1 HV-MOV 1000 11715-CBB 006A 1 0F 3 C7 M0 BFLY 36.000 2 AE CIV LT C OPB VP DC 24 CONTAINMENT PURGE EXHAUST, OUTSIDE CONTAIN-MENT ISOLATION VALVE 1 HV-MOV-101 11715 CBB 006A 1 OF 3 C7 M0 BFLY 8.000 2 AE CIV LT C OPB e'* VP OC 24
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C CONTAINMENT PURGE BYPASS, OUTSIDE CONTAINMENT t
ISOLATION VALVE 1-HV-MOV-102 11715 CBB 006A 10F 3 07 Mo BFLY 18.000 2 AE CIV LT C OPB VP OC 24 CONTAINMENT PURGE ALTERNATE SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1 HV MOV 111A 11715 CBB-D40C 1 0F 3 E8 M0 GATE 4.000 3 B EV O 03 ST 0 03 VP OC 24 CONTROL ROOM CHILLER ISOLAfl0N VALVE 1 HV MOV 111B 11715-CBB-040C 10F 3 C8 M0 CATE 4.000 3 B EV 0 03 ST 0 03 CONTROL ROOM CHILLER ISOLATION VALVE 1-HV-MOV-111C 11715-CBB 040C 10F 3 D8 M0 CATE 4.000 3 B EV O 03 ST C 03 CONTROL ROOM CHILLER ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... . i 1 HV MOV-113A 11715 CBB-0400 1 0F 3 E3 M0 GATE 4.000 3 8 EV 0 03 ST o 03 VP OC 24 l
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m m
VIRGINIA POWER COMPANY PAGE: 35 0F 82 NORTH ANNA UNIT 1 REVIS!DW: 8
\ SECOND INSERVICE TESTING INTERVAL DATE: D8/17/98
[(,,,
- '/ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV- RRV VCN-CONTROL ROOM CONDENSER WATER SYSTEM ISOLATION VALVE 1-HV-MOV 113B 11715-CBB-D40D 1 0F 3 B3 M0 GATE 4.000 3 B EV 0 03 ST 0 03 CONTROL ROOM CONDENSER WATER SYSTEM ISOLATION VALVE 1 HV MOV 113C 11715-CBB 0400 1 0F 3 C3 MO GATE 4.000 3 B EV 0 03 ST 0 03 i
............................................. 1 CONTROL ROOM CONDENSER WATER SYSTEM ISOLATIDW VALVE 1-HV PCV-1235A1 11715 CBB-04DD 1 0F 3 D6 A0 GLOBE 3.000 3 B EV C 03 )
FS C 03 ST C 03 CONTROL ROOM CONDENSER WATER BYPASS LINE PRESSURE CONTROL VALVE 1-HV-PCV 1235A211715-CBB-0400 1 0F 3 E3 A0 GLOBE 3.000 3 8 EV 0 03 FS 0 03 ss ST 0 03 s
( .............................................
\ CONTROL R00M CONDENSER WATER PRESSURE CONTROL VALVE 1 HV-PCV 1235B1 11715 CBB-040D 1 0F 3 A6 A0 GLOBE 3.000 3 8 EV C 03 FS C 03 ST C 03 CONTROL ROOM CONDENSER WATER BYPASS LINE PRESSURE CONTROL VALVE 1 HV PCV-1235B2 11715 CBB 04DD 1 0F 3 C3 A0 GLOBE 3.000 3 B EV 0 03 FS O 03 ST C 03 CONTROL ROOM CONDENSER WATER I PRESSURE CONTROL VALVE 1-HV-PCV.1235C1 11715 CBB-0400 1 0F 3 C6 A0 GLOBE 3.000 3 B EV C 03 FS C 03 ST C 03 CONTROL ROOM CONDENSER WATER BYPASS LINE PRESSURE CONTROL VALVE 1 HV PCV-1235C2 11715 CBB 0400 1 0F 3 83 A0 GLOBE 3.000 3 B EV 0 03 FS O 03 ST 0 03 CONTROL ROOM CONDENSER WATER PRESSURE CONTROL VALVE 1 HV-RV 1200 11715 CBB 040C 1 0F 3 D4 RELIEF VALVE 3 C SP 0 120 f%g i
VIRGINIA POWER COMPANY PAGE: 36 of 82 s bORTH ANNA' UNIT 1
- REVISION: 8
[\ \ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 j
s_,,) INSERVICE TESTING PROGRAM VALVE TABLE 1
l NC ISO REL CS RR ALT l VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST WUMBER WUMBER WUMBER COOR TYPE $!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-CONTROL ROOM CHILLER SYSTEM RELIEF VALVE l ................................................... 4........ ..... .... ... .... .... .... .... ... .... .... ....
1-HV-RV 1201 11715-CBB 040C 1 0F 3 C5 REkIEF VALVE 3 C SP o 120 CONTROL ROOM CHILLER SYSTEM RELIEF VALVE 1-HV RV-1202A 11715 CBB 040C 1 0F 3 E8 RELIEF VALVE .750 3 C SP O 120 )
CONTROL ROOM CHILLER SYSTEM RELIEF VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j 1 HV-RV-12028 11715 CBB 040C 1 0F 3 C8 RELIEF VALVE .750 3 C SP O 120 i CONTROL ROOM CHILLER SYSTEM RELIEF VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 1
1 HV-RV-1202C 11715 CBB 04DC 1 0F 3 D8 RELIEF VALVE .750 3 C SP O 120 i
............................................. i CONTROL ROOM CHILLER SYSTEM RELIEF VALVE 1 HV RV-1205A 11715-CBB D40D 1 0F 3 E3 RELIEF VALVE 3 C SP O 120
.g s .............................................
t CONTROL ROOM CONDENSER WATER SYSTEM
\ RELIEF VALVE 1 HV-RV 12058 11715-CBB-D40D 1 0F 3 53 RELIEF VALVE 3 C SP O 120 CONTROL ROON CONDENSER WATER SYSTEM RELIEF VALVE 1 HV-RV-1205C 11715-CBB-D4DD 10F 3 D3 RELIEF VALVE 3 C SP 0 120
............................................. i i
CONTROL ROOM CONDENSER WATER SYSTEM RELIEF VALVE 1-HV RV-1302A 11715 FM 082M 10F 1 F7 RELIEF VALVE .750 NC C SP 0 120 SAFEGUARD AREA FANS AIR RECEIVER RELIEF VALVE 1 HV RV-1302B 11715 FM -082M 1 0F 1 F6 RELIEF VALVE .750 NC C SP O 120 l
SAFEGUARD AREA FANS AIR RECEIVER RELIEF VALVE l 1-HV SOV 1200A 11715-CBB 0400 1 0F 3 F7 SO GATE .500 3 B EV 0 03 '
l l ST o 03 CONTROL ROOM CONDENSER PUMP SEAL COOLING WATER LINE ISOLATION VALVE 1 HV $0V 120DB 11715 CBB 0400 1 0F 3 BT So GATE .500 3 8 EV 0 03 ST 0 03 CONTROL ROOM CONDENSER PUMP SEAL COOLING G WATER LINE ISOLATION VALVE by ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
VIRGINIA POWER COMPANY PAGE: 37 0F 82
.~ NORTH ANNA UNIT 1 REVISION: 8
\
, ) SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DATE: D8/17/98 NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ABME DM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV VCN-1 HV-BOV 1200C 11715-Cas 04DD 10F 3 D7 SO GATE .500 3 8 EV 0 03 ST C 03 CONTROL ROOM CONDENSER PUMP SEAL COOLING WATER LINE ISOLATION VALVE i
1 1
l I
i i
VIRGINIA POWER COMPANT PAGE: 38 or 82 NORTH ANNA UNIT 1 REVISIDN: 8 f,--~\ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
( ,,j/ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER WUMBER NUMBER COOR TTPE $!ZE CLAS CAT TTPE TTPE POS FRE0 V- CSV- RRV VCN-
...... ....... ...... .... ..... i
..... .... ... .... .... .... .... ... .... .... .... i 1 IA-0055 11715 CBM-082A 1 0F 3 F5 CHECK VALVE 2.000 2 AC CIV CV C RR 5 LT C OPS INSTRUMENT AIR SUPPLY TO CONTAINMENT, INSIDE I CONTAINMENT ISOLATION CHECK VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 1 1 IA 0149 11715 CBM-082N 3 0F 3 C4 CHECK VALVE 1.000 2 AC CIV CV C RR 5 i LT C DP8 RETURN TO CONTAINMFNT FROM RADIATION MONITOR-ING CABINET, INSIDE CONT ISOL CHECK VALVE 1 IA 0925 11715 FM -082M 1 0F 1 E7 CHECK VALVE .250 NC AC CV C 03 LT C 24 2 SAFEGUARD AREA FANS AIR RECEIVER ISOLATION CHECK VALVE 1.IA 0926 11715-FM -082M 1 0F 1 E7 CHECK VALVE .250 NC AC CV C 03 LT C 24 2 SAFEGUARD AREA FANS AIR RECEIVER ISOLATION CHECK VALVE 1 IA 0934 11715-FM -082M 1 OF 1 E6 CHECK VALVE .250 NC AC CV C 03 rs LT C 24 2
,f .............................................
Q SAFEGUARD AREA FANS AIR RECEIVER ISOLATION CHECK VALVE 1.IA-0935 11715-FM 082M 10F 1 E6 CHECK VALVE .250 NC AC CV C 03 LT C 24 2 SAFEGUARD AREA FANS AIR RECEIVER ISOLATION CHECK VALVE 1 IA 0944 11715 FM 082M 1 0F 1 F5 CHECK VALVE 750 NC AC CV C CS 30 LT C 24 3 MAIN STEAM PCV VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE I i
1-IA-0948 11715 FM .082M 1 0F 1 F4 CHECK VALVE .750 NC AC CV C CS 30 LT C 24 3 MAIN STEAM PCV VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE 1 IA 0952 11715 FM .082M 1 0F 1 F3 CHECK VALVE .750 WC AC CV C CS 30 LT C 24 3 i MAIN STEAM PCV VALVE AIR ACCUMULATDR I ISOLATION CHECK VALVE 1 IA 0959 11715 FM 082M 1 0F 1 C4 CHECK VALVE .750 NC AC CV C CS 30 LT C 24 3 AUXILIART FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE p -sg ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
- 1 IA 0963 11715 FM D82M 1 0F 1 C5 CHECK VALVE .750 NC AC CV C CS 30
\
VIRGINIA POWER COMPANY PAGE: 39 0F &2 NORTH ANNA UNIT 1 REVISION: 8
[
\ _,/}
SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FRED V- CSV RRV- VCN-1 IA 0963 11715-FM -082M 1 0F 1 C5 CHECK VALVE .750 NC AC LT C 24 3 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE 1 IA-0967 11715-FM -082M 1 OF 1 C6 CHECK VALVE .750 NC AC CV C CS 30 LT C 24 3 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE 1 IA D971 11715 FM -082M 1 0F 1 C6 CHECK VALVE .750 NC AC CV C CS 30 LT C 24 3 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE 1 I A-D975 11715 FM -082M 1 0F 1 C7 CHECK VALVE .750 NC AC CV C CS 30 LT C 24 3 AUXILIARY fEEDWATER VALVE A!R ACCUMULATOR ISOLATION CHECK VALVE 1 IA 2152 11715-FM -082A 2 OF 3 F7 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 1
,s .............................................
( j, I BOTTLED NITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 1-IA-2153 11715 FM 082A 2 0F 3 F8 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 1 BOTTLED NITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 1 IA 2154 11715-FM 082A 2 0F 3 F7 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 1 BOTTLED WITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 1
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j 1 IA 2155 11715-FM -082A 2 0F 3 F8 CHECK VALVE .750 NC AC CV C RR 1 i LT C 24 1
............................................. l BOTTLED NITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 1 1 IA-RV 110 11715 FM -082A 2 0F 3 F8 RELIEF VALVE' NC C SP O 120 AIR SUPPLY TO 1 RC PCV 1455C RELIEF VALVE 1 IA-RV-111 11715 FM 2 0F 3 F8 RELIEF VALVE NC C $P 0 120 AIR SUPPLY TO 1-RC PCV 1456 RELIEF VALVE l 1 IA SV 105A 11715-FM -082M 1 0F 1 ES RELIEF VALVE NC C SP O 120 m
VIRGINIA POWER COMPANT PAGE: 40 of 82
'N, NORTN ANNA UNIT 1 REVISION: 8 4
SECOND INSERVICE TESTING INTERVAL DATE: D8/17/98
\s / INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-MAIN STEAM PCV VALVE AIR ACCUMULATOR SELIEF VALVE 1 IA SV 1058 11715 FM 082M 1 0F 1 E4 RELIEF VALVE NC C SP 0 120 MAIN STEAM PCV VALVE AIR ACCUMULATOR RELIEF VALVE 1 IA SV 1D5C 11715 FM -082M 1 0F 1 E3 RELIEF VALVE NC C SP 0 120 MAIN STEAM PCV VALVE AIR ACCUMULATOR RELIEF VALVE 1 IA-SV 105D 11715 FM -D82M i 0F 1 A4 RELIEF VALVE NC C SP O 120 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE 1 IA SV 105E 11715 FM -082M 1 0F 1 A4 RELIEF VALVE NC C SP 0 120 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE
<"*s 1 IA SV 1D5F 11715-FM 082M 1 0F 1 A6 RELIEF VALVE NC C SP O 120
( AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE
-1 IA-SV 105G 11715 FM 082M 1 0F 1 A7 RELIEF VALVE NC C SP 0 120 AUXILIARY FEEDWATER VALVE AIR ACCUMULATDR RELIEF VALVE 1 !A-SV 105H 11715 FM 082M 1 0F i A5 RELIEF VALVE NC C SP O 120 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE 1 1A-TV-102A 11715 CBM 082N 10F 3 D3 A0 GLOSE 2.000 2 B EV C 03 FS C 03 ST C 03 VP OC 24 INSTRUMENT AIR SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 1 IA TV 102B 11715 CBM 082N 1 0F 3 D3 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 VP OC 24 INSTRUMENT AIR SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE U
1
l VIRGINIA POWER COMPANY PAGE: 41 0F 82 NORTH ANNA UNIT 1 f'~~'\ REVISION: 8
\v) SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DATE: 08/17/96 NC VALVE 150 REL CS RR ALT DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMSER NUM6ER COOR TYPE
$!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-1 LM-TV.100A 11715 CBM-092A 10F 2 ET A0 GLOSE .375 2 AE CIV LT C DPB YP DC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1 LM TV.100s 11715-cam-D92A 1 0F 2 E6 A0 GLOSE .375 2 AE CIV LT C OPB VP DC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1-LM-TV-100C 11715-CBM-092A 1 0F 2 E6 A0 GLOSE .375 2 AE CIV LT C OPB VP DC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1 LM TV.1DDD 11715 CBM 092A 10F 2 E5 A0 GLOBE .375 2 AE CIV LT C OPS VP OC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1-LM TV-100E 11715-CBM-092A 10F 2 F6 A0 GLOSE .375 2 AE CIV LT C OPS f#~'\ .............................................
(' CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, CUTSIDE CONTAINMENT !$0LATION VALVE 1-LM-TV 100F 11715-CBM-092A 1 0F 2 F5 A0 GLOSE .375 2 AE CIV LT C OPS VP DC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1-LM-TV 100G 11715-CBM D92A 1 0F 2 E7 A0 GLOSE .375 2 AE CIV LT C OPB VP OC 24 ,
CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM l SUPPLY, DUTSIDE CONTAINMENT ISOLAT10N VALVE 1-LM TV-100H 11715-CBM 092A 1 0F 2 E6 A0 GLOBE .375 2 AE Civ LT C DPB VP OC 24 I CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, QUTSIDE CONTAINMENT ISOLATION VALVE 1 LM-TV-101A 11715-CBM 092A 1 0F 2 D5 A0 GLOBE .375 2 Ac' CIV LT C OPB VP DC 24 CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1 LM-TV-1018 11715 CBM-092A- 1 0F 2 DS A0 GLOBE .375 2 AE CIV LT C DPB VP OC 24 CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE
.s ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
t 1 LM-TV-101C 11715 CBM 092A 10F 2 D5 A0 GLOBE .375 2 AE CIV LT C OPS d
VIRGINIA POWER COMPANY PAGE: 42 0F 82 NORTH ANNA UNIT 1 REVIS!DN: 8
[ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST IASIBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-1 LM-TV 101C 11715-CBM 092A 1 0F 2 D5 A0 GLOSE .375 2 AE CIV VP OC 24 CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM SUPPLY, QUTSIDE CONTAINMENT ISOLATION VALVE 1 LM-TV 1010 11715 CBM 092A 1 0F 2 D4 A0 GLOSE .3T3 2 AE CIV LT C OPB VP OC 24 CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATIDW VALVE 4
V 1
i
VIRGINIA POWER COMPANY PAGE: 43 OF B2 NORTH ANNA DNIT 1
- REVisl0N: 8
[,- s SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT ,
VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER' NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-1-MS-018 11715-CBM-070B 1 0F 3 C6 MANUAL GATE 3.000 2 B EV C 03 i'
MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 1 MS-D57 11715-CBM-0708 2 0F 3 C6 MANUAL GATE 3.000 2 B EV C 03 MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 1-MS-D95 11715-CBM-070B 3 0F 3 C6 MANUAL GATE 3.000 2 8 EV C 03 MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 1-MS-119 11715-CBM 070A 3 0F 3 E7 CHECK VALVE 3.000 2 C CV C 03 0 03 . j "A" MAIN STEAM HEADER SUPPLY 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 03 0 03 "B" MAIN STEAM HEADER SUPPLY CHECK VALVE TO l
TURBINE DRIVEN AUXILIARY FEEDWATER PUMP l i ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
\s,,/ 1-MS 124 11715-CBM-07DA 3 0F 3 F7 CHECK VALVE 3.000 2 C CV C 03 0 03 i
............................................. i "C" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1-MS-NRV-101A 11715 CBM-0708 1 0F 3 D3 CHECK VALVE 32.000 2 C CV C CS 13 VP DC 24 "A" MAIN STEAM HEADER NON-RETURN VALVE 1*MS NRV-1018 11715-CBM-0708 2 0F 3 03 CHECK VALVE 32.000 2 C CV C CS 13 VP OC 24 "B" MAIN STEAM HEADER NON RETURN VALVE khsWRVkhh hhhB hhDB h bF h hh hHhhk VkLVE 32$bbb2"' b" ~ ~ ~ ~ bv" b"' bS" ~ ~ ~ kh" ~ ~ ~ ~ ""
VP OC 24 "C" MAIN STEAM HEADER NON-RETURN VALVE 1-MS-PCV-101A 11715 CBM 0708 1 0F 3 E5 A0 ANGLE 6.000 2 B' EV C 03 0 03 FS C 03 ST C 03 0 03 VP DC 24 "A" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE
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9
VIRGINIA POWER COMPANY PAGE: 44 0F 82 g NORTH ANNA UNIT 1 REVISION: 8 j y SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 Q INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE $!ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV- VCN-1-MS-PCV 101B 11715 CBM-070s 2 0F 3 E6 AD ANGLE 6.000 2 5 EV C 03 0 03 FS C 03 ST C 03 0 03 VP OC 24 "B" MAIN STEAM HEADER DISCHARGE TO ATMDSPHERE PRESSURE CONTROL VALVE 1 MS-PCV 101C 11715 COM 0708 3 0F 3 D3 AD ANGLE 6.000 2 B EV C 03 0 03 FS C 03 ST C 03 0 03 VP OC 24 "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 0 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS n 1 MS-SV 101B 11715-COM-0708 2 0F 3 E6 SAFETY VALVE 6.000 2 C SP O 120
( .............................................
\ "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMot 1 MS-SV-101C 11715-CBM-0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP 0 120 "C" MAIN STEAM NEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS-SV 102A 11715 CSM-0708 1 OF 3 E5 SAFETY VALVE 6.000 2 C SP O 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS SV 102B 11715-CBM 0708 2 0F 3 E5 SAFETY VALVE 6.000 2 C SP 0 120 "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS SV-102C 11715-CBM-070s 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP O 120 "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS-SV 103A 11715 CBM-070s 1 of 3 E6 SAFETY VALVE 6.000 2 C SP O 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS-SV 1038 11715 CBM 0708 2 OF 3 E5 SAFETY VALVE 6.000 2 C SP O 120 "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS s ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1-MS SV 103C 11715 CBM 0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C $P O 120 1
VIRGINIA POWER COMPANY PAGE: 45 DF 82 g- NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 k_,e s INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER WUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV- VCN-
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS-SV-104A 11715 CBM-070s 1 0F 3 E6 SAFETY VALVE 6.000 2 C SP 0 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS SV 1048 11715 CBM 070s 2 0F 3 E6 SAFETY VALVE 6.000 2 C SP O 120 "B" MAIN STEAM HEADER SAFETY VALVE, SV l DISCHARGE TO ATMOS 1 MS SV-104C 11715 CBM-070B 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP 0 120 "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS-SV-105A 11715 CBM-070B 10F 3 E5 SAFETY VALVE 6.000 2 C SP O 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS SV 105B 11715 CBM 070B 2 0F 3 E5 SAFETY VALVE 6.000 2 C SP O 120
,c ~ .............................................
g "B" MAIN STEAM HEADER SAFETY VALVE, SV s,_,- DISCHARGE TO ATMOS 1 MS SV 105C 11715 CBM-070s 3 0F 3 D5 SA F" fALVE 6.000 2 C SP O 120 "C" MAIN STEAM HEADER SAFETY Vst,L, .V DISCHARGE TO ATMOS 1 MS TV 101A 11715 CBM 070s 10F 3 04 A0 DISC 32.000 2 B EV C CS 16 FS C CS 16 ST C CS 16 VP DC 24 "A" MAIN STEAM HEADER TRIP VALVE 1 MS TV-1018 11715 CBM-0708 2 0F 3 C4 A0 DISC 32.000 2 B EV C CS 16 FS C CS 16 ST C CS 16 VP OC 24 "B" MAIN STEAM HEADER TRIP VALVE 1-MS TV-101C 11715-CBM-070s 3 0F 3 C4 A0 DISC 32.000 2 B EV C CS 16 FS C CS 16 ST C CS 16 VP DC 24 "C" MAIN STEAM HEADER TRIP VALVE 1-MS-TV-109 11715-CBM-070A 1 0F 3 A8 AD CLOBE 3.000 2 B EV C CR 14 fs FS C 14 (Vl CR ST C CR 14
r VIRGINIA POWER COMPANY PAGE: 46 0F 82
-s NORTM ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V. CSV- RRV VCN-i 1-MS TV 109 11715 CBM 070A 10F 3 A8 A0 GLOBE 3.000 2 B VP DC 24 MAIN STEAM MIGN PRESSURE DRAIN ISOLAfl0N TO CONDENSER 1 MS-TV-110 11715-CBM-0705 3 0F 3 A4 A0 GlosE 1.5D0 2 B EV C 03 FS C 03 ST C 03 VP DC 24 MAIN STEAM NIGN PRESSURE DRAIN HEADER ISO-LATION TO STEAN GENERATOR BLOWOWN SYSTEM 1 MS-TV 111A 11715-CBM-070A 3 0F 3 E5 A0 GLOBE 3.000 2 B EV C 03 0 03 FS O 03 ST C 03 0 03 VP OC 24 MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1 MS TV 1118 11715 CBM 070A 3 0F 3 E4 A0 GLOSE 3.000 2 B EV C 03 0' 03 pI FS 0 03
-(s/ ST C 0
03 03 VP OC 24 MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1-MS-TV-113A 11715 CBM-07DB 1 0F 3 D4 A0 GLOBE 3.000 2 B EV C CS 33 FS C CS 33 ST C CS 33 VP OC 24 "A" MAIN STEAM TRIP BYPASS VALVE 1-MS-TV 113B 11715-CBM 0708 2 0F 3 04 A0 GLOBE 3.000 2 B EV C CS 33 FS C CS 33 ST C CS 33 VP OC 24 "B" Math STEAM TRIP BYPASS VALVE 1-MS TV 113C 11715-CBM-0708 3 0F 3 D4 A0 GLOBE 3.000 2 B EV C CS 33 FS C CS 33 ST C CS 33 VP OC 24 "C" MAIN STEAM TRIP BYPASS VALVE 1 MS TV-115 11715-CBM 070A 3 0F 3 C4 MECH TRIP VLV 3.000 3 E VP OC 24
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VIRGIN!A POWER COMPANY PAGE: 47 0F 82 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 INSERVICE TESTING PROGRAM - VALVE TABLE NC l
!$0 REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NLMBER NUMEER NUMBER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FREQ V-CSV RRV VCN-MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AFW PUMP l
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VIRGINIA POWER COMPANY PAGE: 48 0F 82 A NORTH ANNA UNIT 1 REVISION: 8
( SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
( INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RED JUST JUST TEST NI,mBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TTPE TYPE POS FREQ V* CSV RRV VCN-1-05 011 11715 CBM-091A 2 0F 4 D6 WL CHECK VLv 8.000 2 AC CIV CV C RR 21 0 RR 21 LT C OPB "A" OUENCH SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 1 05-019 11715 CBM-091A 2 0F 4 E6 WL CHECK VLv 8.000 2 AC Civ CV C RR 21 0 RR 21 LT C OPB "B" OUENCH SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 1 08-MOV-100A 11715-CBM-091A 2 0F 4 A3 M0 GATE 10.000 2 E VP OC 24 "A" QUENCH SPRAT PUMP SUCTION ISOLATION VALVE FROM REFUELING WATER STORAGE TAWK 1 05 MOV 1008 11715-CBM-091A 2 0F 4 A3 MO GATE 10.000 2 E VP OC 24 "B" OUENCH SPRAY PUMP SUCTION ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 1 OS MOV 101A 11715 CBM-091A 2 0F 4 05 M0 CATE 8.000 2 A CIV EV C 03 D 0 03
( LT C OPB
( ST C 03 0 03 VP OC 24 "A" OUENCH SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISCLAil0N VALVE 1 05-MOV 1018 11715 CBM 091A 2 0F 4 E5 M0 CATE 8.000 2 A CIV EV C 03 0 03 LT C OPS ST C 03 0 03 VP OC 24 "B" OUENCH SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 05-NOV-102A 11715-CBM 091A 1 of 4 05 M0 GATE 6.000 2 B EV O CS 44 ST 0 CS 44 VP OC 24 CHEMICAL ADDITION TANK DISCHARGE ISOLATION VALVE 1 0$ MOV 1028 11715 CBM-091A 1 0F 4 D6 M0 GATE 6.000 2 B EV O CS 44 ST 0 CS 44 VP OC 24 CHEMICAL ADDITION TANK DISCHARGE ISOLATION VALVE l %
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VIRGIN!A poler C(MPANY PAGE: 49 0F 82 NORTH ANNA UNIT 1 . REVISION: 8 f, .., SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 INSERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER _ NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-1 RC-149 11715-CBM 0938 2 of 3 07 CHECK VALVE 3.000 2 AC CIV CV C RR 6 LT C DPS PRIMARY GRADE WATER SUPPLY TO PRT #2 RCP SEAL STANDPIPES /FLUSN CONNECT, INSIDE CONT ISO VLV 1 RC 176 11715 CBM-0958 1 0F 3 A4 MANUAL NEEDLE .125 1 AE CIV LT C OPS PRESSURIZER PRESSURE DEAD WEIGHT TESTER ISOLATION, OUTSIDE CONT ISOLATION VALVE 1-RC 178 11715 CBM-D935 1 0F 3 A3 MANUAL NEEDLE .125 1 AE CIV LT C DPS PRESSURIZER PRES $URE DEAD WEIGHT TESTER ISOLATION, OUTSIDE CONT ISOLATION VALVE 1 AC NCV-1556A 11715 CBM D93A 1 0F 3 D7 A0 GLOSE 2.000 1 E VP DC 24 RCS LOOP FILL BOUNDARY VALVE 1 RC-NCV 15568 11715 CBM-093A 2 0F 3 D8 A0 GlosE 2.000 1 E VP DC 24 RCS LOOP FILL BOUNDARY VALVE
............................................................. ..... .... ... .... .... .... .... ... +... .... ....
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1-RC-NCV 1556C 11715-COM 093A 3 0F 3 D3 A0 GLOBE 2.000 1 E VP OC 24 RCS LOOP FILL BOUNDARY VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... )
1-RC-MOV 1535 11715 CBM-D938 1 0F 3 E4 No GATE 3.000 1 B EV C 03 0 03 ST C 03 0 03 VP DC 24 BLOCK VALVE FOR PRESSURIZER POWER OPERATED RELIEF VALVE 1-RC MOV 1536 11715 CBM-0938 1 or 3 04 MO GATE 3.000 1 B EV C 03 0 03 ST C 03 0 03 VP OC 24 BLOCK VALVE FOR PRESSURIZER POWER OPERATED RELIEF VALVE 1 RC PCV 1455C 11715 CBM-0938 1 0F 3 D3 A0 GLOSE 3.000 1 BC EV C CR 42 0 CR 42 FS C CR 42 SP 0 RR ,
ST C CR 42 !
O CR 42 l VP OC 24 '
PRESSURIZER POWER OPERATED PRESSURE CONTROL l VALVE DISCHARGE TO PRESSURIZER RELIEF TANK
) 1 RC-PCV 1456 11715 CBM-0938 1 0F 3 E3 A0 GLOSE 3.000 1 BC EV C CR 42 l s_/
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VIRGINIA POWER COMPANY PAGE: 50 OF 82 NORTH ANNA UNIT 1 CEVISION: 8
) SECOND INSERVICE TESTING INTERVAL DATE: D8/17/96
,,/ INSERVICE TESTING PROGRAM . VALVE TABLE 1
! NC i
' ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER WUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-1 RC PCV 1456 11715+CBM 093B 1 0F 3 E3 A0 GLOBE 3.000 1 BC EV 0 CR 42 FS C CR 42 SP O RR ST C CR 42 l 0 CR 42 VP OC 24 PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK 1 RC SOV.101A 1 11715-CBM-093A 3 0F 3 A5 SO GLOBE 1.000 1 B EV C CR 49 0 CR 49 FS C CR 49 ST C CR 49 0 CR 49 VP OC 24 REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY ,
1-RC-SOV-101A 2 11715-CBM 093A 3 0F 3 B5 $3 GLOBE 1.000 1 B EV C CR 49 i 0 CR 49
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t$ C CR 49 l
ST C CR 49 0 CR 49 p .............................................
VP OC 24 (s REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 1-RC SOV-101B 1 11715-CBM-093A 3 0F 3 A5 $0 GLOBE 1.000 1 B EV C CR 49 0 CR 49 FS C CR 49 ST C CR 49 0 CR 49 VP OC 24 REACTOR VESSEL VENT LINE ISOLATION VALVE 10 REFUELING CAVITY 1 RC-SOV 1018 2 11715-CBM-093A 3 0F 3 B5 SO GLOBE 1.000 1 B EV C CR 49 0 CR 49 j F5 C CR 49 l ST C CR 49 l 0 CR 49 VP OC 24 REACTOR VESSEL VENT LINE ISOLATION VALVE TO !
REFUELING CAVITY 1-RC-SV 15514 11715 CBM-0938 1 0F 3 E5 SAFETY VALVE 6.000 1 C $P O 60 PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 1 RC SV 1551B 11715-CBM-D93B 1 0F 3 E5 SAFETY VALVE 6.000 1 C SP 0 60 PRESSURIZER SAFETY VALVE, SV DISCHARGE T0 PCESSURIZER RELIEF TANK
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I 1 RC SV 1551C 11715-CBM-0938 10F 3 E6 SAFETY VALVE 6.000 1 C SP O 60
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VIRCINIA POWER COMPANY PAGE: 51 of 82 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/1T/96 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SWEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRED V- CSV RRV VCN-PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 1 RC TV 1519A 11715 CBM 0938 2 0F 3 D8 A0 GLOSE 3.000 2 A CIV EV C 03 FS C 03 LT C OPS I
ST C 03 VP OC 24 PRIMARY GRADE WATER SUPPLY TO PRT 82 RCP SEAL l STANDPIPES & FLUSH CONNECT, DUT CONT 150 VLV l
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VIRGIN!A POWER COMPANY PAGE: 52 of 82 NORTH ANNA UNIT 1 REVIS10N: 8
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[Q SECDNO INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM
- VALVE TABLE DATE: 08/17/98 NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER WUMBER WUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV- VCN-1 RM 007 11715 CBM-D94A 1 0F 2 E5 CHECK VALVE 10.000 2 C CV C RR 46 0 RR 46 "B" RNR PUMP DISCHARGE CHECK VALVE
............................~................................ ..... .... ... .... .... .... .... ... .... .... ....
1 RM-015 11715 CBM-094A 10F 2 E7 CHECK VALVE 10.000 2 C CV C RR 46 0 RR 46 n............................................
"A" RHR PUMP DISCHARGE CHECK VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 1 RH 036 11715 CBM 094A 2 0F 2 C4 MANUAL GATE 6.000 2 AE CIV LT C DPB 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 OPB j RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE -
TANK, OUTSIDE CONTAINMENT ISOLAT!DN VALVE
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1 RH-MOV 1700 11715-CBM-094A 1 0F 2 A5 M0 GATE 14.000 1 B EV 0 CS 18 ST 0 CS 18 ,
VP OC 24 1 RHR PUMP SUPPLY ISOLATION FROM "A" HOT LEG, ss _, INSIDE MIS $1LE BARRIER 1 RM MOV 1701 11715 CBM 094A 1 0F 2 A4 M0 GATE 14.000 1 B EV O CS 18 ST 0 CS 18 VP OC 24 RHR PUMP SUPPLY ISOLATION FKDM "A" HOT LEG, OUTSIDE MISSILE BARRIER 1 RH-MOV 1720A 11715-CBM-094A 2 0F 2 C3 M0 GATE 10.000 1 B EV 0 CS 18 ST 0 CS 18 s VP OC 24 i l
RHR RETURN ISOLATION TD "B" ACCUMULATOR DISCHARGE LINE 1 RH-MOV-17208 11715-CBM-094A 2 0F 2 B3 MO GATE 10.000 1 B EV 0 CS 18 ST 0 CS 18 VP OC 24 RHR RETURN ISOLATION 70 "C" ACCUMULATOR DISCHARGE LINE 1 RH RV 1721A 11715 CBM-D94A 1 0F 2 E6 RELIEF VALVE 3.000 2 C $P O 120 RHR SYSTEM RELIEF VALVE AT "A" RHR PUMP SUC-TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK 1 RH RV-17218 11715-CBM-094A 1 0F 2 E4 RELIEF VALVE 3.000 2 C SP 0 120 RHR SYSTEM RELIEF VALVE AT "B" RHR PUMP SUC-TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK l i
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VIRGINIA POWER COMPANY PAGE: 53 0F 82 NORTH ANNA UNIT 1 REylsl0N $
% SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 g ,jl INSERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER Coot TTPE SIZE CLAS CAT TTPE TYPE POS FRE0 V- CSV RRV. VCN-1 RM TV 100A 11715 CBM-082N 3 0F 3 C5 A0 GLOSE 1.000 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 VP OC 24 RETURN ISOLATION FROM AIR RADIATION MONITOR TO CONTAINMENT, OUTSIDE CONT ISOLATION VALVE 1 RM TV-1008 11715 CBM 082N 3 0F 3 D5 A0 GLOBE 1.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP DC 24 SUPPLY ISOL TO AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, OUTSIDE CONT ISOLATION VALVE 1 RM-TV-100C 11715 CBM 082N 3 0F 3 D4 A0 GLOBE 1.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24 SUPPLY ISOL TO AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, INSIDE CONT ISOLATION VALVE s
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s 1-RM-TV 1000 11715 CBM-082N 3 0F 3 c5 A0 GlosE 1.000 2 B EV C 03 f5 C 03 ST C 03 VP OC 24 RETURN ISOL FROM AIR RADIAil0N MONITOR TO CONTAINMENT, OUTSIDE CONT ISOLATION VALVE I
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r VIRGINIA POWER COMPANY PAGE: 54 0F 82
, s\ NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTlWG PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-1 RP 006 11715 CBM 088A 2 OF 4 C6 MANUAL. DIA 6.000 2 AE CIV LT C OPB REFLTLING PURIFICATION FROM REACTOR CAVITY TO RP PUMPS, INSIDE CONT ISOLATION VALVE 1 RP 008 11715-CBM-088A 2 0F 4 C4 MANUAL DIA 6.000 2 AE CIV LT C OPS REFUELING PURIFICATION FROM REACTOR CAVITY TO RP PUMPS, OUTSIDE CONT ISOLATION VALVE 1 RP-026 11715-CsM-088A 2 0F 4 C4 MANUAL DIA 6.000 2 AE CIV LT C OPB REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, OUTSIDE CONT !$0LATION VALVE 1-RP-028 11715 CBM 088A 2 0F 4 05 MANUAL DIA 6.000 2 AE CIV LT C OPB REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, INSIDE CONT ISOLATION VALVE l
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r VIRGIN!A POWER COMPANY PAGE: 55 of 82 NORTH ANNA' UNIT 1 -
REVISION: 8
/ -
SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-1 RS-018 11715-CBM 091A 4 0F 4 06 WL CHECK VLV 10.000 2 AC CIV CV C RR 21 0 RR 21 LT C DPB "A" OUTSIDE RECIRC SPRAY PUMP 1,NSIDE CONTAINMENT ISOLATION CHECK VALVE 1 RS 027 11715 CBM-091A 4 of 4 06 WL CHECK VLV 10.000 2 AC CIV CV C RR 21 0 RR 21 LT C OPB "B" OUTSIDE RECIRC SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 1 RS 123 11715-CBM-D918 1 0F 1 E7 CHECK VALVE 8.000 2 C CV 0 RR 33 "A" CASING COOLING PUMP DISCHARGE CHECK VALVE T0 A OUTSIDE RECIRC SPRAY PUMP SUCT 1 RS 138 11715 CBM 091B 1 0F 1 F7 CHECK VALVE 8.000 2 C CV 0 RR 33 "B" CASING COOLING PUMP DISCHARGE CHECK VALVE TO B DUTSIDE RECIRC SPRAY PUMP SUCT 1 RS-MOV-100A 11715 CBM-0918 1 0F 1 E7 M0 GATE 8.000 2 A CIV EV C 03
'e' 0 03
( LT C OPB ST C 03 0 03 VP DC 24 "A" CASING COOLING PUMP DISCHARGE ISOLATION To "A" OUTSIDE RECIRC SPRAY PUMP SUCTION 1-RS MOV 1005 11715 CBM-0915 1 0F 1 F7 M0 GATE 6.000 2 A CIV EV C 03 0 03 LT C OPB si C 03 0 03 VP OC 24 "B" CASING COOLING PUMP DISCHARGE ISOLATION To "B" OUTSIDE RECIRC SPRAY PUMP SUCTION
............................................................. ..... ..v. ... .... .... .... .... ... .... .... ....
1 RS-MOV-101A 11715 CBM 091B 10F 1 E7 MO GATE 6.000 3 A Civ EV C 03 0 03 1.T C OPB I ST C 03 0 03 VP OC 24 l .............................................
"A" CASING COOLING PUMP DISCHARGE ISOLATION TO "A" OUTSIDE RECIRC SPRAY PUMP SUCTION 1 RS-MOV 1015 11715-CBM-0915 1 0F 1 F7 M0 GATE 6.000 3 A clV EV C 03 0 03 LT C OPB ST C 03 0 03 p
VP OC 24
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VIRGINIA POWER COMPANY PAGE: 56 0F 82 e
f NORTH ANNA UNIT 1 REVIS!DN 8
( SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\s _ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-
"B" CASING COOLING PUMP DISCHARGE ISOLATION T0 "B" OUTSIDE RECIRC SPRAY PUMP SUCTION 1.RS MOV-155A 11715 CBM-091A 4 0F 4 B6 MO GATE 12.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 "A" OUTSIDE RECIRC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP & CASihG COOLING 1 RS-MOV 155B 11715-CBM 091A 4 0F 4 A6 M0 GATE 12.000 2 B EV C 03 0 03 ST C 03 0 03 VP OC 24 "B" OUTSIDE RECIRC SPRAY PUMP SUCTION !$0LAT VALVE FROM CONTAINMENT SUMP & CASING COOLING 1 RS MOV 156A 11715-CBM-091A 4 0F 4 05 No GATE 10.000 2 A CIV EV C 03 0 03 LT C DPB ST C 03 0 03
.L VP OC 24 ,
............................................. i "A" OUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO-LATION, OUTSIDE CONTAINMENT ISOLATION VALVE 1 RS Mov-1568 11715 CBM-091A 4 0F 4 05 MO GATE 10.000 2 A CIV EV C 03 0 03 LT C OPB ST C 03 0 03 VP OC 24 )
"B" DUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO-LATION, DUTSIDE CONTAINMENT ISOLATION VALVE
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VIRGINIA POWER COMPANT PAGE: 57 of 82 I NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM VALVE TABLE NC
( ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NLMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV RAV VCN-1 SA 002 11715 CSM 082F 10F 1 C7 MANUAL GATE 2.000 2 AE CIV LT C OPS SERVICE AIR SUPPLY 70 UNIT 1 CONTAINMENT, INSIDE CONTAINMENT ISOLATION VALVE 1 SA 029 11715 CBM-082F 1 OF 1 B7 MANUAL GLOBE 2.000 2 AE CIV LT C OPS SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j l
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VIRGINIA POWER COMPANY PAGE: 58 0F 82 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 INSERVICE TESTING PROGRAM - VALVE TABLE NC N~' ISO REL CS RR ALT VALVC DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS IREO V- CSV RRV VCN-1 51 001 11715 CbM 096A 1 of 3 BT CHECK VALVE 12.000 2 C CV O RR 37 "A" LOW HEAD SI PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1 SI-004 11715 CBM 096A 1 0F 3 C7 CHECK VALVE .750 2 AC CV C RR 17 i
LT C 24 l
"A" LOW HEAD $1 PUMP SEAL WATER SUPPLY CHECK VALVE FROM RWST 1 ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
l 1 81 009 11715 CBM-096A 2 0F 3 56 CHECK VALVE 10.000 2 C CV C RR 7 0 RR 7 "A" LOW siEAD $1 PUMP DISCHARGE CHECK VALVE l
I 1 SI 012 11715-CBM-096A 2 0F 3 B5 CHECK VALVE 2.000 2 C CV o 03 "A" LOW HEAD $1 PUMP MINIMUM FLOW / TEST LINE l DISCHARGE CHECK VALVE 1-51 016 11715-CBM 096A 1 0F 3 B5 CHECK VALVE 12.000 2 C CV O RR 37 "B" LOW HEAD $1 PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 1 $1 018 11715 CBM-096A 1 0F 3 B3 CHECK VALVE 12.000 2 C CV 0 RR 7
(%- RWST SUPPLY CHECK VALVE TO "B" LOW HEAD St PUMP SUCTION 1 SI 021 11715-CBM-096A 1 0F 3 C5 CHECK VALVE .750 2 AC CV C RR 17 LT C 24 l
"B" LOW HEAD $1 PUMP SEAL WATER SUPPLY CHECK VALVE I 1 $1 026 11715 CBM 096A 2 0F 3 B4 CHECK VALVE 10.000 2 C CV C RR 7 0 RR 7 j "B" LOW HEAD $1 PUMP DISCHARGE CHECK VALVE i 1-$1-029 11715-CBM-096A 2 0F 3 B4 CHECK VALVE 2.000 2 C CV 0 03 "B" LOW HEAD $1 PUMP MINIMUM FLOW / TEST LINE DISCHARGE CHECK VALVE 1-SI-047 11715-CBM-096A 10F 3 E5 CHECK VALVE 8.000 2 AC CV C RR 8 0 RR 8 PD CS LT C 24 75 I
RWST SUPPLY CHECK VALVE TO CHARGING PUMP l SUCTION HEADER 1 51 D58 11715-CBM-096A 1 0F 3 E7 MANUAL GLOBE 1.000 2 AE CIV LT C OPB
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VIRGINIA POWER COMPANY PAGE: 59 0F 82
~~ NORTH ANNA UNIT 1 REVISION: 8 l [ ) SECOND INSERVICE TESTING INTERVAL DATE: D8/17/96
\s_,f INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-ACCUMULATOR MAKEUP LINE, OUTSIDE CONTAlWMENT ISOLATION VALVE 1 51 066 11715-CDM-D96A 3 0F 3 D4 CHECK VALVE 1.000 2 C CV C RR 25 BORON INJECTION TANK SUPPLY CHECK VALVE FROM BORIC ACID TRANSFER PUMPS 1 51 077 11715 CBM-0964 3 0F 3 F7 MANUAL GLOSE 1.000 2 AE CIV LT C OP8 BORON INJECTION TANK BYPASS LINE ISOLATION VALVE - TO RCS COLD LEG 1 SI 079 11715-CBM 0968 4 0F 4 E3 CHECK VALVE 3.000 2 AC CIV CV C RR 12 0 RR 43 12 LT C OPB HIGH HEAD S1 FROM CHARGING PUMPS 10 RCS COLD LEGS, INSIDE CONT ISOLATION CHECK VALVE 1 51 083 11715-CBM-0968 4 0F 4 F8 CHECK VALVE 6.000 1 AC P!V CV C RR 10 0 RR 41 10 LT C 24 "A" RCS COLD LEG SI ADMISSION CHECK VALVE (s_ ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1 51-086 11715 CBM-D968 4 0F 4 E8 CHECK VALVE 6.000 1 AC PIV CV C RR 10 0 RR 41 10 LT C 24 "B" RCS COLD LEG $1 ADMIS$10N CHECK VALVE 1 51 089 11715 CBM 0968 4 0F 4 08 CHECK VALVE 6.000 1 AC PIV CV C RR 10 0 RR 41 10 LT C 24 "C" RCS COLD LEG $1 ADMISSION CHECK VALVE 1 SI-090 11715-CBM-0968 4 0F 4 C3 CHECK VALVE 3.000 1 AC CIV CV C RR 12 0 RR 43 12 LT C OPB HIGH HEAD St FROM CHARGING PUMPS TO RCS NOT LEGS, INSIDE CONT ISOLATION CHECK VALVE 1-51 095 11715-CBM 0968 4 0F 4 D8 CHECK VALVE 6.000 1 C CV C RR 12 0 RR 43 12 "B" RCS NOT LEG $1 ADMISSION CHECK VALVE 1-51 D99 11715-CBM-0968 4 0F 4 CB CHECK VALVE 6.000 1 C CV C RR 12 0 RR 43 12 "A" RCS HOT LEG SI ADMIS$10N CHECK VALVE
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VIRGINIA POWER COMPANY PAGE: 60 0F 82 WORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
"*N INSERVICE TESTING PROGRAM - VALVE TABLE
/ \
k NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $1ZE CLAS CAT TYPE TYPE POS FREO V- CSV RRV- VCN-4 51 103 11715 CBM-D968 4 0F 4 88 CHECK VALVE 6.000 1 C CV C RR 12 0 RR 43 12 "C" RCS HOT LEG SI ADMISSION CHECK VALVE l 1 $1-106 11715-CBM-0968 1 0F 4 F4 CHECK VALVE 1.000 2 AC Civ CV C RR 9 LT C OPS NITROGEN SUPPLY TO ACCUMULATOR $, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1 51 110 11715-CBN 0968 1 0F 4 D4 CHECK VALVE 1.000 2 AC Civ CV C RR 9 LT C DPB l .............................................
ACCUMULATOR MAKE UP LINE, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1 51 125 11715-CBM 0968 10F 4 B7 CHECK VALVE 12.000 1 C CV 0 RR 42 11 i
"A" ACCUMULATOR DISCHARGE CHECK VALVE 1 51 127 11715-CBM-0968 10F 4 88 CHECK VALVE 12.000 1 C CV C RR 11 0 RR 42 11 "A" ACCUMULATOR COLD LEC ADMIS$10N CHECK A VALVE (N- ..........,.............................. ................... ..... .... ... .... .... .... .... ... .... .... ....
s 1 51-142 11715 CBM-0968 2 0F 4 B5 CHECK VALVE 12.000 1 C CV 0 RR 42 11 l
"B" ACCUMULATOR DISCHARGE CHECK VALVE l
1-SI 1L4 11715-CBM-0968 2 0F 4 B7 CHECK VALVE 12.000 1 C CV C RR 11 1
0 RR 42 11 l "B" ACCUMULATOR COLD LEG ADMIS$10N CHECK VALVE l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1 81 159 11715 CBM 096B 3 0F 4 85 CHECK VALVE 12.000 1 C CV 0 RR 42 11
- C" ADCUMULATOR DISCHAEGE CHECK VALVE 1 51 161 11715 CBM 0968 3 0F 4 B7 CHECK VALVE 12.000 1 C CV C RR 11 0 RR 42 11 l "C" ACCUMULATOP COLD LEG ADMISSION CHECK l
VALVE 1 51 185 11715 CBM-0968 4 0F 4 F3 CHECK VALVE 3.000 2 AC Civ CV C RR 12 0 RR 43 12 LT C DPB HIGH HEAD S1 FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT ISOLATION CHECK VALVE 1-51 190 11715 CBM 0968 4 OF 4 F7 CHECK VALVE 2.000 1 C CV C RR 13 0 RR 13 O \
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VIRGINIA POWER COMPANY PAGE: 61 0F 82 )
NORTH ANNA UNIT 1 REVISION: 8 '
SEconD INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE
'(,,~~~) NC l x~. ' !$0 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-l .............................................
l HIGH HEAD SI TO "A" RCS COLD LEG, INSIDE MIS $1LE BARRIER CHECK VALVE 1 SI 192 11715-CBM 0968 4 0F 4 E7 CHECK VALVE 2.000 1 C CV C RR 13 0 RR 13 HIGH HEAD St TD "B" RCS COLD LEG, INSIDE MIS $1LE BARRIER CHECK VALVE 1 51 194 11715 CBM-0968 4 0F 4 D7 CHECK VALVE 2.000 1 C CV C RR 13 0 RR 13 HIGH HEAD $1 TO "C" RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE 1-sI 195 11715 CBM-0968 4 0F 4 F6 CHECK VALVE 6.000 1 AC C&P CV C RR 10 0 RR 41 10 LT C 24 LOW HEAD $1 TO "A" RCS COLD LEG, INSIDE CON-TAINMENT !$0LAT10N CHECK VALVE 1 51 197 11715 CBM-0968 4 OF 4 E6 CHECK VALVE 6.000 1 AC C&P CV C RR 10 0 RR 41 10 LT C 24 LOW HEAD St TO 5 RCS COLD LEG, INSIDE CON-TAINNENT ISOLATION CHECK VALVE
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1 $1 199 11715-CBM 0968 4 0F 4 D6 CHECK VALVE 6.000 1 AC C&P CV C RR 10 0 RR 41 10 LT C 24 LOW HEAD $1 To "C" RCS COLD LEG, INSIDE CON-TAINMENT ISOLATION CHECK VALVE 1 $1 201 11715 CBM 0968 4 0F 4 03 CHECK VALVE 3.000 1 AC Civ CV C RR 12 l 0 RR 43 12 LT C OPS HIGH HEAD SI FROM CHARGING PUMPS TO RCS NOT LEGS, INSIDE CONT ISOLATION CHECK VALVE 1 51 206 11715 CBM 0968 4 0F 4 B3 CHECK VALVE 6.000 2 AC CIV CV C RR 12 0 RR 43 12 LT C OPB LOW HEAD St FROM "A" LMSI PUMP TO RCS HOT LEGS, INSIDE CONT ISOLATION CHECK VALVE 1 SI 207 11715 CBM 0968 4 0F 4 B3 CHECK VALVE 6.000 2 AC Civ CV C RR 12 0 RR 43 12 LT C OPS LOW HEAD $1 FROM "B" LHS! PUMP TO RCS HOT LEGS, INSIDE CONT ISOLATION CHECK VALVE 1-51 2D9 11715 CBM 0968 4 0F 4 C7 CHECK VALVE 6.000 1 C CV C RR 12 0 RR 43 12
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VIRGINIA POWER COMPANY PAGE: 62 0F 82 NORTH ANNA UNIT 1 REvls10N: 8 SEf:0ND INSERVICE TESTING INTERVAL DATE: 08/17/98
% INSERVICE TESTING PROGRAM + VALVE TABLE
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\j NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV. RRV VCN-LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO A RCS NOT LEG 1 81 211 11715 CBM 0968 4 0F 4 C7 CHECK VALVE 6.000 1 C CV C RR 12 0 RR 43 12 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO B PCS NOT LEG 1 81 213 11715-CBM-0968 4 OF 4 57 CHECK YALVE 6.000 1 C CV C RR 12 0 RR 43 12 l
l LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO C RCS NOT LEG 1 SI HCV*1936 11715 CBM-0968 1 0F 4 E5 A0 GATE 1.000 2 A CIV EV C 03 1 1
FS C 03 '
LT C OPS i
ST C 03 l
VP OC 24 WASTE GAS FROM ACCUMULATORS TO CHARCOAL FILTERS 1 SI MOV 1836 11715-CBM-096A 3 0F 3 C8 M0 GATE 3.000 2 A CIV EV C CS 23 0 CS 23 !
m s LT C OPS j ST C CS 23 V 0 CS 23 l VP OC 24 I HIGH HEAD $1 FROM CHARGlWG HEADER TO RCS COLD LECS, OUTE10E CONTAINMENT ISOLATION VALVE l 1 51 MOV 1860A 11715-CBM-096A 1 0F 3 BT M0 GATE 12.000 2 8 EV C 03 0 03 l ST C 03 0 03 VP OC 24 "A" LOW HEAD St PUMP SUCTION ISQLATION FROM CONTAINMENT SUMP 1-SI MOV-1860B 11715 CBM-096A 1 0F 3 B5 MO CATE 12.000 2 B EV C 03 0 03 ST C 03 0 03 VP OC 24 "B" LOW HEAD St PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP I 1 St MOV 1862A 11715 CBM-096A 1 0F 3 A3 MO GATE 12.000 2 8 EV C 03 l
ST C 03 i VP OC 24 "A" LOW HEAD SI PUMP SUCTION FROM RWST 1 SI MOV 18628 11715-CBM 096A 1 0F 3 B3 MO GATE 12.000 2 B EV C 03 (A) v
VIRGINIA POWER COMPANY PAGE: 63 0F E2 NORTH ANNA UNIT 1 REVISION! 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE V NC 150 REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV. VCN-1-St-MOV 18625 11715-CBM 096A '1 0F 3 53 M0 GATE 12.000 2 B ST C 03 VP DC 24 "B" LOW HEAD St PUMP SUCTION FROM RWST
......................................s...................... ..... .... ... .... .... .... .... ... .... .... ....
1 SI MOV 1863A 11715 CBM-096A 2 0F 3 C5 MO GATE 8.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24
! "A" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 1 SI MOV-18635 11715 CBM 096A 2 0F 3 D4 No GATE 8.000 2 B EV C 03 0 D3 ST C 03 0 03 VP OC 24 "B" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 1-$1-MOV 1864A 11715 CBM-D96A 2 0F 3 C7 M0 GATE 10.000 2 B EV C 03 0 03 ST C 03 g 0 03
) VP OC 24 s, ,/ .............................................
"A" LOW HEAD $1 PUMP COLD LEG DISCHARGE STOP VALVE 1-SI MOV 18645 11715 CBM-096A 2 0F 3 C6 MO GATE 10.000 2 B EV C 03 0 03 ST C 03 0 03 l VP DC 24 "B" LOW HEAD St PUMP COLD LEC DISCHARGE STOP VALVE 1 SI-MOV 1865A 11715-CBM-0968 10F 4 C7 N0 GATE 12.000 2 B EV C CS 24 0 CS 24 ST C CS 24 0 CS 24 VP OC 24 "A" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG l ............................... ............................. ..... .... ... .... .... .... .... ... .... .... ....
1-St MOV 18658 11715 CBM-0968 2 0F 4 c5 Mo GATE 12.000 2 B EV C <CS 24 0 CS 24 ST C CS 24 1 0 I CS 24 l VP DC 24 1 .............................................
l *B" ACCUMULATOR DISCHARGE ISOLATION VALVE TO l RCS COLD LEG 1-SI-MOV 1865C 11715 CBM-0968 3 0F 4 c5 M0 GATE 12.000 2 B EV C CS 24 l /N
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l VIRGINIA POWER COMPANY PAGE: 64 0F 82 i
r"~wg NORTH ANNA UNIT 1 REVISION: 8 i
( SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM . VALVE TABLE DATE: 06/17/96 NC 150 REL CS RR ALT l VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST l MUMBER WUMBER WUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-1 SI MOV 1865C 11715-CBM-D968 3 0F 4 C5 M0 GATE 12.000 2 B EV 0 CS 24 ST C CS 24 0 CS 24 VP DC 24 "C" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 1 SI MOV-1867A 11715 CBM-D96A 3 0F 3 D4 M0 GATE 3.000 2 B EV C RR 25 0 RR 25 l ST C RR 25 l 0 RR 25
! VP DC 24 BORON INJECTION TANK HlCH HEAD $1 INLET VALVE 1-SI-MOV 1867B 11715-CBM-D96A 3 0F 3 D4 M0 GATE 3.000 2 B EV C RR 25 1
0 RR 25 ST C RR 25 0 RR 25 VP DC 24 BORON INJECTION TAWK HIGH HEAD $1 INLET VALVE fr*~g ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
( ) 1-SI MOV 1867C 11715 CBM 096A 3 0F 3 E7 M0 GATE 3.000 2 A CIV EV C 03 l \_/ 0 03 LT C OPS ST C 03 0 03 VP DC 24 BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI MOV 1867D 11715 CBM 096A 3 0F 3 07 No GATE 3.000 2 A Civ EV C 03 0 03 LT C DPS ST C h3 0 03 VP OC 24 BORON INJECTION TANK DUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI-MOV-1669A 11715-CBM-096A 3 0F 3 C8 M0 GATE 3.000 2 A CIV EV C CS 23 0 CS 23 LT C DPB ST C CS 23 l
0 CS 23 VP OC 24 HIGH HEAD $1 FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLAfl0N VALVE 1 SI MOV 18698 11715 CBM-0964 3 or 3 88 M0 GATE 3.000 2 A CIV EV C CS 23 J 0 CS 23 l LT C OPB
( 0 CS 23 s
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VIRGIN!A POWER COMPANY PAGE: 65 0F 82 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96
.., INSERVICE TESTING PROGRAM . VALVE TABLE NC x- ISO REL CB RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST RED JUST JUST TEST NUMBER' NUMBER NUMBER C00R TYPE $!2E CLAS CAT TYPE TYPE P05 FREO V.
CSV RRV VCN-1 SI Mov 1869B 11715-CBM 096A 3 0F 3 88 MO GATE 3.000 2 A CIV VP OC 24 HIGH HEAD $1 FROM CHARGING HEADER TO RCS NOT LEGS, QUTSIDE CONTAINMENT ISOLAT10N VALVE 1 SI-MOV 1885A 11715 CBM-D96A 2 0F 3 C3 M0 GLOBE 2.000 2 A EV C 03 LT C 24 75 ST C 03 VP DC 24 "A" LOW MEAD SI PUMP MIN! MUM FLOW / TEST LINE ISOLATl0N 1 SI Mov 18855 11715 CBM D96A 2 0F 3 53 M0 CLDBE 2.000 2 A EV C 03 LT C 24 75 ST C 03 VP DC 24 "B" LOW HEAD $1 PUMP MINIMUM FLOW / TEST LINE ISOLATION 1 SI MOV 1885C 11715-CBM-096A 2 0F 3 D3 M0 CLOBE 2.000 2 A EV C 03 LT C 24 75 ST C 03 VP DC 24 "A" LOW NEAD SI PUMP MINIMUM FLOW / TEST LINE ISOLAfl0N f-g ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
} 1 $1 MOV 18850 11715 CBM-096A 2 0F 3 B3 MO GLOBE 2.000 2 A EV C 03
(./ LT C 24 75 ST C 03 VP DC 24 "B" LOW HEAD S1 PUMP MINIMUM FLOW / TEST LINE ISOLATION 1 51 Mov 1890A 11715 CBM 096A 2 0F 3 D7 MO GATE 10.000 2 A CIV EV C CS 23 0 CS 23 LT C OPB ST C CS 23 0 CS 23 VP OC 24 l "A" LOW HEAD $1 PUMP HOT LEG DISCHARGE STOP VALVE, DUTS!DE CONTAINMENT ISOLATION VALVE 1 SI-MOV 1890B 11715-CBM 096A 2 0F 3 D7 M0 GATE 10.000 2 A CIV EV C CS 23 0 CS 23 LT C DPB ST C CS 23 0 CS 23 VP DC 24 "B" LOW HEAD SI PUMP HOT LEG DISCHARGE STOP VALVE, DUTSIDE CONTAINMENT ISOLATION VALVE 1 St MOV 1890C 11715 CBM 096A 2 or 3 C8 No GATE 10.000 2 A CIV EV C 03 0 03 LT C DPB ST C 03 (r-~~
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VIRGIN!A POWER COMPANY PAGE: 66 0F 82 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 03/17/98
- f. INSERVICE TESTING PROGRAM VALVE TABLE a
\'",, NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NLMBER COOR TYPE $1ZE CLAS CAT TYPE TYPE POS FREO V- CSV REV VCN-1 SI MOV 1890C 11715-CBM-0964 2 0F 3 C8 No GATE 10.000 2 A CIV ST C 03 I VP DC 24 l LOW HEAD $1 PUMPS COLD LEG DISCHARGE STOP l VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI-MOV 1890D 11715-CBM-096A 2 0F 3 C7 M0 GATE 10.000 2 A Civ EV C 03 0 03 LT C DPB ST C 03 0 03 VP DC 24 LOW NEAD SI PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI RV 104 11715 CBM-096A 2 0F 3 F5 RELIEF VALVE 3 C SP O 120 CONTAINMENT PENETRATION 106 RELIEF VALVE 1 SI RV-1845A 11715 CBM 096A 2 0F 3 D6 RELIEF VALVE .750 2 C SP 0 120 "A" LOW HEAD S1 PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 1 SI RV 1845B 11715-CBM-096A 2 0F 3 C7 RELIEF VALVE .750 2 C SP O 120 !
(,._ ) LOW HEAD SI HEADER TO COLD LEG RELIEF VALVE, '
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/ RV DISCHARGE TO SAFEGUARDS AREA SUMP ,
l 1 SI RV 1845C 11715 CBM 096A 2 0F 3 C6 RELIEF VALVE .750 2 C SP 0 120 "B" LOW HEAD SI PUMP DISCHARGE RELIEF VALVE, i RV DISCHARGE TO SAFEGUARDS AREA SUMP
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 1 SI RV 1857 11715 CBM 096A 3 0F 3 D7 RELIEF VALVE .750 2 C SP O 120 BORON INJECTION TANK RELIEF VALVE, RV DISCHARGE TO FLOOR DRAIN 1 51-RV 1858A 11715 CBM 0968 1 0F 4 07 RELIEF VALVE 1.000 2 C SP 0 120 "A" ACCUMULATOR RELIEF VALVE 1 SI RV-18588 ti715 CBM-0968 2 0F 4 05 RELIEF VALVE 1.000 2 C SP O 120 "B" ACCUMULATOR RELIEF VALVE 1 SI RV 1858C 11715 CBM-0968 3 0F 4 D5 RELIEF VALVE 1.000 2 C SP O 120 l
I "C" ACCUMULATOR RELIEF VALVE 1 $1 TV 100 11715 CBM-0968 1 0F 4 F3 A0 CLDBE 1.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 p
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VIRGINIA POWER COMPANY PAGE: 67 0F 82 NORTN ANNA Uk!T 1 . REVis10Nt 8
/ SECOND INSERVICE TESTING INTERVAL
' DATE: D8/17/98 INSERVICE TESTING PROGRAM VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUM8ER NUMBER NUMBER CDOR TTPE $!ZE CLAS CAT TYPE TYPE POS FRED V- CSV RRV- VCN-N!TROGEN SUPPLY TO ACCUMULATORS, OUTSIDE CONTAINMENT ISOLATION VALVE 1 81 TV 101 11715-CBM 0968 1 0F 4 E4 A0 GLOSE -
1.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP DC 24 J
ACCUMULATORS TO WASTE GAS CHARCOAL FILTERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI TV 1842 11715-CBM-D968 1 0F 4 D4 A0 GLDBE .750 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP DC 24 ACCUMULATOR TEST LINE, INSIDE CONTAlWMENT ISOLATION VALVE 1 SI TV-1859 11715 CBM-096A 2 0F 3 F7 A0 GLOBE .750 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 OC 24 (O,,,
VP ACCUMULATOR TEST LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI TV 1884A 11715-CBM 096A 3 0F 3 E4 A0 GLOBE 1.000 2 B EV C 03 FS C 03 ST C 03 VP DC 24 BORON INJECTION TANK RETURN ISOLATION TO BORIC ACID STORAGE TANK 1 51 TV 18840 11715 CBM-0964 3 0F 3 E4 A0 GLOBE 1.000 2 B EV C 03 FS C 03 ST C 03 VP DC 24 BORDN INJECTION TANK RETURN ISOLATION TO BORIC ACID STORAGE TANK 1 81 TV-1884C 11715-CBM-D96A 3 0F 3 04 A0 GLOBE 1.000 3 B EV C 03 FS C 03 ST C 03 VP DC 24 BORON INJECT 10N TANK SUPPLY ISOLATION FROM BORIC ACID TRANSFER PUMPS
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l VIRGINIA POWER COMPANT PAGE: 68 0F 82 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
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INSERVICE TESTING PROGRAM VALVE TABLE k
VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST WUMBER NUMBER WUMBER COOR TTPE SIZE CLAS CAT TTPE TTPE PDS FRE0 v. CSV RRV VCN-1 SS TV 100A 11715 CBM-089D 1 0F 1 F6 A0 GLOBE .375 1 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 PRESSURIZER LIQUID SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 1 SS-TV 1DDB 11715-CBM-089D 1 0F 1 F5 A0 GLOBE .375 1 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP DC 24 PRESSURIZER LIDUID SPACE SAMPLE LINE, OUTSIDE CONTAINMENT !$0LATION VALVE 1 SS TV 101A 11715-CBM 0890 1 0F 1 E6 A0 GLDBE .375 1 A CIV EV C 03 FS C 03 l LT C OPB ST C 03 j VP DC 24 PRESSURIZER VAPOR SPACE SAMPLE LINE, INSIDE CONTAIMMENT ISOLAT!DN VALVE l
$< 1-SS TV 1018 11715 CBM 089D 1 0F 1 E5 A0 GLDBE .375 1 A CIV EV C 03 FS C 03
- s. LT C OPS ST C 03 VP OC 24 PRESSURIZER VAPOR SPACE SAMPLE LINE, DUTSIDE CONTAINMENT ISOLATION VALVE ,
1 SS TV 102A 11715-CBM-0890 1 0F 1 D6 So GLOBE .375 1 A CIV EV C 03 I FS C 03 l LT C DPB ST C 03 VP OC 24 REACTDR COOLANT COLD LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATIDN VALVE j ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
l 1 SS-TV 1028 11715-CBM 089D 1 0F 1 D5 So CLDBE .375 1 A CIV EV C 03 l FS C 03 LT C DPB ST C 03 VP DC 24 REACTOR CDOLANT COLD LEGS SAMPLE HEADER, DUTSIDE CONTAINMENT ISOLATIDW VALVE 1 SS TV 103A 11715 CBM 089D 1 0F 1 F6' SO GLDBE .375 2 AE CIV LT C OPB VP DC 24 RHR SAMPLE HEADER, INSIDE CONTAINMENT ISOLA-l TIDN VALVE l
1-SS-TV-103B 11715 CBM-0890 1 0F 1 F5 SO GLOBE .375 2 AE Civ LT C DPB
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VIRGINIA POWER COMPANT PAGE: 69 0F 82 NORTN ANNA UNIT 1 REVISIDW: 8
('~) SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
( ,/ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME QM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TTPE SIZE CLAS CAT TTPE TTPE PDS FREQ V- CSV RAV VCN-1 SS TV 1035 11715 CBM 089D 1 0F 1 F5 So GLOBE .375 2 AE CIV VP OC 24 RNR SAMPLE HEADER, OUTSIDE CONTAINMENT ISOLA-TION VALVE 1 SS TV-104A 11715 CBM 089D 1 0F 1 C6 A0 GLOBE .375 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 VP DC 24 PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 1 SS TV 104B 11715 CBM-089D 1 0F 1 C5 A0 GLOBE .375 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SS TV 106A 11715 CBM-089D 1 0F 1 E6 So GLOBE .375 1 A CIV EV C 03 i FS C 03 LT O ST C
C OPB 03 VP OC 24 i l )
REACTOR COOLANT HOT LEGS SAMPLE HEADER, l INSIDE CONTAINMENT ISOLATION VALVE j ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
I 1 SS TV-1D6B 11715 CBM-089D 1 0F 1 E5 SO GLOBE .375 1 A CIV EV C 03 I FS C 03 LT C OPB ST C 03 VP OC 24 REACTOR COOLANT NOT LEGS SAMPLE HEADER, OUT-SIDE CONTAINMENT ISOLATION VALVE 1 SS TV 112A 11715 CBM-0898 3 0F 4 D3 A0 GLOBE .375 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 STEAM GENERATORS SAMPLE HEADER, INSIDE CON-TAINENT ISOLATION VALVE 1 55 TV 1128 11715 CBM 0898 3 0F 4 C3 A0 GLOBE
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.375 2 A CIV EV C 03 j FS C 03 1 l LT C DPB ST C 03 i VP OC 24 l STEAM GENERATORS SAMPLE NEADER, OUTSIDE CON-TAINMENT ISOLATION VALVE a
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l l VIRGINIA POWER DOMPANY PAGE: 70 0F B2 NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 i
INSERVICE TESTING PROGRAM a VALVE TABLE
( NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE $12E CLAS CAT TYPE TYPE POS FREO V- CSV RRV VCN-1 SV TV-102 1 11715 CBM 072A 2 0F 3 C3 A0 GLOBE 6.000 2 5 EV C 03 FS C 03 ST C 03 VP DC 24 CONDENSER AIR REMOVAL DISCHARG TO CONTAIN-MENT, OUTS!DE CONTAIN ISOLATION VALVE 1 SV-TV-103 11715-CBM-072A 2 0F 3 D3 A0 GLOBE 6.000 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 VP DC 24 CONDENSER AIR REMOVAL DISCHARGE TO CONTAIN-MENT, OUTSIDE CONTAINMENT ISOLATION VALVE i
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VIRGINIA POWER COMPANY PAGE: 71 0F 82 n NORTH ANNA UNIT 1 REVISION: 8
/ \
SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
/ INSERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $1ZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-1 SW 0003 11715 CBM-078A 3 0F 4 D7 CHECK VALVE 20.000 3 C CV C RR 19 0 RR 19 P0 03 UNIT 1 "A" SERVICE WATER PUMP DISCHARGE CHECK VALVE 1 SW-0010 11715-CBM-078A 3 0F 4 D6 CHECK VALVE 20.000 3 C CV C RR 19 0 RR 19 PO 03 UNIT 1 "B" SERVICE WATER PUMP DISCHARGE CHECK VALVE IfSW-0022 11715-CBM-078A 1 0F 4 C3 CHECK VALVE 24.000 3 C CV C 03 0 RR 24 PO 03 UNIT 1 AUXILIARY SERVICE WATER PUMP DISCHARGE CHECK VALVE 1 SW-0114 11715 CBM-0788 1 0F 4 F8 CHECK VALVE 24.000 3 C CV 0 RR 14 "A" SERVICE WATR HEADER SUPPLY CHECK VALVE TO RECIRC SPRAY HX UPSTREAM OF CROSS CONNECT
[m\ 1-SW-0116 11715 CBM-0788 1 0F 4 F8 CHECK VALVE 24.000 3 C CV O RR 14 x.~
"B" SERVICE WATR HEADER SUPPLY CHECK VALVE TO RECIRC SPRAY HX UPSTREAM OF CROSS CONNECT 1 SW 0120 11715-CBM 0788 1 0F 4 E3 CHECK VALVE 16.000 2 C CV 0 RR 14 "A" REClRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE 1 SW-0130 11715 CsM-078s 10F 4 E4 CHECK VALVE 16.000 2 C CV 0 RR 14 "B" RECIRC SPRAY HEAT EXCHANGER SERVICE WATEN SUPPLY CHECK VALVE 1 SW 0140 11715-CBM-0788 1 0F 4 F6 CHECK VALVE 16.000 2 C CV O RR 14 "C" RECIRC SP:nY HEAT EXCHANGER SERVICE WATER SUPPLY CrIECK VALVE 1 SW-0150 11715 C8M 0788 1 0F 4 E7 CHECK VALVE 16.000 2 C CV 0 RR 14 "D" RECIRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE 1 SW-0252 11715-CBM-078C 2 0F 2 88 CHECK VALVE 4.000 3 C CV 0 03 SERVICE WATER SUPPLY CHECK VALVE 1 SW-020 11715 CBM-078C 2 0F 2 B8 CHECK VALVE 4.000 3 C CV 0 03 SERVICE WATER SUPPLY CHECK VALVE
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1 1
VIRGINIA POWER COMPANY p)
V NORTH ANNA UNIT 1 SECOND INSERVICE TESTING INTERVAL PAGE: 72 0F 82 REVISION: 8 DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-1 SW 0630 11715-COM-078G 1 0F 2 E8 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 P0 03 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE CIL COOLER CHECK VALVE 1 SW 0631 11715-CBM-078G 10F 2 E7 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE CIL COOLER CHECK VALVE 1 SW-0641 11715 C8M-078G 1 0F 2 E6 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 1 SW-0644 11715-CBM 078G 1 OF 2 E7 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 N SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE
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1 SW-0647 11715 CBM-078G 10F 2 E6 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 SERVICE WATER SUPPLY TO CHARGlWG PUMP LUBE OIL COOLER CHECK VALVE 1 SW-0648 11715-CBM-078C 1 0F 2 E6 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE CIL COOLER CHECK VALVE 1-SW-0658 11715-CBM 078G 1 0F 2 E5 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 1
SERVICE WATER SUPPLY TO CHARGING PUMP 1 SEAL COOLER CHECK VALVE 1 SW-0661 11715 CBM 078G 10F 2 E5 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PD 03 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 1 SW-0664 11715 CBM 078G 1 0F 2 E4 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 m
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r-VIRGIN!A POWER COMPANY PAGEr 73 0F 82 NORTH ANNA UNIT 1 REVIS10N: 8 SECOND INSERVICE TESTING INTERVAL DATE: 02/25/99 INSERVICE TESTING PROGRAM - VALVE TABLE
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NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $12E CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN*
SERVICE WATER SUPPLY TO CHARGING PUMP LUBE DIL COOLER CHECK VALVE 1*SW 0665 11715 CBM 078G 10F 2 E4 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE 0!L COOLER CHECK VALVE 1 SW-0686 11715 CBM-078G 1 0F 2 E3 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 j PO 03 j SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 1-SW-D689 11715 CBM-078G 1 0F 2 E3 CHECK VALVE 2.000 3 C CV C RR 76 0 RR 76 PO 03 1 SERVICE WATER SUPPLY TO CHARGING PUMP j SEAL COOLER CHECK VALVE i 1-SW 1067 11715 CBM 078A 3 0F 4 E7 MANUAL GATE 1.000 3 B EV C RR 26 SERVICE WATER CHEMICAL ADDITION SYSTEM i
( N.
MANUAL ISOLATION VALVE
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1 SW-1070 11715-CBM 0784 3 0F 4 F7 MANUAL GATE 1.000 3 B EV C RR 26 est SERVICE WATER CHEM ADDITION SYSTEM MANUAL ,
ISOLATION VALVE gg q_,
1 SW 1139 11715 CBN 07BA 3 0F 4 E7 MANUAL GATE 1.500 B EV C RR 26 SERVICE WATER CHEM ADDIT!DN SYSTEM MANUAL ISOLAT10N VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 1 SW MOV 101A 11715 CBM 07BA 4 0F 4 B3 M0 BFLY 24.000 3 B EV 0 CS 34 ST 0 CS 34 VP DC 24
- A" SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC $ PRAY HEAT EXCHANGERS 1 $W-MOV 101B 11715-CBM 078A 4 0F 4 B3 M0 BFLY 24.000 3 B EV 0 CS 34 ST 0 CS 34 VP OC 24 "A" SERVICE WATER HEADER SUPPLY !$0LAfl0N TO RECIRC SPRAY MEAT EXCHANGERS 1 SW-MOV-101C 11715 CBM 07BA 4 0F 4 B3 M0 BFLY 24.000 3 B EV 0 CS 34 ST 0 CS 34 VP DC 24 "B" SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS x .
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VIRGINIA POWER COMPANY PAGE: 74 0F 82 s-~~ NORTH ANNA UNIT 1 REVISION: 8
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SECOND INSERVICE TESTING IN1ERVAL DATE: 08/17/96 INSERVICE TESTING PROGRAM - VALVE TABLE NC b 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST l NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-l
( 1 SW-MOV 101D 11715-CBM 078A 4 0F 4 C3 Mo BFLY 24.000 3 B EV 0 CS 34 ST 0 CS 34 VP OC 24 I "B" SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1 SW-MOV 102A 11715 CBM-0788 1 0F 4 F8 M0 BFLY 24.000 3 B EV C 03 ST C 03 VP DC 24 SERVICE WATER SUPPLY CROSS CONNECTS To RECIRC SPRAY HEAT EXCHANGERS 1 SW-MOV-102B 11715-CBM 0788 1 0F 4 F8 M0 BFLY 24.000 3 B EV C 03 ST C 03 VP DC 24 SERVICE WATER SUPPLY CROSS CONNECTS TO RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV 103A 11715-CBM 07BB 1 0F 4 E3 M0 BFLY 16.000 2 A CIV EV C 03 0 03 LT C DPB ST C 03 fss n 0 03
( _,,) VP OC 24 SERVICE WATER SUPPLY TO "A" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1 SW MOV-1038 11715 CBM 0788 1 0F 4 E4 NO BFLY 16.000 2 A CIV EV C 03 0 03 l LT C DPB ST C 03 0 03 i VP OC 24 l SERV!CE WATER SUPPLY TO "B" RECIRC SPRAY HEAT EXCHANLER, OUTSIDE CONT ISOLATION VALVE i
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j 1 SW MOV-103C 11715-CBM-0788 10F 4 E6 MO BFLY 16.000 2 A CIV EV C 03 0 03 LT C DPB ST C 03 0 03 l VP OC 24 I SERVICE WATER SUPPLY TO "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT !$0LAT10N VALVE 1 SW-MOV-103D 11715 CBM nT88 1 0F 4 E7 M0 SFLY 16.000 2 A CIV EV C 03 0 03 LT C OPB ST C 03 0 03 VP OC 24 SERVICE WATER SUPPLY TO "D" REclRC SPRAY HEAT A EXCHANGER, OUTSIDE CONT ISOLAfl0N VALVE
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VIRGIN!A POWER COMPANY PAGE: 75 0F 82
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NORTH ANNA UNIT 1 SECOND INSERVICE TESTING INTERVAL REVISION: 8 DATE: 08/17/98
( INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REO JL*ST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RAV- VCN-1 BW MOV 104A 11715 CBM-0788 1 0F 4 C3 M0 BFLY 16.000 2 A CIV EV C 03 0 03 LT C OPS ST C 03 l 0 03 VP OC 24 SERVICE WATER RETURN FROM "A" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT !$0LAT10N VALVE 1-BW-MOV-1048 11715-CBM 0788 1 0F 4 C5 MO BFLY 16.000 2 A CIV EV C 03 0 03 LT C OPB ST C 03 0 03 VP OC 24 SERVICE WATER RETURN FROM "B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLAfl0N VALVE 1-SW-MOV 104C 11715-CBM-0788 1 0F 4 C6 M0 BFLY 16.000 2 A Civ EV C 03 0 03 LT C DPB ST C 03 0 03 es -
VP OC 24 f .............................................
\s SERVICE WATER RETURN FROM "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1 SW-MOV 104D 11715 CBN 0788 1 0F 4 C7 M0 BFLY 16.000 2 A CIV EV C 03 0 03 LT C OPB ST C 03 0 03 VP OC 24 SERVICE WATER RETURN FROM "D" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLAfl0N VALVE 1 SW-MOV 105A 11715-CBM-078A 4 0F 4 C3 M0 BFLY 24.000 3 8 EV 0 CS 34 l
ST 0 CS 34 i VP OC 24 "B" SERVICE WATER HEADER RETURN ISOLATION l FROM RECIRC SPRAY HEAT EXCHANGERS
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 1 SW MOV 105B 11715 CBM 078A 4 of 4 C3 MO BFLY 24.000 3 B EV 0 CS 34 ST 0 CS 34 VP OC 24 l "B" SERVICE WATER HEADER RETURN !$OLATION FROM RECIRC SPRAY HEAT EXCHANGERS i 1 SW-MOV-105C 11715 CBM 078A 4 0F 4 C3 M0 BFLY 24.000 3 8 EV 0 CS 34 ST 0 CS 34 VP OC 24 <
"A" SERVICE WATER HEADER RETURN ISOLAT!DN !
, FROM RECIRC SPRAY HEAT EXCHANGERS
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VIRGINIA POWER COMPANY PAGE: 76 of 82
~s' NORTH ANNA UNIT 1 REVISION: 8
/ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\s INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER WUMBER NUMBER COOR TYPE $!ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV- VCN-1 $W-MOV 1050 11715 CBM-078A 4 0F 4 C3 M0 SFLY 24.000 3 B EV 0 CS 34 ST 0 CS 34 VP OC 24 "A" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC $ PRAY HEAT EXCHANGERS ;
l 1 $W-MOV-106A 11715 CBM 0788 1 0F 4 58 MO BFLY 24.000 3 B EV C 03 ST C 03 VP OC 24 SERVICE WATER RETURN CROSS CONNECTS FROM RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-1068 11715-CBM-0788 10F 4 A8 M0 BFLY 24.000 3 B EV C 03 ST C 03 VP OC 24 SERVICE WATER RETURN CROSS CONNECTS FROM RECIRC SPRAY HEAT EXCHANGERS 1 SW-MOV 1D8A 11715-CBM 07BC 1 0F 2 83 Mo BFLY 24.000 3 8 EV C CS 43 0 CS 43 ST C CS 43 0 CS 43 e VP OC 24
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\s "A" SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1-SW MOV-1088 11715 CBM-078C 1 0F 2 B3 M0 BFLY 24.000 3 8 EV C CS 43 0 CS 43 ST C CS 43 0 CS 43 VP DC 24 "A" SERVICE WATER HEADER SUPPLY !$0LAT10N TO COMPONENT COOLING HEAT EXCHANGERS 1 SW-MOV-110A 11715-CBM 078A 4 0F 4 C4 M0 BFLY 8.000 3 F VP DC 24 SERVICE WATER HEADER SUPPLY TO RECIRCULATION AIR COOLERS 1 -SW-MOV- 11 DB 11715-CBM-07BA 4 0F 4 C4 M0 BFLY 8.000 3 E VP DC 24 SERVICE WATER HEADER SUPPLY TO RECIRCULATION AIR COOLERS 1 SW MOV 113A 11715 CBM-078A 4 0F 4 B7 M0 BFLY 10.000 3 E VP OC 24 1
SERVICE WATER RETURN ISOLATION FROM FUEL PIT i COOLERS i
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 1 1-SW-MOV 1138 11715 CBM-07BA 4 0F 4 B5 M0 BFLY 10.000 3 E VP OC 24 l SERVICE WATER SUPPLY ISOLATION TO FUEL Pif COOLERS
<"'- 1 SW-MOV-114A 11715-CBM-07BA 4 0F 4 C4 M0 BFLY 8.000 3 E VP DC 24 v
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VIRGINIA POWER COMPANY PAGE: 77 0F 82
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NORTH ANNA UNIT 1 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 s
w INSERVICE TESTING PROGRAM - VALVE 1ABLE NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-SERVICE WATER HEADER RETURN FROM RECIRCULATION AIR COOLERS 1 SW-MOV 1148 11715-COM 0784 4 0F 4 C4 Mo BFLY 8.000 3 E VP OC 24 SERVICE WATER HEADER RETURN FROM RECIRCULATION AIR COOLERS 1 SW-Mov 115A 11715 COM 078A 1 0F 4 E7 M0 BFLY 24.000 3 8 EV 0 03 ST C 03 VP OC 24 SERVICE WATER HEADER SUPPLY ISOLATION VALVE FROM AUXILIARY SERVICE WATER PUMPS 1 SW-MOV-117 11715-CBM 078A 1 0F 4 C3 M0 BFLY 24.000 3 B EV o 03 ST C 03 VP OC 24 UNIT 1 AUXILIARY SERVICE WATER PUMP DISCHARGE ISOLATION VALVE 1-SW-Mov-118 11715 COM 078A 10F 4 D4 M0 BFLY 24.000 3 E VP OC 24 AUXILIARY SERVICE WATER SUPPLY HEADEA CROSS
[O CONNECT VALVE 1-SW-Mov-119 11715-CBM-078A 10F 4 04 M0 BFLY 8.000 3 8 EV C 03 ST C 03 VP OC 24 MAKEUP PUMP SUPPLY VALVE 1 SW-Mov 120A 11715 COM-078A 4 0F 4 F3 M0 BFLY 10.000 NC E VP OC 24 AUXILIARY SERVICE WATER RETURN HEADER VALVE 1-SW-Mov-1208 11715-CBM-078A 4 0F 4 F3 M0 BFLY 10.000 NC E VP OC 24 AUXILIARY SERVICE WATER RETURN HEADER VALVE 1 SW MOV 121A 11715-CBM-078N 1 0F 1 85 M0 BFLY 18.000 3 8 EV O 03 ST 0 03 !
VP OC 24 1
............................................. i SERVICE WATER TO SPRAY ARRAYS STOP VALVE l
1 SW Mov-121B 11715 CBM 078H 1 0F 1 B7 M0 BFLY 18.000 3 B EV 0 03 ST 0 03 VP OC 24 SERVICE WATER TO SPRAY ARRAYS STOP VALVE 1 SW MOV-122A 11715-COM-078N 1 0F 1 C5 M0 BFLY 18.000 3 B EV 0 03
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VIRGIN!A POWER COMPANY PAGE: 78 0F 82
,, WORTH ANNA UkIT 1 REVISION: 8 SECOND IPSERVICE TESTING INTE* VAL DATE: 08/17/98 k' INSERVICE TESTING PROGRAM . VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV. RRV. VCN-1 SW-MOV 122A 11715 CBM-078H 1 0F 1 C5 No BFLY 18.000 3 B VP OC 24 SERVICE WATER 70 SPRAY ARRAYS STOP VALVE 1 BW-MOV-1228 11715 CBM-078H 1 0F 1 C6 M0 BFtY 18.000 3 8 EV O 03 ST 0 03 VP OC 24 SERVICE WATER TO SPRAY ARRAYS STOP VALVE 1 SW-MOV 123A 11715-CBM-078H 10F 1 E4 M0 BFLY 24.000 3 B EV C 03 ST C 03 VP DC 24 SERVICE WATER BYPASS VALVE 1 SW-MOV 123B 11715 CBM-078H 10F 1 E8 M0 BFLY 24.000 3 B EV C 03 ST C 03 VP OC 24 i
.............................-............... 4 SERVICE WATER BYPASS VALVE
, 1 SW-RV-100A 11715 CBM-0788 1 0F 4 E3 RELIEF VALVE .750 2 C SP 0 120 "A" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1 SW-RV-1008 11715 CBM-0788 1 0F 4 E4 RELIEF VALVE .750 2 C SP O 120 "B" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1 SW RV 100C 11715 CBM 0788 1 0F 4 E6 RELIEF VALVE .750 2 C SP 0 120 "C" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1-SW-RV-1000 11715 CBN-0788 1 0F 4 E7 RELIEF VALVE 750 2 C SP O 120 "D" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1 SW-kV-101A 11715 CBM-078C 1 0F 2 E5 RELIEF VALVE .750 3 C SP 0 120 UNIT 1 M" COMPONENT COOLING HEAT EXCHANGER SERVICE WATER RELIEF VALVE 1 SW RV 1018 11715-CBM-078C 10F 2 E6 RELIEF VALVE .750 3 C SP O 120 UNIT 1 "B" COMPONENT COOLING HEAT EXCHANGER l SERVICE WATER RELIEF VALVE 1*SW TCV 102A 11715 CBM 078G 1 0F 2 C4 A0 GATE 2.000 3 8 EV 0 03 FS 0 03 ST 0 03
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VIRGINIA POWER COMPANY PAGE: 79 0F 82 g NORTH ANNA UNIT 1 . REVISION: 8 SECONo INSERVICE TESTING INTERVAL DATE: 08/17/98 s,,,/ INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SHEE' DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE Pos FRE0 V- CSV- RRV- VCN-SERVICF WATER FROM CHARGING PUMP LUBE DIL COOLER TEMP CONTROL VALVE
.....................................................u....... ..... .... ... .... .... .... .... ... .... .... ....
1 BW-TCV 102B 11715 CBM 078G 1 0F 2 C6 A0 , GATE 2.000 3 B EV 0 03 FS 0 03 ST 0 03 l SERVICE WATER FROM CHARGING PUMP LUBE DIL COOLER TEMP CONTROL VALVE l 1 SW TCV 102C 11715 CBM 078G 1 0F 2 C8 A0 GATE 2.000 3 5 EV 0 03 l FS 0 03 l
ST 0 03 SERVICE WATER FROM CHARGING PUMP LUBE CIL
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l COOLER TEMP CONTROL VALVE l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
I 2 SW-MOV-2158 11715-CBN 078A 10F 4 E6 M0 BFLY 24.000 3 B EV 0 03 l ST 0 03 VP OC 24 SERVICE W1.TER HEADER SUPPLY ISOLATION VALVE FROM AUXILIARY SERVICE WATER PUMPS v
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VIRGINIA POWER COMPANY PAGE: 80 0F 82
- s NORTH ANNA UN!1 1 .
REVIS10W: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
!NSERVICE TESTING PROGRAM
- VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-1 VG TV 100A 11715 CBM-090C 1 0F 3 F3 A0 GLosE 1.500 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, OUTSIDE CONT ISOL 1 VG-TV 100s 11715-CSM-D90C 1 0F 3 D3 A0 GLOBE 1.500 2 A CIV EV C 03 J
FS C 03 -
LT C OPS ST C 03 VP OC 24 VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, INSIDE CONT ISOL VLV k.
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1 VIRGINIA POWER COMPANY PAGE: 81 0F 82 NORTH ANNA UNIT 1 REVISION: 8 l BECOND INSERVICE TElf!NC INfERVAL DATE: 08/17/96 l INSERVICE TESTING PROGRAM VALVE TABLE NC l 180 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST ]
NUNSER NUMBER NUMBER COOR TYPE $1ZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-1 VP-012 11715 CBM-072A 2 0F 3 E3 CHECK VALVE 6.000 2 AC CIV CV C RR 15 )
LT C DPB CONDENSER AIR REMOVAL DISCHARG TO CONTAINMENT INSIDE CONTAIN ISOLATION CHECK VALVE i
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VIRGINIA POWER COMPANY PAGE: 82 0F 82
.s NORTH ANNA UNIT 1 REVISION: 8
[ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\, INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMSER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV 9RV VCN-1-WT 038 11715-CsM-102A 2 0F 2 F7 CHECK VALVE .750 2 C CV C 03
- A" STEAM GENERATOR CH[MICAL FEED SUPPLY CHECK VALVE 1 WT 050 11715 CsM 102A 2 0F 2 E7 CHECK VALVE .750 2 C CV C 03 "B" STEAM GENERATOR CHEMICAL FEED SUPPLY CHECK VALVE 1 WT 066 11715-CBM-102A 2 of 2 D7 CHECK VALVE .750 2 C CV C 03
.C" STEAM GENERATOR CHEMICAL FEED SUPPLY CHECK VALVE 1 WT 465 13075-CBM 102C 1 0F 1 E6 MANUAL GATE 3.000 2 AE CIV LT C OPB WET LAY UP RETURN FROM "A" $ TEAM GENERATOR, INSIDE CONTAINMENT ISOLATION VALVE 1*WT 468 13075-CBM-102C 10F 1 E5 MANUAL CATE 3.000 2 AE CIV LT C DPB WET LAY UP RETURN FROM "A" STEAM GENERATOR, OUTSIDE CONTAINMENT !$0LAT10N VALVE
,- 1 WT 488 13075-CBM-102C 1 0F 1 D6 MANUAL GATE 3.000 2 AE CIV LT C OPB WET LAY UP RETURN FROM "B" STEAM GENERATOR, INSIDE CONTAlWMENT ISOLATION VALVE 1 WT 491 13075 CBM-102C 10F 1 D5 MANUAL GATE 3.000 2 AE CIV LT C OPB I WET LAY UP RETURN FROM "B" STEAM GENERATOR, OUTSIDE CONTAINMENT ISOLATION VALVE l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1 WT-511 13075-CBM-102C 1 0F 1 B6 MANUAL GATE 3.000 2 AE CIV LT C OPB WET LAY UP RETURN FROM "C" STEAM GENERATOR, INSIDE CONTAINMENT ISOLATION VALVE 1-WT 514 13075 CBM-102C 10F 1 B5 MANUAL GATE 3.000 2 AE CIV LT C OPB j .............................................
WET LAY UP RETURN FROM "C" STEAM GENERATOR, OUTSIDE CONTAINMENT ISOLATION VALVE i
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4.5 VALVE INSERVICE TESTING PROGRAM RELIEF REQUESTS i V l Relief requests identify those Section XI Code i requirements considered to be impractical. The l basis for the relief request and the alternate testing to be performed is given.
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/ D U 4-8 N1PVI2R8' Revision 8 August 17, 1998
RELIEF' REQUEST V-1 Relief Request withdrawn.
RELIEF REQUEST V-2 Replaced by Cold Shutdown Justification CSV-1 RELIEF REQUEST V-3 Replaced by' Reactor Refueling Justification RRV-1 l
l l RELIEF REQUEST V-4 1
L 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 Replaced by Cold Shutdown Justification CSV-4 l RELIEF REQUEST V-8 l
l Replaced by Cold Shutdown Justification CSV-8 ,
l RELIEF REQUEST V-9 l ,J Replaced by Cold Shutdown Justification CSV-48 i O
l O 4-9 N1PVI2R8 Revision 8 December 1, 1998 1
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/ 'i RELIEF REQUEST V-10 C#
Replaced by Reactor Refueling Justification RRV-2 RELIEF REQUEST V-11 Replaced by Cold Shutdown Justification CSV-10 RELIEF REQUEST V-12 Relief Request withdrawn, valve removed from IST Program.
RELIEF REQUEST V-13 Relief Request withdrawn.
RELIEF REQUEST V-14 Relief Request withdrawn.
r RELIEF REQUEST V-15 Relief Request withdrawn.
RELIEF REQUEST V-16 Replaced by Reactor Refueling Justification RRV-3 RELIEF REQUEST V-17 Replaced by Cold Shutdown Justification CSV-11 RELIEF REQUEST V-18 Replaced by Cold Shutdown Justification CSV-12 4-10 N1PVI2R8 Revision 8 l August 17, 1998 l l
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RELIEF REQUEST 9-19 Relief Request withdrawn.
RELIEF REQUEST V-20 Replaced by Reactor Refueling Justification RRV-4 l
RELIEF REQUEST V-21 Replaced by Reactor Refueling Justification'RRV-5 j
)
-RELIEF REQUEST V-22 Replaced by Cold Shutdown Justification CSV-13 RELIEF REQUEST V-23 i
Replaced by Cold Shutdown Justification CSV-14 RELIEF REQUEST V-24 Replaced by Cold Shutdown Justification CSV-15 RELIEF REQUEST V-25 Relief Request Withdrawn RELIEF REQUEST V-26 Replaced by Cold Shutdown Justification CSV-17 RELIEF REQUEST V-27 Replaced by Cold Shutdown Justification CSV-42 )
4-11 -
N1PVI2R8 Revision 8 August 17, 1998 i
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/N RELIEF REQUEST V-28 b
Replaced by Reactor Refueling Justification RRV-6 RELIEF REQUEST V-29 l
Replaced by Cold Shutdown Justification CSV-18 RELIEF REQUEST V-30 Replaced by Cold Shutdown Justification CSV-19 RELIEF REQUEST V-31 Replaced by Cold Shutdown Justification CSV-20 RELIEF REQUEST V-32 Replaced by Cold Shutdown Justification CSV-21 i
(v 4-12 N1PVI2R8 Revision 8 August 17, 1998 l
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I 'T RELIEF REQUEST V-33 V.
-System : Recirculation' Spray
. Valve (s): 1-RS-123 1-RS-138 Category:. C Class : 2-Function: Casing Cooling-Pump Discharge Check Valves-OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4 (c) reads in part that, " disassembly l every refueling outage to verify operability of check valves may I be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage.
Basis For Request l
These check valves must open in order to perform their safety O- 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.
Alternate Testing Proposed 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.
This test frequency is in accordance with Generic Letter 89-04, ,
Position 2.
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() 4-13 N1PVI2R8 Revision 8 August 17, 1998
RELIEF REQUEST V-34 Replaced by Cold Shutdown Justification CSV-22 RELIEF REQUEST V-35 Replaced by Cold Shutdown Justification CSV-23 RELIEF REQUEST V-36 Replaced by Cold Shutdown Justification CSV-24 O
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\s RELIEF REQUEST V-37 System. : Safety Injection Valve (s): 1-SI 1-SI-16 Category:1 C Class : 2 Function': Low. Head SI Pump Suction from Containment Sump Check
' Valves OM Part 10-Code Requirements-For Which Relief Is Requested OM Part'10, Paragraph 4.3.2.4 (c) reads in part that, " disassembly every refueling _ outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage.
Basis For Request 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 stunp. This untreated water should not lua introduced into the system.
Alternate. Testing Proposed 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..
This test frequency is in accordance with Generic Letter 89-04,
' Position 2.
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O 4-15 N1PVI2R8 Revision 8 ,
August 17, 1998 )
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RELIEF REQUEST V-38 Replaced by Reactor Refueling Justification RRV-7 I
RELIEF REQUEST V-39 Replaced by Reactor Refueling Justification RRV-8 RELIEF REQUEST V-40 i
Replaced by Reactor Refueling Justification RRV-9 1
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[~'h L) 4-16 l N1PVI2R8 Revision 8 i August 17, 1998
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RELIEF REQUEST V-d1 l
System : Safety Injection
- Valve (s) :- 1-SI 1-SI-195
'l-SI-86 1-SI-197' 1-SI-89 1-SI-199 Category:~ AC- -
Class : 1-Function: -RCS Cold Leg SI Admission. Check Valves
'OM Part 10' Code Requirements For Which Relief Is Requested OM Part110, Section 4.3.2.4 (a) - This section states in part that, "The- necessary. valve obturator movement shall be demonstrated by exercising the valve and observing that either the-obturator travels to the seat on cessation or reversal of flow,.or opens to the position required to fulfill its function, as specified in para. 1.1, or both. Observation may be by fT ~ observing a direct indicator such as a position indicating
\_ / device, or by other indicator (s) such as changes in system pressure, flow rate, level, temperature, seat leakage testing or other positive means." This section implies that the techniques used to verify obturator movement be applied to every valve on a j test frequency that is practical. 1 Basis For Request There is no installed instrumentation that can measure individual flow rates for these valves. The alternate testing described below will be used.
' Alternate Testing Proposed With-low head pump flow, the cold leg injection valves will be '
acoustically monitored using a sampling. plan for the disk striking the back seat every reactor refueling. The data will be analyzed- to show that the disk struck the back seat, which 1 verifies that the disk stroked to the full open position.
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\J 4-17 -
N1PVI2R8- Revision 8
~ August 17, 1998
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l RELIEF REQUEST V-41 (Cont.)
l l The sampling plan will follow the recommended alternative testing l
method described in NUREG 1482, Section 4.1.2. Per this plan, the valves will be placed into two groups with valves 1-SI-83, 86 and 89 in one group, and valves 1-SI-195, 197 and 199 in the other group. During initial testing using nonintrusive techniques, each valve in the group will be verified as operable.
During subsequent testing, nonintrusive verification will be performed for only one valve of.the group on a rotating schedule each time the testing is performed, and the balance of the group will be flow tested. In this context, flow testing means that flow will be established in the lines but not measured. Indirect means can be used to verify that flow is established. If problems are found with the sample valve that are determined to affect the operational readiness of the valve, all valves in the group must be tested using nonintrusive techniques during the same outage. The test frequency is in accordance with Generic Letter 89-04, Position 2.
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'w 4-18 N1PVI2R8 Revision 8 August 17, 1998
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[' RELIEF REQUEST V-42 System : Safety Injection Valve (s): 1-SI-125 1-SI-144 1-SI-127 1-SI-159 1-SI-142 1-SI-161 Category: C 4
Class : 1 Function: SI Accumulator Discharge Check Valves OM Part.10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.3.2.4(a) - This section states in part that, "The necessary valve obturator movement shall be demonstrated by exercising the valve and observing that either the obturator travels to the seat on cessation or reversal of flow, or opens to the position required to fulfill its function, as specified in para. 1.1, or both. Observation may be by
. (__) observing a direct indicator such as a position indicating
\- / device, or by other indicator (s) such as changes in system pressure, flow rate, level, temperature, seat leakage testing or other positive means." This section implies that the techniques used to verify obturator movement be applied to every valve on a test frequency that is practical.
Basis For Request There is no installed instrumentation that can measure individual l flow rates for these valves. The alternate testing described below will be used.
Alternate Testing Proposed With flow from each accumulator, these check valves will be l
acoustically monitored using a sampling plan for the disk striking the back seat every reactor refueling. The data will be l analyzed to show that the disk struck the back seat, which i verifies that the disk stroked to the full open position. l tx O 4-19 N1PVI2R8 Revision 8 August 17, 1998 m- )
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IN RELIEF REQUEST V-42 (Cont.)
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The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2. Valves 1-SI-127, 144 and 161 are closest to the reactor coolant system and will be in one group, and valves 1-SI-125, 142 and 159 will be in the other group. During initial testing using nonintrusive techniques, each valve in the group will be verified as operable.
l During subsequent testing, nonintrusive verification will be performed for only one valve of the group on a rotating schedule each time the testing is performed, and the balance of the group will be flow tested. In this context, flow testing means that flow will be established in the lines but not measured. Indirect means can be used to verify that flow is established. If problems are found with the sample valve that are determined to affect the operational readiness of the valve, all valves in the group must be tested using nonintrusive techniques during the same outage. The test frequency is in accordance with Generic Letter 89-04, Position 2.
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b 4-20
, N1PVI2R8 Revision 8
) August 17, 1998 i
(~) RELIEF' REQUEST V-43 X_/
System : Safety _ Injection
' Valve (s): 1-SI-95 1-SI-209 1-SI-99 1-SI-211 1-SI-103 1-SI-213 Category: .. C Class : 1 )
- Function: SI to RCS Hot-Legs Check Valves OM Part'10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.3.2.4(a) - This section states in part
!that,- "The necessary valve obturator movement shall be
' demonstrated by exercising the valve and observing that either the obturator travels to the seat on cessation or reversal of flow, or opens to the position required to fulfill its function, ;
as specified in para. 1.1, or both. Observation may be by J
(~'Y observing =a direct indicator such as a position indicating
(- / device, or by other indicator (s) such as changes in system pressure, flow rate, level, temperature, seat leakage testing or other positive means." This section implies that the techniques used to verify obturator movement be applied to every valve on a test frequency that is practical. '
Basis For Request l
.There is no installed instrumentation'that can measure individual flow rates for these valves. The alternate testing described below will be used. l
-Alternate Testing Proposed !
With low head pump flow, the hot leg injection valves will be !
acoustically monitored using a sampling plan for the disk i striking the back seat every reactor refueling. The data.will be j analyzed to show that the disk struck the back seat, which i verifies that the disk stroked to the full open position.
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kms i l 4-21 l N1PVI2R8 Revision 8 August 17, 1998 '
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f i ,Ns/ RELIEF REQUEST V-43 (Cont.)
The sampling plan will follow the recommended alternative testing method described-in NUREG 1482, Section 4.1.2. Per this plan, the valves will be placed into two groups with valves 1-SI-95, 99 and 103 in one group, and valves 1-SI-209, 211 and 213 in the other group. During initial testing using nonintrusive techniques, each valve in the group will be verified as operable.
During subsequent testing, nonintrusive verification will be performed for only one valve of the group on a rotating schedule each time the testing is performed, and the balance of the group will be flow tested. In this context, flow testing means that flow will be established in the lines but not measured. Indirect means can be used to verify that flow is established. If I problems are found with the sample valve that are determined to affect the operational readiness of the valve, all valves in the group must be tested using nonintrusive techniques during the same outage. The test frequency is in accordance with Generic Letter 89-04, Position 2.
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4-22 N1PVI2R8 Revision 8 August 17, 1998 l
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RELIEF REQUEST i-44 Replaced by Reactor Refueling Justification RRV-13 RELIEF REQUEST V-45 Replaced by-Reactor Refueling Justification RRV-14 RELIEF REQUEST V-46 i
Replaced by Reactor Refueling Justification RRV-15 RELIEF REQUEST V-47 Replaced by Reactor Refueling Justification RRV-16 RELIEF REQUEST V-48 Relief Request Withdrawn
.- RELIEF REQUEST V-49 Relief Request Withdrawn RELIEF REQUEST V-50 Relief Request Withdrawn j l
I RELIEF REQUEST V-51 Relief Request Withdrawn RELIEF REQUEST V-52 Relief Request Withdrawn L i i
4-23 -
N1PVI2R8 Revision 8 August 17, 1998
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RELIEF REQUEST V-53 Replaced by Reactor Refueling Justification RRV-17 RELIEF REQUEST V-54 Relief Request Withdrawn RELIEF REQUEST V-55 Replaced by Non-Code Alternative Testing Description VNC-4 l
l RELIEF REQUEST.V-56 1
( Relief Request Withdrawn RELIEF REQUEST V-57 e.
Replaced by Cold Shutdown Justification CSV-49 l
() RELIEF REQUEST V-58 l Relief Request' Withdrawn RELIEF REQUEST V-59 l Relief. Request Withdrawn 1
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RELIEF REQUEST V-60 Relief Request Withdrawn l
RELIEF REQUEST V-61 Relief Request Withdrawn 4-24 N1PVI2R8 Revision 8 December 1, 1998
y RELIEF REQUEST V-62
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,, Replaced by Reactor Refueling Justification RRV-18 RELIEF REQUEST V-63 Replaced by Reactor Refueling Justification RRV-19 RELIEF REQUEST V-64 Replaced by Non-Code Alternative Test Description VNC-2 ,
l RELIEF REQUEST V-65 Replaced by Reactor Refueling Justification RRV-20 RELIEF REQUEST V-66 Relief Request Withdrawn O RELIEF REQUEST V-67 Replaced by Reactor Refueling Justification RRV-21 RELIEF REQUEST V-68 Relief Request Withdrawn v l 1
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O 4-25 ,
N1PVI2R8 Revision 8 August 17, 1998 l
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fh RELIEF REQUEST V-69 L
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.
Category: A and AC Class :
Function: Provide Containment Isolation I OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.2.2.3 (f) - Valves or valve combinations with leakage rates exceeding the values specified by the Owner in (e) above shall be declared inoperable and be either repaired or replaced.
Basis For Request Permissible valve leakage rates are based on each 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 individual valve's permissible leakage rate may have no affect on the containment's ability to maintain an overall leakage rate less than 0.6La.
1 Also, there may be plant conditions, or schedule constraints, that preclude repair or replacement of a valve when the j individual leakage limit is exceeded, but the overall leakage i 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. I i
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N1PVI2R8 Revision 8 August 17, 1998
O RELIEF REQUEST V-69 (Cont.)
lL Alternate Testing Proposed i
In addition to repair or replacement as corrective actions, an evaluation can'be performed which demonstrates that even if a
, valve has~ exceeded its permissible leakage rate, the overall containment leakage rate will be maintained below 0.6La until the next Type C tests. -No repair or replacement is 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.
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0 4-27 N1PVI2R8 Revision 8 August 17, 1998
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RELIEF REQUEST V-70 x
Replaced by Reactor Refueling Justification RRV-22 '
! RELIEF REQUEST V-71 Relief Request Withdrawn RELIEF REQUEST V-72 l
Replaced by Reactor Refueling Justification RRV-23 RELIEF REQUEST V-73
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Replaced by Reactor Refueling Justification RRV-24 RELIEF REQUEST V-74 I Replaced by Cold Shutdown Justification CSV-46 f
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4-28 N1PVI2R8 Revision 8 l August 17, 1998 l
l REL~IEF REQUEST V-75 System : Chemical and Volume Control and Safety Injection Valve (s): 1-CH-MOV-1115B 1-SI-MOV-1885A 1-CH-MOV-1115D 1-SI-MOV-1885B 1-SI-47 1-SI-MOV-1885C
- 1-SI-MOV-1885D Category: A for 1-CH-MOV-1115B and D, and 1-SI-MOV-1885A-D AC for 1-SI-47 Class : 2 Function: RWST Isolation Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.2.2.3(f) - Valves or valve combinations with leakage rates exceeding the values specified by the Owner in (e) above shall be declared inoperable and be either repaired or replaced.
Basis For Request Valves 1-CH-MOV-1115B and D, and 1-SI-47 are in the supply line to the charging pumps from the RWST. Valves 1-SI-MOV-1885A, B, C and D are on test lines that run from the discharge of the low head SI pumps to the RWST. During recirculation mode transfer, the RWST is isolated and the low head SI pumps recirculate highly contaminated water from the containment sump to the reactor vessel.
The RWST isolation valves work as a system of valves to protect the RWST from the contaminated sump water. Permissible valve leakage rates are based on each valve's possible contribution to the total' allowable leakage rate to the RWST. When the leakages from each valve have been measured and summed, an individual valve's permissible leakage rate may have been exceeded but the I overall allowable leakage to the RWST may not have been exceeded.
In these cases, a repair or replacement m6y not be necessary because the system of isolation valves has been verified to be performing adequately.
4-29 -
N1PVI2R8 Revision 8 August 17, 1998
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( RELIEF REQUEST V-75 (Cont.)
Alternate Testing Proposed In addition to repair or replacement as corrective actions, an evaluation.can,be performed which demonstrates that even if a valve has. exceeded its permissible leakage rate, the overall leakage rate to the RWST will be maintained below the ovetall-allowable RWST leakage rate. No repair or replacement is necessary ifethe evaluation is performed.
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4-30 l :N1PVI2R8- Revision 8 l August 17, 1998
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RELIEF REQUEST V-76
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System : ~ ServicesWater
. Valve (s) : 1-SW-630 1-SW-647 1-SW-664 1-SW-631 1-SW-648 1-SW-665 1-SW-641 1-SW-658 1-SW-686
- 1-SW-644 1-SW-661 1-SW-689 Category: C Class : 3 Function: Service Water Supply to Charging Pump Lube Oil and ,
Gear Box Coolers Isolation Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4 (c) reads in part that, " disassembly every refueling outage to verify operability of check valves may
'be used." This sentence implies that each valve in the group given'above must be disassembled every refueling outage.
Basis For Request These check valves must'open to supply service water to the charging pump lube oil and gear box coolers and'close if one of the service water headers become depressurized to prevent the diversion of service water away from the coolers. There is no permanently installed instrumentation to measure flow through the valves for testing to the full open position.
-Due to the system configuration, it is not practical to perform a l
backpressure / backseat test on these valves every quarter for testing to the closed position. Both service water headers are pressurized during normal operation and are shared between the two units.- Therefore, header pressure cannot be used to create a pressure differential across the check valves without putting the plant through a major evolution to depressurize one header.
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4-31 ;
N1PVI2R8 Revision 8 August 17, 1998 l i
l RELIEF REQUEST V-76 (Cont.)
To verify open/close' capabilities,-these valves will be disassembled and inspected.- The valves can be disassembled and inspected while the plant is operating. To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, .the valves will be disassembled on.a reactor refueling frequency (not to exceed 24 months) but not necessarily during refueling outages.
Alternate Testing Proposed The' valves will be placed in groups of two, two groups per pump, according'to valve manufacturer, type, size and service conditions. One valve from each group will be disassembled and inspected on a refueling frequency (not to exceed 24 months).
The second valve in the group will be disassembled during the next inspection and the cycle will continue on a rotating basis.
.The valves will-be stroked to the partially open position every three months. .The test frequency and sampling plan are in accordance with Generic Letter 89-04, Position 2.
O 4-32 N1PVI2R8 Revision.8 August 17, 1998 i
i 4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the full stroke exercising of valves during Cold Shutdown }
(but not more frequently than every three months) if D the valves cannot be exercised during normal operation.
Therefore, no request.for relief from testing every three months is necessary. I However, OM Part:10, Section 6.2 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.
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V 4-33 N1PVI2R8 Revision 8 August 17, 1998
l j), COLD SHUTDOWN JUSTIFICATION CSV-1 l -V i
l System : . Component Cooling Valve (s): 1-CC-TV-101A 1-CC-TV-102E l-CC-TV-101B' 1-CC-TV-102F )
1-CC-TV-102A 1-CC-TV-104A 1-CC-TV-102B' 1-CC-TV-104B 1-CC-TV-102C 'l-CC-TV-104C 1-CC-TV-102D Category: A Class : 2 Function: Reactor Coolant. Pump CC Supply and Return Containment
, isolation Valves l' 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 j thermal barriers, lube oil, stator and/or shroud coolers. The
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i increased level of safety gained from exercising these valves I
\ during power operation does not justify the operational )
consequences should they fail in the closed position. The valve J controllers do not allow for a part-stroke exercise test.
l Testing Frequency These valves will be full stroke. exercised every cold shutdown ,
but'not more frequently than once every three months.
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4-34 N1PVI2R8 Revision 8 August 17, 1998
COLD SHUTDOWN JUSTIFICkTION CSV-2 Replaced by Relief Request V-62 O
O 4-35 -
N1PVI2R8 Revision 8 August 17, 1998
COLD SHUTDOWN JUSTIFICATION CSV-3 System .: 'CH TValve(s): 1-CH-84 1-CH-102 Category: 'C
. Class : 3 Function: -Boric Acid Transfer Pump Discharge Check Valves 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 the reactor coolant system which would upset the boron. concentration in the primary plant
. water.
Testing Frequency These valves will be partial stroke exercised every quarter and O., ' full' stroke exercised every cold shutdown but not more frequently than once every three months.
I 4 N1PVI2R8 Revision 8 j
August 17, 1998 m ./
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COLD SHUTDOWN' JUSTIFICATION CSV-4
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System : Chemical & Volume Control System Valve (s) : - 1-CH-MOV-1350 i 1-CH-238 l
.1-CH-240 1-CH-241 CH-242 Category: B for 1-CH-241 and 1-CH-MOV-13'05 C for 1-CH-238, 240 and 242 Class : 2 for 1-CH-238, 242 and 1-CH-MOV-1350 3 for 1-CH-240 and 241
! Function: Emergency Boration Line and Alternate Boration Line Valves I Cold Shutdown Justification Full or part-stroke exercising these valves during power operation would cause a sudden increase in reactor coolant' system i O boron inventory by providing flow from the emergency and alternate boration paths to charging pump suctions. Also, the valve controller for 1-CH-MOV-1350 does not allow for a part-
-stroke exercise-test. The increased level of safety gained from l full or part-stroke exercising these valves during power j l operation does not justify the operational consequences i I associated with reactivity transients.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months. Manual valve 1-CH-241 will be stroked open when the alternate boration path is established every cold shutdown. The increased level of safety gained by exercising this valve every quarter does not justify the added burden of performing a separate test just for the manual valve.
O 4-37 N1PVI2R8 Revision 8 i August 17, 1998 {
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. System :. Chemical & Volume Control System Valve (s): 1-CH-TV-1204A 1-CH-LCV-1460A 1-CH-TV-1204B 1-CH-LCV-1460B Category: B for 1-CH-LCV-1460A and B A for 1-CH-TV-1204A and B Class : 2 Function: Letdown Line Isolation Valves ,
1 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 valves should fail closed, reactor coolant inventory. control 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 (ss)/ reactor coolant pump seal injection flow into the RCS matches letdown flow.
Also, exercising these valves during normal operation will 1 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. l Testing Frequency ,
These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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Q 4-38 N1PVI2R8 Revision 8 l August 17, 1998
() COLD SHUTDOWN JUSTIFICATION CSV-6 System : -Chemical & Volume Control System Valve (s) : CH-MOV-1115B 1 1-CH-MOV-1115C 1-CH-MOV-1115D 1-CH-MOV-1115E Category: A for 1-CH-MOV-1115B and D B for 1-CH-MOV-1115C and E Class- : 2 Function: Charging Pump Supply from the VCT and RWST Isolation Valves 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
(_s part-stroke exercising these valves during power operation does not justify the operational consequences of reactivity transients.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months, fN 1
4-39 l N1PVI2R8 Revision 8 August 17, 1998
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v COLD SHUTDOWN JUSTIFICATION CSV-7
' System : Chemical'& Volume Control System
. Valve (s): 1-CH-MOV-1289A 1-CH-MOV-1289B Category: A for_1-CH-MOV-1289A B;for 1-CH-MOV-1289B Class : 2 Function: Main Charging Header Isolation Valves-Cold Shutdown Justification
' Varying letdown flow through the Regenerative Heat Exchanger will cause. variations in charging flow temperatures. This is not l desirable since decreased charging temperatures result in l
reactivity increases and thermal stress on the piping and heat exchanger.
.n211 or part-stroke exercising _these valves during power
(s, 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.
Testing Frequency
'These valves will'be full stroke exercised every cold shutdown but not more frequently than once every three months.
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.U 4-40' N1PVI2R8 Revision 8 August 17, 1998 l
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COLD SHUTDOWN JUSTIFICkTION CSV-8
- Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-9 Replaced by Relief Request V-9 COLD SHUTDOWN JUSTIFICATION CSV-10 Cold Shutdown Justification Withdrawn l
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NJ 4-41 -
N1PVI2R8 Revision 8 August 17, 1998 t
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l l [^') COLD SHUTDOWN JUSTIFICATION CSV-11 v
System : Feedwater Valve (s): 1- FW-FCV-14 7 8 1- FW-MOV-154 A 1- FW-FCV-14 7 9 1- FW-MOV-154 B 1- FN-FCV-14 8 8 1- FW-MOV-154 C 1- FW- FCV-14 8 9 1-FW-FCV-1498 1-FW-FCV-14 9 9 Category: B Class : NC Function: Main Feedwater Regulating, Bypass and Isolation Valves Cold Shutdown Justification These valves are in positions required 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 move during normal operation as they perform
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their regulating function. In order to perform a partial stroke test during normal operation, the plant would have to reduce power to cause the valve disks to move. Reducing power for the purpose of performing an exercise test is considered impractical according to the NRC response to Comment 2.4.5-1 in NUREG-1482, Appendix G.
The bypass valves 1-FW-FCV-1479, 1489 and 1499 are used 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.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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i 4-42 ;
N1PVI2R8 Revision 8 l August 17, 1998 4
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b COLD. SHUTDOWN JUSTIFICATION CSV-12 N) .
System : 'Feedwater Valve (s) : 1-FW-47 1-FW-79
.1-FW-111
( Category: C l Class : 2 Function: Main Feedwater Suphly Isola' tion Check Valves Cold Shutdown Justification' These check valves must seat upon reversal of' flow to fulfill l
their safety: functions.. The only method to verify this actuation l is to: perform a back pressure test. Since the valves must be l -open'to sustain power operation,.they cannot-be-tested every three months.
. Testing Frequency l t
's / These check valves will be tested in the closed position every cold shutdown but not more frequently than once every three months.
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l 4-43 N1PVI2R8- Revision 8 August 17, 1998
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\s' COLD SHUTDOWN JUSTIFICATION CSV-13 System : Main Steam Valve (s): 1-MS-NRV-101A 1-MS-NRV-101B 1-MS-NRV-101C Category: C Class : 2 l
Punction: Main Steam Header Non-return Valves Cold Shutdown Justification Valve Description 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 l
(_/ 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 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 one 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 Testing 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.
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%) 4-44 N1PVI2R8 Revision 8 August 17, 1998
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I'\ COLD SHUTDOWN JUSTIFICATION CSV-13 (Cont.)
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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 F and 195 *F 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 3
steam flow.
After the main steam trip valve is closed, the Valve Operation j 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 the 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 equipment and interpret the results.
The VOTES provides two methods for detecting changes in the f~}/
- s. running' force. The test can be performed either at the valve by monitoring the yoke strain using a permanently mounted VOTES force sensor or at the motor control center (MCC) by monitoring motor current. The first method converts yoke strain directly to stem load. A signature is generated that will show'any changes in the stem. load which would indicate a stuck or binding valve I disk. The second and more sensitive method monitors a single l phase of the motor current. The motor current information is l used to generate motor power and power factor signatures which :
are very sensitive to changes in stem load. Changes in motor l load would again indicate a stuck or binding valve disk. In both methods, the valve switch probes are monitored to determine the status of the torque and limit switches, and the open and closed i bypass switches in the motor operator control circuit over the I course of stem travel. The second method is preferred. l Testing Frequency Discussion Full stroke or part stroke exercising of these valves during power operation would result in a turbine and reactor trip.
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sl k_h H 4-45 I N1PVI2R8 Revision 8 August 17, 1998 j i
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T COLD SHUTDOWN JUSTIFICATION CSV-13 (Cont.)
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(d 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, 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 shutdown 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. However, 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 evidence in the valve history t11at 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 O' 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.
Testing Frequency The. VOTES test described above will be performed on 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. .
4-46 N1PVI2R8 Revision 8 August 17, 1998
o f') COLD SHUTDOWN JUSTIFICkTION CSV-14
%d System :- Main Steam
. Valve'( s ) : 1-MS-TV-109' Category: B
. Class : 2 Function: Main Steam High Pressure Drain'to Condenser-Isolation Valve Cold Shut'down Justification Full or part-stroke exercising this valve c'.uring power operation would cause undesirable pressure transients in the High Pressure Secondary Drains System. Also, the valve controller does not allow for a part-stroke exercise test. The increased level of
. safety gained from exercising this valve during power operation does not justify the operational consequences of these pressure variations..
Testing Frequency i This valve will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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4-47 -
L .N1PVI2RB- Revision 8 4 August 17, 1998 l
l COLD SHUTDOWN JUSTIFICATION CSV-15 Cold Shutdown Justification withdrawn O
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O 4-48 N1PVI2R8 Revision 8 August 17, 1998 j i
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. COLD SHUTDOWN JUSTIFICATION CSV-16 System : Main Steam -
, Valve (s) :- 1-MS-TV-101A 1-MS-TV-101B l-MS-TV-101C Category: B Class :- 2 Function: Main Steam Header. Trip Valves I
' 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.
. Testing Frequency O
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s These valves will be full stroke exercised every cold shutdown but notLmore frequently than once every three months.
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\ s' i 4-49 l N1PVI2R8 Revision 8 .
j August 17, 1998
1 COLD SHUTDOWN JUSTIFICATION CSV-17 Replaced by Relief Request V-67 1
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4-50 N1PVI2R8 Revision 8 August 17, 1998
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[') COLD SHUTDOWN JUSTIFICATION CSV-18 v
System : Residual Heat Removal Valve (s): 1-RH-MOV-1700 1-RH-MOV-1701 l 1-RH-MOV-1720A '
1-RH-MOV-1720B i
Category: B Class : 1
(
l Function: RHR Supply and Return Isolation Valves Cold Shutdown Justification i
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.
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Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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r~x l 4-51 l N1PVI2R8 Revision 8 l August 17, 1998 l
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l i f COLD SHUTDOWN JUSTIFICATION CSV-19 l \s.
l Replaced by Relief Request V-74 COLD SHUTDOWN JUSTIFICATION CSV-20 Cold Shutdown Justification withdrawn COLD SHUTDOWN JUSTIFICATION CSV-21 Replaced by Relief Request V-67 COLD SHUTDOWN JUSTIFICATION CSV-22 Cold Shutdown Justification Withdrawn
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4-52 N1PVI2R8 Revision 8 August 17, 1998
() COLD SHUTDOWN JUSTIFIC$ TION.CSV-23 System : Safety' Injection Valve (s): 1-SI-MOV-1836 1-SI-MOV-1869A 1-S I-MOV-18 69B -
1-SI-MOV-1890A ~
1-SI-MOV-1890B -
Category:- A Class : 2 Function: High Head (1-S I-MOV-183 6, 1869A and B) and Low Head (1-SI-MOV-1890 A and B) SI to RCS Containment Isolation Valves 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.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
4-53 -
N1PVI2R8 Revision 8 )
August 17, 1998
f/F l.
V COLD SHUTDOWN JUSTIFICATION CSV-24
' System : Safety' Injection Valvefs): . 1-SI-MOV-1865A 1-SI-MOV-1865B-1-SI-MOV-1865C-Category: B Class- : 2 Function: ' SI' Accumulator Discharge Isolation Valves
. Cold ~ Shutdown Justification-
.The Accumulatos Discharge Isolation Valves are in their safety.
positions with power removed from.the: valve actuators during
- 4. . Modes 1, 2, and 3, and when the 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.
Testing-Frequency These valves will be full stroke exercised every cold shutdown but not-more frequently than once every three months.
l O 4-54 I N1PVI2R8 Revision'8 l '
August 17, 1998
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l /~'T COLD SHUTDOWN JUSTIFICATION CSV-25 l N~sl Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-26 Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-27 Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-28 Replaced by Relief Request V-70 O
i O 4-55 N1PVI2R8 Revision 8 August 17, 1998
COLD SHUTDOWN JUSTIFICATION CSV-29
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System : Auxiliary Feedwater LValve(s): 1- FW- 61 1-FW 1- FN- 63 1-FW-125 Category:' C Class : Function: Auxiliary Feedwater Header Check Valves 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 are required by Technical Specification Section 3.7.1.2 for normal operation.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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4-56 N1PVI2R8 Revision 8 August 17, 1998
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l COLD SHUTDOWN JUSTIFICATION CSV-30
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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 Category: AC Class ': NC Punction: Air Accumulator Isolation Check Valves 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- l 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, 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
Testing Frequency These check valves will be tested in the closed position every cold shutdown but not more frequently than once every three months.
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4-57 l N1PVI2R8 Revision 8 August 17, 1998 l l
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l f~'} COLD SHUTDOWN JUSTIFICATION CSV-31 v
! System. : Auxiliary Feedwater Valve (s) : 1- FW-HCV-100A 1-FW-HCV-100B 1-FW-HCV-100C Category: B Class : 3 Function: Standby Auxiliary Feedwater Supply Nalves 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
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because these valves mur,t be available in the event of a reactor trip.
Testing Frequency These valves will be partial stroke exercised every three months and full stroke exercised every cold shutdown but not more frequently than once every three months. The partial stroke exercise test does not require that stroke time be measured.
1 4-58 N1PVI2R8 Revision 8 August 17, 1998
p I [~' COLDfSHUTDOWN JUSTIFIC$ TION CSV-32 I
l Q.)Y' system : Auxiliary Feedwater Valve (s): : 1-FW-PCV-159A '
l-FW-PCV-159B Category:- B- '
9 Class .: 3 Function: Auxiliary Feedwater' Pressure Control Valves-Cold Shutdown Justification During normal operation, these valves control' auxiliary 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.
Testing Frequency These; valves'will be' partial stroke exercised every three months and full stroke exercised every cold shutdown but not more frequently than once every three months. The partial stroke exercise test does not require that stroke time be measured.
L 4-59 -
N1PVI2R8 Revision 8
' August 17, 1998 L. .
L COLD SHUTDOWN JUSTIFICATION CSV-33
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System : Main Steam l
. Valve (s): 1-MS-TV-113A 1-MS-TV-113B 1-MS-TV-113C Category: B Class : 2 Function: Main Steam' Trip Bypass Valves Cold Shutdown Justification These trip valves are opened only during plant startup to provide flowpaths for steam from each of the steam generators to equalize pressure across the main ste&. ' rip valves. They remain closed during normal operation to avvart~the unrestricted release of steam from multiple steam geherators in the event of a downstream steamline' rupture and to isolate the steam generators i (automatically'close on steamline or IHH isolation) in the event
- of a LOCA or steam generator tube rupture. When closed, they t
( s) provide isolation of the unaffected steam generators thus ensuring an adequate supply of steam for AFW pump turbine operation. They are designated as containment isolation valves (non-leak tested). There is a remote possibility that these valves would have to close during plant startup; therefore, they are considered active to the closed position only during plant startup. During normal operation-they are passive'in the closed position and do not require quarterly testing. They will be tested prior to startup to ensure' operability.
Testing Frequency These valves will be full stroke' exercised every cold shutdown prior to startup but not more frequently than once every three months. ;
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O 4-60 N1PVI2R8 Revision 8 August 17, 1998
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COLD SHUTDOWN JUSTIFICATION CSV-34 L 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 l
Category: B Class ': .3 Function:. Recirculation Spray Heat Exchanger' Service Water
. Supply and Discharge Isolation Valves.
-Dur'ing' normal operation, the lines between the Service Water supply 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
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ensure that no service water enters the heat exchangers. Full or i partially stroking the header isolation valves described above s would introduce service water-into the lines. These lines would have to be drained ~after each test.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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l (3 COLD SHUTDOWN JUSTIFICATION CSV-35 GI Replaced by Relief Request V-76 COLD SHUTDOWN JUSTIFICATION CSV-36 Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-37 Cold Shutdown Justification Withdrawn i
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'v 4-62 N1PVI2R8 Revision 8 August 17, 1998
i 1
COLD SHUTDOWN JUSTIFICATION CSV-38
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System : Chemical-~and Volume Control Valve (s):. 1-CH-252 1-CH-264 1-CH-277 1-CH-649
' Category: C Class .: 2' Function:- Charging Pump Recirculation Line Check Valves l
Cold Shutdown Justification These' check valves must open to allow charging pump
- recirculation. There is no permanently mounted instrumentation to measure full flow 11n the recirculation flow path. Therefore, full-flow conditions will have to be measured by using temporary ultrasonic flow instrumentation. The ultrasonic flow transducers and their mounting _ carriages must be installed and the transducers referenced to a no flow condition before each test.
C') After each test, the equiptent must be removed-from the field and decontaminated if necessary. Therefore, use of the ultrasonic flow instrumentation is very labor' intensive and not practical for quarterly testing.
Testiexperience 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.
Testing-Frequency
- These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
l O 4-63 N1PVI2R8 Revision 8 August 17, 1998 l
COLD SHUTDOWN JUSTIFICATION CSV-39 Cold Shutdown Justification Withdrawn l
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O 4-64 N1PVI2R8 Revision 8 August 17, 1998 I
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e COLD SHUTDOWN JUSTIFICATION CSV-40 l
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System : Auxiliary Feedwater Valve (s): 1-FW-062 1-FW-149 1-FW-064- 1- FW-155 1-FW-094 1- FW-16 6 1- FW- 0 9 6 1-FW-172 1- FW-12 6 1- FW-18 4.
1- FN-12 8 1-FW-190 Category: B Class : 3 Function: Auxiliary Feedwater Header Alignment and Cross Connect Manual Valves 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 k feed line break or steam line break, no credit is taken for operator action during the first 30 minutes. When manual operator action is taken the faulted steam generator is isolated ,
and manual flow control is required. The auxiliary feedwater I pumps are realigned using the manual valves. Therefore, the
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manual valves must be known'to be operable.
i 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 i cold shutdown is adequate to demonstrate that these valves can be i
. manipulated in-case the auxiliary feedwater paths need to be j changed. j Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
O 4-65 ,
N1PVI2R8 Revision 8 August 17, 1998 L
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-COLD SHUTDOWN JUSTIFICATION CSV-41 l . LSystem : Auxiliary Feedwater Valve (s) : 1-FW-145 1- FN-18 0 FW-162 1- FW-227 Category: B Class :- 3 Function: Auxiliary Feedwater Pump Alternate Supply Manual
' Valves Cold Shutdown Justification 1These 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 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.
Testing Frequency These valves will be full stroke exercised every cold shutdown L but.not more frequently than once every three months.
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COLD SHUTDOWN JUSTIFICATION CSV-42
' System :- Reactor' Coolant
, Valve (s): 1-RC-PCV-1455C 1-RC-PCV-1456 Category: -BC Class : l' Function: Pressurizer Power Operated Pressure _ Control Valves 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.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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'N1PVI2R8 Revision 8 August 17, 1998 i;
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/N COLD SHUTDOWN-JUSTIFICATION CSV-43 V'
System- : Service Water Valve (s): 1-SW-MOV-108A 1-SW-MOV-108B Category: .B 4
Class- : 3 Function:' Component Cooling Heat Exchanger Service Water Supply
' j Isolation Valves Cold Shutdown Justification These isolation valves are located in series on service water supply to the component cooling heat exchangers. The component cooling heat exchangers carry a majority of the heat load for the service water system. When the heat exchangers are isolated, service water flow decreases to less than 10% of normal flow.
Due to the design of the service _ water pumps, the pumps experience harmful high-magnitude vibrations as the service water 7] flow decreases through a range from 7000 gpm to 6000 gpm. These
(_) pumps cannot be stopped during the valve exercise test because they provide service water to other plant heat loads. Therefore, performing the valve exercise test as frequently as once every three months should be avoided due to the harmful affects that the testing has on the service water pumps.
The valve controllers do not allow for a partial-stroke exercise test. To reduce the harmful affects of high-magnitude vibrations on the service water pumps, the isolation valves will be full-stroke exercised on a cold shutdown frequency.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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4-68 -
.N1PVI2R8 Revision 8
' August 17, 1998
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' COLD. SHUTDOWN JUSTIFICATION CSV-44 O.
[ System : Quench Spray Valve (s) : 1-OS-MOV-102A
'l-OS-MOV-102B Category: B Class- :- 2 Function: Chemical Ad'dition Tank' Discharge Isolation Valves Cold Shutdown Justification These normally closed six inch motor operated isolation valves are located in parallel flow paths from the refueling water chemical' addition tank to the reactor water storage tank (RWST).
The piping between the isolation valves and the chemical addition tank contains high concentrations of sodium hydroxide. To exercise the-motor. operated valves, downstream manual isolation valves must be closed to prevent the sodium hydroxide from entering the quench spray system and chemically contaminating the boric acid solution in the RWST.
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After the motor operated isolation valves are stroked open and closed, the piping between the motor operated valves and the downstream manual isolation. valves must be drained of sodium hydroxide. Approximately five gallons of highly caustic fluid are drained into a plastic container after each valve test.
Draining the piping presents a significant personnel hazard.
Sodium hydroxide causes severe burns if it comes in contact with the skin. The test personnel must wear rubber gloves, boots and face shields.
-The. drains are located outdoors and are near to the ground, which makes collection difficult. Any soil that is contaminated with sodium hydroxide must be neutralized by the test personnel.
Partial' stroke testing of-these valves presents the same hazards as full stroke testing.
To reduce the number of times that test personnel are exposed to sodium hydroxide, the motor operated isolation valves will be tested on a cold shutdown frequency.
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4-69 N1PVI2R8 Revision 8 August 17, 1998 l
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( COLD SHUTDOWN JUSTIFICATION CSV-44 (Cont.)
l Testing Frequency i
These valves will be full stroke exercised on a cold shutdown frequency but not more frequently than once every three months.
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ks O 4-70 N1PVI2R8 Revision 8 August 17, 1998
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( COLD SHUTDOWN JUSTIFICATION CSV-45 Replaced by Reactor Refueling Justification RRV-26 y 2
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O 4-71 N1PVI2R8 Revision 8 February 25, 1999
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('N COLD SHUTDOWN JUSTIFICATION CSV-46 l
Ns-System : Residual Heat Removal Valve (s): 1-RH-7 I
l-RH-15 l
Category: C
. Class' :- 2 l . Function:- RHR Pump Discharge. Check Valves
. Cold Shutdown Justification These.RHR pump' discharge check valves can only be' partial-stroke or full-stroke exercised to the open position and verified closed when 'the IGR pumps 1-RH-P-1A and 1-RH-P-1B are running. 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, partial-stroke or full-stroke testing during normal operation is
'not practical.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
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)() 4-72 N1PVI2R8 Revision 8 August 17, 1998 l
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COLD SHUTDOWN JUSTIFICATION CSV-47 Replaced by Reactor Refueling Justification RRV-25 l
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O 4-73 N1PVI2R8 Revision 8 August 17, 1998
COLD' SHUTDOWN JUSTIFICN' TION CSV-48
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System : Chemical &-Volume Control
- Valve (s): il-CH-MOV-1380 1-CH-MOV-1381 Category: , A -
Class : 2 Function: Reactor Coolant Pump Seal Water Return Containment Isolation-Valves Cold Shutdown' Justification Charging. flow-to the reactor coolant pump seals is required st all
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' times while.the pumps are in operation. Failure of one of these valves in the closed position could result in damage to the reactor coolantfpump 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 exerciseLtests.. j Testing. Frequency Exercise every cold shutdown when the reactor coolant pumps are secured and reactor coolant pressure is above 100 psig but not more_ frequently than once every three months.
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- O 4-74 -
'N1PVI2R8 Revision 8
' August 17, 1998
a COLD SHUTDOWN DUSTIFICATION CSV L [VY l
l ' 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 : l' Function: Reactor Vessel Vent Line Isolation Valves Cold Shutdown Justification These valves are-the Reactor Vessel Head Vent Valves. Full or part-stroke exercising these valves.at power could release reactor coolant into the 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 O- Reactor Coolant System is pressurized. These valves will be
. exercised during each cold shutdown when the Reactor Coolant System is depressurized.
Testing Frequency
. Exercise for operability during cold shutdown when the Reactor Coolant System is depressurized but not more frequently than once per three months.
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O 4-75 N1PVI2R8 Revision 8 August 17,.1998
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! ~4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS
!. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the l
full stroke exercising of valves during reactor refueling ' (but not more frequently than every three months) if-the valves cannot be exercised during normal operation or cold shutdown. Therefore, no request for relief from testing every three months is necessary.
However, OM Part 10, Section 6.2 does require that these valves be specifically identified by the owner.
The reactor refueling justifications identify and provide the technical basis for valves exercised during reactor refueling outages.
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1 IO l 4-76 N1PVI2R8 Revision 8 August 17, 1998
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r REACTOR REFUELING JUSTIFICATION RRV-1 System :- Component Cooling-Valve (s):' 1-CC-84 1-CC-119-1-CC-154 Category: C Class : 2 Function: CC Supply to Reactor Coolant Pump Containment Isolation Check Valve Reactor Refueling Justification 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. Since the valves are located inside containment and their systems are required during power operation, they cannot be tested every three months. The valves will be exercised only during O 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.
Testing Frequency Exercise for operability each reactor refueling.
O 4-77 N1PVI2R8 Revision 8 August 17, 1998
I
(] REACTOR REFUELING JUSTIFICATION RRV-2 U
System : Chemical & Volume Control Valve (s): 1-CH-322 1-CH-336 1-CH-380 1-CH-330 1-CH-358 1-CH-402 Category: AC for 1-CH-322, 330 and 402 C for 1-CH-336, 358 and 380 Class : 1 for 1-CH-330, 336, 358 and 380 2 for 1-CH-322 and 402 Function: Charging Supply Inside Containment' Isolation Check Valves (1-CH-322, 330), RC Pump Seal Water Supply Isolation Check valves (1-CH-336, 358 and 380), and RC Pump Seal Water Return Containment Isolation Check Valve (1-CH-402)
Reactor Refueling Justification These check valves must seat upon reversal of flow in order to fulfill their safety functions. The only method to verify this
//
's-t 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 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 testss Testing Frequency Exercise for operability each reactor refueling.
(s / I 4-78 N1PVI2R8 Revision 8 August 17, 1998 ,
R
/ ' REACTOR REFUELING-JUSTIFICATION RRV-3 System :: Fire Protection
. Valve (s): 1-FP-272-1 Category: AC Class .: 2 Function: Fire Protection System Supply Containment Isolation
-Check' Valve Reactor Refueling Justification This-check valve.must seat upon reversal of flow in order to fulfil 1 Lits safety function. The only method to verify this actuation isLto perform a leak rate /back pressure test. Since the valve is located inside. containment, it cannot be tested every three months. 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 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.. This technical basis is consistent with the NRC' position on this subject that is described in NUREG-1482, Section 4.1.4, entitled " Extension of Test Interval to
' Refueling Outage for Check. Valves Verified Closed by Leak Testing."
Testing Frequency
. Exercise for operability each reactor refueling.
4-79
'N1PVI2R8 Revision 8 August 17, 1998
m REACTOR REFUELING JUSTIF5 CATION RRV-4 System : Post Accident Hydrogen Removal Valve (s) : 1-CV-8 1-HC-14 1-CV-14 1-HC-18 Category: AC for 1-HC-14 and 18 C for 1-CV-8 and 14 Class : 2 Class : 2 l Function: Containment Vacuum System Isolation Check Valves and Hydrogen Analyzer /Recombiner Containment Isolation Check Valves Reactor Refueling Justification Check valves 1-CV-8 and 14, 1-HC-14 and 18 must open to sample hydrogen to fulfill their safety functions. To test valves 1-HC-14 and 18 either partially or full open, and to test valves 1-CV-8
'("'s and 14 full open requires a significant manipulation of the s ,)
m hydrogen recombiner system. In addition, should a containment pressurization event occur while operating the hydrogen recombiners, there is a possibility of exceeding the design pressure of the recombiner system, which may result in a loss of recombiner function. The hydrogen recombiner is a low pressure system intended for use after the containment depressurizes.
Valves 1-CV-8 and 14 can be tested to the partially open position every quarter using the containment vacuum pumps while maintaining the recombiner system isolated from the containment atmosphere.
These valves will be verified open at least once every 18 months during the surveillance testing of the hydrogen recombiner system as required by Technical Specification Section 4.6.4.2. The small increase in safety' gained by testing during normal operation or cold shutdown does not justify the potential risk of overpressurizing the hydrogen recombiner system, or the added ;
burden of disrupting normal plant operations to manipulate the recombiner system and performing the test on the more fregi: int basis.
l Check valves 1-HC-14 and 18 also provide containment isolation.
These check valves must seat upon reversal of flow in order to fulfill their safety functions. The only exercise method to i
/~~T verify closure-is to perform a leakage /back pressure test.
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L N1PVI2R8 Revision 8
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(~) REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)
l V Since the valves are located inside containment, they cannot be tested every three months. Performing a leakage /back pressure test requires installing temporary leakage test equipment.
Because of the effort involved, it is impractical to perform this test during cold shutdowns. They will be verified closed only during refueling outages. This technical basis is consistent with the NRC position on this subject that is described in NUREG-1482, Section 4.1.4, entitled " Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing."
Testing Frequency Check valves 1-HC-14 and 18 will be exercised to the closed position every reactor refueling. Check valves 1-CV-8 and 14, 1-HC-14 and 18 will be exercised to the full open position at least once every 18 months. Valves 1-CV-8 and 14 will be exercised to the partially open position once every three months.
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V 4-81 N1PVI2R8 Revision 8 August 17, 1998
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' REACTOR REFUELING JUSTIFICATION RRV-5 j
System; ; Instrument Air j
Valve (s) : . 1-IA-55 1-IA-149 Category: AC Class -: 2' Function: Instrument Air Supply Containment Isolation Check Valves Reactor Refueling Justification These check valves must seat upon reversal of flow in order tt 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 instrument air supply line to
< containment. Testing this valve renders the instruments and components' supplied by instrument' air inside containment
/s inoperable.
U
.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 performing leak rate tests. This technical basis is consistent with the NRC position on this subject that is described in NUREG-1482,.Section 4.1.4, entitled
" Extension ofLTest Interval to Refueling Outage.for Check Valves
. Verified Closed'by Leak Testing."
Testing Frequency Exercise for operability each reactor refueling.
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. N1PVI2R8 Revision 8 August 17, 1998
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l REACTOR REFUELING JUSTIFICATION RRV-6
. System : Reactor' Coolant Valve (s): 1-RC-149-Category:. AC Class :- 2 Function: Primary Grade Water' Supply Containment Isolation Check Valves Reactor Refueling Justification 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. 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 during normal cold shutdowns. Standpipe level must be maintained
'/ Y when the RCS is pressurized to control'1eakage. 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. This technical basis is consistent with the NRC position on this subject that is described in NUREG-1482, Section ,
4.1.4, entitled " Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing."
Testing Frequency Exercise for operability each reactor refueling.
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-fD 3s _/ i 4-83 N1PVI2R8 Revision 8 August 17, 1998
I
-REACTOR REFUELING JUSTIFICATION RRV-7
' System : Safety Injection
. Valve (s) : 1-SI-9 l-SI-18!
l-SI Category:- C Class : 2 Function: Low Head SI Pump Discharge Check Valves Reactor Refueling Justification Due to system design, check valves 1-SI-9 and 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-18 can only be partial stroked every quarter because the quarterly test loop is a mini-flow loop.
During cold shutdown, the reactor coolant system pressure still O. 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, the low head safety injection system must be isolated which can only be done at reactor refueling., By isolating the system, the test boundary is established to demonstrate adequate seat tightness for the discharge valve to the non-running pump.
l Testing Frequency
. Valves 1-SI-9 and 26 will be exercised to the full open and i closed position every reactor refueling. Valve 1-SI-18 will be !
partial stroke tested every quarter and full flow tested every reactor refueling. j l
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4-84 N1PVI2R8 Revision 8 August 17, 1998
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y REACTOR REFUELING JUSTIFICATION RRV-8 System- : ESafety Injection' Valve (s): 1-SI-47' Category: AC Class : 2-Function: RWST Supply to Charging Pump Suction Header Check Valves-Reactor Re'ueling f Justification 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. Full
'l flow for the charging system can only be established during 1 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 Specification O 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. This technical basis-is consistent with the NRC position on this subject'that is described in NUREG-1482, Section 4.1.4, entitled
" Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing."
Testing Frequency
-Exercise-to the partially open position during cold shutdown, i exercise to the fullLopen and closed positions every reactor refueling.
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- N1PVI2R8 Revision 8 l August 17, 1998 ;
g o l-REACTOR REFUELING JUSTIF3 CATION RRV-9
' System : Safety Injection Valve (s) : 1-SI-106 1-SI-110 Category:- AC -
Class : 2.
Function:: Nitrogen Supply to Accumulators' Containment Isolation Check Valves Reactor' Refueling Justification These check valves must seat-upon reversal of flow in order to fulfill their safety functions. The only method to verify closure is 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 O
\
performing a leak rate test. This technical basis is consistent with the'NRC position'on this subject that is described in NUREG-
- 14 82, Section .4.1. 4, entitled " Extension of Test Interval to Refueling' Outage for; Check Valves Verified Closed by' Leak Testing." l Testing Frequency Exercise for operability every reactor refueling. .
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N1PVI2R8 Revision 8
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-REACTOR REFUELING JUSTIFICATION RRV-10 System : Safety Injection Valve (s):- 1-SI-83 1-S7-195 SI-86 1-SI-197 1-SI-89 1-51-199 Category:- AC Class : 1 Function: RCS Cold Leg SI Admission Check Valves Reactor Refueling Justification These Safety ~ Injection check valves must open and close to fulfill their safety functions. 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. Flow cannot be established in the low head injection lines during normal plant operation.
O 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 I and force'a safety system to function.
These valves can only be tasted to the closed position by draining the lines and performing a back. seat leak test. They are identified as pressure isolation' valves in Technical Specification Table 3.4-1 and as such are leakage tested every reactor refueling outage.
For testing to the open position, these valves will be nonintrusively monitored using a sampling plan every reactor refueling as described in Relief Request V-41.
. Testing Frequency Exercise to the open position using nonintrusive techniques every reactor refueling. Exercise to the closed position every reactor refueling per Technical Specification 4.4.6.2.2.
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'N1PVI2R8 Revision 8 August 17, 1998 n
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O REACTOR' REFUELING JUSTIFICATION RRV-11
.J System :- Safety Injection 1
i 1
Valve (s): 1-SI-125 1-SI-144 SI-127 1-51-159 1-SI-142 1-SI-161 Category: C Class : 1
-Function: SI Accumulator Discharge Check Valves Reactor Refueling Justification These valves cannot be partial or full flow tested during normal operation because the accumulator 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 accumulators would challenge g the Low Temperature Overpressure Protection System.
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 i 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. 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 1 safety gained by performing the back seat check valve tests every cold shutdown versus every reactor refueling does not justify the added burden of the increased test frequency.
For. testing to the open position, these valves will be
'nonintrusively monitored using a sampling plan every reactor refueling as described in Relief Request V-42. {
l O 4-88 N1PVI2R8' Revision 8 August 17, 1998 l
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) REACTOR REFUELING JUSTIFICATION RRV-11 (Cont.)
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. Testing Frequency Exercise to the open position using nonintrusive techniques every reactor refueling. Valves 1-SI-127, 144 and 161 will be confirmed closed every reactor refueling.
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'\s] 4-89 N1PVI2R8 Revision 8 August 17, 1998
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. REACTOR REFUELING JUSTIFICATION.RRV-12 l 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 1-51-207 1-SI-103 1-SI-209 Category: AC for 1-SI-79, 90, 185, 201, 206 and 207 C for 1-SI-95, 99,.103,~ 209, 211 and 213 Class : 1 for 1-SI-90, 95, 99, 103, 201, 209, 211 and 213
'2 for 1-SI-79, 185, 206, 207 Function: High Head SI to RCS Cold Legs Check Valves (1-SI-79 and 185), High Head SI to RCS Hot Legs Check Valves (1-SI-90 and 201), SI to RCS Hot Legs Check Valves (1-SI-95, 99 and 103), Low Head to RCS Hot Legs Check Valves -(1-SI-206, 207, 209, 211 and 213)
Reactor Refueling Justification 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~cause safety injection' flow into the Reactor Coolant System which would thermally shock the injection system i and cause unnecessary plant transients. Flow cannot be !
testablished in the' low head injection lines during normal plant operation.
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 l and force a safety system to function.
'TheseLvalves can only be tested ~to the closed position by a back '
seat' leak test, which requires draining the lines.
For testing to'the open position, the hot leg injection valves 1-SI-95, 99, 103, 209, 211 and 213 will'be nonintrusively monitored using a sampling plan every reactor refueling as described in ,
Relief' Request V-43. The remaining check valves can be full flow '
tested using' installed' instrumentation.
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-N1PVY2R8 Revision 8 I August 17, 1998 l
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"5 REACTOR REFUELING JUSTIFICATION RRV-12 (Cont.)
(V .
Testing Frequency Exercise valves 1-SI-79, 90, 185, 201, 206 and 207 to the open position using flow every reactor refueling. Exercise valves 1-SI-95, 99, 103, 209, 211 and 213 to the open position using nonintrusive techniques every reactor refueling. Exercise each valve to the closed position every reactor refueling.
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N1PVI2R8 Revision 8 August 17, 1998
[~N REACTOR REFUELING JUSTIFICATION RRV-13
- System 'i Safety Injection Valve (s): 1-SI-190 1-SI-192 1-SI-194 Category: C .
Class : -1 Function: High Head SI to RCS Cold' Legs Check Valves Reactor Refueling Justification 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.
During cold shutdown, the Reactor Coolant System pressure still O 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.
Testing Frequency Exercise to the open position using flow and to the closed position.every reactor refueling.
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REACTOR REFUELING JUSTIFICATION RRV-14 System : -Service Water Valve (s): 1-SW-114 1-SW-140 1-SW-116- 1-SW-150 1-SW-120 1-SW-130 Category: C Class : 2 for 1-SW-120, 130, 140, 150 3'for 1-SW-114, 116
-Function: Recirculation' Spray Heat Exchanger Service Water Supply Check Valves Reactor Refueling Justification Fullfor 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
(~T exchangers are drained, purged with air and maintained in dry layup. The logistics of this procedure make testing at cold shutdown impractical considering the small increase in. system safety gained from exercising the valves.
Testing Frequency Exercise for operab111ty every reactor refueling.
4-93 N1PVI2R8 Revision 8 August 17, 1998
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. REACTOR REFUELING JUSTIFICATION RRV-15 System :. Vacuum Priming Valve (s): 1-VP-12 Category: AC Class :- 2 Function: Condenser. Air Removal Discharge Containment Isolation Check Valve Reactor Refueling Justification 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. This technical-basis is consistent with the-NRC position on this
/% subject'that is described in'NUREG-1482, Section 4.1.4, entitled
'ss / . " Extension of Test-Interval to Refueling Outage for Check-Valves
' Verified Closed.by Leak Testing."
Testing Frequency Exercise'for operability every reactor refueling.
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N1PVI2R8- Revision 8 l August 17, 1998 a '
REACTOR-REFUELING JUSTIFICATION RRV-16 System, : LCH~
q-
' Valve (s) : 1-CH-254 1-CH-267
.1-CH-279 Category:. C Class .: 2 Function: Charging Pump Discharge Check Valves Reactor Refueling Justification 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 system and could force a safety system to function..
-Testing Frequency Exercise closed every three months and exercise full open every.
reactor refueling. Valves are partial exercised open during {
normal' operation when the charging train is in service.
O 4-95 j N1PVI2R8 Revision 8 August 17, 1998 4
n REACTOR REFUELING JUSTIFICATION RRV-17 System : SI Valve (s): 1-SI 1-SI Category: AC Class : 2 Function: . Low Head SI Pump Seal Water Supply Check Valves Reactor' Refueling Justification Due to the plant configuration, these valves cannot be-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 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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
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 test 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. This technical basis is consistent with the NRC position on this subject that is described in.NUREG-1482, Section 4.1.4, entitled " Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing."
l fy l 4-96 L N1PVI2R8 Revision 8 L August 17, 1998 u
l l-REACTOR REFUELING JUSTIFICATION RRV-17 (Cont.)
Testing Frequency Exercise to the closed position every reactor refueling.
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4-97 N1PVI2R8 Revision 8 August 17, 1998
O. ' REACTOR ~ REFUELING JUSTIFICATICN RRV-18 D
System' :' Component = Cooling Valve (s): 1-CC-546 1-CC-559-1-CC-572
' Category: AC- -
Class- .: 2 Function: CC Water Supply to Containment Recirculation Air Coolers Containment Isolation Check Valves }
Reactor Refueling Justification 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 ihvolve isolating.the containment air
. cooling coils. The containment recirculation air cooling coils are required for normal operation to maintain' containment
('l . temperature below technical specification limits. Therefore, V.' these valves cannot be tested every three months.
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 test. performed every cold shutdown, the performance of a leak test everyLrefueling outage is an alternative that provides an acceptable level of quality and safety. This technical basis is consistent with the NRC position on this subject that is described in NUREG-1482, Section'4.1.4, entitled " Extension of
, Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing."
-Testing Frequency Exercise to the closed position every reactor refueling.
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N1PVI2R8 Revision 8 August 17, 1998 L
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N, REACTOR REFUELING JUSTIFICATION RRV-19 System :- Service Water Valve (s): 1-SW-3 1-SW-10 Category: C Class : 3 Function: Service Water Pump Discharge Check Valves I l
Reactor Refueling' Justification l These. check valves cannot be full flow tested during' normal l operation or cold shutdown because the Recirculation Spray Heat ;
Exchangers must be included in the. flow path in order for full I flow conditions to be established. As described in Reactor Refueling Justification RRV-14, introduction of service water to i the-Recirculation Spray Heat Exchangers is prohibited without subsequently draining the heat exchangers. This requirement makes testing during normal operation or cold shutdowns
(\ impractical.
d
. 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 l of the non-running pumps. However, the observation of the non- i running pump discharge gauge to detect gross failure can and should be performed every three months.
Testing Frequency i These valves will be partial flow tested every three months, and
. full flow and closure tested every reactor refueling. The non- ,
running pump discharge gauge will be observed once every three '
months to_ detect gross failure of the disk to seat.
4-99 j N1PVI2R8 Revision 8 j August 17, 1998 1 i
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REACTOR REFUELING JUSTIFICATION RRV-20 System : Component Cooling ' -
Valve (s): 1-CC-111 1-CC-146 1-CC-181 Category: C Class :' 3 Function: CC Supply to RC Pump Thermal Barrier Cooler Isolation Check Valves Reactor Refueling Justification 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 Testing' Frequency Exercise to the closed position every reactor refueling.
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4-100 N1PVI2RB q Revision 8 August 17, 1998 ,
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REACTOR REFUELING JUSTIFICATION RRV-21 System : Recirculation Spray Valve (s): 1-RS-18 1-QS-11 1-RS 1-0S-19 Category: AC L
Class : 2 Function: Quench Spray and Outside Recirculation Spray
. Containment Isolation Check Valves Reactor Refueling Justification These valves must seat to maintain containment 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. Howe'rer, the valves are located inside containment and require the construction of scaffolding before they can be exercised. The small increase in
'~'i safety gained by exercising the valves during cold shutdown does
(_/ not justify the burden of co.nstructing the scaffolding.
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 test 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. This technical basis i is consistent with the NRC position on this subject that is described.in NUREG-1482, Section 4.1.4, entitled " Extension of Test Interval to Refueling Outage for Check Valves Verified l Closed by Leak Testing." ~
Testing Frequency These valves will be exercised to the open and closed positions every reactor refueling.
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() 4-101 N1PVI2R8 Revision 8 August 17, 1998 l
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Kj} REACTOR REFUELING JUSTIFICATION RRV-22 System. : Component Cooling Valve (s):' 1-CC-193.
1-CC-198 Category: AC Class' : 2-l Function: CC Water. Supply to the RHR Heat Exchangers Containment Isolation Check Valves.
Reactor Refueling Justification i
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.
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5-s 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.
Testing' Frequency Exercise-for closure and full open every reactor refueling.
Partial stroke open every quarter.
(G 4-102 N1PVI2R8 Revision'8 August 17, 1998
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REACTOR REFUELING JUSTIFICATION RRV-23
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System : Chemical & Volume Control System Valve (s): 1-CH-215 1-CH-649 Category: AC Class : 2 Function: Charging Pump Supply from the VCT (1-CH-215) and Charging Pump Recirculation and Seal Water Return (1- I CH-649) Containment Isolation Check Valves Reactor Refueling Justification )
l Due to the plant configuration, these valves cannot be verified 1 closed using flow. The only method to verify closure other than disassembly and inspection is to perform a leak rate /back l pressure test on each valve. 1 During normal operation, these valves cannot be isolated to t)
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perform a back pressure test because normal letdown and charging flow, and reactor coolant pump seal flow would be interrupted. i Also, if the valves were isolated during normal operation, the !
charging pumps would have to be secured. .
These valves are also subject to leak testing, which is performed l every reactor refue'ing. A leak test provides more information l
! concerning the condition of the valve seats then just a back i pressure test. When compared to the Code requirements for a backseat test 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. This technical basis I is consistent with the NRC position on this subject that is
! described in NUREG-1482, Section 4.1.4, entitled " Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing."
I Testing Frequency Exercise to the closed position every reactor refueling.
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4-103 N1PVI2RB Revision 8 August 17, 1998
REACTOR REFUELING' JUSTIFICATION RRV-24 ji System; : Service Water
- Valve (s) : 1-SW-22 Category: Cs Class : 3 .
Function: Auxiliary Service Water Pump Discharge Check Valve Reactor Refueling Justification 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 used.
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Testing Frequency-This valve will be disassembled and inspected on a reactor refueling test. frequency and partial flow tested every three months.
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() 4-104 -
N1PVI2R8 .
Revision-8
' August 17, 1998
_ 4.
REACTOR REFUELING JUSTIFICATION RRV-25 System- : Safety Injection Valve (s) : 1-SI-MOV-1867A 1-SI-MOV-1867B 1-SI-66 Category: B (1-SI-MOV-1867A and B)
C (1-SI-66)
Class : 2 Function: Boron Injection Tank Inlet Isolation valves (1-SI-MOV-1867A and B) and Boric Acid Recirculation Line Check
. Valve (1-SI-66)
Reactor-Refueling Justification During normal operation, the boron injection tank (BIT) is isolated from the charging system and the reactor coolant system by the inlet isolation valves 1-SI-MOV-1867A and B and the outlet isolation valves 1-SI-MOV-1867C and D. These valves open upon safety injection initiation. As shown in Figure RRV-25, the O' inlet valves are located on parallel paths. The normal operating
-pressure just upstream of the isolation valves is batween 2600 !
and 2650 psig which is the discharge pressure of the charging pumps. The downstream pressure is approximately 40 psig. The l reason for this low pressure is that the BIT boric acid solution is constantly circulated by the relatively low pressure boric acid transfer pumps.
i Tests.have revealed that when either 1-SI-MOV-1867A or B is opened using the normal valve actuator, the BIT and the associated piping experience a significant hydraulic transient. ,
This hydraulic transient also perturbs the reactor coolant pumps (RCPs) seal injection flow because the RCP seal flow comes off the same header as the BIT flow. When the BIT inlet isolation ,
valve is opened, flow to the RCP seals decreases until the BIT volume becomes pressurized. - While this is happening the charging Innnp discharge header flow increases because of the newly opened
' flow path to the BIT.- Once-the BIT volume is pressurized, the
- increased ~ charging pump discharge header flow is diverted to the RCP seal injection paths which momentarily causes a high flow
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. condition in the RCP seals. During one test, the reactor coolant system controlled leakage limit of 30 gpm (T.S. Paragraph 3.4.6.2.e) for total seal injection flow was exceeded.
4-105 N1PVI2R8 Revision 8 August 17, 1998
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-O REACTOR' REFUELING JUSTIFICATION RRV-25 (Cont.)
V L In the past, the BIT volume-was pressurized slowly by manually
. cracking one of the inlet isolation valves, thus avoiding the 1
hydraulic. transient described above. However, this practice has been discontinued because it could be construed as.
-preconditioning in light of IN 97-16, "PRECONDITIONONG OF PLANT STRUCTURES,' SYSTEMS,-AND COMPONENTS BEFORE ASME CODE INSERVICE TESTING OR TECHNICAL SPECIFICATION SURVEILLANCE TESTING."
Preconditioning a' valve can-invalidate its ASME test.
During cold shutdowns the charging system is still in use.
~Therefore, a high differential pressure exists across the BIT inlet isolation _ valves even during cold shutdowns. The hydraulic transient caused by. opening'the BIT inlet isolation valve with a high differential pressure across the valves places stress on the BIT and the associated piping. Also, the oscillating RCP seal injection flow may have.a degrading effect on the RCP seals when the RCPs are operating. To. eliminate these concerns, the ;
exercise tests will be performed during reactor refueling when l' the charging system is not operating.
In the.past, the BIT recirculation line isolation check. valve 1-(
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SI-66 was backseat tested using charging system' pressure to create a. pressure differential-across the valve disk._ Leakage was collected'at a point upstream of the check valve. . This test was performed'after the' inlet isolation valves are opened. The hydraulic transient described above was avoided by disabling one ofothe inlet isolation' valves and manually cracking the valve open_so as.to slowly pressurized the BIT. However,1this method of testingLdisables the BITJinlet valves and presents the potential-for causing a_ hydraulic-transient if the inlet valve is opened too.quickly. The preferred method for backseat testing- !
the check valve is during reactor refuelings when the charging l system isusecured and a local backseat / leak test can be 1 performed.. According to NUREG-1482, Section 4.1.4, "The NRC has !
. determined that the need to set up test equipment is adequate justification to defer back flow testing of a check valve until a refueling outage." 1 Testing Frequency l
.The.BITfinlet isolation valves will be full stroke exercised and the BIT recirculation line check valve will be backseat tested
'every reactor refueling.
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4-106
.N1PVI2R8 Revision 8 !
August 17, 1998 4
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REACTOR REFUELING JUSTIFICATION RRV-25 (Cont.)
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TO BORIC NORM 1-88-RV 1857 AcaD TAN 4 CHARGING 1-86480V-1867D TO M RCS ##'I2" 186-M -1867C 1-CnMcN-12808 g RCS n
i V-18678 PUMP DISOdRGE 1 .
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s R SEAL ri 1-88 66 1-88-MOV 1867A
,.8, , ,,,8 1C-= 12= s PROM BORIC 1&MOV-1287A b RCP SEAL TO -- -
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RCS n RCP Ei(AL IPUECTION 1 ChP 1A FIGURE RRV-25 i
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4-107 N1PVI2R8 Revision 8 l August 17, 1998 ;
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/3 i t REACTOR REFUELING JUSTIFICATION RRV-26 N_/
System : Service Water Valve (s) : 1-SW-1067 1-SW-1070 1-SW-1139 Category: B Class : 3 Function: Chemical Addition Service Water Manual Isolation Valves Reactor Refueling Justification These normally open manual 1 inch (1-SW-1067 and 1070) and 1.5 inch (1-SW-1139) valves are closed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the accident as required by the abnormal operating procedures to prevent loss of service water in the event that the connected ;
non-seismic pipe fails. These valves are located in an expansion '
joint vault outside the service water pump house. The vault is
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(_j defined as a confined space due to possible consumption resulting from an expansion joint failure. Entry into this confined space requires an entry permit, an air meter and two operators (buddy system). Also, special tools are required to remove the manhole cover which weighs in excess of 300 lbs and is a missile barrier.
(2 Closing these valves would require securing the service water O addition system which could adversely affect the biological agent concentration in the service water.
These valves are simple manual valves and are not subject to degradation mechanisms experienced by power operated valves.
Because the valves are normally open and not exercised frequently, they experience little wear. Closing these valves ,
every three months or every cold shutdown to fulfill test !
frequency requirements creates an undue burden with no compensating benefit to quality and safety. Exercising these valves on a reactor refueling test frequency is adequate to i demonstrate that the valves can be closed in case service water 1 isolation is required. The valves can be exercised while the !
plant is operating. To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be exercised on a reactor refueling frequency (not to exceed 24 months) but not necessarily during refueling outages, j
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('~) 1 4-107a N1PVI2R8 Revision 8 February 25, 1999 ;
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s REACTOR REFUELING JUSTIFICATION RRV-26 (Cont.)
Testing Frequency
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W These valves will be full stroke exercised to the closed position d.
on a reactor refueling frequency (not to exceed 24 months) but O not:necessarily during refueling outages.
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LO l 4-107b I -- N1PVI2R8 Revision 8 February 25, 1999
4 4.8 ALTERNATIVE TESTING FOR NON-d' ODE VALVES 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 I
pumps and valves not covered by the Code. If non-Code l 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 l Commission regulttions (10 CFR 50.55a) do not require a
' request for relief' to be submitted to the staff.
Nevertheless, documentation that'provides assurance of l the continued operability of the non-Code components l 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 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 l
available at the plant site.
As indicated in the minutes of public meeting on Generic Letter 89-04, a ' request for relief' need not l be submitted for non-Code components. Therefore, the l
alternative tests described in this section are not i ' requests for relief' but are provided for information.
l 4-108 -
N1PVI2R8 Revision 8 August 17, 1998
NON-CODE ALTERNATIVE TESTING VNC-1 1 System : Service Air Valve (s): 1-GN-225- '1-IA-2152 1-GN-229 1-IA-2153 1-IA-2154 1-IA-2155 Category: AC Class : NC Function: Bottled Air System Supply to PORV Isolation Check eValves OM Part 10 Code Requirements Which Will Not Be Met OM Part 10, Section 4.3.2.2(b) - During plant operation, each check valve shall be exercised or examined in a manner which
. verifies obturator travel to the closed, full-open or partially open position required to fulfill its function.
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\- / Basis For Alternate Testing 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.
Reactor Refueling Justification Due to the plant configuration, these valves cannot be verified closed using flow.
The only method to verify closure other than 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 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.
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4-109 N1PVI2R8 Revision 8 August 17, 1998
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r T NON-CODE ALTERNATIVE TESTING VNC-1 Nd l
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.
Alternate Testing proposed 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.
Testing Frequency
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(_,/ Exercise to the closed position every reactor refueling.
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4-110 N1PVI2R8 Revision 8 August 17, 1998
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NON-CODE ALTERNATIVE TESTING VNC-2 System : Instrument Air Valve (s): 1-IA-925 1-IA-926 1-IA-934 1-IA-935 Category: AC Class : NC j Function: Safeguard Area Fans Air Receiver Isolation Check Valves OM Part 10 Code Requirements Which Will Not Be Met 1 OM Part 10, Section 4.3.2.2 (b) - During plant operation, each check valve shall be exercised or examined in a manner which verifies obturator travel to the closed, full-open or partially .
open position required to fulfill its function. I Basis For Alternate Testing Back seating these valves requires that the lines upstream of the ;
valves be vented. The 1-IA-925 and 926 valves are in series,with j 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.
Alternate Testing proposed These valves will be leak /back seat tested in groups. 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. If the group fails the .
leak /back seat tests, both valves in the group will be j disassembled, inspected and repaired if necessary. '
f3 L) 4-111 N1PVI2R8 Revision 8 August 17, 1998
E f' NON-CODE ALTERNATIVE TESTING VNC-3 System : Instrument Air Valve (s): 1-IA-944 1-IA-963 l 1-IA-948 1-IA-967 l 1-IA-952 1-IA-971 i 1-IA-959 1-IA-975 g i l Category: AC ]
I Class : NC Function: Main Steam Pressure Control and Auxiliary Feedwater Valves Air Accumulators Isolation Check Valves l
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-(2d Part 10 Code Requirements Which Will Not Be Met OM Part 10, Section 4.3.2.3 - Category A valves, which perform a function other than containment isolation, shall be seat leakage tested to verify their leak-tight integrity.
/~N Basis For Alternate Testing
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l l Check valves 1-IA-944, 948 and 952_ isolate the normal instrument 1 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 l auxiliary feedwater valves 1-FW-HCV-100A, B and C. Valves 1-IA-l 967 and 975 isolate the normal instrument 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 i main steam PCVs and the 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 period in order to meet their design requirements. In lieu of a leakage test for the isolation i check valves given above, the main valves will be cycled the l 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.
/'N U 4-112
~N1PVI2R8 Revision 8 August 17, 1998 l
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NON-CODE-ALTERNATIVE TESTING VNC-3'(Cont.')
Alternate Testing proposed l' 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.
O 4-113 N1PVI2R8 Revision 8 August 17, 1998 e
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l NON-CODE ALTERNATIVE TNSTING VNC-4 V
l System : Emergency Diesel Air Services l
l 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 Category: B for 1-EG-SOV-600HA, HB, JA and JB and 60lHA and 607JA C for 1-EB-15, 34, 65 and 84 1 l Class : NC Function: Diesel Air Receiver Tank Discharge Check Valves and Diesel Air Start Solenoid Valves OM Part 10 Code Requirements Which Will Not Be Met OM Part 10, Section 4.2.1.4 (b) - The stroke time of all power- j operated valves shall be measured to at least the nearest second. '
,m ks OM Part 10, Section 4.3.2.2 (b) - During plant operation, each j check valve shall be exercised or examined in a manner which -
verifies obturator travel to the closed, full-open or partially open position required to fulfill its function.
Basis For Alternate Testing l The solenoid valves have actuation times considerably under a 3 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 air bank. A diesel alarm will activate if the starting time exceeds start failure requirements.
Verification that the diesel starts without an alarm constitutes
(~N) a full stroke test for the check valves. The test to start the 4-114 -
N1PVI2R8 Revision 8 August 17, 1998 l
i NON-CODE ALTERNATIVE' TESTING VNC-4 (Cont.)
-diesels on one air bank'is performe'd on a rotating basis once every six months. . Based on this rotation, each check: valve will be full flow tested once every 18 months.
' Alternate Testing proposed. I J
The solenoid' valve will be full _ stroke exercised and check valves- I 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).
I Every 18 months, the~ check valves will be full stroke tested by l 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 j with the operability of these valves. The diesel start time will i be recordedLand compared to a maximum allowable start time during i
this test.
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j-m l l N~s l 4-115 N1PVI2R8 Revision 8 August 17, 1998 l
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/~'T 5.0 REPORTING OF INSERVICE TEST RESULTS b
5.1 PUMP INSERVICE TESTING PROGRAM A record of.each pump will be maintained in accordance with OM Part 6, Section 7.1 that includes the following:
- 1) the manufacturer and the manufacturer's model and serial or other-identification number,
- 2) a copy or summary of the manufacturer's acceptance test report if available,
- 3) a-copy of the pump manufacturer's operating limits.
A record of inservice test plans will be maintained in accordance with OM Part 6, Section 7.2 that includes the following:
- 1) 'the hydraulic circuit to be used,
- 2) the location and type of measurement for the required test parameters, i
s/ 3) the reference values and !
- 4) the method of determining reference values.which are not directly measured by instrumentation.
A record of test results will be. maintained in accordance with OM Part 6, Section 7.3 that includes the following:
- 1) pump identification,
- 2) date of test,
- 3) reason for test (e.g., post maintenance, routine
' inservice test establishing reference values, etc.),
- 4) values of measured parameters, 5)_ identification of instruments used,
- 6) comparisons with allowable ranges of test values and analysis of deviations, l O 5-1 N1PVI2R8 Revision 8 August 17, 1998
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- 7) requirement for corrective action, 8)- evaluation and justification for changes to reference values and
- 9) signature.of the person or persons responsible for conducting and analyzing the test.
A record of corrective action will be maintained in l
accordance with OM Part 6,-Section 7.4 that includes a
. summary of the corrections-made, the subsequent
, inservice tests and confirmation of operation adequacy, l and the signature of the individual responsible for the l corrective action and verification of-results.
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 the Authorized Nuclear Inservice Inspector and the NRC.
5.2 VALVE INSERVICE TESTING PROGRAM A record of each valve will be maintained in accordance O with OM Part 10, Section 6.1-that includes the following:
-1) the manufacturer and the manufacturer's model and serial or other unique identification number,
- 2) a copy or summary of the manufacturer' acceptance test report if available,
- 3) preservice test results and
- 4) limiting value of full stroke time. ,
This IST Program Plan meets the requirements of OM Part 10, Section 6.2, Test Plans.
A record of test results will be maintained in accordance with OM Part 10,-Section 6.3 that includes the following:
i
- 1) valve identification,
- 2) date of test, O 5-2 L N1PVI2R8 Revision 8 l
August 17, 1998 1
/ 3) reason for test (e.g., post maintenance, routine inservice test establishing reference values,
.etc.),
- 4) _ . values.of measured parameters,
- 5) identification of instruments used,
- 6) comparisons with allowable ranges of test values and analysis of deviations,
- 7) requirement for corrective action and i
- 8) . signature of the person or persons responsible for conducting and analyzing the-test.
A record of corrective action will be maintained in accordance with OM Part 10, Section 6.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results.
The Valve Inservice Test Program, associated
~N surveillance test procedures and results will be kept at North Anna Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC. l i
l O 5-3 N1PVI2R8 Revision 8 August 17, 1998 j l
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[ T 6.0 QUALITY ASSURANCE PROGRAM
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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.
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v 6-1 N1PVI2R8 Revision 8 August 17, 1998
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