ML20195B588
| ML20195B588 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/14/1999 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20195B544 | List: |
| References | |
| PROC-990514-01, PROC-990514-1, NUDOCS 9906020029 | |
| Download: ML20195B588 (300) | |
Text
? l e
1
SUMMARY
OF CHANGES TO THE NORTH ANNA UNIT 2 SECOND INTERVAL IST PROGRAM i
J FROM REVISION 7, CHANGE 4 TO !
REVISION 8, CHANGE 2 O
~
EP#88 sir 88sg3, PDR ,
t < ..
J
i
GENERAL COMMENT
S This summary describes changes to the North Anna Unit 2 Inservice Testing (IST) Program from
^
! Revision 7, Change 4 to Revision 8, Change 2. With Revision 8 to the North Anna Units 1 and 2 IST Programs, the programs have been updated from the 1986 Edition of ASME Section XI to the 1989 Edition in its entirety and several changes 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-67 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 pmvided that North Anna complies 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 allows for exercise testing every reactor refueling.
The general format of the IST Program Plan has been changsd 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 2 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 j of Section XI. .
l 2.0 ' GENERAL PROGRAM DEVELOPMENT in a NRC Safety Evaluation Report for Surry dated October 20,1994, the NRC wanted a description of how the IST program was developed, how scope was determined and how l the program is updated. This description was included in the Surry IST program and is i now being included in the North Anna IST program. Section 2 describes the IST l
program administrative process as it is now and does not commit North Anna to imposing additional requirements. ;
l l
3.0 PUMP lNSERVICE TEST PROGRAM DESCRIPTION Reference is made to the 1989 Code Edition of Section XI and OM Part 6, OMa-1988 for pump testing. Also, verbiage 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.
O l
l L[
3.5 PUMP INSERVICE TEST TABLES O
V Unit 2 Pump Number Prooram Chance 2-CC-P-1 A Relief Request P-16 was withdrawn for these pumps. P-16 requests 2-CC-P 1B relief from measuring static inlet pressure for a pump that is already in 2-CH-P-1 A operation prior to testing. OM Part 6 does not require the measurement 2-CH-P-1 B of static inlet pressure, therefore, the relief is no longer necessary.
2-CH-P-1 C 1-CH-P-2C 1-CH-P-2D 2-FW-P-2 2-FW-P-3A 2-FW-P-3B 2-QS-P-1 A 2-QS-P-1 B 2-RH-P-1 A 2-RH-P-1 B 2-RS-P-3A 2-RS-P-3B 2-HV P-20A 2-HV-P-20B 2-HV-P-20C 2-HV-P-22A 2-HV-P-22B 2-HV-P-22C (Rev. 8) 3.6 PUMP TEST PROGRAM RELIEF REQUESTS Unit 2 Pump Relief Request Proaram Chance P-1 Requests for relief from measuring Pump bearing temperature and (Rev. 8) vibration displacement in mils were withdrawn from P-1, along with the description of using vibration velocity in inches per second. OM Part 6 requires that vibration velocity be measured instead of bearing temperature and vibration displacement.
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 unnseessary corrective action by maintaining a small but reasonable acceptable operating range. This portion of P-1 was retained in the revised relief request.
5 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 cutve. The figure provided no more information than that provided in the attemate testing discussion of P-12. Therefore, the figure is not necessary.
P-16 Relief request was withdrawn. The relief requested that static inlet O (Rev. 8) pressure not be measured for pumps already operating prior to the 2
inservice test. OM Part 6 does not required that static inlet pressure be measured. Therefore, the relief request is no longer necessary.
3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS Unit 2 Pump Non-Code Altemative Testing Description ]
i 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 identified as having a full scale of 0 to 30 psig, and reference values ranging from 7.5 to 8.5 psig which does not meet the one third scale requirement of OM Part 6, paragraph 4.6.1.2 for reference values.
However, test results show the data is repeatable. Therefore, the accuracy of the instruments provides acceptable results.
l- A note was added to enhance clarity. The note reads, "The diesel oil
. transfer pumps are positive displacement pumps. According to OM Part l 6, Table 2, discharge pressure, flow and vibration need to be measured
- for positive displacement pumps. Differential pressure does not have to l be measured."
l 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION l
l 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, j 4.4 VALVE INSERVICE TEST TABLES l The valve table column heading explanations were revised to pruvide more
!. complete and accurate descriptions. Also, the test frequency for each test was l 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 l Justification, the partially open test (PO) designation was added to the table.
l This addition of the PO test to the table is not an increase in the commitments to l test, but is an enhancement to the table to provide a clearer description of existing test commitments. '
O l 3 L
r5 O Unit 2 Valve Number Proaram Chanae 2-CC-78 Program change: Relief Request V 3 was replaced by Reactor 2-CC-115 Refueling Justification RRV-1. According to OM Part 10, paragraphs 2-CC 152 4.2.1.2 (e) and 4.3.2.2(e), 'If exercising is not practicable during plant I (Rev. 8) 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.
2-CC-107 Program change: Relief Re 2-CC-144 Refueling Justification RRVquest V-66 basis
- 22. The technical was replaced by Reactor for the deferral 2-CC-181 has not changed.
(Rev. 8) )
2-CC-194 Program change: Relief Request V-71 was replaced by Reactor 1 2-CC-199 Refueling Justdication RRV-24. The technical basis for the 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-24 and is not a new test commitment.
2-CC-276 Relief Request V-63 was replaced by Reactor Refueling Justification 2-CC-289 RRV-20. Also, reference to NUREG 1482, Section 4.1.4, entitled 2 CC-302
- Extension of Test interval to Refueling Outage for Check Valves Verified Closed by Leak Testing" was added to provide additional (Rev 8)
O Justification to the basis. The remaining technicalJustification for deferral was expanded to enhance clartty.
1 Program charge: Relief Request V-83 was replaced by Reactor j Refueling Justmcation RRV-20.
2-CC-RV-204A Credit is taken for these relief valves protecting penetrations 9,10 and 2-CC-RV-204B 11 in a memorandum from E. W. May entitled ' OVERPRESSURE 2-CC-RV-204C . 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.
2-CC-RV 226 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.
o O
4 u
i
. Unit 2 Valve Number Prooram Chance 2-CC-RV-231A These relief valves protect the RHR Seal Coolers from over-pressure 2-CC-RV-231B as a result of thermal expansion when a cooler is isolated. If a cooler is (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 10 if the equipment being protected is required for accident mitigation (refer to ASME Interpretation: 95-9).
Program change: The valves were added to the program.
2-CH-118 Program change: The test to the partially open position (PO) was 2-CH-133 added to the valve table to enhance clarity. This partially open test is (Rev. 8) described in Cold Shutdown Justification CSV-3 and is not a new test commitment.
2-CH-153 Relief Request V-73 was replaced by Reactor Refueling Justification 2-CH-495 RRV-25. 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 clamy.
Program change: Relief Request V-73 was replaced by Reactor Refueling Justification RRV-25.
2-CH-178 Program change: Relief Request V-48 was replaced by Reactor Refueling Justification RRV-18. The technical basis for the deferral O 2-CH-193 2-CH-208 (Rev. 8) has not changed.
2-CH-260 Program change: Relief Request V-10 was replaced by Reactor 2-CH-284 Refueling Justification RRV-2. The technical basis for the deferral has 2-CH-308 not changed.
2-CH-331 2-CH-332 2-CH-335
. (Rev. 8) 2-CH-331 Relief Request V-59 was withdrawn. V-59 requested relief from the 2-CH-MOV-2380 IWV requirement to individually leak test valves. Certain valves 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 is being withdrawn.
2-CH-MOV-2380 ' Program change: Relief Request V-9 was replaced by Cold Shutdown 2-CH-MOV 2381 Justification CSV-47. The technical basis for the deferral has not changed.
(Rev. 8)
,O v
5
.l Unit 2 Valve Number Prooram Chanoe 2-CH-RV-2382A This valve protects the seal water leakoff piping from over-pressure (Rev. 8) during an accident when the associated piping segment is isolated and may be subjected to heating or seal failure. Credit is taken for this relief valve protecting penetration 19 in a 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.
2-CV-8 Valves 2-CV-8 and 15 were added to RRV-4. To test these valves full 2-CV-15 open requires a significant manipulation and operation of the hydrogen 2-HC-15 recombiner system. In addition, should a containment pressurization 2-HC-20 event occur while the recombiner system is operating, the design (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 Sedion 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 frequent basis. Valves 2-CV-8 and 15 can be O 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 valves 2-HC-15 and 20. The remaining portion of the technical basis was used in RRV-4. Also, for closure testing, 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 additionalJustification to the basis.
Program change: Valves 2-CV-8 and 15 were added to RRV-4 to be full flow 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 2-HC-15 and 20, is being replaced by Reactor Refueling Justification RRV-4, 2-FP-79 Program charge: Relief Request V-16 was replaced by Reactor (Rev. 8) Refueling Justmcation 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 provide additionaljustification to the basis. The remaining technical ustification for deferral has not changed.
O !
l i
Unit 2 Valve Number Proaram Chance 2-FW-FCV-2478 The requirement to perform a partial open exerc!se test every three 2-FW-FCV-2488 months was deleted for the main feedwater regulating valves 2-FW-2-FW FCV-2498 FCV-2478,2488 and 2498. In order to perform a partial stroke test during normal operation, the plant has to reduce power to cause the (R,y.8) valve disks to move. Reducing power forthe 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.
Program change: The three month partial stroke test was deleted from Cold Shutdown Justification CSV-11.
2-FW-HCV-200A Per OM Part 10, paragraph 4.2.1.2(b) if full-stroke exercising during 2-FW-HCV-2008 - plant operation is not practicable, it may be limited to part-stroke during 2-FW-HCV-200C plant operation and full-stroke during cold shutdowns These valves can be part-stroke exercised during normal operation. Note that the (Rev. 8) valve stroke time need not be measured during a part-stroke test.
Program change: The three month partial stroke test was added.
2-FW-PCV-259A Per OM Part 10, paragraph 4.2.1.2(b) if full-stroke exercising during 2-FW-PCV-2598 plant operation is not practicable, it may be limited to part-stroke during plant operation and full-stroke during cold shutdowns. These valves (Rev. 8) can be part-stroke exercised during normal operation. Note that the valve stroke time need not be measured during a part-stroke test.
Program change: The three month partial stroke test was added.
2-HV-MOV-2008 Relief Request V-59 was withdrawn. V-59 requested relief from the 2-HV-MOV-2000 IWV requirement to individually leak test valves. Certain valves 2-HV-MOV-201 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 2-HV-MOV-202 combination of valves at the same time. Therefore, relief is no longer (Rev. 8) necessary forthese valves.
Program change: Relief Rsquest V 59 was withdrawn.
2-IA-250 Program change: Relief Request V-21 was replaced by Reactor l 2-IA-428 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 xovide additionaljustification to the basis. The remaining technical ustification for deferral has not changed.
2-IA-RV-210 These relief valves protect instrument air supply piping to the PORVs.
2-IA-RV-211 This piping must remain intact so that the safety related bottled air can (Rev. 8) supply the pressurizer PORVs (2-RC-PCV 2455C and 2458). i l
Program change: The valves were added to the program.
2-MS-NRV-201A Program change: The method of testing described in Cold Shutdown 2-MS-NRV-201B . Justification CSV-13 was changed to incorporate the use of motor 2-MS-NRV 201C current instead of yoke strain to detect changes in running force. Motor ,
(Rev. 7, Chg. 4) current is more sensitive to changes in stem load.
O 7
i
. Unit 2 Valve Number Prooram Chanoe 2-QS-11 Relief Roquest V-68 was replaced by Reactor Refueling Justification 2-QS-22 RRV 23. Also, reference to NUREG 1482, Section 4.1.4, entitled 2-RS-20 " Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing" was added to provide additional 2-RS-30 Justification to the basis. The remaining technicaljustification for (Rev. 8) deferral was expanded to enhance clamy.
Program change: Relief Request V-68 was replaced by Reactor Refueling Justmcation RRV-23.
2-RC-182 Program change: Relief Request V-28 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 Chock Valves Verified Closed by Leak Testing" was added to xovide additional Justification to the basis. The remaining technical ustification for deferral has not changed.
2-RC-SOV-201A-1 Relief Request V-58 was replaced by Cold Shutdown Justification CSV-2-RC-SOV-201 A-2 48. V-58 was originally a cold shutdown justification but with 2-RC-SOV-2018-1 provisions. Therefore, there could be cold shutdowns where the testing wou be impracdcam aM a reHef requed was me app @ ate means 2-RC-SOV-201B-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 coid shutdown justification.
Program change: Relief Request V-58 was by Cold Shutdown Justification C=V-48. The technical justification for deferral has not changed.
O 2-SI-6 2-SI-2g Program change: Relief Request V-54 was replaced by Reactor Refueling Justification RRV-19. 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 xovide additional justification to the basis. The remaining technical ustification for deferral has not changed.
2-SI.9 Program change: Relief Request V-39 was replaced by Reactor 2-SI-19 Refueling Justification RRV-9. The technical justification for deferral 2-SI-32 has not changed. The test to the partially open position (PO) was added to the valve table to enhance clarity for valve 2-SI-19. This (Rev. 8) partially open test is described in Reactor Refueling Justification RRV-9 and is not a new test commitment.
2-SI-18 Program change: Relief Request V-40 was replaced by Reactor (Rev. 8) Refueling Justification RRV-10. 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 i provide additional Justification to the basis. The remaining technical i 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-10 and is not a new test commitment.
1 I
O !
8
Unit 2 Valve Number Prooram Chance 2-S1 70 Tests have revealed that when either 2-SI-MOV-2867A or B is opened 2-SI-MOV-2867A using the normal valve actuator, the BIT and the associated piping -
2-SI-MOV-2867B experience a significant hydraulic transient.- This hydraulic transient also peduh the reador coolant pumps @ cps) seal Injoh flow
@ev* 8) ' because the RCP seal flow comes off J' e 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 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 preasure 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 2-SI-70 is during reactor refuelings when the charging system is secured and a local backseat / leak test can be performed. According to NUREG-1482, (q
V j
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."
Program change: These valves will be exercised every reactor refueling. Refer to Reactor Refueling Justification RRV-27.
2-SI-85 Program change: The technical justification for deferring the testing of 2-SI-g3 the hot and cold leg Si check valves to refueling outages was moved 2-SI-107 from Relief Request V-42 to Reactor Refueling Justification RRV-14.
2-SI-11g 2-SI-126 2-SI-128 (Rev. 8) 2-SI 90 Program change: The technicaljustification for deferring the testing of 2-SI-98 the cold leg SI check valves to refueling outages was moved from 2-SI-104 Relief Request V-45 to Reactor Refueling Justification RRV-15. ;
(Rev. 8)
I y
4 g
i Unit 2 Valve Number Proaram Chance 2-SI-g1 The technical justification for defening the testing of the cold leg Sl 2-SI-gg check valves to refueling outages was moved from Relief Request V-l' 2-SI-105 42 to Reactor Refueling Justification RRV-12. The technical ,
justification has not changed. The remaining portion of V-42 addresses !
(Rev. 8) the non-intrusive techniques used to test the hot leg Si check valves, along with a sampling plan for instrumenting the valves. This portion remains in V-42 and has been editorially changed to enhance clarity.
Also, per NUREG 1482, to use the sampling plan the check valves must De grouped based on valve design and service conditions. No new commitments have been made by the changes described above.
l Program change: The deferral to test every reactor refueling was
! moved to Refueling Justification RRV-12.
2-SI-g2 The technicaljustification for deferring the testing of the cold leg SI ;
check valves to refueling outages was moved from Relief Request V.
2 SI 100
! 2'SI-106 44 to Reactor Refueling Justification RRV-12. The technical ;
justification has not changed. The remaining portion of V-44 addresses (Rev. 8) the non-intrusive techniques used to test the cold leg Si check valves, along with a sampling plan for instrumenting the valves. This portion 1 l was moved to V-42 and has been editorially changed to enhance l clarity. Relief Request V-44 was deleted. It is logical to group these i
cold leg check valves in the same relief request as the other cold leg -
check valves from V-42 because they are all non-intrusively tested with the same test procedure.
Also, per NUREG 1482, to use the sampling plan the check valves must De grouped based on valve design and service conditions. No
% new commitments have been made by the changes described above.
Program change: The deferral to test every reactor refueling was moved to Refueling Justification RRV-12.
2-SI-112 The technical justification for deferring the testing of the hot leg Si 2-SI-113 check valves to refueling outages was moved from Relief Request V-2-SI-117 45 to Reactor Refueling Justification RRV-14. The technical justification has not changed. The remaining portion of V-45 addresses 2~SI~118 the non-intruhive techniques used to test the hot leg Si check valves, 2 SI-124 along with a sampling plan for instrumenting the valves. This portion 2-SI-125 remains in V-45 and has been editorially changed to enhance clarity.
(Rev. 8) Also, per NUREG 1482, to use the sampling plan the check valves must be grouped based on valve design and service conditions. No new commitments have been made by the changes described above.
Program change: The deferral to test every reactor refueling was moved to Refueling Justification RRV-14.
2 SI-132 Program change: Relief Request V-41 was replaced by Reactor 2 SI 136 Refueling Justification RRV-11. 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 remaining technical l ,
ustification for deferral has not changed.
l l O 10 l-l
Unit 2 Valve Number Prooram Chanoe 2-SI-151 The technical justification for deferring the testing of the Si accumulator 2-SI-153 discharge check valves to refueling outa0es was moved to Reactor 2 SI-168 Refueling Justification RRV-13. The technicaljustification has not 2'SI~170 changed. The remaining postion of V43 addresses the non-intrusive techniques used to test the check valves along with a sampling plan for 2-SI-185- instrumenting the valves. This portion remains in V43. References in 2-SI-187 V43 to evaluating non-intrusive monitoring techniques and using (Rev. 8) disassembly and inspection as an altamative 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-13. Also, the use of non-intmsive techniques has been accepted as the test of choice as described in Relief Request V43.
2-SI-MOV-2836 Program change: Relief Re 2-SI-MOV-2869A Refueling Justification RRV quest
- 7. The V 35justification technical was replaced by Reactor for deferral 2-SI-MOV-2869B has not changed.
2-SI-MOV-2890A 2-SI-MOV-28908 2-SI-MOV-2867C Relief Request V-59 was withdrawn. V-59 requested relief from the 2-SI-MOV-2867D IWV requirement to individually leak test valves. Certain valves 2-SI-MOV-2890C - cannot be individually tested, but must be tested as a group or O 2-SI-MOV-2890D (Rev. 8) comNnation. N Part 10, paragraph (2.2.3(c)(2) aHows for testing a combination of valves at the same time. Therefore, relief is no longer necessary for these valves. Also, the technical justification for deferring the testing to refueling outages was moved from Relief i
Request V-37 to Reactor Refueling Justification RRV-8. The technical justification has not changed.
Program change: Relief Request V-59 was withdrawn and Relief '
Request V-37 is being replaced by Reactor Refueling Justification RRV-8.
2-SI-RV-204 This valve protects the Si accumulator test line containment l (Rev. 8) penetrations from overpressure when samples are being drawn and
, there is back leakage through the Si accumulator isolation check valves. (valve installed by DCP 97-135) 4 Program change: The valve was added to the program.
l 2 SI-RV-28578 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 piping and BIT. The ASME Subcommittee on Valves has interpreted :
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).
Program change: The valve was added to the program.
O 11
[
Unit 2 I Valve Number Prooram Chanoe 2-SI-RV-2858A According to FSAR Section 6.3.2.1.4.5, these Si accumulator tank 2-SI-RV-28580 relief valves are sized to pass nitrogen at a rate in excess of the 2-SI-RV-2858C - accumulator gas fill line delivery rate. Therefore, they protect the ;
(Rev. 8) accumulators from an uncontrolled release from the gas delivery I system.
Program change: The valves were added to the program.
2-SW Program change: Relief Request V44 was replaced by Reactor 2-SW-10 Refueling Justification RRV-21. 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 clartty. This pastially open test is described in Reactor Refueling Justification RRV-21 and is not a new test commitment.
2-SW-24 Program change: Relief Request V-74 was replaced by Reactor (Rev. 8) Refueling Justmcation RRV-25. The technical justification for deferral has not changed. The test to the partially pen position (PO) was added to the valve table to enhanot 1 erit . This partially open test is described in Reactor Refueling Justificati RRV-26 and is not a new test commitment.
2-SW48 Program change: Relief Request V-46 was replaced by Reactor 2-SW-70 Refueling Justification RRV-16. The technical justification for deferral l
2-SW-74 has not changed.
2-SW-84 2-SW-94 l
i O . 2-SW-104 '
- (Rev. 8) t 2-SW-281 The intemals to these service water supply to control room condenser i 2-SW-306 check valves were removed.
i 2-SW-337 l (Rev. 7, Chg. 4) Program change: The valves were removed from the IST program.
l l 2-SW-580 The failure of a service water pump to start with one pump out-of-
, 2-SW-581 service and the remaining two pumps lined up to the same header l'
2-SW 591 would result in a depressurized header. In this case, no credit can be
! 2 SW 592 taken for operator action to manually isolate a depressurized header.
2-SW 597 To ensure automatic isolation of the headers, closure tests for check l 2 SW-598 valves that are required to close to allow adequate cooling water for the
- 2-SW-608 service water to charging pump coolers were added to the IST l 2 SW409 program. I l : 2-SW-615 .
I 2 SW-616 These check valves were tested to the full open position using
< 2 SW-626 - temporary ultrasonic flow instrumentation Because the use of this 2-SW-627. equipment is very labor intensive, testing was deferred to every cold i i (Rev. 7, Chg. 4) . shutdown. This test method was replaced by disassembly and i
! inspection that will verify the capability of the check valves to open and ;
close. I
\
1 l
Program change:' Closure tests were added to the IST program and ,
' the full flow open test method using ultrasonic flow instrumentation was 1- replaced with disassembly and inspection. The capability of these
. check valves to closed will be verified by disassembly and inspection 12 o ___
Unit 2 Valve Number Prooram Chance as described in Relief Request V-77. Also, in Rev. 8, Chg. 2, the partial open (PO) test was added to the valve table and the test frequency corrected from CS to RR. The PO test is not a new commitment and was erroneously excluded from the valve table.
2-SW-RV-201 A These valves open to provide over-pressure protection for an isolated 2-SW-RV-2015 component cooling heat exchanger if 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 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 ACME Interpretation: 95-9).
Program change: The valves were added to the program.
2-VP-24 Program change: Relief Request V-47 was replaced by Reactor (Rev. 8) Refueling Justification RRV-17. 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 additionaljustification to the basis. The remaining technical ustification for deferral has not changed.
/
4.5 VALVE TEST PROGRAM RELIEF REQUESTS Unit 2 Valve Relief Recuest Prooram Chanoe 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), *lf exercising is not practicable during plant operation or cold shutdown, it may be limited to i full-stroke during refueling outages." Therefore, relief is no longer l required to defer testing until refueling outages, however, the l l Justification for the deferral should be described in the IST Program Plan per NUREG 1482, Section 2.4.5. The techi.ical basis for the deferral j has not changed.
V.9 Replaced by Cold Shutdown Justification CSV-47. V 9 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.
V-10 Replaced by Reactor Refueling Justification RRV 2. The technical basis (Rev. 8) for the deferral has not changed. 7 '
l V-16 Replaced by Reactor Refueling Justification RRV-3. The technical basis 1 (Rev. 8) for the deferral has not changed.
4 O
13
Unit 2 Valve Q Relief Reauest Proaram Chance
\'/
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 2-HC-15 and 20. The remaining portion of the technical basis was used in RRV-4.
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-35 Replaced by Reactor Refueling Justification RRV-7. The technical basis (Rev 8) for the deferral has not changed.
V-37 Replaced by Reactor Refueling Justification RRV-8. The technical basis (Rev. 8) for the deferral has not changed.
V-39 Replaced by Reactor Refueling Justification RRV-9. The technical basis j (Rev. 8) for the deferral has not changed.
V-40 Replaced by Reactor Refueling Justification RRV-10. The technical (Rev 8) basis for the deferral has not changed.
V-41 Replaced by Reactor Refueling Justification RRV-11. The technical (Rev. 8) basis for the deferral has not changed.
V-42 The technical justification for deferring the testing of the RCS cold leg SI (Rev. 8) admission check valves 2-SI-91,99 and 105 to refueling outages was moved to Reactor Refueling Justification RRV-12. The technical justification has not changed. The remaining portion of V-42 addresses i the non-intrusive techniques used to test these check valves along with '
a sampling plan for instrumenting the valves. This portion remains in V-42 and has been editorially changed to enhance clarity. However, no new commitments have been made.
Relief Request V 42 also contained the technical justification for deferring the testing of the RCS cold and hot legs Sl admission check valves 2-SI-85,93,107,119,126 and 128 to refueling outages. This technical justification was moved to Reactor Refueling Justification RRV-14 V-43 The technical justification for deferring the testing of the Si accumulator (Rev. 8) discharge check valves to refueling outages was moved to Reactor Refueling Justification RRV-13. The technical justification has not changed. The remaining portion of V-43 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-43. References in V-43 to evaluating non-intrusive monitoring techniques and using i disassembly and inspection as an attemative were deleted and the 1 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.
O I
14
f.
?:
, Unit 2 Valve i
Rehof Reauest Prooram Chance V-44 The technicalJustification for defening the testing of the cold leg Sl I (Rev. 8) check valves to refueling outages was moved from Relief Request V-44 I to Reactor Refueling Justificat6on RRV 12. The technical justification has not changed. The remaining Portion of V-44 addresses the non-intrusive techniques used to test the cold leg Si check valves, along with a sampling plan for instrumenting the valves. This portion was moved to V-42 and has been editorially changed to enhance clartty. Relief Request V-44 is being deleted. It is logical to group these cold leg
- l. check valves in the same relief request as the other cold leg check l valves from V-42 because they are all non-intrusively tested with the l same test procedure.
V-45 The technical justification for deferring the testing of the RCS hot leg SI (Rev. 8) admission check valves 2-S1-112,113,117,118,124 and 125 to refueli outages was moved to Reactor Refueling Justification RRV-14.
Thet nical justification has not changed. The remaining portion of V-45 addresses the non-intrusive techniques used to test these check l valves along with a sampling plan for instrumenting the valves. This portion remains in V 45 and has been editorially changed to enhance clarity. However, no new commitments have been made.
l Relief Request V-45 also contained the technical justification for l deferring the testing of the RCS cold leg Si admission check valves 2-SI-90,98 and 104 to refueling outages. This technicaljustification was moved to Reactor Refueling Justification RRV-15 V-46 Replaced by Reactor Refueling Justification RRV-16. The technical (Rev. 8) basis for the deferral has not changed.
V-47 Replaced by Reactor Refueli Justification RRV-17. The technical l (Rev. 8) basis for the deferral has not anged. .
! V 48 Replaced by Reactor Refueling Justification RRV-18. The technical L _ (Rev. 8) basis for the deferral has not changed.
-V 54 Replaced by Reactor Refueling Justification RRV-19. The technical (Rev. 8) basis for the deferral has not changed.
l V-55 Relief request was withdrawn. V-55 deferred the corrective action l
(Rev. 8) requirements of IWV-3417(a) for rapid acting valves with stroke times increased if the stroke time exce(eded the previous stroke time by ale l certain percentage. OM Part 10, paragraph 4.2.1.8(e) addresses rapid l acting valves. Therefore, relief is no longer necessary.
V-58 Replaced by Cold Shutdown Justification CSV-48. V-58 was originally a (Rev. 8) cold shutdown justification but with provisions. Therefore, there could l 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. >
V-59 Relief request was withdrawn. V-59 requested relief from the IWV !
(Rev. 8) requirement to individually leak test valves. Certain valves cannot be ,
individually tested, but must be tested as a group or combination. OM i Part 10, paragraph 4.2.2.3(c)(2) allows for testing a combination of l valves at the same time. Therefore, relief is no longer necessary for i these valves.
15 .
l
Unit 2 Valve Relief Reauest Prooram Chance V41 Relief request was withdrawn. V41 requested relief from the (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.
V43 Replaced by Reactor Refueling Justification RRV-20. The technical (Rev. 8) basis for the deferral has not changed.
~V44 Replaced by Reactor Refuelina Justification RRV-21. The technical (Rev. 8) basis for the deferral has not changed.
V-66 Replaced by Reactor Refueling Justification RRV-22. The technical (Rev. 8) basis for the deferral has not changed.
V47 Relief request was withdrawn. V47 inquested relief from the (Rev. 8) requirements of IWV-3417(a) to compare the current stroke time to the previous measured stroke time and increase the test frequency if there is an increase by a certain percentage. V47 used OM Part 10 paragraphs 4.2.1.8 and 4.2.1.g as the attematives to IWV-3417(a).
After committing to OM Part 10 in its entirety relief is no longer necessary.
V48 Replaced by Reactor Refueling Justification RRV 23. The technical (Rev. 8) basis for the deferral has not changed.
V-71 Replaced by Reactor Refueling Justification RRV-24. The technical (Rev. 8) basis for the deferral has not enanged.
V 73 Replaced by Reactor Refueli Justification RRV-25. The technical (Rev 8) basis forthe deferral has not anged.
- V 74 Replaced by Reactor Refueling Justification RRV-26. The technical (Rev. 8) basis for the deferral has not changed, l V-77 This relief request was added to the IST program to describe the testing l (Rev. 7, Chg. 4) method for the service water to charging pump coolers check valves.
l These valves will be verified to the full open position and to the closed I
position using disassembly and inspection as the test method on a l reactor refueling frequency. The valves will be stroked to the partially i 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 pressurited 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.
The valves can be disassembled and inspected while the plant is N operating. To allow for flexibility in planning for refueling outages and !
still meet ?.he intent of OM Part 10, the valves will be disassembled on a i
16 l
t
I l
Unit 2 Valve Q
V Relief Reaygit Prooram Chance 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 flowinstrumentation. Because the use of this equipment is very labor intensive, testing was deferred to every cold i shutdown. This test method was replaced by disassembly and inspection that will verify the capability of the check valves to open and close.
4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS ;
Unit 2 Valve !
p Cold Shutdown l Justificatior} Prooram Chance CSV-11 The requirement to perform a partial open exercise test every three (Rev. 8) months was deleted for the main feedwater regulating valves 2-FW- ,
FCV-2478,2488 and 2498. In order to perform a partial stroke test I during normal operation, the plant would have to reduce power to cause i 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.
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 changes in stem load.
CSV 34 This cold shutdown justification was revised to indicate that the main l
(Rev. 8) steam trip bypass valves 2-MS-TV-213A, B and C are passive in the closed position during normal operation and do not require quarteriy l testing. These trip valves are opened only during plant startup to provide flowpaths for steam from each of the steam generators to l
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 l 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 A isolation valves (non-leak tested). There is a remote possibility that 17 L
4 l Unit 2 Valve
, Cold Shutdown Justification Proaram Chance l these valves would have to close during plant startup; therefore, they are considered active to the closed position only during plant startup. )
4 l 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.
CSV 36 This cold shutdown justification was replaced by Relief Request V-77. .
I (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 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.
l The increase in safety provided by the full open flow test does not justify i the burden of using the ultrasonic flow instrumentation given that an l attemative 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-46 Replaced by Reactor Refueling Justification RRV-27 (Rev. 8) 4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS j Unit 2 Valve Reactor Refueling 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 2-CV-8 and 15 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 hydrogen recombiner could be exceeded.
Valves 2-CV-8 and 15 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 loca;ly installed rotameter was deleted from the original technical basis for the deferral for valves 2-HC-15 and 20. The remaining portion of the technical basis was used in RRV-4.
RRV5 Replaces Relief Request V-21 18
p Unit 2 Valve Reactor Refueling Justification Prooram Chanoe (Rev. 8)
RRV-6 Replaces Relief Request V-28 (Rev. 8)
RRV Replaces Relief Request V-35
' (Rev. 8)
RRV-8 Replaces Relief Request V 37 (Rev. 8)
I RRV 9 Replaces Relief Request V-39 j (Rev. 8) l RRV-10 Replaces Relief Request V-40 (Rev. 8)
RRV 11 Replaces Relief Request V-41
. (Rev. 8) !
1 RRV-12 Portions of Relief Requests V-42 pertaining to valves 2-SI-91,99 and j (Rev. 8) 105, and V-44 pertaining to valves 2-SI-92,100 and 106 that address :
deferral of testing to reactor refueling outages were moved to this reactor refueling justification.
O RRV-13 (Rev. 8)
The portion of Relief Request V-43 that addresses deferral of testing to reactor refueling outages was moved to this reactor refueling justification.
RRV-14 Portions of Relief Requests V-42 pertaining to valves 2-SI-85,93,107, (Rev. 8) 119,126 and 128, and V-45 pertaining to valves 2-S1-112,113,117, J 118,124 and 125 that address deferral of testing to reactor refueling outages were moved to this reactor refueling justification.
RRV-15 The portion of Relief Request V-45 that addresses deferral of testing to (Rev. 8) reactor refueling outages for valves 2-SI 90, 98 and 104 was moved to this reactor refueling justification.
RRV-16 Replaces Relief Request V-46 l (Rev. 8)
RRV-17 Replaces Relief Request V-47 (Rev. 8)
RRV-18 Replaces Relief Request V-48 .
(Rev. 8) ,
RRV-19 Replaces Relief Request V-54 i (Rev. 8)
RRV-20 Replaces Relief Request V-63 (Rev. 8)
RRV-21 Replaces Relief Request V-64 19
1 l
l Unit 2 Valve l Reactor Refueling l
Justification PJoaram Chance (Rev. 8)
RRV-22 Replaces Relief Request V-66 l (Rev. 8)
' RRV-23 Replaces Relief Request V 68 (Rev. 8) 1 RRV-24 Replaces Relief Request V-71 i (Rev. 8)
RRV 25 Replaces Relief Request V-73 (Rev 8)
RRV-26 Replaces Relief Request V-74 (Rev,8) l RRV-27 Replaces Cold Shutdown Justification CSV-46. Refer to the discussion
- (Rev. 8) for valves 2-SI-70,2-SI-MOV-2867A and 2-SI-MOV-28678.
l 5.0 REPORTING OF INSERVICE TEST RESULTS
- Section 5 was changed to reference the reporting requirements of OM Part 6, Section 7, O and OM Part 10, Section 6.
- U 1
l l
l l
O n i
h? )
U lO l
1 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 i
INSERVICE TESTING PROGRAM PLAN l FOR PUMPS AND VALVES SECOND INSPECTION INTERVAL i DECEMBER 14, 1990 - DECEMBER 14, 2000
' REVISION 8 O
t i
L l
i l'
l 1
- 6 i
O
l i TABLE OF CONTENTS
-(
INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES L
1.0 INTRODUCTION
2.0 GENERAL PROGRAM DEVELOPMENT 2.1 Program Scope 2.2 Program Update 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION l
3.1 Program Development Philosophy 3.2 Program Implementation 3.3 Program Administration 3.4 Pump Reference List 3.5 Pump Inservice Test 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 Valve Test Program Cold Shutdown Justifications 4.7 Valve Test Program Reactor Refueling Justifications 4.8 Alternative Testing for Non-Code Valves 5.0 REPORTING OF INSERVICE TEST RESULTS l 5.1 Pump Inservice Test Program 5.2 Valve Inservice Test Program l 6.0 QUALITY ASSURANCE PROGRAM ,
l l
r 11 j N2PVI2R8 Revision 8 August 17, 1998 l
L
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
\~
1.0 INTRODUCTION
This Pump and Valve Inservice Test (IST) Program Plan is {
applicable to the North Anna Power Station Unit 2 which received its construction permit on February 19, 1971 and began commercial operation in December 1980. North Anna Power Station Unit 2 is a Pressurized Water Reactor located on Lake Anna in Louisa County, Virginia. The plant employs a Westinghouse Electric Corp. Nuclear Steam System.
The IST Program Plan is comprised of two independent subprograms - the Pump Inservice Test Program and the Valve f 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 2 which started on December 14, 1990 and ends on December 14, 2000.
i For IST, 10CFR50. 55a (g) was replaced by 10CFR50.55a (f) which j was approved for use by the Federal Register, Vol. 57, No. ;
152, dated August 6, 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 2 )
complies with these addenda and edition.
l I
l \
j u l
r'N.
(/)
s.
N2PVI2R8 Revision 8 August 17, 1998
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 Regulations (Para. 50.55a). With respect to the elements of that plan related to the testing of pumps and valves,Section XI, Subsections IWP and IWV direct 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 rules apply only to ISI Classes 1, 2 and 3 as stated by the NRC in the Federal Register, Vol. 56, No. 21 dated January 31, 1991.
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 i I
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. 1
- 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 I
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 i the cold shutdown condition or mitigating the consequences i of an accident.
In addition to the general Code requireme'tsn 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
(~N was established by which the scope of the North Anna ASME
\ m-2-1 Revision 8 N2PVI2R8 August 17, 1998
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 documented.
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:
- 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 op available l documentation, staff review or general experience of the evaluator. Testing requirements were derived based on the component function (s) and the applicable rule (s).
2-2 Revision 8 N2PVI2R8 August 17, 1998
n 1
- 4) Available documents were reviewed and specific or 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 I 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 UPDATE !
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, i
- 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.
n i
L
[T
'k/ 2-3 Revision 8
, N2PVI2R8 August 17, 1998
f-3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION
'A V' 3.1 PROGRAM DEVELOPMENT PHILOSOPHY The North Anna Unit 2 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 2 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) .
l 10CFR50, Section 50.55a(f) (4) (iv) states that inservice examinations of components, test of pumps and valves, and system pressure tests, may meet the requirements set forth in subsequent editions and addenda of ASME Section XI that have been approved by the NRC, subject to Commission approval. North Anna Unit 2 will test l 3 those pumps that fall under the scope of ASME Section l( XI using Subsection IWP of the 1989 Edition. The 1989 Edition of Subsection IWP references OM Part 6, Edition I OM-87, ASME/ ANSI, Operation and Maintenance of Nuclear Power Plants, Addenda.OMa-1988. The scope of the l 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 t
3-1 Revision 8 N2PVI2R8 August 17, 1998 1 .
L l
V Code requirements considered to be impractical, provide
-('}
\m-technical basis for the request and propose alternate testing when warranted.
3.2 PROGRAM IMPLEMENTATION Surveillance testing is performed to detect equipment malfunction or degradation and to initiate corrective action. Since the safeguards pumps are normally in standby mode, periodic testing of this equipment is
! especially important. The North Anna Power Station Unit 2 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 L permanently installed instrumentation is.not available, portable instrumentation is used to record the required parameters.
l 'During subsequent surveillance tests, flow rate is
! /~' normally selected as the independent test parameter and k is set to match the reference flow rate. Other hydraulic and mechanical performance parameters are
- measured'and evaluated against the appropriate l reference values. The results of such evaluations l 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 I include, as minimum:
- 1)
References:
This section identifies references I applicable to Technical Specifications and other necessary material as drawings.
2)
Purpose:
This section identifies test objectives.
- 3) Initial Conditions: Each proced're u should identify those independent actions or procedures which shall be completed and station conditions which shall exist prior to use.
- 4) Precautions: Precautions should be established to alert the individual performing the task to those 3-2 Revision 8 N2PVI2R8 August 17, 1998 l l
l
i situations in which important measures should be taken ;
(^)
\_/
early or where extreme care shculd 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.
Finally, it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements.
Additional testing is performed, as required, after 4 pump maintenance or as determined necessary by personnel at North Anna Power Station.
3.3 PROGRAM ADMINISTRATION
(~'g The Engineering staff at North Anna is responsible for
- (_/ 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.
2-CC-P-1A Component Cooling Water Pumps 2-CC-P-1B Drawing: ll715-CBM-79A, Sh 2 of 3 i Function: Supply cooling water to transfer heat from i heat exchangers containing reactor coolant or other radioactive fluids.
/~N U 3-3 Revision 8 N2PVI2R8 August 17, 1998
2-CH-P-1A High Head Safety Injection / Charging Pumps 2-CH-P-1B Drawing: 12050-CBM-95B, Sh 2 of 2 2-CH-P-1C Function: Supply high pressure borated water to the Reactor Coolant System following a Safety Injection Signal, and to provide normal charging to the Reactor Coolant' System.
1-CH-P-2C Boric Acid Transfer Pumps 1-CH-P-2D 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.
2-EG-P-2HA Emergency Diesel Generator Fuel Oil 2-EG-P-2HB Transfer Pumps 2-EG-P-2JA Drawing: 11715-CBB-35A, Sh 2 of 2 2-EG-P-2JB Function: Supply fuel oil to the Emergency Diesel Generator Fuel Oil Day Tank which directly supplies the Emergency Diesel Generator.
2- FW- P-2 Auxiliary Feedwater Pumps 2-FW-P-3A Drawing: 12050-CBM-74A, Sh 3 of 3 2- FW- P-3 B Function: Supply feedwater to the steam generators following a loss of normal feedwater flow.
2-OS-P-1A Quench Spray Pumps 2-QS-P-1B Drawing: 12050-CBM-91A, Sh 2 of 4 Function: Supply a borated, chemically treated spray to cool, remove iodine from, and depressurize the containment atmosphere following a Containment Depressurization Actuation signal, y i
l 2-RH-P-1A Residual Heat Removal Pumps 2-RH-P-1B Drawing: 12050-CBM-94A, Sh 1 of 2 Function: Remove decay heat from the reactor core and
()
\s /
the Reactor Coolant System during plant cooldown.
3-4 Revision 8 N2PVI2R8 August 17, 1998 i
i r
(/ 2-RS-P-1A Inside Recirculation Spray Pumps 2-RS-P-1B Drawing: 12050-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.
2-RS-P-2A Outside Recirculation Spray Pumps 2-RS-P-2B Drawing: 12050-CBM-91A, Sh 4 of 4 Function: Supply borated spray to cool and depressurize the containment atmosphere following a Containment Depressurization Actuation signal and maintain containment subatmospheric following an accident.
2-RS-P-3A Casing Cooling Pumps 2-RS-P-3B Drawing: 12050-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.
2-SI-P-1A Low Head Safety Injection Pumps 2-SI-P-1B Drawing: 12050-CBM-96A, Sh 1 of 3 Function: Supply low pressure borated water to the Reactor Coolant System following a Safety Injection signal.
2-SW-P-1A Service Water Pumps 2-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.
l 2-SW-P-4 Auxiliary Service Water Pump Drawing: 11715-CBM-78A, Sh 1 of 4 O
L) 3-5
, Revision 8 N2PVI2R8 August 17, 1998 t
Function: Provide make up to the Service Water Reservoir-and can be used as the normal supply to the
(\~s) Service Water system.
2-HV-P-20A Control and Relay Room Chilled Water 2-HV-P-20B Pumps 2-HV-P-20C _ Drawing: 11715-CBB-40C, Sh 2 of 3 Function: Circulate chilled water for the Control and Relay Room Cooling Coils.
2-HV-P-22A Control and Relay Room Condenser 2-HV-P-22B Water Pumps 2-HV-P-22C Drawing: 11715-CBB-40D, Sh 2 of 3 Function: Supply service water to the Control and Relay Room air conditioning condenser water system.
3.5 PUMP INSERVICE TEST TABLES 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
()i N_ impractical. Where relief is requested, technical justification is provided along with alternative test methods when applicable.
For non-Code pumps, a request for relief is not
! 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
! 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 10CFR50.55a and Regulatory Guide 1.26.
O GI 3-6 Revision 8 N2PVI2R8 August 17, 1998
l Note: NC is for non-Code pumps. These pumps are l
()
(/
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 j system resistance that can ba varied. i
- 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 j Lubrication Level / Pressure are given as column I headings. The following abbreviations are used to describe the test status:
l 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 4 i
deviating from Section XI test frequency requirements
~ NA - the test is not applicable, see corresponding relief request j l (\ -} !
RR - the test will be performed every reactor l refueling. A relief request explains the need for ,
deviating from Section XI test frequency !
requirements. 1 i
2Y - the test will be performed every 24 months l Under pump speed, NA applies to constant speed pumps which do not require the measurement of I speed. Therefore, no relief is necessary.
l Under Lubrication Level / Pressure, NA applies to pumps that have a lubrication system with no level or pressure indication. No relief is necessary.
n
\_ /
,7 Revision 8 N2PVI2R8 August 17, 1998
.O t) 3 3 3 3 3 5 5 1 1 1 1
_ fs 1 1 1 1 1 1 1 - - - -
ee , , , , , , , N N N N -
_ iu 2 2 1 1 1 1 1 C C C C 8 l q- 1 1 P P P P eeP , , , , , ,
9 RR( 1 1 1 1 1 1 9
1
. 8 ,
rp 7 am ee A A A A A A A A A. A A n1
/ / / / / / / / / / / o BT N N N N N N N N N N N i t e' ss bl A A A A ivgu ui / / / / e u -
o
_ i t
a _
- r
. b E i L V Q Q Q Q Q Q Q Q Q Q Q B
A
_ T we ot G la R R N FR Q Q Q Q Q R R Q Q Q Q
_ I T l S a E i
. OE T t ne
_ er C ru 8 I es -
V fs 3
_ R f e A A A A
_ E i r / / / /
S DP Q Q Q Q Q Q Q N N N N N -
I e r
_ P u M ts U es P l e A A A A nr / / / / .
Q Q Q Q Q N N N N IP Q Q _
.d 3 _
e 2 2 _
. t
) e A A A A A A A A A A A .
1 p / / / / / / / / / / / _
( S N N N N N N N N N N N .
_ mt es D D .
ti . . . . . E E . . . .
ss ye R R R R R X X R R R R
_ A A A A A I I A A A A ;
SR V V V V V F F V V V V C C C C
_ s 3 3 2 2 2 3 3 N N N N _
Es -
Ma A B A B -
Sl A B A B C C D H H J J
_ AC 1 1 1 1 1 2 2 2 2 2 2 8
- - - - - - - - - - - R .
P P P P P P P P P P P 2 t - - - - - - - - - - - I pn C C H H H H H G G G G V O me ud PI C
2 C
2 C
2 C
2 2
C C
1 C
1 E
2 2
E E
2 2
E P
2 N
4 e
t) 1 1 1 1 1 5 5 1 1 1 1 1 1 f s , ,
ee 1 1 iu 8 l q-eeP 9 RR( 9 1
rp -
8 ,
am ee A
/
A
/
A A A A A A A A A A A n1 7 BT N N
/
N
/ / / / / / / / / / o N N N N N N N N N N i t e ss bl A A A A iu vg ui S S LO Q Q Q Q Q C C
/
N
/
N
/
N
/
N Q Q eu RA --
n -
o i
t b
a r - _
E i S S R R Y Y .
L V Q Q Q Q Q C C R R 2 2 Q Q B
A T we ot G l a S S R R Y Y N FR Q Q Q Q Q C C R R 2 2 Q Q -
I T l S a E i 3
T t ne _
E er -
C ru 9 I es -
V f s 3 R f e E ir S S R R Y Y S DP Q Q Q Q Q C C R R 2 2 Q Q N
I e r
P u M ts U es P l e nr S S R R Y Y IP Q Q Q O Q C C R R 2 2 Q Q d
e
) e 1 p A
/
A
/
A
/
A
/
A A A A A A A A _
/ / / / / / / /
( S Q N N N N N N N N N N N N mt es D D ti . . . E E . . . . . . . .
ss R R R X X R R R R R R R R ye A A A I I A A A A A A A A _
SR V V V F F V V V V V V :V V .
s 3 3 3 2 2 2 2 2 2 2 2 3 3 _
Es Ma -
Sl A B A B A B A B A B A B AC 2 3 3 1 1 1 1 1 1 2 2 3 3 8
- - - - - - - - - - - - - R P P P P P P P P P P P P P 2 t - - - - - - - - - - - - - I -
pn W W W S S H H S S S S S S V .
me E E E Q Q R R R R R R R R P
, ud - - - - - - - - - - - - - 2 -
PI 2 2 2 2 2 2 2 2 2 2 2 2 2 N -
g) jQ -
~
t) 1 1 2 2 2 1 1 1 fs' 1 1 1 ee , , ,
iu 9 9 0 8 l q- , , 1 9 '-
eeP 1 1 ,
9 "
RR( '
1 1
. 8 ,
rp 7 am A A A A A A A A n1 ee / / / / / / / / o BT N N N N N N N N i t e ss u bl A A A iu vg ui LO Q Q Q Q Q
/
N
/
N
/
N eu RA h
n o -
i t J a
r b
E i L V Q Q Q Q Q Q Q Q B m A
T we h ot G l a N FR Q Q Q Q Q Q Q Q I
T l S a A E
i _
T t e
< ne -
E er 0 C ru 1 -
es I r.
V fs 3 R f e A A A .
E i r / / /
S DP Q Q N N N Q Q Q m _
N I e r
P u M ts U es P l e A A A .
nr m
/ / /
IP Q Q N N N Q Q Q
.d .
e
) e A A A A 'A A A A 1 p / / / / / / / /
( S N N N N N N N N m a
mt es D D ,.
ti E E . . . . . . 2 .
ss X X R R R R R R ye I I A A A A A A ;
SR F F V V V V V V s 2 2 3 3 3 3 3 3
_ Es Ma A B C Sl A B A B 0 0 0 AC 1 1 1 1 4 2 2 2 8
- - - - - - - - R P P P P P P P P 2 t - - - - - - - - I s,). pn I I W W W V V V V -
. me S S S S S H H H P f N ud PI 2 2
2 2
2 2
2 2
- 2 N
ii l!!l)i!llllll i illll l 1. 1Il1l!l\lil p d m n u a p
_ t) 1 1 1 _
d fs d e ee e e iu e p 8 .
lq- p s 9 eeP s 9 RR( h 1 e g
. l i 8 rp -
b h am A 7 A A a n1
_ ee / / / i e o BT N N N r h i t a t ss e v i u bl A A A y t vg ui / / / a eu LO N N N l RA
- n d o e n t o e s i h e t t t a
r s e b i r E i a L V Q Q Q 2 ym B
A P ea T we - hr G
ot l a W tg N FR Q Q Q E
- ,r o
I 2 rp T l e S
E i a
veis T t s wh ne p ot E er m h 1 C ru u r 1
- I es p ;e -
V sp fs 3 R fe d d E
S i r DP Q Q Q e
e e
eps
_ N p pm
_ I e s sup r
_ P u e o M
U ts es l
b wd P a te epe l e nr i va s IP Q Q Q r a
d v ht e n
) e A A A r Da 1 p / / / o t
(
S N N N f ds d
nn ao mt e . c es ti ' . '. .
rm ua C
2d ss ye R
A R
A R
A sr ag Pr
-e _
V e mro SR V V - e -
H d -
p Ci s 3 3 3 s - s Es is 1 n -
Ma A B C i o Sl AC 2
2 2
2 2
2 dh et sp c 8 _
- - - e me R
. t P
P P
pn Si Pa ur 2 I
pn V V V V .
me H H H ) ) P ud - - - 1 2 2 _
PI 2 2 2 ( (
N
3.6 ' PUMP TEST PROGRAM RELIEF REQUESTS 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 performed is given.
l l
I l.
I l
o !i i
1 i
n l
O 3-12 N2PVI2R8 Revision 8 August 17,.1998
1[) RELIEF REQUEST P %)
Systems: Various Pump (s) : : IWP Program Pumps. See PUMP INSERVICE TEST TABLE.
Class :
~(24 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 (V,) 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
' minimum value for V, of 0.05 in/see has been ' established for kTL s/ 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.
o I
l' .
l h v 3-13 N2PVI2R8 Revision 8 August 17, 1998 l L.
1 1
i RELIEF REQUEST P-2 Relief Request _ Withdrawn f l
' RELIEF REQUEST P-3 i
{ Relief Request-withdrawn.
l RELIEF REQUEST P-4 Relief Request withdrawn.
l l
l l
0 0 3-14 I2R8 Revision 8 August 17, 1998
1 1
i
'i RELIEF REQUEST P-5 L) l Systems: Residual Heat Removal Pump (s) : 2-RH-P-1A~
2-RH-P-1B Class : 2 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 F.eques_t; The low pressure pumps take suction from and discharge to the Reactor Coolant System (RCS)which operates at 2235 psig. This pressure is well above the operating pressure of the pumps; therefore, testing during normal operation is not possible.
Also, the pumps are located inside containment and are inaccessible during normal operation.
t%
(_) As a result of 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 tne 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 in NUREG 1482, Section 5.2, "Use of Variable Reference Values for Flow Rate and Differential Pressure During Pump Testing," will be followed. ,,
1
,< \
g 3-15 N2PVI2R8 Revision 8 August 17, 1998 L
RELIEF ~ REQUEST P-5 (Cont.)
If vibration is found to vary significantly over the range of flow' rates, flow rate versus vibration velocity data for at'least l ~ five points 1will be.taken, and a curve fit for these data points l 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.
i l
i 1
i i
l- o i
3-16
! N2PVI2R8. Revision-8 l August 17, 1998 i.
L k
l i
RELIEF REQUEST P-6 Relief Request Withdrawn l
l RELIEF REQUEST P-7 Relief Request Withdrawn RELIEF REQUEST P-8 Relief Request withdrawn.
I
\
, 9 O 3-17 N2PVI2R8 Revision 8 August 17, 1998
p
/h RELIEF REQUEST P-9 V
' Systems: Service Water Pump (s) : 2-SW-P-1A 2-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 dischprge 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
(' \
3-18 N2PVI2R8 Revision 8 August 17, 1998
(~~) RELIEF REQUEST P-9 (Cont.)
L/
to the pump impeller, and subtracting the height from the reservoir surface to the pump impeller.
Therefore, the measured discharge pressure will always be a smaller number than the actual total head developed by the pump.
Applying the Section XI acceptance criteria to just the discharge pressure instead of the total developed head for a deep draft pump is a conservative application of the acceptance criteria because the operability band is smaller.
Alternate Testing Proposed Discharge pressure will be measured in place of differential pressure.
^
,x b'
,3 N_.]
3-19 N2PVI2R8 Revision 8 August 17, 1998
F
(~'T RELIEF REQUEST P-10 V
Systems: Service Water Pump (s) : 2-SW-P-4 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, gs k,
s However, the lake level fluctuates very little from test to test l and can be considered to be constant. The lake has a minimum level of 244 feet elevation as required by Technical ;
Specifications, and maximum and minimum recorded levels during 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 pressure is measured.
Applying the Code acceptance criteria to discharge pressure instead of differential pressure is a conservapive application of the accept &nce criteria for the deep draft pump. For this pump, the total c'eveloped head is calculated by adding the measured discharge pressure to the height from the discharge pressure gauge i
I 3-20 N2PV12R8 Revision 8 August 17, 1998
rn j RELIEF REQUEST P-10 (Cont.)
(}
to the pump impeller, subtracting the height from the lake surface to'the pump impeller.
Therefore, the measured discharge' pressure will always be a'
' smaller number than-the actual total _ head developed by the pump.
Applying the Section XI acceptance criteria to just the discharge pressure instead of the total developed head for a deep draft pump is a conservative application of the acceptance criteria because the operability band is smaller.
Alternate Testing Proposed Discharge pressure will be measured in place of differential pressure.
l 1
! I i
O l
l l-i vg O 3-21 N2PVI2R8 Revision 8 August 17, 1998
)
RELIEF REQUEST P-11' Relief Request withdrawn.
O n
i l
O 3-22 N2PVI2R8 Revision 8 !
August 17, 1998 I l
r--
RELIEF REQUEST P-12 (l]N
\~- ;
Systems: Component-Cooling and Service Water Pump (s): 2-CC-P-1A 2-SW-P-1A 2-CC-P-1B 2-SW-P-1B 2-SW-P-4 )
I
. Class : 3 OM Part 6 Code Requirements For Which Relief-Is Requested (2( Part 6, Paragraph 4.3 requires reference values to be points of '
operation readily duplicated during subsequent tests. All subsequent test'results shall lua compared to these initial reference values.
Basis For Request Plant conditions may not be the same as when the reference values i were established. Many reference points must be established to i 1 anticipate future plant conditions. In the Component Cooling and
("}
\_/
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 significantly with flow rate over the range of the test flow rates.
Alternate Testing Proposed All subsequent test results will be compared to calculated reference values which are determined using the following method.
A set of at least five pressure / flow points will be recorded.
From these points an equation for the line will be calculated by a
-' computer using polynomial regression. The resulting polynomial equation describes the reference curve. y l
3-23
- -N2PVI2R8 Revision 8 August 17, 1998 r i
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.
O O 3-24 N2PVI2R8 Revision 8 August 17, 1998
~
RELIEF REQUEST P-13
[v]-
Systems: Component Cooling Chemical and Volume control Service Water.
, Pump (s): 2-CH-P-1A 2-CC-P-1A 2-CH-P-1B 2-CC-P-1B 2-CH-P-1C 2-SW-P-4 Class :' 3 OM Part.6 Code Requirements For Which Relief'Is Requested OM.Part 6, Section 4.6, Table 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 accuracy is found by the root sum of the squares. The only variables in this formula are the sensor calibration accuracy and the. indicator accuracy. Installing new sensors and indicators to i 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 j
.FI-2122 2-CH-P-1A,B,C Flow 2.34%
-FI-CC-200A 2-CC-P-1A Flow 2.69% '
FI-CC-200B 2-CC-P-1B Flow 2.69%
PI-SW-210 2-SW-P-4 Discharge Pressure 2.61%
Alternate Testing Proposed i None.
l-3-25 f N2PVI2R8 Revision 8 August 17, 1998 L
r RELIEF REQUEST P-14 Relief Request withdrawn.
l l
l l
t l
O l
l l
l s
l O 3-26 N2PVI2R8 Revision 8 August 17, 1998
n l
/~'N RELIEF REQUEST P-15 b
Systems: Boric Acid Transfer Pump (s) : 1-CH-P-2C 1-CH-P-2D 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
()
v 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 boren balance in the RCS.
Therefore, to limit the amount of boric acid injected 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 N2PVI2R8 Revision 8 August 17, 1998 l
() RELIEF REQUEST P-15 (Cont. )
Alternate Testing Proposed These pumps will.beLtested 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.
i l
I Vi l
3-20
.:N2PVI2R8. Revision.8 '
August 17, 1998 I
r-RELIEF REQUEST P-16 Relief Request withdrawn.
l l
l l
\
, l
! I 1
l 1
l l
3-29 N2PVI2R8 Revision 8 August 17, 1998
3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS According to the Minutes of the Public Meeting on Generic Letter 89-04, " Paragraph (g) of 10CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. ;
For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a
' request for relief' to be submitted to the staff.
Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety, but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.
North Anna Power Station has elected to include certain 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.
n 3-30 N2PVI2R8 Revision 8 August 17, 1998 E -~ _ _ _ _ _ - _ _ _ _ _
m 1
() NON-CODE ALTERNATIVE TESTING PNC-1 System : Fuel Oil Pump (s):~ 2-EG-P-2HA 2-EG-P-2JA j 2-EG-P-2HB 2-EG-P-2JB Class- :- NC OM Part-6 Code Requirements!
-Which'Will Not Be Met-
-OM Part 6, Paragraph 5.6 requires that test' quantities be measured af ter the Innnp 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
_T when the fuel, oil level in the day tank reaches the low level switch, and stop when the level reaches the high level switch. 1 I
The pump run time can vary depending upon the diesel load and the resulting fuel consumption rate. If~the-pumps are allowed to run.
l for.twofminutes 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 I'ange from 7.5 to 8.5 l
psig,: less than the required 1/3 of full-scale or 10 psig. Test I 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.
l 1
V4 l
f-~\
V 3-31 ,
N2PVI2R8 Revision 8 August 17, 1998 l
c . _w -
.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 measurements will be performed with reference values _slighty-.below:the 1/3 full-scale requirement.
I Note: The diesel oil trans_fer 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. l i
1 O :
l O 3-32 1
N2PVI2R8 Revision 8 August 17, 1998 i
I TN !
4.0 VALVE INSERVICE TESTING PROGRAM DESCRIPTION i b
4.1 PROGRAM DEVELOPMENT PHILOSOPHY l
\
l North Anna Power Station Unit 2 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 2 Valve Inservice Test Program satisfies these requirements.
l The program will detect potentially adverse changes in j 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
/"'s perform a specific' function in shutting down a reactor
(_s/ to the cold shutdown condition or in mitigating the ,
consequences of an accident." It is important to note I that the scope of ASME Section XI and the North Anna 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 there cases, the requirements of Section XI, OM Part 10 shall be met except where relief has been granted.
To generate the North Anna Unit 2 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 2 is committed to mSeting the leak rate testing requirements of:
- 1) 10CFR50, Appendix J for containment isolation valves and e- s 4-1 N2PVI2R8 Revision 8 August 17, 1998
/N 2) OM Part 10 for other valves for which seat (m l leakage is limited to a specific maximum amount (i.e. pressure isolation valves) unless relief is specifically requested from OM Part 10 i requirements.
Valves subject to leak testing per Appendix J will be i 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 j testing where warranted (refer to Section 4.5) .
The North Anna Unit 2 Valve Inservice Test Program complies with the intent of the applicable codes, i I
regulations and guidelines and makes a positive
('")%
\s , contribution to the safe operation of the plant.
l 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 valvc 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, this can be accomplished using normal control circuits.
4-2 N2PVI2R8 Revision 8 August 17, 1998
p O)
\s- 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 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 l complete cold shutdown testing."
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 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 wil.1 be performed if practicable.
To. test check valves to the full open position, the maximum required accident condition flow must be measured through 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 me,thod.
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 requires that each valve in the group be the same design (manufacturer, size, model number, and materials 4-3 N2PVI2R8 Revision 8 August 17, 1998
(T
\/
of. construction) and have the same service conditions including-valve orientation. The group size cannot exceed four valves.
Additionally, at each disassembly 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 i 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 for the administration of the Valve Inservice
(~'
1 Testing Program. The Operations staff is 3 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. I 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.
I
- 1) Valve Number - Each valve in the plant has a unique
" mark" number which identifies the system to which l the equipment belongs and type of equipment.
4-4 N2PVI2R8 Revision 8 August 17, 1998
O)-
\._ 2) Drawing and Sheet Number, Coordinate - The specific
. coordinates 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
\ important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.
- 6) Category - Categories are defined by OM Part 10, Section 1.4. Each valve has specific testing requirements which are determined by the category to which it belongs. Valves marked with an "E" are passive valves.
- 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 ,
l Appendix J, Option B leakage testing as described 1 l in Technical Specification Section 4.6.1.2.
PIV - Pressure Isolation Valve which protects low l 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.
\
4-5 N2PVI2R8 Revision 8 August 17, 1998
o I
l l
f
( ,
C&P - Valves that serve both CIV and PIV functions l
- 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 l 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 10, Section 4.2.2.2.
VP - Valve position indication shall be verified per OM Part 10, Paragraph 4.1 or as modified by a specific relief request.
l SP - Set points of safety and relief valves shall I be tested per OM Part 1, 1987 Edition or as 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 l 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 used to describe normal valve positions to which 4-6 i N2PVI2R8 Revision 8 l August 17, 1998 l
r.
I
() ;
T s-the valves are tested (including the valve safety l position):
1 0 - Open 1 '
C - Closed OC .Open and Closed PO - Partially Open' PS - Partially Stroked i
- 10) Test Frequency - The following abbreviations are I 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 I RR - Every reactor refueling outage OPB - Per the test frequency determined by the Appendix J, Option B program for leak testing containment isolation valves
- 11) Relief Request Reference '
i
- 12) Cold Shutdown Justification Reference i
- 13) Reactor Refueling Justification Reference
- 14) Non-Code Alternative Test Reference
- 15) Function - A brief description of the function of the valve.
n I
O 4-7 N2PVI2R8 Revision 8 August 17, 1998 t.
F VIRGINIA POWER COMPANY PAGE: 1 0F 84 NORTN ANNA UNIT 2 REVISION: 8 (O S?COND INSERVICE TESTING INTERVAL 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 REQ JUST JUST TEST NLDISER NUMBER IEMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-I 2-3D TV 200A 12050-CBM-098A 2'0F 5 C6 A0 GLORE 3.000 2 A CIV EV C 03 i FS C 03 .
t LT C OPS ST C 03 VP OC 24 "A" STEAM GENERATOR BLOWOWN, OUTSIDE CON-TAIMMENT ISOLATION VALVE l
- 2 BD-TV 2008 12050-CBM-098A 2 0F 5 C5 A0 GLOSE 3.000 2 A CIV EV C 03 FS C 03 LT C OP5 ST C 03 VP OC 24 "A" STEAM GENERATOR BLOWOWN, INSIDE CON-TAINMENT ISOLATION VALVE 2 80-TV-200C 12050-CBN-098A 3 0F 5 C6 A0 GLOBE 3.000 2 A CIV EV C 03 i FS C 03
'LT C OPB i ST C 03 VP OC 24 "B" STEAM GENERATOR BLOW OWN, OUTSIDE CON-TAINMENT ISOLATION VALVE f ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
2 BD-TV-2000 12050-COM-098A 3 0F 5 C5 A0 GLosE 3.000 2 A CIV EV C 03 l (V) FS LT C
C 03 OPS ST C 03 VP OC 24 "B" STEAM GENERATOR BLOWDOWN, INSIDE CON-TAINMENT ISOLATION VALVE 2 BD TV 200E 12050 CBM 098A 4 0F 5 C6 A0 GLOBE 3.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 "C" STEAM GENERATOR BLOWDOWW, OUTSIDE CON-l TAINMENT !$0LATION VALVE l
2 BD TV 200F 12050 CBM 098A 4 0F 5 C5 A0 GLOSE 3.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 i "C" STEAM GENERATOR BLOWDOWN, INSIDE CON- "3 I
TAINMENT ISOLATION VALVE A
V e
VIRGINIA POWER COMPANY PAGE: 2 0F 84 NORTH ANNA UNIT 2 REVISION: 8 I/} SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DATE: 08/17/98 I
l d
NC 180 REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-2-CC 010 11715 CBM-079A 2 0F 3 E6 CHECK VALVE 18.000 3 C CV C 03 i 0 03 I "A" COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 2-CC-027 11715 CBM-079A 2 DF 3 D6 CHECK VALVE 18.000 3 C CV C 03 4 0 03 "B" COMPONENT COOLING PUMr DISCHARGE CHECK VALVE 2 CC-078 12050-CBM-079A 2 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 24 1 LT C OPS i
CC SUPPLY TO "A" RC PUMP LO, STATOR SKROUD & j THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV 2-CC 107 12050-CBM 079A 2 0F 5 C7 CHECK VALVE 3.000 3 C CV C RR 22 I
CC SUPPLY TO "A" RC PUMP THERMAL BARRIER COOLER CHECK VALVE 2-CC 115 12050-CBM 079A 3 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 24 1 )
LT C OPB l
............................................. j r~ CC SUPPLY TO "B" RC PUMP LO, STATOR SHROUD &
f l g THERM BARRIER COOLERS, IN CONT ISOL CHECK VLV 2 CC-144 12050 CBM-079A 3 0F 5 C7 CHECK VALVE 3.000 3 C CV C RR 22 CC SUPPLY 70 "B" RC PUMP THERMAL BARRIER COOLER CHECK VALVE 2-CC-152 12050-CBM 079A 4 0F 5 F7 CHECK VALVE 6.000 2 AC CIV CV C 24 1 LT C OPS CC SUPPLY To "C" RC PUMP LO, STATOR SHROUD &
THERM BARRIER Co0LERS, IN CONT ISOL CHECK VLV 2 CC-181 12050-CBM-079A 4 0F 5 C7 CHECK VALVE 3.000 3 C CV C RR 22 CC SUPPLY TO "C" RC PUMP THERMAL BARRIER COOLER CHECK VALVE 2-CC 194 12050-CBM-079A 10F 5 F7 CHECK VALVE 18.000 2 AC CIV CV C 24 24 0 RR 24 P0 03 LT C OPB CC SUPPLY T0 "A" RNR HEAT EXCHANGER
's 2 CC 199 12050-CBM-079A 1 of 5 F7 CHECK VALVE 18.000 2 AC Civ CV C 24 24 0 RR 24 P0 03 LT C OPB CC SUPPLY TO "B" RNR HEAT EXCHANGER
'"'s ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
O i
l l
VIRGIN!A POWER COMPANY PAGE: 3 0F 84 NORTH ANNA UNIT 2 REVISION: 8 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 RE0 JUST JUST TEST NUMBER NUMBER NUMBER Cook TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-2 CC 276 12050-CeM-0798 3 0F 3 E8 CHECK VALVE 6.000 2 AC CIV CV C 24 20 LT C OPS CC SUPPLY TO "A" RECIRC AIR COOLING COILS, QUTSIDE CONTAINMENT ISOLAfl0N CHECK VALVE
-2 CC 289 12050 ceM-0795 3 0F 3 08 CHECK VALVE 6.000 2 AC CIV CV C 24 20 LT C OPS CC SUPPLY TO "B" RECIRC AIR COOLING ColLS, CUTSIDE CONTAINMENT ISOLATION CHECK VALVE 2 CC 302 12050 CeM-0795 3 0F 3 C8 CHECK VALVE 6.000 2 AC Civ CV C 24 20 LT C OPS CC SUPPLY TO "C" RECIRC AIR COOLING C0!LS, OUTSIDE CONTAINMENT ISOLATION CHECK VALVE 2-CC-MOV 200A 12050 CeM 079A 1 0F 5 A3 M0 BFLY 18.000 3 5 EV 0 03 ST C 03 VP OC 24 COMPONENT COOLING WATER RETURN THROTTLING VALVE FROM "A" RNR NEAT EXCHANGER 2-CC MOV 2005 12050-CsM-079A 1 0F 5 33 M0 BFLY 18.000 3 8 EV 0 03
[
OC 24 03 COMPONENT COOLING WATER RETURN THROTTLING VALVE FROM B RNR NEAT EXCHANGER 2CC-RV20$A 12050 CBM 0795 3 0F 3 E5 RELIEF VALVE .750 NC C SP O 120 CONTAINMENT PENETRATION 11 RELIEF VALVE -
CC SUPPLY TO RECIRC AIR COOLERS 2 CC-RV 2048 12050 CsM 0798 3 0F 3 D5 RELIEF VALVE .750 NC C SP O 120 CONTAINMENT PENETRAfl0N 10 RELIEF VALVE -
CC SUPPLY TO RECIRC AIR COOLERS 2-CC RV 204C 12050 cum 0798 3 0F 3 C5 RELIEF VALVE .750 NC C SP O 120 CONTAINMENT PENETRATION 9 RELIEF VALVE - ;
CC SUPPLY TP RECIRC Alt COOLERS i 2-CC RV 224A1 12050-CBM-079A 2 0F 5 F6 RELIEF VALVE 3.000 3 C SP O 120 COMPOWENT COOLING WATER To REACTOR SMROLE HEAT EXCNANGER RELIEF VALVE .,
2-CC-RV 2248 12050 CeM-079A 3 0F 5 F6 RELIEF VALVE 3.000 3 C SP 0 120 COMPONENT C00Ll#G WATER TO REACTOR SMROUD l NEAT EXCNANGER RELIEF VALVE 2 CC-RV 224C 12050 CBM 079A 4 0F 5 F6 RELIEF VALVE 3.000 3 C SP O 120 r
i
C.
h VIRGINIA POWEP COMPANY PAGE: 4 0F 84 C NORTM ANNA UNIT 2 REVISION: 8 (s if.0ND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAV Li SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUF d COOR TYPE $!ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-COMPONENT COOLING WATER TO RCACTOR SMROLD NEAT EXCNANGER RELIEF VALVE 2-CC-PV 225A 12050-CBM-079A 2 0F 5 C6 RELIEF VALVE .750 3 C SP O 120 CC SUPPLY TO "A" RC PUMP THERMAL BARRIER RELIEF VALVE 2 CC-RV-225B 12050 CBM 079A 3 0F 5 C6 RELIEF VALVE .750 3 C SP O 120 CC SUPPLY TO "B" RC PUMP THERMAL BARRIER RELIEF VALVE 2-CC-RV-225C 12050-CBM-079A 4 0F 5 C6 RELIEF VALVE .750 3 C SP 0 120 CC SUPPLY To "C" RC PLMP THERMAL BARRIER RELIEF VALVE 2-CC-RV 226 12050 CBM-079A 5 OF 5 C6 RELIEF VALVE 1.000 3 C SP 0 120 EXCESS LETDOWN NEAT EXCHANGER COMPONENT COOLING WATER PENETRATION 1 RELIEF VALVE 2 CC-RV 228A 12050-CBM 079A 1 OF 5 E3 RELIEF VALVE .750 3 C SP 0 120 g) t V
"A" RHR NEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 2-CC-RV-228B 12050-CBM-079A 1 0F 5 D3 RELIEF VALVE .750 3 C SP O 120 "B" RHR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 2-CC-RV 231A 12050 CBM-079A
- 5 0F 5 C4 RELIEF VALVE .750 3 C SP O 120 RHR PUMP SEAL COOLER RELIEF VALVE 2 CC-RV 231B 12050-Cid 079A 5 0F 5 C4 RELIEF VALVE .750 3 C SP O '20 RHR PUMP SEAL COOLER RELIET VALVE 2 CC-TV 200A 12050-CBM-079B 3 0F 3 E3 A0 BFLY 6.000 2 A CIV Eb c 03 FS C 03 LT C OPB ST C 03 VP OC 24 CC RETURN FRCA "A" RECIRC AIR COOLING COILS, g OUTS!DE CONTAINMENT ISOLATION VALVE 2-CC TV 2008 120$0-CBM-0795 3 0F 3 D3 A0 BFLY 6.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 i
7"N
\u
)
VIRGINIA POWER COMPANY PAGE: 5 0F 84 f, NORTH ANNA UNIT 2 REVisl0N: 8
[ j SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\ ,,/ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-CC TURN FROM "B" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION VALVE 2 CC TV 200C 12050-CBM-0798 3 DF 3 C3 A0 BFLY 6.00S 2 A CIV EV C 03 FS C 03 l LT C OPE I ST C 03 I VP OC 24 i l
CC RETURN FROM "C" RECIRC AIR COOLING COILS, i OUTSIDE CONTAINMENT ISOLATION VALVE 2 CC TV 201A 12050-CDM-079A 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 24 CC RETURN FROM REACTOR COOLANT PUMP THERNAL BARRIERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CC-TV-201B 12D50-CBM-079A 10F 5 D6 A0 GLOBE 4.000 2 A CIV EV C CS 1 FS C CS 1 LT C OPB
[, ~}_,,
CC RETURN FROM REACTOR COOLANT PUMP THERMAL :
BARRIERS, INSIDE CONTAINMENT ISOLATION VALVE I 2-CC TV 202A 12050-CBM-079A 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 CC RETURN FROM "C" RC PUMP LO, STATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE i
2-CC-TV-202B 12050-CBM-079A 4 0F 5 A3 A0 BFLY 8.000 2 A CIV EV C CS 1
! FS C CS 1 LT C OPS ST C CS 1 VP DC 24 CC RETURN FROM "C" RC PUMP LO, STATOR & SHROUD COOLERS, INSIDE CONTAINMENT ISOLATION VALVE 2-CC-TV-202C 12050-CBM 079A 3 0F 5 A5 A0 BFLY 8.000 2 A CIV EV C CS 1 3
FS C CS 1 LT C DPB ST C CS 1 VP OC 24 CC RETURN FROM #B" RC PUMP LO. STATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CC TV-202D 12050 CBM-079A 3 0F 5 A3 A0 BFLY 8.000 2 A CIV EV C CS 1 FS C CS 1 f -%s t LT C 28
\s L-.
1
- v!RGINIA POWER COMPANY PAGE
- 6 0F 84 l
I ,-s) NORTH ANNA UNIT 2 SECOND INSERVICE TESTING INTERVAL REVISION: 8 DATE: 08/17/98 l \s ,_ / INSERVICE TESTING PROGRAM - VALVE TABLE WC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRED V- CSV- RRV VCN-
...... ....... ...... .... ..... ..... .... ... .... .... .... .... ... .... .... .... 3
! 2 CC TV 202D 12050 CBM-079A 3 of 5 A3 A0 SFLY 8.000 2 A CIV ST C CS 1 l VP DC 24 CC RETURN FROM "B" RC PUMP LO, STATOR & SHROUD COOLERS, INSIDE CONTAINMENT ISOLATION VALVE
........................................... 4................. ..... .... ... .... .... .... .... ... .... .... ....
2-CC-TV-202E 12050-CBM-079A 2 0F 5 A5 A0 BFLY 8.000 2 A CIV EV C CS 1 FS C CS 1 LT C OPS l
ST C CS 1 VP DC 24 CC RETURN FROM "A" RC PUMP LO, STATOR & SHROJD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2 CC-TV 202F 12D50-CBM 079A 2 OF 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 l COOLERS, INSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 2-CC TV-203A 120$0-CBM-079A 10F 5 A7 A0 BFLY 18.000 2 A CIV EV C 03 l pg o 03 f ) FS C 03 i
b/ LT C OPS ST C 03 0 03 VP DC 24 CC RETURN FROM "A" RHR HEAT EXCHANGER, OUT-SIDE CONTAINMENT ISOLATION VALVE 2 CC TV 2038 12050-CBM-079A 1 0F 5 BT A0 BFLY 18.000 2 A CIV EV C 03 0 03 FS C 03 i LT C DPB 1 ST C 03 0 03 VP DC 24 CC RETURN FROM "B" RHR HEAT EXCHANGER, OUT-SIDE CONTAINMENT ISOLATION VALVE
! 2-CC-TV 2D4A 12050-CBM 079A 2 0F 5 E8 A0 BFLY 8.000 2 A CIV EV C CS 1 i FS C CS 1 l
LT C OPB ST C CS 1 g VP DC 24 CC SUPPLY TO "A" RC PUMP LO, STATOR, SHROUD &
THERM BARRIER COOLERS, OUTSIDE CONT ISOL W V 2 CC-TV 204B 12050-CBM-079A 3 0F 5 E8 A0 BFLY 8.000 2 A CIV EV C *S 1 FS C CS 1 LT C OPS ST C CS 1 i p)
\~
VP OC 24 l l
l
VIRGINIA POWER COMPANY PAGE: 7 0F 84 l f ~s NORTH ANNA UNIT 2 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 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-CC SUPPLY T0 "B" RC PUMP LO, STATOR, SNROUD &
THERM BARRIER COOLERS, OUTSIDE CONT ISOL VLV 2 CC TV-204C 12050-CBM 079A 4 0F 5 E8 A0 SFLY 8.000 2 A CIV EV C CS 1 FS C CS 1 LT C OPS ST C CS 1 VP OC 24 CC SUPPLY TO "C" RC PUMP LO, STATOR, SHROUD &
THERM BARRIER COOLERS, OUTS!DE CONT ISOL VLV 2-CC TV-205A 12050-CBM 0799 3 0F 3 E4 A0 BFLY 6.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24 CC RETURN FROM "A" RECIRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATION VALVE 2-CC TV 2058 12050 CBM-079B 3 0F 3 D4 A0 BFLY 6.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03
(-s
(, .............................................
VP OC 24 l
CC RETURN FROM "B" RECIRC AIR COOLING COILS, j INSIDE CONTAIMMENT ISOLATl0N VALVE j 2 CC-TV-205C 12050 CBM-079B 3 0F 3 B4 A0 BFLY 6.000 2 A CIV EV C 03 FS C 03 LT C DPB l ST C 03 i VP OC 24 l CC RETURN FROM "C" REClRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATION VALVE Y f.
e
.v
VIRGIMIA POWER COMPANY PAGE: 8 0F 84
(
( NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM . VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NLMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TTPE TYPE POS FREG V- CSV RRV VCN-2 CD 163 11715 C88 040C 2 0F 3 E6 CHECK VALVE 3.000 3 C CV o 03 CONTROL ROOM CHILLED WATER SYSTEM PUMP DISCHARGE CHECK VALVE 2 CD 187 11715 ca8 fKOC 2 of 3 D6 CHECK VALVE 3.000 3 C CV 0 03 CONTROL kfam CHILLED WATER SYSTEM PUMP DISCHARGE CHECK VALVE 2 CD 211 11715 Cat-040C 2 0F 3 C4 CHECK VALVE 3.000 3 C CV 0 03 CONTROL ROOM CHILLED WATER SYSTEM PUMP DISCHARGE CHECK VALVE h
i
'\
< -. )
1-i l VIRGINIA POWER COMPANT PAGE: 9 0F 84 f
rs g NORTH ANNA UNIT 2 REVISION: 8
( SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
% INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT I VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUNCCR NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-1*CH 118 11715 CBM 095A 1 0F 4 C6 CHECK VALVE 2.000 3 C CV 0 CS 3 j PO 03 I
"C" BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE 1*CH 133 11715-CBM-D95A 1 0F 4 C7 CHECK VALVE 2.000 3 C CV 0 CS 3 PO 03 "D" BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE 2 CH-153 12050 CBM-095B 1 0F 2 B6 CHECK VALVE 4.000 2 AC CV C RR 25 0 03 LT C 24 CHARGING PUMP SUPPLY FROM VOLUME CONTROL TANK ISOLATluN VALVE i ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
2 CH 155 12050 CBM-0958 1 0F 2 C3 CHECK VALVE 1.000 3 C CV O CS 4 ALTERNATE EMERGENCY BORATION LINE CHECK VALVE 2-CH 156 12050-CBM-0958 1 0F 2 B4 MANUAL GATE 1.000 3 8 EV 0 CS 4
[ ) ALTERNATE EMERGENCY BORATION LINE (f MANUAL VALVE 2 CH 157 12050-CBM-0955 1 0F 2 B4 CHECK VALVE 1.000 2 C CV 0 CS 4 ALTERNATE EMERGENCY B0 RATION LINE 10 CHARGING PUMP SUCTION CHECK VALVE I 2 CH 159 12050 CEM-0958 1 0F 2 85 CHECK VALVE 2.000 2 C CV 0 CS 4 1 .............................................
MAIN EMERGENCY BORATIDN LIN. TO CHARGING l PUMP SUCTION CHECK VALVE 2 CH-176 12050 CBM 0958 2 0F 2 04 CHECK VALVE 3.000 2 C CV 0 CS 39 "A" CHARGING PUMP DISCHARGE RECIRC LINE CHECK l VALVE l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1 2-CH 178 12050 CBM-0958 2 0F 2 D4 CHECK VALVE 3.000 2 C CV C 03 0 RR 18
..................... ....................... l "A" CHARGING PUMP DISCHARGE CHECK VALVE 2 CH 191 12050 CBM 0958 2 0F 2 D6 CHECK VALVE 3.000 2 C & CV 0 CS 39 "B" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE ,
2* CH+193 12050-CBM-0955 2 0F 2 D6 CHECK VALVE 3.000 2 C CV C 03 0 RR 18 "B" CHARGING PUMP DISCHARGE CHECK VALVE gO) ............................................................. ..... .... ... .... .... .... .... ... .... .... .... ,
\s. // i
VIRGINIA P0bER COMPANY PAGE: 10 0F 84
/~~5 NORTH ANNA UNIT 2 REVISION: 8 g
f' SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96
!NSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST IEMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-2-CH 206 12050-CBM-095B 2 0F 2 07 CHECK VALVE 3.000 2 C CV 0 CS 39 "C" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 2*CH-208 12050-CBM-0958 2 0F 2 D7 CHECK VALVE 3.000 2 C CV C G3 0 RR 18 "C" CHARGING PtmP DISCHARGE CHECK VALVE 2 CH 260 12050-CBM 095C 2 of 2 B8 CHECK VALVE 2.000 1 C CV C RR 2 "A" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-CH 264 12050 CBN-095C 2 0F 2 57 CHECK VALVE 2.000 1 C CV C RR 2 "B" RC PUMP SEAL WAhR SUPPLY, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2 CH 308 12050-CBM-095C 2 0F 2 B5 CHECK VALVE 2.000 1 C CV C RR 2 "C" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT !$0LATION CHECK VALVE j f-s
( 2*CH-331 12050-CBM 095C 2 0F 2 F4 CHECK VALVE .750 2 AC CIV CV C 24 2
( .............................................
LT C OPB RC PUMP SEAL WATER u TLRN, INSIDE CONTAINMENT Isot ATION CHECK VALVE 2-CH-332 12n5L-CBM 095C 1 0F 2 A5 CHECK VALVE 2.000 1 AC Civ CV C 24 2 LT C OPB CHARGING SUPPLY TO LOOP FILL HEADER, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2 CH 335 12050-CBM-095C 1 0F 2 D4 CHECK VALVE 3.000 2 AC Civ CV C 24 2 LT C OPB l
MAIN CHARGING $UPPLY HEADER, INSIDE CONTAIN-MENT ISOLATION CHECK VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 1
2 CH-495 12050-CBM 095B 1 0F 2 B6 CHECK VALVE 2.000 2 AC CV C RR 25 0 CS 39 CHARGING PUMP RECIRC AND RCP SEAL WATER RETURN LINE ISOLATION CHECK VALVE 2 CH-FCV-2113A 12050-CBM-095B 1 0F 2 C3 A0 GATE 1.000 3 8 s EV 0 03 FS 0 03 ST C 03 VP OC 24 l ALTERNATF EMERGENCY BORATION LINE FLOW CONTROL VALVE 2-CH FCV 2114A 12050 CBM-0958 1 el 2 D4 A0 GLOBE 1.000 3 5 EV C 03 )
p FS ST C
C 03 03
\
n l
l VIRGINIA POWER COMPANY PAGE: 11 0F 84 j'-'s NORTH ANNA UNIT 2 REVISION: 8 ;
/ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 j
\s. s') INSERVICE TESTING PROGRAM - VALVE TABLE I NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST RES JUST JUST TEST NUMBER NUMBER NUMBEP C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREG V- CSV RRV- VCN-2-CH FCV 2114A 12050 CBM-095B 1 0F 2 D4 A0 GLOBE 1.000 3 B VP OC 24 I PRIMARY GRADE WATER FLOW CONTROL VALVE 2 CH-FCV 2160 12050-CBM 0950 1 0F 2 A4 A0 GLOBE 2.000 2 AE CIV LT C OPS VP OC 24 l CHARGING FLOW CONTRJ. TO LOOP FILL HEADER, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CH t.CV-2460A 12D50-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 LETDOWN ISOLATION VALVE 2 CH LCV 24608 12050 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 LETDOWN ISOLATION VALVE T 'S I
D) 2-CH-MOV-2115B 12050 CBM-095B 2 0F 2 B8 M0 GATE 8.000 2 A EV C CS 6 0 CS 6 LT C 24 76 ST C CS 6 0 CS 6 VP OC 24 CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 2 CH-MOV-2115C 12050-CBM 0958 1 0F 2 C6 M0 GATE 4.000 2 B EV C CS 6 ST C CS 6 VP OC 24 CHARGING PUMP SUPPLY ISOLATION FROM VOLUME CONTROL TANK 2-CH-MOV 21150 12050-CBM-095B 2 0F 2 B8 M0 GATE 8.000 2 A EV C CS 6 0 CS 6 LT C 24 76 ST C CS 6 0 CS 6 VP OC 24
............................................. 4 3
CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 2-CH-MOV 2115E 12050-CBM-0958 1 0F 2 C6 M0 GATE 4.000 2 B EV C CS 6 ST C CS 6 VP OC 24 CHARGING PUMP SUPPLY ISOLATION VALVE FROM VOLUME CONTROL TANK
('O ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
VIRGINIA POWER COMPANY PAGE: 12 0F 84 f'~'sg* NORTH ANNA UNIT 2 REVISION: 8 i SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\~_ I INSERVICE TESTING PROGRhM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SKEET DRWG VALVE VALVE A9ME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV- VCN-2 CH-MOV 2267A 12050 CBM 0955 2 0F 2 C3 MO GATE 6.000 2 E VP OC 24 "A" CHARGING PLMP SUCTION ISOLATION FROM RWGT AND VCT 2 CH-M0V-2267B 12050-CBM-0958 2 0F 2 C3 M0 GATE 6.000 2 E VP OC 24 "A" CHARGING PUMP SUCTION ISOLATION FROM LHS!
2-CH-MOV-2269A 12050 COM 0958 2 0F 2 C5 M0 GATE 6.000 2 E VP DC 24 "B" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 2-CH MOV 2269B 12050-CBM-095B 2 0F 2 C5 MO GATE 6.000 2 E VP DC 24 CHARGING PUMP SUCTION ISOLATION FROM LHS!
".B" .
{
2 CH-MOV-2270A 12050-CBM-0958 2 0F 2 C7 MO GATE 6.000 2 E VP OC 24 "C" CHARGlWG PUMP SUCTION ISOLATION FROM RWST AND VCT j p
, t 2 CH-MOV 22705 12050 CBM 0958 2 0F 2 C7 No GATE 6.000 2 E VP OC 24 D! "C" CHARGING PtMP SUCTION !$0LATION FROM LMSI 2-CH MOV 2275A 12050 CBM 095B 2 0F 2 D4 NO GATE 2.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 "A" CHARGING PUMP MINIMUM RECIRCULATION 150-LATION VALVE 2 CH-MOV-22758 12050 CBM 095B 2 0F 2 D5 M0 GATE 2.000 2 B EV C 03 0 03 ST C 03 0 03 VP OC 24 "B" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE I
2-CH-MOV 2275C 12050-CBM 095B 2 0F 2 D7 No GATE 2.000 2 B EV C C3 0 03
.: ST C 03 0 03 VP DC 24 "C" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE 2-CH-MOV 2286A 12050-CBM-0955 2 Of 2 E4 M0 GATE 3.000 2 B EV C 03 0 03 A ST C 03 4
l I O 03 V
VIRGINIA POWER COMPANY PAGE: 13 0F 84 f- .
NORTH ANNA UNIT 2 REVISION: 8
( SEconD INSERVICE TESTING INTERVAL DATE: 08/17/98
\s,,, INSERVICE TESTING PROGRAM - VALVE TABLE WC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-2-CH-MOV 2286A 12050-CBM-0955 2 0F 2 E4 M0 GATE 3.000 2 B VP OC 24 "A" CHARGING PLMP MAIN DISCHARGE ISOLATION VALVE 2 CH MOV 22868 12050 CBM-0955 2 0F 2 E6 MO GATE 3.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 "B" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2 CH MOV-2286C 12050 CBM-0958 2 of 2 ET M0 GATE 3.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 "C" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2-CH-MOV 2287A 12050 CBN-095B 2 0F 2 D4 N0 GATE 3.000 2 B EV C 03 0 03 p ST C 03
( l 0 03
\_/ .............................................
VP OC 24 "A" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 2 CH Mov 2287B 12050-CBM-0958 2 0F 2 D6 M0 CATE 3.000 2 B EV C 03 0 03 ST C 03 4 0 03 VP OC 24 l
............................................. j "B" CHARGING PUMP ALTERNATE AND LOOP F1LL DISCHARGE ISOLATION VALVE j 2 CH-MOV 2287C 12050 CBM-0958 2 0F 2 D7 M0 GATE 3.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 "C" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 2 CM-MOV 2289A 12050-CBM-095C 1 0F 2 04 N0 GATE 3.000 2 A CIV EV C CS 7 LT C OPB ST C CS 7 VP DC 24
.................. y.........................
MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2 CH-MOV 22895 12050-CBM-095C 1 0F 2 53 M0 GATE 3.000 2 B EV C CS 7 A ST C CS 7
\
s%,
1 l
l 1
l 1
l VIRGINIA POWR COMPANY PAGE: 14 0F 84 ps' NORTH ANNA UNIT 2 REVISION: 8
( SECOND INSERVICE TESTING INTERVAL " ATE: 08/17/98
\s INSERVICE TESTIkG PROGRAM . VALVE TABLE i NC 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-MAIN CKARGING HEADER ISOLATION VALVE, OUTSIDE j CONTAINMENT 1 2-CH-MOV 2350 12050-CBM 0958 1 0F 2 B5 No GATE 2.000 2 B EV 0 CS 4 ST 0 CS 4 VP OC 24 EMERGENCY BORATION TO CHARGING PUMP SUCTION 2-CH-MOV 2373 12050-CBM-095B 1 0F 2 A8 MO GATE 3.000 2 E VP OC 24 CHARGING PUMP RECIRCULATION HEADER ISOLATION VALVE 2-CH-MOV 2380 12050 CBM 095C 2 0F 2 F4 MO GATE 3.000 2 A CIV EV C CS 47 LT C DPB ST C CS 47 YP OC 24 REACTOR COOLANT PUMP SEAL WATER RETURN, INSIDE CONTAINMENT ISOLATION VALVE 1 i
2 CH MOV 2381 12050-CBM-0958 1 0F 2 C8 MO GATE 3.000 2 A CIV EV C CS 47 l
<-~s LT C OPB l
/ \
47
OC 24 CS REACTOR COOLANT PUMP SCAL WATER RETURN, OUT-SIDE CONTAINMENT ISOLATION VALVE 2 CH-RV 2203 12050-CBM 095C 1 0F 2 F3 RELIEF VALVE 2.000 2 C SP O 120 LETDOWN RELIEF VLV D96MSTREAM OF REGEN HX, RV DISCHARGE TO PRESSURIZER RELIEF TANK 2-CH RV-2382A 12050-CBM-095C 2 0F 2 F5 RELIEF VALVE 2.000 2 C SP O 120 CONTAINMENT PENETRATION 19 RELIEF val %E -
RCP SEAL WATER RETURN PIPING 2-CH RV-23828 12050 CBM 095B 1 0F 2 C7 RELIEF VALVE 2.000 2 C SP O 120 SEAL WATER HEAT EXCHANGER RELIEF VALVE, RV DISCHARGE TO VOLUMC CONTROL TANK 2 CH-TV-2204A 12050-CBM-095C 10F 2 E3 A0 GLOBE 2.000 2 A CIV EV C CS 5 FS C CS 5 LT C DPB 6 ST C CS 5 VP OC 24 LETDOWN CONTROL FROM REGEN HX, INSIDE CONTAINMENT ISOLATION VALVE 2-CH-TV 22D4B 120$0-CBM 095A 2 0F 2 C3 A0 GLOBE 3.000 2 A CIV EV C CS 5 FS C CS 5 LT C DPB 5
(
VIRGINIA POWER COMPANY PAGE: 15 0F 84 NORTN ANNA UNIT 2 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 NUMBER NUMBER NUMBER COOR TYPE $1ZE CLAL CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-LETDOWN CONTROL FROM REGEN NW, OUTSIDE CONTAINNENT ISOLATION VALVE a
1 I
VIRGIN!A POWER COMPANY PAGE: 16 0F 84 7'~'sg NORTM AkuA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 (s-. 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 NUMBER NUMBER COOR TYPE SIZE CLAS CAi TYPE TYPE POS FRE0 V- CSV RRV- VCN-2-CV 004 12050-CBM 092A 2 0F 2 AS MANUAL GATE 8.000 2 AE CIV LT C OPB CONTAINMENT VACUUM EJECTOR SUFPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CV 08 12050-CBM D92A 2 OF 2 B3 CHECK VALVE 2.000 2 C CV 0 18 4 PO 03 i
............................................. j CONTAlWMENT VACUUM SYSTEM ISOLATION CHECK VALVE 2 CV 15 12050 CBM-092A 2 0F 2 C3 CHECK VALVE 2.000 2 C CV o 18 4 PO 03 CONTAINMENT VACUUM SYSTEM ISOLATION CHECK VALVE 2-CV TV 200 12050 CBM 092A 2 0F ? A3 A0 BFLY 8.000 2 AE CIV LT C OPB VP OC 24 CONTAINMENT VACUUM EJECTOR, INSIDE CONTAIN-MENT ISOLATION VALVE 2-CV-TV-250A 12D50-CBM-092A 2 0F 2 E4 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 O LT C OPB i ( ST C 03 55
's. VP OC 24 1 .............................................
! "A" CONTAINMENT VACUUM PUMP SUCT!DN ISOLATION j VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE l 2-CV-TV-250B 12050 CPM-09?A 2 0F 2 B5 A0 GLOBE 2.000 2 A CIV EV C 03 i l FS C 03 !
VP OC 24 i
............................................. q "A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CV TV-250C 12050-CBM-092A 2 0F 2 C4 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 55 VP OC 24 "B" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2 CV-TV-2500 12050-CBM D92A 2 0F 2 C5 A0 GLOBE 2.000 2 A CIV EV C 03 F5 C 03 LT C DPS ST C 03 55 VP DC 24 "B" CONTAINMENT VACUUM PUMP SUCTION ISOLATIott VALVE, QUTSIDE CONTAINMENT ISOLATION VALVE k-
VIRGIN!A POWER COMPANY PAGE: 17 0F 84 r s, WORTH ANNA UNIT 2 REVISION: 8
(
SECOND INSERVICE TESTING INTERVAL DATE: 08/17/90 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NLSESER WUMBER NLaiBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-2 DA-007 12050-CRM 090A 3 0F 3 D3 MAN DIAPHRAM 2.000 2 AE CIV LT C OPB VENT LINE FROM PRIMARY VENT POT, INSIDE CONTAINMENT ISC.ATION VALVE 2 DA 009 12050 tam-090A 3 0F 3 E3 MAN DIAPHRAM 2.000 2 AE CIV LT C OPB
............................................. j VENT LINE FROM PRIMARY VENT POT, OUTSIDE l
CONTAINMENT ISOLATION VALVE i
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j 2-DA TV 200A 12050-CBM-090B 10F 1 ET A0 GLOSE 2.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 55 VP OC 24 REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, OUTSIDE CONTAINMCNT ISOLATION VALVE 2-DA TV-200s 12050-CBM-090A 3 0F 3 C3 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24 REACTOR CONTAINMENT SUMP PUMPS D!$ CHARGE,
) INSIDE CONTAINMENT ISOLATION VALVE
,_,i ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
2 DA TV.203A 12050 CSM-090A 3 0F 3 87 A0 GLOBE 2.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 55 VP OC 24 POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT ISOLATION VALVE 2 DA TV 203B 12050 CBM-090A 3 0F 3 88 A0 GLOSE 2.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 55 VP OC 24 POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT TRIP VALVE I
h s
,/-- ,
I
VIRGINIA POWER COMPANY PAGE: 18 0F 84 NORTM ANNA UNIT 2 REVISION: 8 f-'s SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM VALVE TABLE DATE: 08/17/98 WC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RES JUST JUST TEST IMESER WUMBER WL8EBER COOP. TTPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRVa VCN-2-DG TV 200A 12050-CeM 090A 1 0F 3 B8 A0 GLOSE 2.000 2 A CIV EV C 03 FS C 03 LT C OP5 ST C 03 VP DC 24 PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, OUT-SIDE CONTAINMENT ISOLATION VALVE 2-DG TV 200s 12050 CBM 090A 1 0F 3 B7 A0 GLOSE 2.000 2 A CIV EV C 03 F5 C 03 LT C OPB ST C 03 VP DC 24 PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, INSIDE CONTAINMENT !$0LATION VALVE
(
l l
s t"'%
(
l VIRGINIA POWER COMPANT PAGE 19 0F 84 frg NORTH ANNA UNIT 2 REVISION: 8 I d SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\s_ / INTERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TTPE SIZE CLAS CAT TTPE TTPE POS FREQ V- CSV RRV VCN-2 EB 015 12050-FM -1073 1 0F 4 E6 CHECK VALVE 1.500 NC C CV 0 18 4 2H DIESEL "NA" AIR RECEIVER TANK DISCHARGE VALVE 2 EB 034 12050 FM -107A 3 0F 4 E6 CHECK VALVE 1.500 NC C CV 0 18 4 2J DIESEL "JA" AIR RECEIVER TANK DISCHARGE VAL VE 2-EB 041 12050-FM *107A 10F 4 D6 CHECK VALVE .750 NC AC CV C 03 LT C 24 2H DIESEL "HA" AIR RECEIVER TANK ISOLATION VALVE 2-EB-051 12050-FM -107A 3 0F 4 D6 CHECK VALVE .750 NC AC CV C 03 LT C 24 2J DIESEL "JA" AIR RECEIVER TANK ISOLAT!DN VALVE 2 EB 061 12050 FM 107A 2 0F 4 E6 CHECK VALVE 1.500 NC C CV O 18 4 2H DIESEL "HB" AIR RECEIVER TANK DISCHARGE VALVE
{A
\
2 EB-068 12050-FM 107A 2 0F 4 06 CHECK VALVE .750 NC AC CV C 03 LT C 24 2H DIESEL "HB" AIR RECEIVER TANK ISOLATION i VALVE
)
l 2-EB 078 12050-FM 107A 4 0F 4 E6 CHECK VALVE 1.500 NC C CV 0 18 4 2J DIESEL "JB" AIR RECEIVER TAWK DISCHARGE VALVE
.......................................................................v .... .... .... .... ... .... .... ....
2 EB 085 12050 FM -107A 4 0F 4 D6 CHECK VALVC .750 NC AC CV C 03 LT C 24 2J DIESEL "JB" AIR RECE!VER TANK ISOLATIDN I VALVE i h
(d k
T- i l
l l
i VIRGINIA POWER COMFAA) PAGE: 20 0F 84 I j"% - NORTH ANNA UNIT 2 REVISION: 8 l
t J SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 '
V INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CC RR ALT VALVE DRAWING SMEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST ;
NUMBER IRMBER NUMBER COOR TYPE SIZE CLAS CAT TTPE TYPF POS FREQ V- CSV RRV- VCN- 1 2-EG 260 11715 FB -035A 2 0F 2 C7 CHECK VALVE 1.500 WC C CV O 03 2H DIESEL "A" EMERGENCY GENERATOR PUMP DISCHARGE CHECK VALVE 2-EG 272 11715-FB -035A 2 of 2 F7 CHECK VALVE 1.500 NC C CV O 03 !
2J DIESEL "A" EMERGENCY GENERATOR PUMP i DISCHARGE CHECK VALVE l 2 EG-284 11715 FB 035A 2 0F 2 F6 CHECK VALVE 1.500 NC C CV o 03 2J DIESEL "B" EMERGENCY GENERATOR PUMP DISCHARGE CHECK VALVE !
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 2-EG 289 11715 FB 035A 2 0F 2 C6 CHECK VALVE 1.500 NC C CV 0 03 i i
2H DIESEL "B" EMERGENCY GENERATOR PUMP DISCHARGE CHECK VALVE 2-EG RV-204A 11715 FB 035A 2 0F 2 C7 RELIEF VALVE 1.000 NC C SP O 120 I l
2H DIESEL "A" EMER GENERATOR PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION j f
r 2-EG RV-204B 11715-FB 035A 2 0F 2 C6 RELIEF VALVE 1.000 NC C SP 0 120
\, 2H DIESEL "B" EMER GENERATOR PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION l
2 EG-RV 206A 11715-FB 035A 2 0F 2 F7 RELIEF VALVE 1.000 NC C SP O 120 i
2J DIESEL "A" EMER GENERATOR PUMP DISCHARGE j RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION 2 EG RV-2D6B 11715 FB 035A 2 0F 2 F6 REL!EF VALVE 1.000 NC C SP O 120 2J DIESEL "B" EMER GENERATOR PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO PUMP SUCTION 2 EG RV 702HA 12050-FM -107A 1 0F 4 E4 RELIEF VALVE 2.000 NC C SP O 120 2H DIESEL "A" AIR RECElvik TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERL 2 EG-RV-702HB 12050-FM 107A 2 0F 4 E4 RELIEF VALVE 2.000 NC C SP 0 120 2H DIEsfL "B" AIR RECE!VER TANK RELIEF VALVE, RV DISCHARGE 10 ATMOSPHERE 2-EG RV-702JA 126s0 FM *107A 3 0F 4 E4 RELIEF VALVE 2.000 NC C . SP O 120 2J DIESEL "A" AIR RECEIVER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE 2 EG-RV-702JB 12050 FM 107A 4 0F 4 E4 RELIEF VALVE 2.000 NC C $P 0 120 2J DIESEL "B" AIR RECEIVER TANK RELIEF VALVE, RV DISCHARGE TO ATMOSPHERE ysg ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
2-EG SoV-700HA 12050-FM 107A 10F 4 E6 SO GATE 1.500 NC B EV 0 03 (d d
1 l
1 l
l VIRGIN!A POWER COMPANT PAGE: 21 0F 84 NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/1T/96 INSERVICE TESTING PROGRAM - VALVE TASLE 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 TTPE SIZE CLAS CAT TTPE TTPE POS FREQ V- CSV RRV- VCN-2 EG 50V 700HA 12050 FM *107A 10F 4 E6 $0 GATE 1.500 NC B ST 0 03 4 DIESEL AIR START SOLENOID VALVE 2 EG-80V 700Hs 12050 FM 107A 2 0F 4 E6 So GATE 1.500 WC B EV 0 03 ST C 03 4 DIESEL AIR START S0LENotD VALVE i
2 EG 80V 700JA 12050-FM 107A 3 0F 4 E6 SO GATE 1.500 NC 5 EV 0 03 ST 0 03 4 DIESEL Alt START SolFNDID VALVE 2 EG $0V 700JB 12050 FM 107A 4 0F 4 E6 $0 GATE 1.500 NC B EV 0 03 ST 0 03 4 DIESEL AIR START $0LEN0lu VALVE 2 EG 80V-701RA 12050-FM -107A 10F 4 E6 50 GATE 1.500 NC 8 EV 0 03 ST 0 03 4 I DIESEL AIR START SOLENOID VALVE 2 EG-50V-707JA 12050 FM -107A 3 0F 4 E6 SO GATE 1.500 NC B EV 0 03 ST 0 03 4 I l
DIESEL AIR START SOLENOID VALVE 1 I
l N )3
VIRGINIA POWER COMPANY PAGE: 22 0F 84 NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 06/17/96 INSERVICE TESTING PROGRAM
- VALVE TA8LE j l
1 NC l ISO REL CS RR ALT J VALVE DRAWING SHEET DRWG VALVE VALVE ASME CM VALV TEST TEST TEST REQ JUST JUST TEST NUNBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-2 FP 079 12050 CBB 104A 1 0F 1 A7 CHECK VALVE 4.000 2 AC CIV CV C RR 3 LT C RR FIRE PROTECTION SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2 FP-081 12050-CBS 104A 1 0F 1 A6 MANUAL GATE 4.000 2 AE CIV LT C OPS FIRE PROTECTION SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE A '
b
(
VIRGINIA POWER COMPANY PAGE: 23 0F 84 (A
(_-)
NORTH ANNA UNIT 2 SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE REVISION: 8 DATE: 08/17/98 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 COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV RRV- VCN-2 FW-062 12050 CBM-074A 1 0F 4 E6 CHECK VALVE 16.000 2 C CV C CS 12 "A" MAIN FEEDWATER SUPPLY, CONTAINMENT PENETRATION CHECK VALVE 2 FW-063 12050-CBM 074A 1 0F 4 B5 CHECK VALVE 3.000 3 C CV o CS 30 STANDBY "A" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 2-FW 064 12050-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 2-FW 065 12050 CBM 074A 1 0F 4 B6 CHECK VALVE 3.000 3 C CV 0 CS 30 STANDBY "A" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 2 FW 066 12050 CBM 074A 1 0F 4 B6 MANUAL GATE 3.000 3 B EV C CS 40 0 CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION O VALVE FROM MOTOR DRIVEN PUMP HEADERS
( ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
( 2-FW-070 12050-CBM 074A 1 0F 4 D6 CHECK VALVE 3.000 2 C CV 0 03 "A" AUXILIARY FEEDWATER HEADERCHECK VALVE AT MAIN FEEDWATER HEADER 2-FW-094 12050 CBM-074A 10F 4 D6 CHECK VALVE 16.000 2 C CV C CS 12 "B" MAIN FEEDWATER HEADER SUPPLY, CONTAll. MENT PENETRATION CHECK VALVE 2 FW 095 12050 CBM-074A 1 0F 4 B6 CHECK VALVE 3.000 3 C CV O 03 "B" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 2- FW-0% 12050-CBM 074A 1 0F 4 B6 MANUAL GATE 3.000 3 B EV C CS 40 0 CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 2 FW 097 12050-CBM 074A 1 0F 4 C6 CHECK VALVE 3.000 2 C CV 0 CS 30 I "B" AUXILIARY FEEDWATER HEADER CHECK VALVE AT "s MAIN FEEDWATER HEADER {
i 2-FW-098 12050-CBM 074A 1 0F 4 56 MANUAL GATE 3.000 3 B EV C CS 40 0 CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR-DRIVEN PUMP HEADERS A 2-FW-102 12050-CBM-074A 1 0F 4 C6 CHECK VALVE C CV O 03 f
\ l l
r
VIRGIN!A POWER COMPANY PAGE: 24 0F 84 s NORTH ANNA UNIT 2 REVISION: 8 (f' w ) SECOND INSERVICE TESTING INTERVAL DATE: 06/17/98
\( / INSERV!CE TESTING PROGRAM VALVE TABLE NC IB0 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 SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-
"B" AUXILARY FEEDWATER NEADER CHECK VALVE AT MAIN FEEDWATER NEADER 2 FW 126 12050 CBM 074A 1 0F 4 B6 CHECK VALVE 16.000 2 C CV C CS 12 "C" MAIN FEEDWATER SUPPLY, CONTAINMENT-PENETRATION CHECK VALVE 2 FW 127 1205S t4M 074A 1 0F 4 B7 CHECK VALVE 3.000 3 C CV 0 CS 30 STANDBY "C" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 2 FW-128 12050-CBM 074A 10F 4 67 MANUAL GATE 3.000 3 8 EV C CS 40 0 CS 40 AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR DRIVEN PUMP HFADERS 2-FW-129 12050 CBM-074A 10F 4 B7 CHECK VALVE 3.000 3 C CV 0 03 "C" AUXILIARY FEEDWATER HEADER CHECK VALVE, OUTSIDE OF CONTAINMENT x 2 FW 130- 12050-CBM-074A 10F 4 B7 MANUAL GATE 3.000 3 B EV C CS 40
-, ) O CS 40 i
\g .............................................
AUXILIARY FEEDWATER HEADER MANUAL ISOLATION VALVE FROM MOTOR DRIVEN PUMP HEADERS 3.000 2 2 FW 134 12050 CBM 074A 1 0F 4 U7 CHECK VALVE C CV 0 03 "C" AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 2 FW 147 12050-CBM-074A 3 0F 4 B7 MANUAL GATE 6.000 3 8 EV O CS 41 ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS 2 FW-150 12050 CBN-074A 3 0F 4 D7 CHECK VALVE 1.000 3 C CV 0 03 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE 2 FW-156 12050-CBM 074A 3 0F 4 D8 CHECK VALVE 6.000 3 C CV 0 03 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP l DISCHARGE CHECK VALVE 2 FW-157 12050-CBM 074A 3 0F 4 E7 MANUAL GATE 6.000 3 B EV C CS 40 0 CS 40 ;
AFW PUMP DISCMARGE NEADER ALIGNMENT / CROSS CONNECT VALVE i
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 2-FW-164 12050 CBM-074A 3 0F 4 B6 MANUAL GATE 6.000 3 B EV 0 CS 41 oV i a
i i
\
VIRGINIA P0lER CMPANY PAGE: 25 0F 84 NORTH ANNA UNIT 2 REVISION: 8
- s-(m SECOND INSERVICE TESTING INTERVAL 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 RE0 JUST JUST TEST IRmBER NUMBER NUMBER C00R TYPE . SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- ERV VCN-ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS 2 FW 167 12050-COM-074A 3 0F 4 D6 CHECK VALVE 1.000 3 C CV 0 03 "A" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE 2-FW-172 12050 COM-074A 3 0F 4 D6 CHECK VALVE 4.000 3 C CV 0 03 "A" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 2 FW-173 12050-COM-074A 3 OF 4 E6 MANUAL GATE 6.000 3 B EV C CS 40 0 CS 40 AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS CONNECT VALVE
............................................................. ..... .... ... .... .... . . . . . . . . . . . . . . . . . . . . . . . {
t 2 FW-174 12050 COM-074A 3 0F 4 E6 MANUAL GATE 6.000 3 B EV C CS 40 1 0 CS 40 AFW PLMP DISCHARGE HEADER ALIGNMENT / CROSS CONNECT VALVE 2-FW-182 12050-CBM-074A 3 0F 4 85 MANUAL GATE 6.000 3 8 EV 0 CS 41
\q ............................................. ,
ALTERNATE WATER SUPPLY TO AFW PUMP SUCTIONS !
l
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 2 FW-185 12050 CSM-074A 3 0F 4 05 CHECK VALVE 1.000 3 C CV 0 03 l "9d MOTOR DRIVEN AUXilllRY FEEDWATER PUMP RECIRC LINE CHECK VALVE 2-FW-192 12050-CBH 074A 3 0F 4 D5 CHECK VALVE 4.000 3 C CV 0 03 "C" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 2-FW-193 12050-CBM-074A 3 0F 4 ES MANUAL GATE 6.000 3 B EV C CS 40 0 CS 40 AFW PUMP DISCHARGE HEADER ALIGNMENT / Cross CONNECT VALVE 2-FW 194 12050-CSM 074A 3 0F 4 E5 MANUAL GATE 6.000 3 B EV C CS 40 0 CS 40 AFW PUMP DISCHARGE HEADER ALIGNMENT / CROSS 9 CONNECT VALVE
-2 FW-202 12050 CsM-074A 3 of 4 A7 MANUAL GATE 6.000 3 B EV 0 CS 41 SERVICE WATER SUPPLY TO AFW PUMP SUCTIONS 2-FW-279 12050-COM-OF4A 3 0F 4 D8 CHECK VALVE 4.000 3 C CV 0 03
- m. l
\
(V t .
l I
i
VIRGIN!A POWER COMPANY PAGE: 26 0F 84 rg NORTH ANNA UNIT 2 REVISION: 8
) SECOND INSERVICE TESTING INTERVAL DATE: 05/17/98 Ns _,/ INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST IRMBER NUMBER 1RMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-
"A" AUKILIARY FEEDWATER NEADER CHECK VALVE, OUTSIDE OF CONTAINMENT 2 FW-317 12050 CBM-074A 3 0F 4 E8 MANUAL GATE 6.000 3 5 EV C CS 40 0 CS 40 AFW PLMP DISCHARGE NEADER ALIGNMENT / CROSS CONNECT VALVE 2 FW-609 12050-CBM-074A 3 0F 4 CHECK VALVE 1.000 3 C CV O 03 PUMP LUBE O!L COOLER CHECK VALVE 2-FW-610 12050 CBM-074A 3 0F 4 CHECK VALVE 1.000 3 C CV 0 03 PUMP LUBE CIL COOLER CHECK VALVE 2-FW-611 12050 CBM-074A 3 0F 4 CHECK VALVE 1.000 3 C CV 0 03 PUMP LUBE DIL COOLER CHECK VALVE feg 2 FW-FCV 2478 12050 CBM-074A 1 0F 4 E4 A0 GLOBE 16.000 NC B EV C CS 11
VP OC 24 l "A" MAIN FEEDWATER REG VALVE 2 FW-FCV-2479 12050 CBM 074A 1 0F 4 F4 A0 GLOBE 6.000 NC B EV C CS 11 FS C CS 11 ST C CS 11 1 "A" BYPASS FEEDWATER REG VALVE 2 FW-FCV-2488 12050-CBM 074A 10F 4 D4 A0 GLOBE 16.000 NC B EV C CS 11 FS C CS 11 ST C CS 11 VP DC 24 "B" MAIN FEEDWATER REC VALVE 2-FW-FCV-2489 12050-CBM 074A 1 0F 4 04 A0 GLOBE 6.000 NC B EV C CS 11 FS C CS 11
- s ST C CS 11 "B" BYPASS FEEDWATER REG VALVE 2-FW-FCV-2498 12050-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 v
VIRGIN!A POWER COMPANY PAGE: 27 0F 84 NORTH ANNA UNIT 2 REVIsl0N: 8 le'~' k SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\s_,/ INSERVICE TESTING PROGRAM VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWILS $NEET DRP; VALVE VALVE ABME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER rs0R TYPE SIZE CLAS CAT TYPE TYPE Pos FREQ V- CSV RRV VCN-l' ...... ....... ...... .... ..... ..... .... ... .... .... .... .... ... .... .... ....
"C" MAIN FEEDWATER REG VALVE 2 FW-FCV-2499 12050 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 2 FW NCV 200A 12050-CBM 074A 1 0F 4 A5 A0 GLOBE 3.000 3 B EV 0 CS 32 P 03 32 FS 0 CS 32 ST 0 CS 32 VP OC 24 STANDBY AUXILI ARY FEEDWATEP. SUPPLY TO "A" STEAM GENERATOR 2-FW-NCV 2005 12050-CBM 074A 1 0F 4 A6 A0 GLOBE 3.000 3 B EV 0 CS 32 P 03 32 FS 0 CS 32 ST 0 CS 32 VP OC 24 s .............................................
A STANDBY AUXILI ARY FEEDWATLR SUPPLY To "B"
.\ STEAM GENERATOR 2-FW-HCV 200C 12050 CBM 074A 1 0F 4 A7 A0 GLOBE 3.000 3 B EV O CS 32 P 03 32 FS 0 CS 32 ST 0 CS 32 VP OC 24 NORMAL AUXILIARY FEEDWATER SUPPLY To "C" STEAM GENERATOR 2 FW MOV 200A 12050-CBM-074A 1 0F 4 85 M0 GLOBE 3.000 3 B EV C 03 0 03 ST C 03 0 03 VP OC 24 STANDBY AUXILIARY FEEDWATER SUPPLY T0 "A" STEAM GENERATOR 2 FW-MOV-2006 12050-CBM 074A 10F 4 B6 MO GLOBE 3.000 3 B EV C 03 0 03 ST C 03 0 03 VP OC 24 NORMAL AUXILIARY FEEDWATER SUPPLY TO "B" STEAM GENERATOR 2-FW-MOV 200C 12050-CBM-074A 10F 4 BT MO GLOBE 3.000 3 B EV C 03 0 03 l ST C 03
)
['N e 4 VP O
OC 24 03
\j 1
l l
l
t I
l 1
1 VIRGINIA POWER COMPANY PAGE: 28 0F 84 yg NORTH ANNA UPIT 2 REVISION: 8
( ) SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 N_/s INSERVICE TESTING PROGRAM VALVE TABLE NC
!$0 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST InsSER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-STANDBY AUXILIARY FEEDWATER SUPPLY TD "C" STEAM GENERATOR 2 FW-MOV 2000 12050 CBM-074A 3 0F 4 EB MO GLOBE 3.000 3 B EV C 03 0 03 ST C 03 0 03 VP DC 24 NORMAL AUXILIARY FEEDWATER SUPPLY TO "A" STEAM GENERATOR i
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 1 2 FW-MOV-254A 12D50 CBM-074A 1 0F 4 E3 MO GATE 16.000 NC B EV C CS 11 ST C CS 11 VP DC 24 "A" MAIN FEEDWATER SUPPLY ISOLATION VALVE 2 FW-MOV 25/3 12050 CBM 074A 1 0F 4 03 MO GATE 16.000 NC B EV C CS 11 ST C CS 11 VP OC 24 "B" MAIN FEEDWATER SUPPLY ISOLATION VALVE f ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
's- - 2 FW-MOV 254C 12050 CBM-074A 10F 4 B3 Mo GATE 16.000 NC B EV C CS 11 ST C CS 11 VP OC 24 "C" MAIN FEEDWATER SUPPLY ISOLATION VALVE 2-FW-PCV 259A 12050-CBM 074A 3 0F 4 F8 A0 GLOBE 4.000 3 B EV 0 CS 33 P 03 33 FS 0 CS 33 ST 0 CS 33 ,
VP OC 24 l l
AUXILIARY FEEDWATER PRESSURE CONTROL VALVE j 2-FW-PCV 2598 12050-CBM 074A 3 0F 4 E8 A0 GLOBE 4.000 3 B EV 0 CS 33 P 03 33 FS 0 CS 33 ST 0 CS 33 VP OC 24 AUXILIARY FEEDWATER PRESSURE CONTROL VALVE
............................................................. ..... .... ... ..'.. .... s 2 FW RV 200 12D50-CBM-074A 3 0F 4 D8 RELIEF VALVE 3.D00 3 C SP O 120 TURBINE DRIVEN AUXILIARY FEED PUMP FEEDWATER i DISCHARGE RELIEF VALVE l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
l l
O \
s
's,
VIRGINIA P0bER COMPANY PAGE: 29 0F 84 NORTH ANNA UNIT 2 REVIS!0N: 8
[ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96
\q,,, INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RES JUST JUST TEST NUMBER NUMBER WUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-2-GN-101 12050 FM .105A 1 0F 3 B6 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 BOTTLED NITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 2-GN 102 12050-FM .105A 1 0F 3 B4 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 BOTTLED NITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 2 GN RV 20BA-1 12050-FM .105A 1 0F 3 B4 RELIEF VALVE .750 NC C SP O 120 BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE 2-GN RV 208A 2 12050-FM 105A 1 0F 3 C5 RELIEF VALVE .750 NC C SP O 120 BOTTLED N!TROGEN SUPPLY TO PORV RELIEF VALVE 2-GN RV 208A 3 12050-FM .105A 1 of 3 C5 RELIEF VALVE .750 NC C SP 0 120 BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE O ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
\s_,sl 2 GN RV-2088 1 12050-FM .105A 10F 3 B7 RELIEF VALVE .750 NC C SP O 120 BOTTLED NITROCEN SUPPLY TO PORY RELIEF VALVE 2-GN*RV 2088 2 12050-FM -105A 1 0F 3 C6 RELIEF VALVE .750 NC C SP O 120 BOTTLED WITROGEN SUPPLY TO PORV RELIEF VALVE 2-GN RV-2088-3 12050 FM .105A 1 0F 3 C6 RELIEF VALVE .750 NC C SP O 120 BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE 9
l l
(,
I l
I 1
l J
I 1
1 4
VIRGINIA POWER COMPANY PAGE: 30 0F 64 NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 s s/ INSERVICE TESTING PROGRAM - VALVE TABLE l
WC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV. VCN-2-HC 015 11715 CBM-106A 1 0F 4 E3 CHECK VALVE 2.000 2 AC CIV CV C RR 4 0 18 4 LT C DPB UNIT 2 RETURN LINE FROM UNIT 1 HYDROGEN ANA-LYZERS & RECOMB, INSIDE CONT ISOL CHECK VALVE 2-HC-020 11715 CBM 106A 2 0F 4 E4 CHECK VALVE 2.000 2 AC CIV CV C RR 4 0 18 4 LT C OPS UNIT 2 RETURN LINE FROM UNIT 2 HYDROGEN ANA-LYZERS & RECOMB, INSIDE CONT ISOL CHECK VALVE 2-HC 068 11715 CBM 106A 2 0F 4 c5 CHECK VALVE .375 NC C CV o 03 HYDROGEN ANALYZER DISCHARGE CHECK VALVE 2 HC TV 200A 11715 CBM-106A 1 0F 4 E3 SO GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C DPB ST C 03 55 0 03 55 s VP OC 24 s_s-
) UNIT 2 SAMPLE LINE To UNIT 1 HYDRDGEN ANA- (
LYZERS, INS!DE CONTAINMENT ISOLATION VALVE 2 HC-TV-2005 11715 CBM 106A 1 0F 4 E4 50 GLOBE .375 2 A CIV EV C 03 0 03 F5 C 03 LT C DPB ST C 03 55 0 03 55 VP DC 24 UNIT 2 SAMPLE LINE To UNIT 1 HYDROGEN ANA-LYZERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2 HC TV 201A 11715 CBM-106A 1 0F 4 D4 So CLOBE .375 2 A CIV EV C 03 0 03 FS C 03 l LT C DPB ST C 03 55 0 03 55 VP OC 24 RETURN ISOLATION FROM UNIT 1 HYDRDGEN ANA-LYZERS TO UNIT 2 DONT,0UTSIDE CONT ISOL VALVE 's 2 NC TV 2018 11715 CBM-106A 1 0F 4 04 SO GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C DPB ST C 03 55 0 03 55 VP OC 24 O*
U
VIRGINIA POWER COMPANY PAGE: 31 0F 84 g
e- s g NORTH ANNA UNIT 2 REVISION: 8
, 1 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96
\s,_,/ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REG JUST JUST TEST 1RMBER NUMBER NUMBER COOR TYPE $12E CLAS CAT TYPE TYPE POS FREO V- CSV RRV VCN-RETURN ISOLATION FROM UNIT 1 HYDROGEN ANA-LYZERS 70 UNIT 2 CONT,0UTSIDE CONT ISOL VALVE 2-NC TV-202A 11715-CBM-106A 2 0F 4 E4 SO GLOSE .375 2 A Civ EV C 03 0 03 FS C 03 LT C DPS ST C 03 55 0 03 55 VP OC 24 UNIT 2 SAMPLE LINE TO UNIT 2 HYDROGEN ANA-LYZERS, INSIDE CONTAINMENT !$0LATION VALVE 2 HC TV 202B 11715-CBM-106A 2 0F 4 E4 SO GLOBE .375 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 55 0 03 55 VP OC 24 UNIT 2 SAMPLE LINE To UNIT 2 HYDROGEN ANA-LYZERS, OUTSIDE CONTAINV?NT !$0LAT10N VALVE p ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
i, 2-HC.TV 203A 11715 CBM-106A 2 0F 4 D3 So GLOBE .375 2 A CIV EV C 03
\s_ 0 03 FS C 03 LT C OPS ST C 03 55 0 03 55 VP DC 24 RETURN ISOLATION FROM UNIT 2 HYDROGEN ANA-LYZERS TO UNIT 2 CONT,0UTSIDE CONT ISOL VALVE 2-HC TV-2038 11715-CBM-1D6A 2 0F 4 D3 SO GLOBE .375 2 A Civ EV C 03 0 03 FS C 03 LT C DPB ST C 03 55 0 03 55 VP OC 24 RETURN ISOLATION FROM UNIT 2 HYDROGEN ANA-LYZERS TO UNIT 2 CONT.0UTSIDE CONT ISOL VALVE 2-HC TV 204A 11715-CBM-106A 4 0F 4 F4 A0 CLOBE 2.500 2 A CIV EV C 03 p 0 03 FS C 03 LT C OPB ST C 03 55 0 03 55 VP DC 24 SUPPLY ISOL FROM UNIT 1 CONT TO N1 NYDR0 RE-COMB & N2 CONT BLOWER,0UTSIDE CONT ISOL VALVE f'~'N 2-NC TV-204B 11715 CBM 106A 4 0F 4 F5 A0 GlosE 2.500 2 A CIV EV C 03
( 0 03
VIRGIN!A POWER COMPANY PAGE: 32 0F 84
- e'*] NORTH ANNA UNIT 2 SECOND INSERVICE TESTING INTERVAL REVISION: 8 DATE: D8/17/98 s.,- INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-2-NC TV 2048 11715-CDM 106A 4 0F 4 F5 A0 GLOBE 2.500 2 A Civ FS C 03 LT C OPB ST C 03 55 0 03 55 VP OC 24 SUPPLY ISOL FROM UNIT 1 CONT TO N1 HYDRO RE-COMB & N2 CONT BLOWER,0UTSIDE CONT ISOL VALVE 2-NC TV 205A 11715-CBM-106A 1 0F 4 E4 A0 GLDBE 2.500 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 55 0 03 55 VP OC 24 RE7 URN ISOLATION FROM UNIT 1 HYDROGEN RECOMB
& ANAL To UNIT 2 CONT, OUTSIDE CONT ISOL VALVE 2 NC TV 2058 11715 CBM 106A 10F 4 E5 A0 CLOBE 2.500 2 A CIV EV C 03 0 03 FS C 03 LT C OPS ST C 03 55 0 03 55 VP OC 24 RETURN ISOLATION FROM UNIT 1 HYDROGEN RECOMB
& ANAL TO UNIT 2 CONT, OUTSIDE CONT ISOL VALVE 2 HC TV 206A 11715 CBM 106A 4 0F 4 F3 A0 GLOBE 2.500 2 A CIV EV C 03 0 03 FS C 03 LT C OPB ST C 03 55 0 03 55 VP JC 24 UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE BLOW & N2 HYDRO RECOMB, OUTSIDE CONT ISOL VLV 2-HC TV-206B 11715 C94-106A 4 0F 4 F3 A0 GLOBE 2.500 2 A CIV EV C 03 0 03 FS C 03 LT C OPS ST C 03 55 0 03 55 VP OC 24 UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE BLOW & N2 NYDRO RECOMB, OUTSIDE CONT ISOL VLV 2-HC TV 207A 11715-CBM 106A 2 0F 4 F3 A0 GLOBE 2.500 2 A CIV EV C 03 0 03 FS C 03 LT C DPB ST C 03 55 0 03 55 C
VP OC 24
I r
VIRGINIA POWER COMPANY PAGE: 33 0F 84 m NORTH ANNA UNIT 2 REVISION: 8 T
i l
i
,,,/ SEDOND INSERV!CE TESTING INTERVAL INSERVICE TESTING PROGRAM . VALVE TABLE DATE: 08/1T/98 i
NC
! VALVE DRAWING SNEET 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 FRE0 V- CSV- RRV VCN-RETURN ISOLATION FROM UNIT 2 NYDROGEN RECOMB
& ANAL TO UNIT 2 CONT, OUTSIDE CONT ISOL VALVE l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
L 2 NC TV 207s 11715 CBM 106A 2 0F 4 E3 A0 GLOBE 2.500 2 A CIV EV C 03 l 0 03 I
FS C 03 LT C OPS ST C 03 55 0 03 55 VP DC 24 RETURN ISOLATION FROM UNIT 2 HYDROGEN RECOMB
& ANAL TO UNIT 2 CONT, OUTSIDE CONT ISOL VALVE 2 NC TV 208A 11715-CBM-106A 3 0F 4 E3 50 CLOBE .375 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 55 VP DC 24 UNIT 2 SAMPLE LINE TO AIR SAMPLE PANEL, INSIDE CONTAINMENT ISOLATION VALVE 2 HC TV 208B 11715-CBM 1D6A 3 0F 4 E4 $0 GLOBE .375 2 A CIV EV C 03 i FS C 03 LT C OPB Q ST VP C
DC 24 03 55 UNIT 2 SAMPLE LINE TO AIR SAMPLE PANEL, j OUTSIDE CONTAINMENT ISOLATION VALVE j u
I
(
r~
l l VIRGINIA POWER COMPANY PAGE: 34 0F $4 l NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 s INSERVICE TESTING PROGRAM - VALVE TABLE I
NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-2 HV-MOV 200A 11715 CBB-006A 2 0F 1 D3 MO BFLY 36.000 2 AC CIV LT C OPB VP DC 24 CONTAINMENT PURGE SUPPLY, INSIDE CONTAINMENT I SOLATION VALVE 2-HV-MOV 2005 11715 CBB 006A 2 OF 3 D3 M0 BFLY 36.000 2 AE CIV LT C OPB VP DC 24 CONTAINMENT PURGE SUPPLY, OUTSIDE CONTAINMENT
!$0LAT10N VALVE 2-HV MOV-200C 11715 CBB-006A 2 0F 3 C3 M0 BFLY 36.000 2 AE CIV LT C DPB VP OC 24 CONTAINMENT PURGE EXHAUST, INSIDE CONTAINMENT ISOLAT10N VALVE 2-HV-MOV 200D 11715 CBB 006A 2 0F 3 C3 M0 BFLY 36.000 2 AE CIV LT C OPB VP OC 24 CONTAINMENT PURGE EXHAUST, OUTSIDE CONTAIN*
MENT ISOLATION VALVE
.............................................. ..e........... ..... .... ... .... .... .... .... ... .... .... ....
2 HV-MOV 201 11715 CBB 006A 2 0F 3 C3 MO BFLY 8.000 2 AE CIV LT C OPS p .............................................
VP OC 24
( CONTAINMENT PURGE BYPASS, OUTSIDE CONTAINMENT ISOLATION VALVE 2 HV-MOV-202 11715 CBS-006A 2 0F 3 D3 M0 BFLY 18.000 2 AE CIV LT C DPB VP OC 24 CONTAINMENT PURGE ALTERNATE SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-HV-MOV 211A 11715 CBB 040C 2 0F 3 E8 MO GATE 4.000 3 B EV O 03 ST 0 03 VP OC 24 CONTROL ROOM CHILLER ISOLATION VALVE 2 NV-MOV 211B 11715-CBB-040C 2 OF 3 C6 M0 GATE 4.000 3 B EV 0 03 ST 0 03 CONTROL ROOM CHILLER ISOLATION VALVE 2 HV-MOV-211C 11715-CBB-040C 2 0F 3 08 M0 GATE 4.000 3 8 EV 0 03 l
ST 0 03 CONTROL ROOM CHILLER isotATION VALVE l
2 HV-Mov 213A 11715 CBB-040D 2 0F 3 E3 M0 GATE 4.000 3 B EV 0 03 ST o 03 J VP DC 24 O
V l
i I
l
y-
)
VIRGIN!A POWER COMPANY PAGE: 35 of 84 NORTM ANNA UNIT 2 REVISIDN: 8 SECOND INSERVICE TESTING INTERVAL DATE: D8/17/96 ks _, INSERVICE TESTING PROGRAM . VALVE TABLE NC ISO REL CS RR ALT i VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $12E CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV* VCN-CONTROL ROOM CONDENSER WATER SYSTEM ISOLATION VALVE 2-HV-MOV-2138 11715-CBB 04DD 2 0F 3 B3 M0 GATE 4.000 3 8 EV 0 03 ST 0 03 CONTROL ROOM CONDENSER WATER SYSTEM ISOLATION VALVE 2 HV-MOV 213C 11715 CBB 0400 2 0F 3 C3 MO GATE 4.000 3 B EV 0 03 !
ST C 03 !
CONTROL ROOM CONDENSER WATER SYSTEM ISOLATION VALVE 2-HV-PCV 2235A1 11715 CBB D400 2 0F 3 D6 A0 CLDBE 3.000 3 B EV C 03 FS C 03 ST C 03 CONTROL ROOM CONDENSER WATER BYPASS LINE PRESSURE CONTROL VALVE 2 HV PCV 2235A2 11715-CBB-0400 2 0F 3 E3 A0 GLOBE 3.000 3 B EV 0 03 FS 0 03 x ST 0 03
) .............................................
d CONTROL ROOM CONDENSER WATER PRESSURE CONTROL VALVE 2 HV PCV 223581 11715-CBS-0400 2 0F 3 A6 A0 GLOBE 3.000 3 B EV C 03 FS C 03 ST C 03 CONTROL ROOM CONDENSER WATER BYPASS LINE PRESSURE CONTROL VALVE 2 HV-PCV 2235B2 11715 CBB-04DD 2 OF 3 C3 A0 GLOBE 3.000 3 B EV O 03 FS 0 03 i ST C 03 ;
CONTROL ROOM CONDENSER WATER PRESSURE CONTROL VALVE 2-HV PCV 2235C1 11715 CBB 04DD 2 0F 3 C6 A0 GLOBE 3.000 3 8 EV C 03 <
FS C 03 ST C 03 2 CONTROL ROOM CONDENSER WATER BYPASS LINE I i
PRESSURE CONTROL VALVE l
I 2 HV-PCV-2235C2 11715-CBB-04DD 2 0F 3 83 A0 GLOBE 3.000 3 B EV O 03 l FS 0 03 l ST C 03 t ............................................. ;
r t CONTROL ROOM CONDENSER WATER l PRESSURE CONTROL VALVE 2 HV RV-2200 11715 CBB 040C 2 0F 3 D3 RELIEF VALVE 3 C SP 0 120 A
i s
4 1
1
t i
i I
i VIRGINIA POWER COMPANY PAGE: 36 0F 84
5 f(' g s NORTH ANNA UNIT 2 SECOND INSERVICE TESTING INTERVAL REVISION: 8 DATE: 08/17/98
\s. / INSERVICE TEST?NG PROGRAM VALVE TADLE l
1 NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NLMBER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-
...... ....... ...... .... ..... ..... .... ... .... .... .... .... ... .... .... .... j CONTROL ROOM CHILLER SYSTEM RELIEF VALVE 2 HV RV 2201 11715 CBB-040C 2 0F 3 C3 RELIEF VALVE 3 C SP 0 120 CONTROL ROOM CHILLER SYSTEM RELIEF VALVE I I'
2-HV RV 2202A 11715-CBB 040C 2 0F 3 E8 RELIEF VALVE 3 C SP O 120 I
............................................. 1 CONTROL ROOM CHILLER SYSTEM RELIEF VALVE i i
1
............................................................. ..... .... ... .... .... .... .... ... .... .... .... q 2 HV-RV 2202B 11715 CBB D40C 2 0F 3 C6 RELIEF VALVE 3 C SP 0 120 i CONTROL ROOM CN!LLER SYSTEM RELIEF VALVE 2-HV RV 2202C 11715-CBB-040C 2 0F 3 DB RELIEF VALVE 3 C SP O 120 CONTROL ROOM CHILLER SYSTEM RELIEF VALVE 2-HV-RV 2205A 11710-CBB 0400 2 0F 3 E3 RELIEF VALVE 3 C SP O 120 f#~5I .............................................
CONTROL ROOM CONDENSER WATER SYSTEM RELIEF VALVE 2-HV RV-22058 11715 CBB 0400 2 0F 3 B3 RELIEF VALVE 3 C SP O 120 CONTROL ROOM CONDENSER WATER SYSTEM '
RELIEF VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 1 2-HV-RV 2205C 11715 CBB 04DD 2 0F 3 D3 RELIEF VALVE 3 C SP O 120 l
............................................. 1 CONTROL ROOM CONDENSER WATER SYSTEM l RELIEF VALVE I
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j 2-HV-RV 2302A 12050 FM 082B 3 0F 3 D3 RELIEF VALVE .750 NC C SP 0 120 )
SAFEGUARD AREA FANS AIR RECE!VER l RELIEF VALVE 2 HV RV 23028 12050-FM 0828 3 0F 3 05 RELIEF VALVE .750 NC C SP O 120 SAFEGUARD AREA FANS AIR RECEIVER RELIEF VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 4 2 HV-$0V 2200A 11715 CBB-040D 2 0F 3 F7 SO GATE .500 3 B EV 0 03 ST 0 03 CONTROL ROOM CONDENSER PUMP SEAL COOLING WATER LINE ISCLAfl0N VALVE 2-HV-SUV 22008 11715-CBB-D400 2 0F ! B7 S0 CATE .500 3 B EV O 03 ST 0 03 CONTROL ROOM CONDENtER PUMP SEAL C00LirG WATER LIWS ISOLAfl0N VALVE lV
(-
VIRGINIA POWER COMPANY PAGE: 37 0F 84
! WORTM ANNA UNIT 2 REVISION: 8 l SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTlWG PROGRAM VA'I TABLE WC ISO REL C5 RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASNE DM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUNSER NUMBER COOR TYPE 512E CLAS CAT TYPE TYPE POS FRE0 V- Csv. RRV VCN-2-NV BOV-2200C 11715 Caa 0400 2 0F 3 D7 50 GATE .500 3 B EV 0 03 ST C 03 CONTROL ROOM CONDENSER PUMP SEAL COOLING WATER LINE ISOLAT!DN VALVE ,
]
l I
1 1
l i
I i
l 4
<s i
4 l
l VIRGINIA POWER COMPANY PAGE: %8 0F 84 )
f "'N WORTH ANNA UNIT 2 REVISION: 8 f i SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\,
INSERVICE TESTING PROGRAM VALVE TABLE NC 1 50 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 $!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV* VCN-2 !A-2130 12050 FM 082A 2 0F 3 E7 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 1 BOTTLED hlTROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 2 IA 2131 12050-FM 082A 2 0F 3 E8 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 1 BOTTLED WITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 2-IA-2132 12050-FM 082A 2 0F 3 E7 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 1 BOTTLED NITROGEN SUPPLY TO PORY ISOLATION CHECK VALVE 2 IA 2133 12050-FM 082A 2 0F 3 E8 CHECK VALVE .750 NC AC CV C RR 1 LT C 24 1 BOTTLED NITROGEN SUPPLY TO PORV ISOLATION CHECK VALVE 2-IA 250 12050-CBM 082A 1 0F 3 F3 CHECK VALVE 2.000 2 AC CIV CV C RR 5 LT C OPB D INSTRUMENT AIR SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLAT!DN CHECK VALVE 2-IA 396 12050 FM 0828 3 0F 3 B3 CHECK VALVE .250 WC AC CV C 03 LT C 24 2 SAFEGUARD AREA FANS AIR RECEIVER ISOLATION CHECK VALVE 2 I A 397 12050-FM D82B 3 0F 3 B3 CHECK VALVE .250 NC AC CV C 03 LT C 24 2 SAFEGUARD AREA FANS AIR RECElVER ISOLATION CHECK VALVE 2 IA-405 12050-FM -0S2B 3 of 3 B5 CHECK VALVE .250 NC AC CV C 03 LT C 24 2 SAFEGUARD AREA FANS AIR RECEIVER ISOLAT10N CHECK VALVE 2 IA 4D6 12050 FM -082B 3 0F 3 B5 CHECK VALVE .250 NC AC CV C 03 LT C 24 2 SAFEGUARD AREA FANS AIR RECEIVER ISOLATloN CHECK VALVE 2-IA-428 12050 CBM-0825 2 0F 3 C7 CHECK VALVE 1.000 2 AC CIV CV C RR 5 LT C OPB I
RETURN TO CONTAlWMENT FROM RADI ATION MONITOR-ING CAB] NET, INSIDE CONT ISOL CHECK VALVE I
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 2 IA-497 11715-FM-082C 1 0F 1 C7 CHECK VALVE .500 NC AC CV C 24 5 I
i
VIRGINIA POWER COMPANY PAGE: 39 0F 84 f ~N NORTN ANNA UNIT 2 REVISION: 8 I SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 (s ,s/ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $1ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV- VCN-2 IA 497 11715 FM-082C 1 0F 1 C7 CHECK VALVE .500 NC AC LT C 24 BOTTLED AIR SUPPLY TO HYDROGEN RECOMBINER l VALVES ISOLATION CHECK VALVE I 2 IA.499 11715 FM-082C 10F 1 C7 CHECK VALVE .500 NC AC CV C 24 5 LT C 24 BOTTLED AIR SUPPLY TO HYDROGEN RECOM81NFR VALVES ISOLAT10N CHECK VALVE ;
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 2-IA-504 12050-FM 082C 1 0F 2 E3 CHECK VALVE .750 NC AC CV C CS 31 I LT C 24 3 MAIN STEAM PCV VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE 2 IA-510 12050-FM -082C 1 0F 2 E4 CHECK VALVE .750 NC AC CV C CS 31 LT C 24 3 MAIN STEAM PCV VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE 2 IA 516 12050-FM -082C 1 0F 2 E4 CHECK VALVE .750 NC AC CV C CS 31 LT C 24 3
- ,s - .............................................
i MAIN STEAM PCV VALVE AIR ACCUMULATOR
{
j ISOLATION CHECK VALVE 2-IA-525 12050-FM 082C 1 0F 2 E6 CHECK VALVE .750 NC AC CV C CS 31 l l LT C 24 3 l AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE 2-IA 531 12050-FM -D82C 1 0F 2 E5 CHECK VALVE .750 NC AC CV C CS 31 LT C 24 3 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE
\
2 IA-537 12050 FM 082C 10F 2 E6 CHECK VALVE .750 NC AC CV C CS 31 LT C 24 3 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE l
i 2-IA 543 12050 FM 082C 1 0F 2 E7 CHECK VALVE .750 NC AC CV C CS 31 l LT C 24 3 I
AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR 's ISOLATION CHECK VALVE 2-IA-549 12050 FM -082C 1 0F 2 E8 CHECK VALVE .750 NC AC CV C CS 31 LT C 24 3 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR ISOLATION CHECK VALVE
<~~' 2 IA-RV-210 12050-FM -082A 2 0F 3 E8 RELIEF VALVE NC C SP O 120 s
l
VIRGINIA POWER COMPANY PAGE: 40 0F 84 NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96
\s - INSERVICE TESTING PROGRAN VALVE TABLE NC 180 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER COOR TTPE SIZE CLAS CAT TYPE TYPE Pos FRE0 V- CSV RRV VCN-AIR SUPPLY TO 2-RC PCV 2455C 2 IA-RV 211 12050 FM 082A 2 0F 3 E8 RELIEF VALVE NC C SP O 120 AIR SUPPLY TO 2 RC PCV 2456 RELIEF VALVE 2 IA SV-205A 12D50-FM 082C 1 0F 1 03 RELIEF VALVE NC C SP O 120 MAIN STEAM PCV VALVE AIR ACCUMULATOR RELIEF VALVE 2 IA SV 205B 12050 FM 082C 1 OF 1 D4 RELIEF VALVE NC C SP O 120 MAIN STEAM PCV VALVE AIR ACCUMULATOR RELIEF VALVE 2 IA SV 205C 12050 FM 082C 1 0F 1 D4 RELIEF VALVE NC C SP O 120 MAIN STEAM PCV VALVE AIR ACCUMULATOR RELIEF VALVE 2 IA SV 205D 12050 FM *D82C 1 0F 1 D5 RELIEF VALVE NC C SP 0 120 j AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR s RELIEF VALVE 2 IA SV-205E 12050 FM 082C 10F 1 D6 RELIEF VALVE NC C SP O 120 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE 2 !A-SV 205F 12050 FM 082C 1 0F 1 D7 RELIEF VALVE NC C SP 0 120 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE 2-IA SV 205G 12050-FM -082C 10F 1 D7 RELIEF VALVE WC C SP 0 120 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE 2 IA SV 205H 12050 FM 082C 1 OF 1 DB RELIEF VALVE NC C SP O 120 AUXILIARY FEEDWATER VALVE AIR ACCUMULATOR RELIEF VALVE 2-IA TV-201A 12050 CBM 082C 2 0F 2 F7 A0 GLOSE 3.000 2 AE CIV LT C OPB l 't VP DC 24 INSTRUMENT AIR SUPPLY FROM CONTAINMENT, INSIDE CONTAINMENT ISOLAfl0N VALVE 1-IA-TV 201B 12050-CBM 082C 2 0F 2 F7 A0 GLOBE 3.000 2 AE CIV LT C OPB VP OC 24 INSTRUMENT AIR SUPPLY FROM CONTAINMENT, h
y INSIDE CONTAINMENT ISOLATION VALVE I
1
n-- ,
VIRGINIA POWER COMPANY PAGE: 41 0F 84 NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC 130 REL CS RR ALT VALVE DRAWING SHEET DR M VALVE VALVE ASME ON VALV TEST TEST TEST RES JUST JUST TEST NLDIBER NUMBER NUMBER COOR TTPE SIZE CLAS CAT TTPE TTPE POS FREO V- CSV ARV VCN-2 IA-TV 202A 12050-CBM 0828 1 0F 3 D7 A0 GLOBE 3.000 2 A Civ EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24 INSTRUMENT AIR SUPPLY TO CONTAINMEWT, OUTSIDE CONTAINMENT ISOLATION VALVE 2 IA TV 202B 12050-CBM-082B 1 0F 3 D7 A0 GLOBE 3.000 2 8 EV C 03 f5 C 03 ST C 03 55 j OC 24 VP INSTRUMENT AIR SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE a i 4
i l
l l
I
r VIRGINIA POWER COMPANY PAGE: 42 0F 84 j r
g' r~ WORTH ANNA UNIT 2 REVISION: 8 1 5
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 DM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $1ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV VCN-2-LM-TV 200A 12050-CBM 092A 1 0F 2 E7 A0 GLOBE .375 2 AE CIV LT C OPS VP OC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2 LM TV 2005 12050-CBM-092A 10F 2 E6 A0 GLOBE .375 2 AE CIV LT C OPB VP DC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM TV-200C 12050-CBM-092A 1 0F 2 E7 A0 GLOBE .375 2 AE CIV LT C OPS VP OC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2 LM-TV-200D 12050-CBM D92A 1 0F 2 E5 A0 CLOBE .375 2 AE CIV LT C OPB VP DC 24 CONTAINMENT LEAKAGE MONITD2tNG OPEN SYSTEM l
SUPPLY, DUTSIDE CONTAINMEbf ISOLATION VALVE l 2 LM TV-200E 12050 CBM-092A 1 0F 2 F6 A0 GLOBE .375 2 AE CIV LT C DPB VP OC 24
, CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE ,
2 LM TV 200F 12050-CBM 092A 1 0F 2 F5 A0 GLOBE .375 2 AE CIV LT C DPB I VP OC 24 )
CONTAINMENT LEAKAGE MONITORING UPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT !$0LATION VALVE 2 LM TV-200G 12050-CBM-092A 10F 2 E7 A0 GLOBE .375 2 AE CIV LT C DPB I VP OC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM l SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2 LM TV 200H 12050 CBM-092A 1 OF 2 E6 A0 CLOBE .375 2 AE CIV LT C DPB VP OC 24 CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2 LM TV 201A 12050 CBM-092A 1 0F 2 05 A0 GLOBE .375 2 AE CIV LT C DPB VP DC 24 l .............................................
I CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM i SUPPLY, DUTSIDE CONTAINMENT ISOLATION VALVE 2-LM TV 201B 12050-CBM-D92A 1 0F 2 D5 A0 GLO6E .375 2 AE CIV LT C OPB VP DC 24 CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE g ) 2 LM-TV-201C 12050-CBM-DV2A 1 0F 2 D5 A0 GLOBE .375 2 AE CIV LT C OPB v
i
l VIRGINIA POWER COMPANY PAGE: 43 0F 84 NORTH ANNA UNIT 2 REVISION: 8
[ SECOND INSERVICE TESTING INTERVAL ' DATE: 08/17/98
\
INSERVICE TESTING PROGRAM - VALVE TABLE NC 180 REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE Pot FREQ V- CSV- RRV- VCN-2 LM TV 201C 12050-COM-092A 1 0F 2 D5 A0 GLOSE .375 2 AE CIV VP OC 24 CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM SUPPLY, GUTSIDE CONTAINMENT ISOLATION VALVE 2 LM TV 2010 12050-COM 092A 1 0F 2 05 A0 GLOSE .375 2 AE CIV LT C OPS l VP OC 24 l
I CONTAINMENT LEAKAGE MONITORING SEALED SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLAfl0N VALVE i
)
1 l
l l
l l
I l
\
'& I l
l l
l ,
l l
l
I l VIRGINIA POWER COMPANY PAGE: 44 0F B4
/'"'g NORTH ANNA UNIT 2 REVISION: 8
( ) SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 A_/
s INSERVICE TESTING PROGRAM VALVE TABLE NC I IBO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE S!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-2-MS 018 12050-CBM-070B 1 0F 3 B7 MANUAL GATE 3.000 2 B EV C 03 MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 2-MS-057 12050 CBM-0708 2 0F 3 B7 MANUAL GATE 3.000 2 B EV C 03 MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 2-MS 095 12050-CBM 070B 3 0F 3 87 MANUAL GATE 3.000 2 B (V C 03 MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE
.......................c .................................... ..... .... ... .... .... .... .... ... .... .... ....
2-MS-117 12050-CBM 070A 3 0F 3 F7 CHECK VALVE 3.000 2 C CV C 03 0 03 "C" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 4
............................................................. ..... .... ... .... .... .... .... ... .... .... .... 1 2 MS.119 12050-CBM-070A 3 0F 3 F7 CHECK VALVE 3.000 2 C CV C 03 0 03
)
- B" MAIN STEAM HEADER SUPPLY CHECK VALVE TD TURBINE DRIVEN AUXILIARY FEEDWATER PUMP I( N) ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
\ss/ 2-MS 121 12050-CBM-07DA 3 0F 3 ET CHECK VALVE 3.000 2 C CV C 03 0 03 l "A" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 2 MS NRV-201A 12050-CBM 0708 10F 3 D3 CHECK VALVE 32.000 2 C CV C CS 13 VP DC 24 "A" MAIN STEAM HEADER NON* RETURN VALVE 2 MS-NRV 2018 12050-CBM-070s 2 0F 3 03 CHECK VALVE 32.000 2 C CV C CS 13 VP OC 24 "B" MAIN STEAM HEADER NON RETURN VALVE 2-MS-NRV 201C 12050-CBM 070B 3 0F 3 D3 CHECK VALVE 32.000 2 C CV C CS 13 VP DC 24 "C" MAIN STEAM HEADER NON-RETURN VALVE 2 MS PCV 201A 12050-CBM-070B 1 0F 3 E5 AD ANGLE 6.000 2 B EV C CS 0 CS FS C 03 ST C CS 0 CS VP DC 24 "A" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE f PRESSURE CONTROL VALVE t
c
- '~s VIRGINIA POWER COMPANY PAGE: 45 0F 84 s WORTH ANNA UNIT 2 REVISION: 8
[ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96
\s. INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ABME DM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE S!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-2-MS PCV 2015 12050 CBM 0705 2 0F 3 E6 A0 ANGLE 6.000 2 B EV C CS 0 CS FS C 03 ST C CS !
............................................. )
"B" MAIN STEAM HEADER DISCHARGE'TO ATMOSPHERE PRESSURE CONTROL VALVE 2 MS-PCV-201C 12050-CBM-070B 3 0F 3 D5 AD ANGLE 6.000 2 B EV C CS 0 CS FS C 03 ST C CS l 0 CS VP OC 24 "C" MAIN STEAM HEADER DISCHAdGE TO ATMOSPHERE PRESSURE CONTROL VALVE 2-MS SV-201A 12050-CBM-07DB 1 0F 3 E6 SAFETY VALVE 6.000 2 C SP 0 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS f 2 MS-SV 201B 12050-CBM-070B 2 0F 3 D6 SAFETY VALVE 6.000 2 C SP 0 120 f .............................................
\s- - "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS I 1
2 MS-SV 201C 12050-CBM-070B 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP 0 120 l "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS SV-202A 12050 CBM-0708 1 0F 3 E5 SAFETY VALVE 6.000 2 C SP O 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS SV-2028 12050-CBM-0708 2 0F 3 05 SAFETY VALVE 6.000 2 C SP 0 120 "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2 MS-SV 202C 12050 CBM-07DB 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP O 120 "C" MAIN STEAM HEADER SAFETY VALVE, SV l DISCHARGE TO ATMOS 2-MS-SV-203A 12050-CBM-0708 1 0F 3 E6 SAFETY VALVE 6.000 2 C 8 SP O 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS SV 2038 12050-tam-0708 2 or 3 05 SAFETY VALVE 6.000 2 C SP O 120 "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHAPGE TO ATMOS g "~'g ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
( j'
\
2-MS SV-203C 12050-CBM-9708 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP O 120
e VIRGINIA POE R COMPANY PAGE: 46 0F 84 f g WORTH ANNA UNIT 2 REVISION: C g ) SECOND INSERVICE TESTING INTERVAL DATE: 08/1T/98 i./
s INSERVICE TESTING PROGRAM VALVE TABLE NC IB0 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-204A 12050 CBM 0708 1 0F 3 E6 SAFETY VALVE 6.000 2 C SP O 120 "A" MAIN STEAM P'ADER SAFETY VALVE, SV DISCHARGE TO 4 G M 2-MS-SV 2048 12050 CBM 070s 2 0F 3 D6 SAFETY VALVE 6.000 2 C SP O 120 "B" MAIN STEAN HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS SV-204C 12050-CBM-0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C SP O 120 "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS i
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 2-MS SV 205A 12050-CBM 070B 10F 3 E5 SAFETY VALVE 6.000 2 C SP 0 120 "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS l
2-MS SV-205B 12050-CBM 0708 2 0F 3 D5 SAFETY VALVE 6.000 2 C SP 0 120 l "B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS SV 205C 12050-CBM 070B 3 of 3 05 SAFETY VALVE 6.000 2 C SP O 120 "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2 MS TV-201A 12050-CBM 07DB 1 0F 3 D4 A0 DISC 32.000 2 B EV C CS 16 FS C CS 16 ST C CS 16 VP DC 24 "A" MAlW STEAM HEADER TRIP VALVE 2 MS-TV-2018 12050 CBM 070B 2 0F 3 C4 A0 DISC 32.000 2 B EV C CS 16 FS C CS 16 ST C CS 16 VP DC 24 "B" MAIN STEAM HEADER TRIP VALVE 2 MS-TV 201C 12050-CBM-070B 3 OF 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 l 1
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 2 MS TV 209 12050-CBM 070A 3 0F 3 D3 A0 GLOBE 3.000 2 B EV C CR 14 l FS C CR 14
('A ST C CR 14 1
i 1
1 I
I VIRGINIA POWER COMPANY PAGE: 47 0F B4 I -g\ NORTH ANNA UNIT 2 REVISION: B SECOND INSERVICE TESTING INTERVAL DATE: 08/1T/96 k_,,/
s INSERVICE TESTING PROGRAM - VALVE TABLE 1
l NC 180 REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER WUMBER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-2-MS TV-209 12050-CBM-070A 3 0F 3 D3 A0 GLOBE 3.000 2 B VP OC 24 MAIN STEAM HIGN PRESSURE DRAIN !$0LAT10N TO l CONDENBER 1 ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
l 2-MS-TV 210 12050-CBM 0708 3 0F 3 A4 A0 GLOBE 1.500 2 B EV C 03 FS C 03 ST C 03 VP DC 24 l MAIN STEAM HIGH PRESSLRE DRAIN HEADER ISO-l LATION TO STEAM GENERATOR BLOWDOWN SYSTEM 2 MS TV-211A 12050 CBM 070A 3 0F 3 E5 A0 GLOBE 3.000 2 B EV C 03 0 03 FS 0 03 ST C 03 0 03 VP OC 24 MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUMILIARY FEEDWATER PUMP 2 MS-TV-211B 12050-CBM-070A 3 0F 3 E4 A0 GLOBE 3.000 2 B EV C 03 0 03 p FS 0 03 ST C 03 l
(,
0 03 I
1 VP DC 24 MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 2 MS TV 213A 12050 CBM-070s 1 0F 3 D4 A0 GLOBE 3.000 2 B EV C CS 34 FS C CS 34 ST C CS 34 VP DC 24 "A" MAIN STEAM TRIP BYPASS VALVE 2 MS-TV 2138 12050-CBM-070B 2 0F 3 04 A0 CLDBE 3.000 2 B EV C CS 34 FS C CS 34 ST C CS 34 VP DC 24 "B" MAIN STE AM TRIP BYPASS VALVE 2 MS-TV 213C 12050-CBM-0708 3 0F 3 D4 A0 GLOBE 3.000 2 B EV C CS 34
, FS C CS 34 ST C CS 34 VP DC 24 "C" MAIN STEAM TRIP BYPASS VALVE 2 MS TV 215 12050 CBM-0TDA 3 0F 3 C4 MECH TRIP VLV 3.000 3 E VP DC 24 l s v
l l
F i
VIRGINIA POWER COMPANY PAGE: 48 0F 84
[N WORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE WC 150 REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-
...................................e.........
MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AFW PUMP
7_ .
l l
l l
VIRGINIA POWER COMPANY PAGE: 49 0F 84
{A
\
NORTH ANNA UNIT 2 SECOND INSERVICE TESTlWG INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE REVISION: 8 DATE: 08/17/98 WC 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-2 05 011 12050-CBM-091A 2 0F 4 D6 WL CHECK VLV 8.000 2 AC Civ CV C 24 23 0 RR 23 LT C OPB "A" GUENCH SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 2 08-022 12050 CBM-091A 2 0F 4 E6 WL CHECK VLV 8.000 2 AC CIV CV C 24 23 0 RR 23 LT C OPB l .............................................
"B" GUENCH SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 2 05-MOV 200A 12050-CBM-091A 2 DF 4 A3 M0 GATE 10.000 2 E VP OC 24 "A" OUENCH SPRAY PUMP SUCTION ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 2-08-MOV 2006 12050-CBM-091A 2 0F 4 A3 MO GATE 10.000 2 E VP OC 24 I "B" OUENCH SPRAY PUMP SUCTION ISOLATION VALVE FROM REFUELING WATER 510 RAGE TANK 2-05-MOV 201A 12050-CBM 091A 2 0F 4 D5 O GATE 8.000 2 A CIV EV C 03 0 03 l
l
^\ LT C OPB ST C 03 0 03 l VP OC 24 "A" QUENCH SPRAY PUMP DISCHARGE ISOLATION j VALVE, OUTSIDE CONTAINMENT !$0LATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 2-05 MOV 2018 12050-CBM-091A 2 0F 4 E5 M0 GATE 8.000 2 A CIV EV C 03 0 03 LT C OPS ST C 03 0 03 l VP OC 24 "B" QUENCH SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT !$0LATION VALVE 2 05-MOV 202A 12050 CBM-091A 10F 4 D5 M0 GATE 6.000 2 B EV 0 CS 44 ST 0 CS 44 VP OC 24 CHEMICAL ADDITION TANK DISCHARGE ISOLAfl0N VALVE l 2-0$ MOV 202B 12050-CBM-091A 1 0F 4 D6 MO GATE 6.000 2 B EV 0 CS 44 l ST 0 CS 44 I
VP OC 24 CHEMICAL ADDITION TANK DISCHARGE ISOLATION VALVE 4
i
VIRGINIA POWER COMPANT PAGE: 50 0F 84 f sg NORTH ANNA UNIT 2 REVISION: 8 i d SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 ,
\s__// INSERVICE TESTING PROGRAM - VALVE TABLE I NC 150 REL CS RR ALT VALWE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-2 RC.143 12050-CBM-0938 1 0F 3 A4 NANUAL NEEDLT .125 1 AE CIV LT C OPS PRESSURIZER PRESSURE DEAD WEIGHT TESTER ISOLATION, OUTSIDE CONT ISOLATION VALVE 2-RC-145 12050 CBM-0938 1 0F 3 A3 MANUAL NEEDLE .12$ 1 AE CIV LT C OPS PRESSURIZER PRESSURE DEAD WEIGHT TESTER ISOLATION, OUTSIDE CONT ISOLATION VALVE 2-RC 162 12050-CBM 0938 2 0F 3 D7 CHECK VALVE 3.000 2 AC CIV CV C 24 6 LT C OPB PRIMARY GRADE WATER SUPPLY TO PRT #2 RCP SEAL STANDP! PES / FLUSH CONNECT, INSIDE CONT ISO VLV 2-RC-NCV-2556A 12050*CBM-093A 10F 3 07 A0 GLOBE 2.000 1 E VP DC 24 RCS LOOP FILL BOUNDARY VALVE 2-RC-NCV 25568 12050 CBM D93A 2 0F 3 DB A0 GLOBE 2.000 1 E VP DC 24 RCS LOOP FILL BOUNDARY VALVE f ~~g ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
t 2 RC HCV 2556C 12050-CBM-093A 3 0F 3 03 A0 GLOBE 2.000 1 E VP OC 24
\ .............................................
RCS LOOP FILL BOUNDARY VALVE 2 RC-Nov-2535 12050-CBM 093B 1 0F 3 E4 M0 GATE 3.000 1 B EV C 03 0 03 ST C 03 0 03 l
BLOCK VALVE FOR PRESSURIZER POWER OPERATED RELIEF VALVE 2-RC MOV 2536 12050-CBM-093B 1 0F 3 04 NO GATE 3.000 1 B EV C 03 0 03 ST C 03 0 03 VP DC 24 BLOCK VALVE FOR PRESSURIZEk POWER OPERATED RELIEF VALVE 2 RC-PCV-2455C 12050-CBM-093B 10F 3 D3 A0 GLOBE 3.000 1 BC EV C CR 42 0 CR 42 FS C CR 42 SP Q RR )
ST C CR 42 ;
O CR 42 )
VP OC CR PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK
~ ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
2-RC PCV 2456 12050 CBM 0930 1 of 3 E3 A0 GLOBE 3.000 1 BC EV C CR 42 l 1
i I
is
?
VIRGINIA POWER COMPANY PAGE: 51 0F B4 f- s NORTN ANNA UNIT 2 REVIsl0N: 8 LEconD INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICC TESTING PROGRAM - VALVE TABLE NC IBO REL CS RR ALT VALVE DRAWING . SNEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REe JUST JUST TEST IRMBER NUMBER NUMBER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-2-RC PCV 2456 12050 CBM-0938 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 0 CR 42 VP DC CR PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK 2-RC 80V-201A 1 12050-CBM-093A 3 0F 3 B5 to GLOBE 1.000 1 B EV C CR 48 0 CR 48 I FS C CR 48 ST C CR 48 0 CR 48 VP DC CR i REACTOR VESSEL VENT LINE ISOLATION VALVE TO I
REFUELING CAVITY 2-RC 50V-201A 2 12050-CBM 093A 3 0F 3 A5 50 GLOSE 1.000 1 B EV C CR 48 0 CR 48 FS C CR 48 ST C CR 48 0 CR 48 VP OC CR j REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 2-RC 50V-2018-1 12050-CBM-D93A 3 0F 3 35 So CLDBE 1.000 1 B EV C CR 48 0 CR 48 FS C CR 48 ST C CR 48 0 CR 48 VP OC CR l .............................................
REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 2-RC-$0V 2018 2 12050-CBM 093A 3 0F 3 A5 SO GLOBE 1.000 1 B EV C CR 48 0 CR 48 FS C CR 48 ST C CR 48 0 CR 48 VP DC CR REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 2 RC SV-2551A 12050-CBM-D938 1 0F 3 E5 SAFETY VALVE 6.000 1 C 7 SP 0 60 PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 2 RC SV 2551B 12050-CBM-093B 1 0F 3 E5 SAFETY VALVE 6.000 1 C SP 0 60 PREESURIZER SAFETY VALVE, SV DISCHARGE TO PRES $URIZER RELIEF TANK 2 RC SV 2551C 12050 CBM-D933 1 0F 3 E6 SAFETY VALVE 6.D00 1 C SP 0 60 l
l VIRGINIA POWER COMPANY PAGE: 52 0F 84
% NORTH ANNA UNIT 2 REVI510N: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/1T/96 INSERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME QM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R 1YPE SIZE CLAS CAT TYPE TYPE Pos FRE0 V- CSV RRV VCN-PRESSUR1ZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 2-RC TV 2519A 12050 CBM-0935 2 0F 3 D8 A0 GLOBE 3.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP GC 24 PRIMARY GRADE WATER SUPP!Y TO PRT #2 RCP SEAL STANDPIPES & FLUSH CONNECT, OUT CONT ISO VLV 1
i
f 1
1 VIRGINIA POWER COMPANY PAGE: 53 0F 84 NORTH ANNA UNIT 2 REVISION: 8 (N _,, SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 s INSERVICE TESTING PROGRAM - VALVE TABLE NC 1 150 REL CS RR ALT l VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-2 RM-007 12050-CBM-094A 1 DF 2 E7 CHECK VALVE 10.000 2 C CV C RR 45 0 RR 45 "A" RHR PUMP DISCHARGE CHECK VALVE 2-RH 015 12050 CBM 094A 1 0F 2 E5 CHECK VALVE 10.000 2 C CV C RR 45 0 RR 45 "B" RHR PUMP DISCHARGE CHECK VALVE 2-RM-037 12050-CBM 094A 2 of 2 C4 MANUAL GATE 6.000 2 AE CIV LT C OPS RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, INSIDE CONTAINMENT ISOLATION VALVE 2 RM-038 12050-CBM-094A 2 0F 2 D3 MANUAL GATE 6.000 2 AE CIV LT C OPS RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, DUTSIDE CONTAINMENT ISOLATloN VALVE 2 RM-MOV-2700 12050-CBM-094A 1 0F 2 A5 M0 GATE 14.000 1 A PlV EV O CS 18 LT C 24 ST VP 0
OC 24 CS 18 )
d RHR PUMP SUPPLY ISOLATION FROM "A" HOT LEG, INSIDE MIS $1LE BARRIER 2-RH-MOV 2701 12050 CBM 094A 1 0F 2 A4 M0 GATE 14.000 1 A PIV EV 0 CS 18 i LT C 24 l ST 0 CS 18 '
VP OC 24 l RHR PUMP SUPPLY ISOLATION FROM "A" HOT LEG, OUTSIDE MIS $1LE BARRIER
)
2-RM MOV 2720A 12050 CBM 094A 2 0F 2 C3 No GATE 10.000 1 A P!V EV O CS 18 LT C 24 ST 0 CS 18 VP DC 24 RHR RETURN ISOLATION TO "B" ACCUMULATOR DISCHARGE LINE 2 RH MOV 2720B 12050-CBM-094A 2 0F 2 B3 No GATE 10.000 1 A PIV EV 0 CS 18 LT C 24 ST 0 CS 18 l VP DC 24 RHR RETURN ISOLATION TO "C" ACCUMULATOR DISCHARGE LINE 2-RH-RV-2721A 12050 CBM 09&A 1 0F 2 E6 RELIEF VALVE 3.000 2 C SP O 120 RHR SYSTEM RELIEF VALVE AT "A" RHR PUMP SUC-TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK 2 RH RV-2721B 12050-CBM-094A 1 0F 2 E4 RELIEF VALVE 3.000 2 C SP O 120 i
e VIRGINIA POWER COMPANY PAGE: 54 0F 84
(
f NORTN ANNA UNIT 2 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 QM VALV TEST TEST TEST REG JUST JUST TEST
! IUtBER NUMBER NLMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV VCN-l l .............................................
j RHR SYSTEM RELIEF VALVE AT "B" RHR PUMP SUC- j i TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK i l ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
l
! l I
I l
l l
l l
l l
1 i
I l i t
I 1
1 i
I l
1 I
1 i
.. g
VIRGIN!A POWER COMPANT PAGE: 55 0F 84
[q NORTH ANNA UNIT 2 SECOND INSERVICE TESTING INTERVAL REVISION: 8 DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC
!$0 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NLMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-2-RM-TV 200A 12050 CsM-082s 2 0F 3 C7 A0 GLOBE 1.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 55 YP OC 24 RETURN ISOLATION FROM AIR RADIATION MONITOR 70 CONTAINMENT, OUTSIDE CONT ISOLATION VALVE 2-RM TV 2008 12050 CBM-082B 2 0F 3 DT A0 GLOBE 1.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 55 VP OC 24 SUPPLY ISOL TO AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, OUTSIDE CONT ISOLATION VALVE 2 RM TV-200C 12050-CBM 0828 2 0F 3 D8 A0 GLOBE 1.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 55 VP OC 24 SUPPLY ISOL 70 AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, INSIDE CONT ISOLATION VALVE s 2 RM-TV 200D 12050-CBM 0828 2 0F 3 C7 A0 GLOBE 1.000 2 B EV C 03 FS C 03 ST C 03 55 VP OC 24 RETURN ISOL FROM AIR RADIAfl0N MONITOR TO CONTAINMENT, OUTSIDE CONT ISOLAfl0N VALVE b
\
l
' ~
c VIRGIN!A POWER COMPANY PAGE: 56 0F 86 NORTH ANNA UNIT 2 REvlsl0N: 8
+ SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98
\s INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SWEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NU41ER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-1 RP D50 11715 CBM-088A 3 0F 4 r? MANUAL DIA 6.0C0 2 AE CIV LT C OPB REFUELING PURIFICAfl0N FROM REACTOR CAVITY TO RP PUMPS, OUTSIDE CONT !$0LATION VALVE 1 RP 084 11715-CBM-088A 3 0F 4 07 MANUAL DIA 6.000 2 AE CIV LT C OPS REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, OUTSIDE CONT ISOLATION VALVE 2-RP-006 11715-CsM-088A 3 0F 4 c5 MANUAL DIA 6.000 2 AE CIV LT C OPS REFUELING PURIFICATION FROM REACTOR CAVITY TO RP PUMPS, INSIDE CONT ISOLATION VALVE 2 RP 007 11715 CBM-088A 3 0F 4 05 MANUAL DIA 6.000 2 AE CIV LT C DPB REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, INSIDE CONT ISOLATION VALVE j C .
l
p-i l VIRGINIA POWER COMPANY PAGE: 57 0F 64 s NORTH ANNA UNIT 2 s REVISION: 8 SEDOND 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 QM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBLt C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-2-RS-020 12D50-CBM-D91A 4 0F 4 06 WL CHECK VLV 10.000 2 AC CIV CV C 24 23 0 RR 23 LT C OPS "A" OUTEIDE RECIRC SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 2 RS-030 12D50-CBM-091A 4 0F 4 D6 WL CHECK VLV 10.000 2 AC CIV CV C 24 23 0 RR 23 LT C DPS "B" OUTSIDE RECIRC SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-RS 103 12050-CBM D91B 1 0F 1 E7 CHECK VALVE 8.000 2 C CV 0 RR 33 "A" CASING COOLING PUMP DISCHARGE CHECK VALVE TO A OUTSIDE RECIRC SPRAY Pur# SUCf 2-RS-118 12050-CBM D918 1 0F 1 F7 CHECK VALVE 8.000 2 C CV 0 RR 33 "B" CASING COOLING PUMP DISCHARGE CHECK VALVE
................. To..".."......................................
B OUTSIDE RECIRC SPRAY PUMP SUCT 2 RS MOV-200A 12050-CBM-D91B 1 GF 1 E7 M0 GATE 8.000 2 A CIV EV C 03 0 03 LT C DPB s, ST C 03 0 03 VP OC 24 "A" CASING COOLING PUMP DISCHARGE ISOLATION TO "A" DUTSIDE RECIRC SPRAY PUMP SUCTION 2-RS-MOV-2008 12050-CBM-091B 10F 1 F7 MO GATE 6.000 2 A CIV EV C 03 0 03 LT C OPS ST C 03 0 03 VP OC 24 "B" CASING COOLING PUMP DISCHARGE ISOLATION TD B OUTSIDE RECIRC SPRAY PUMP SUCTION 2 RS-MOV-201A 12050-CBM-091B 10F 1 E7 M0 GATE 6.000 3 A CIV EV C 03 0 03 LT C OPS ST C 03 0 03 VP OC 24 "A" CASING COOLING PUMP DISCHARGE ISOLATION TO A OUTSIDE RECIRC SPRAY PUMP SUCTION 2 RS-Mov 201B 12050 CBM-091B 10F 1 F7 MO GATE 6.000 3 A CIV EV C 03 0 03 LT C DPB ST C 03 0 03 VP OC 24 x
I i
l l
i VIRGINIA POWER COMPANY PAGE: 58 0F 84
^I NORTH ANNA UNIT 2 REVISION: 8 (d SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DA)E 08/17/98 NC 180 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST l NUMBER NUMBER NUMBER C90R TYPE SIZE CLAS CAT TYPE TYPE POS FREG V- CSV RRV- VCN-l ...... ....... ...... .... ..... ..... .... ... .... .... .... .... ... .... .... ....
"B" CASING COOLING PUMP DISCHARGE ISOLATION 70 "S" OUTSIDE RECIRC SPRAY PUMP SUCTION 2 RS-MOV 255A 12050 CBM 091A 4 0F 4 B5 M0 GATE 12.000 2 B EV C 03 0 03 ST C 03 1 0 03 i VP OC 24 1 .............................................
"A" OUTSIDE RECIRC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP & CASING COOLING 2-RS-MOV 2558 12050-CSM-091A 4 0F 4 A5 No GATE 12.000 2 B EV C 03 0 03 ST C 03 0 03 VP OC 24 "B" OUTS!DE RECIRC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP & CASING COOLING 2-RS-MOV-256A 12050-CBM 091A 4 0F 4 D5 M0 CATC 10.000 2 A CIV EV C 03 0 03 LT C OPS ST C 03 0 03
\ VP OC 24 "A" OUTSIDE RECIRC SPRAY PUMP DISCHARGE !$0-LATION, OUTSIDE CONTAINMENT ISOLATION VALVE 2-RS Mov 2565 12050-CsM-091A 4 0F 4 D5 M0 GATE 10.000 2 A CIV EV C 03 0 03 LT C OPS ST C 03 0 03 VP OC 24 "B" OUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO-LATION, OUTSIDE CONTAINMENT ISOLATION VALVE l
i a
1
r- ~ l i
l l
?
I t
j VIRGINIA POWER COMPANT PAGE: 59 0F 84 l l NORTH ANNA UNIT 2 REVISION: 8 l SECOMO INSERVICE TESTING INTERVAL l DATE: 08/17/96 i
i INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ABME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUNSER COOR TYPE $1ZE CLAS CAT TYPE TYPE POS FREO V- CSV RRV VCN-2 SA 065 12050 CBM-082F 2 0F 2 ST MANUAL GLOSE 2.000 2 AE CIV LT C OPS l
SERVICE AIR SUPPLY 70 UNIT 1 CONTAINMENT, i
OUTSIDE CONTAINMENT ISOLATION VALVE j ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
! 2 SA 123 12050 COM-082F 2 0F 2 D6 MANUAL GATE 2.000 2 AE CIV LT C OPS l SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, INSIDE CONTAINMENT ISOLAT10N VALVE i ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
1 l
D i
1 I
VIRGIN!A POWER COMPANY PAGE: 60 0F 84 N NORTH ANNA UNIT 2 REVISION: 8 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 REG JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV VCN-2 SI 001 12050 CsM 096A 1 or 3 B6 CHECK VALVE 12.000 2 C CV O RR 38 "A" LOW HEAD SI PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 2-SI 006 12050-COM 096A 1 0F 3 C7 CHECK VALVE .750 2 AC CV C RR 19 LT C 24 "A" LOW HEAD $! PUMP SEAL WATER SUPPLY CHECK VALVE FROM RWST 2-51-009 12050-CsM-096A 2 0F 3 B6 CHECK VALVE 10.000 2 C CV C RR 9 0 RR 9 "A" LOW HEAD St PUMP DISCHARGE CHECK VALVE 2 SI 012 12050-CBM-096A 2 or 3 B5 CHECK VALVE 2.000 2 C CV O 03 "A" LOW HEAD $1 PUMP MINIMUM FLOW / TEST LINE DISCHARGE CHECK VALVE 2 SI-018 12050-CBM 096A 1 0F 3 E5 CHECK VALVE 8.000 2 AC CV C RR 10 0 RR 10 PO CS 10 Q 4 .............................................
LT C 2A 76 RWST SUPPLY CHECK VALVE To CHARGING PUMP SUCTION NEADER 2 51 019 12050-CBM-096A 1 0F 3 83 CHECK VALVE 12.000 2 C CV O RR 9 j Po 03 RWST SUPPLY CHECK VALVE TO "B" LOW HEAD SI PUMP SUCTION 2 81 021 12050-CBM 096A 1 0F 3 85 CHECK VALVE 12.000 2 C CV O RR 38 "a" LOW HEAD SI PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 2-$1-029 12050-CBM 096A 1 0F 3 C5 CHECK VALVE .750 2 AC CV C RR 19 LT C 24 "B" LOW HEAD $1 PUMP SEAL WATER SUPPLY CHECK VALVE 2 51 032 12050-CBM 096A 2 cr 3 B4 CHECK VALVE 10.000 2 C CV C RR 9 0 RR #9 "B" LOW HEAD $1 PUMP D!$ CHARGE CHECK VALVE 5 2-51 035 12050 CBM 096A 2 0F 3 84 CHECK VALVE 2.000 2 C CV 0 03 "S" LOW HEAD SI PUMP MINIMUM FLOW / TEST LINE DISCHARGE CHECK VALVE 2 $1 047 120$0-CBM 096A 10F 3 E7 MANUAL GLOBE 1.000 2 AE CIV LT C OPS O*
\J
p:
VIRGINIA POWER COMPANY PAGE: 61 0F 84 j -- NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96
\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 WUMBER NUMBER COOR TYPE $!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-ACCUMULATOR MAKEUP LINE, QUTSIDE CONTAINMENT ISOLATION VALVE 2 51 070 12050-CBM-096A 3 0F 3 04 CHECK VALVE 1.000 2 C CV C RR 27 BORON INJECTION TANK SUPPLY CHECK VALVE FROM BORIC ACID TRANSFER PUMPS 2 51 083 12050-CBM 096A 3 0F 3 F7 MANUAL GLOBE 1.000 2 AE CIV LT C OPB BORON INJECTION TANK BYPASS LINE ISOLATION VALVE - TO RCS COLD LEG 2 SI 085 12050 CBM 0968 4 0F 4 F3 CHECK VALVE 3.000 2 AC C&P CV C RR 14 0 RR 14 LT C 24 HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT ISOLAT10N CHECK YALVE 2-51-D90 12050-CBM-096B 4 0F 4 F7 CHECK VALVE 2.000 1 C CV C RR 15 0 RR 15 HIGH HEAD SI TO "A" RCS COLD LEG, INSIDE fm MIS $1LE BARRIER CHECK VALVE I ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
sj 2-51-091 12050-CBM-096B 4 0F 4 F6 CHECK VALVE 6.000 1 AC C&P CV C RR 12 0 RR 42 12 LT C 24
............r................................
LOW HEAD SI TO *A" RCS COLD LEG, INSIDE CON-TAINNENT ISOLATION CHECK VALVE 2 51 092 12050-CBM-0968 4 0F 4 F8 CHECK VALVE 6.000 1 C CV C RR 12 0 RR 42 12 "A" RCS COLD LEG SI ADMIS$10N CHECK VALVE 2 51 093 12050-CBM D96B 4 0F 4 E3 CHECK VALVE 3.000 2 AC C&P CV C RR 14 0 RR 14 LT C 24 HIGH HEAD $1 FROM CHARGING PUMPS TO RCS COLD LECS, INSIDE CONT ISOLAT10N CHECK VALVE i 1
2 51-098 12050 CBM-0968 4 0F 4 E7 CHECK VALVE 2.000 1 C CV C RR 15 0 RR 15 HIGH HEAD SI To "B" RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE 2 S1-099 12D50-CBM-096B 4 0F 4 E6 CHECK VALVE 6.000 1 AC C&P CV C RN 12 0 RL 42 12 LT C 24 LOW HEAD SI 70 "B" RCS COLD LEG, INSIDE CONTAINMENT ISOLATION CHECK VALVE
, ,s ~s ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
2-SI 100 12050 CBM 096B 4 0F 4 E8 CHECK VALVE 6.000 1 l ( ) C CV C RR 12
VIRGINIA POWER COMPANY PAGE: 62 0F 84
(N) NORTH ANNA UNIT 2 SECONO INSERVICE TESTING INTERVAL REVISION: 8 g
sm _,/
DATE: D8/1T/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-2 51 100 12050-CBM 0968 4 0F 4 E8 CHECK VALVE 6.000 1 C CV 0 RR 42 12 "B" RCS COLD LEG St ADMISSION CHECK VALVE 2-51 104 12050-CBM-0968 4 0F 4 D7 CHECK VALVE 2.000 1 C CV C RR 15 0 RR 15 HIGH HEAD SI TO "C" RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE 2 $1 105 12050 CBM-0968 4 0F 4 D6 CHECK VALVE 6.000 1 AC C&P CV C RR 12 0 RR 42 12 LT C 24 LOW HEAD SI To "C" RCS COLD LEG, INSIDE CON-TAINMENT ISOLATION CHECK VALVE 2-51 106 12050-CBM-0968 4 0F 4 D8 CHECK VALVE 6.000 1 C CV C RR 12 0 RR 42 12 "C" RCS COLD LEG SI ADMISSION CHECK VALVE 2-51 107 12050-CBM 0968 4 or 4 D3 CHECK VALVE 3.000 1 AC C&P CV C RR 14 pg i LT 0
C RR 24 14
\_,) .............................................
HIGH HEAD $1 FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT ISOLATION CHECK VALVE I 2 51 112 12050-CBM-0968 4 OF 4 C7 CHECK VALVE 6.000 1 C CV C RR 14 0 RR 45 14 1 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE j TO C RCS HOT LEG 2 51 113 12050-CBM 0968 4 0F 4 C8 CHECK VALVE 6.000 1 C CV C RR 14 0 RR 45 14 "B" RCS HOT LEG St ADMISSION CHECK VALVE 2-S1-117 12050 CBM 0968 4 0F 4 C7 CHECK VALVE 6.000 1 C CV C RR 14 0 RR 45 14 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE To B RCS HOT LEG 2-51 118 12050-CBM-0968 4 0F 4 88 CHECK VALVE 6.000 1 C CV C RR 14 0 RR 45 14 "A" RCS HOT LEG St ADMISSION CHECK VALVE 2 51 119 12050-CBM 0968 4 0F 4 C3 CHECK VALVE 3.000 1 AC C&P CV C RR 14 0 RR 14 LT C 24 l
VIRGINIA POWER COMPANY PAGE: 63 0F 84 WORTH ANNA UNIT 2 REVISION: 8
[~~ SECONO INSERVICE TESTING INTERVAL DATE: 08/17/96
\s INSERVICE TESTING PROGRAM - 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 COOR TYPE SIZE CLAS CAT TYPE TYPE PDS FREQ V- CSV RRV VCN-HIGH HEAD $1 FROM CHARGING PUMPS TO RCS NOT LEGS, INSIDE CONT ISOLATION CHECK VALVE 2-SI 124 12050-CBM-0968 4 0F 4 87 CHECK VALVE 6.000 1 C CV C RR 14 0 RR 45 14 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE To A RCS NOT LEG 2 51 125 120$0-CBM-0968 4 0F 4 08 CHECK VALVE 6.000 1 C CV C RR 14 0 RR 45 14 "C" RCS HOT LEG SI ADMISSION CHECK VALVE 2-51 126 12050-CBM-0968 4 0F 4 B3 CHECK VALVE 6.000 2 AC C&P CV C RR 14 0 RR 14 LT C 24 LOW HEAD SI FROM "A" LHS! PUMP TO RCS NOT LEGS, INSIDE CONT ISOLATION CHECK VALVE 2 51-128 12050 CBM-0968 4 0F 4 B3 CHECK VALVE 6.000 2 AC C&P CV C RR 14 0 RR 14
/$s LT C 24 i .............................................
k LOW HEAD $1 FROM "B" LHS! PUMP TO RCS NOT LEGS, INSIDE CONT ISOLATION CHECK VALVE 2-SI 132 12050 CBM 0968 1 0F 4 F4 CHECK VALVE 1.000 2 AC Civ CV C RR 11 LT C OPS NITROGEN SUPPLY TO ACCUMULATORS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-$1 136 12050 CBM-0968 1 0F 4 D4 CHECK VALVE 1.000 2 AC CIV CV C RR 11 LT C OPS ACCUMULATOR MAKE UP LINE, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2 SI 151 12050 CBM 0968 1 0F 4 BT CHECK VALVE 12.000 1 AC P!V CV O RR 43 13 LT C 24 "A" ACCUMULATOR DISCHARGE CHECK VALVE 2 $1 153 12050-CBN-0968 1 0F 4 88 CHECK VALVE 12.C00 1 AC P!V CV C RR 13 0 RR 43 13
'6 LT C 24 "A" ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 2 $1 168 12050 CBM-0968 2 0F 4 B5 CHECK VALVE 12.000 1 AC PlV CV O RR 43 13 LT C 24 "B" ACCUMULATOR DISCHARGE CHECK VALVE O
g ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
r VIRGINIA POWER COMPANY PAGE: 64 0F 84 WORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 sms/ INSERVICE TESTING PROGRAM - VALVE TABLE NC IBO 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 FREQ V- CSV RRV VCN-2 SI 170 12050-CBM-0965 2 0F 4 B7 CNECK VALVE 12.000 1 AC PlV CV C RR 13 0 RR 43 13 LT C 24 "B" ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 2 51 185 12050-CBM 0968 3 0F 4 B5 CHECK VALVE 12.000 1 AC PIV CV 0 RR 43 13 LT C 24 "C" ACCUMULATOR DISCHARGE CHECK VALVE 2 SI 187 12050-CBM 0968 3 of 4 B7 CHECK VALVE 12.000 1 AC PIV CV C RR 13 0 RR 43 13 LT C 24 "C" ACCUMULATOR COLD LEG ADMIS$10N CHECK VALVE 2-St-HCV 2956 12050 CBM 0968 1 0F 4 E5 A0 GATE 1.000 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP DC 24 WASTE GAS FROM ACCUMULATORS TO CHARCOAL
\- FILTERS 2-SI-MOV-2836 12050-CBM 096A 3 0F 3 C8 MO GATE 3.000 2 A C&P EV C RR 7 0 RR 7 LT C 24 ST C RR 7 I O RR 7 l VP OC 24 HIGH HEAD $! FROM CHARGING HEADER TO RCS COLD LEGS, OUTSIDE CONTAINMENT !$0LATION VALVE 2 SI MOV 2860A 12050-CBM 096A 1 0F 3 B7 MO GATE 12.000 2 B EV C 03 0 03 i ST C 03 0 03 VP OC 24
............................................. i "A" LOW HEAD SI PUMP SUCTION ISOLATION FROM I CONTAINMENT SUMP 2-SI MOV 2860B 12050-CBN-096A 1 0F 3 85 Mo GATE 12.000 2 B EV C 03 l 0 03 l 's ST C 03
! 0 03 l
1 VP OC 24 "B" LOW HEAD $1 PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP 2-SI-Mov 2862A 12050-CBM-096A 1 0F 3 A3 M0 GATE 12.000 2 B EV C 03 ST C 03 VP OC 24
)
L
T i
VIRGINIA POWER COMPANY PAGE: 65 0F 84 s NORTH ANNA UNIT 2 REVIS!ON: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE WC 180 REL CS RR ALT VALVE DPAWING SHEET DRWG VALVE VALVE ABME QM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE $12E CLAS CAT TYPE TYPE POS FRE0 V- CSV- ARV VCN-
"A" LOW NEAD St PUMP SUCTION FROM RWST 2-SI MOV 2862B 12050 CBM 096A 10F 3 B3 M0 GATE 12.000 2 B EV C 03 ST C 03 VP DC 24 "B" LOW HEAD St PLMP SUCTION FROM RWST l 2 51-MOV 2863A 12050-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 l
"A" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLAfl0N TO CHARGING PUMPS 2 SI-MOV 28638 12050 CBM 096A 2 0F 3 D4 MO GATE 8.000 2 8 EV C 03 0 03 ST C 03 0 03 VP DC 24 "B" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLAfl0N TO CHARGING PUMPS 2 SI MOV 2864A 12050 CBM 096A 2 0F 3 C7 M0 GATE 10.000 2 B EV C 03 0 03 ST C 03 0 03 VP OC 24 "A" LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALVE 2 SI-MOV-2864B 12050-CBM 096A 2 0F 3 C6 M0 GATE 10.000 2 B EV C 03 0 03 ST C 03 0 03 VP DC 24 "B" LOW HEAD $1 PUMP COLD LEG DISCHARGE STOP VALVE 2 SI MOV-2865A 12050 CBM-096B 1 0F 4 C7 MO GATE 12.000 2 B EV C CS 24 0 CS 24 ST C CS 24 l
O CS 24 VP OC CS "A" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2 $1 MOV 28658 12050 CBM 0968 2 0F 4 c5 M0 GATE 12.000 2 B EV C CS 24 0 CS 24 ST C CS 24
- w o s CS 24
l l
VIRGINIA POWER COMPANY PAGE: 66 0F 84 NORTH ANNA UNIT 2 REVis!DN: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 N
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 C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV- VCd-
"B" ACCUMULATOR DISCHARGE ISOLAT!0N VALVE T@
RCS COLD LEG 2-51 MOV 2865C 12050-CBM 0968 3 0F 4 C5 M0 GATE 12.000 2 B EV C CS 24 0 CS 24 ST C CS 24 0 CS 24 VP OC CS "C" ACCUMULATOR DISCHARGE ISCLATION VALVE TO RCS COLD LEG 2-SI-MOV-2867A 12050-CBM 0P6A 3 0F 3 D4 M0 GATE 3.000 2 B EV U RR 27 0 RR 27 ST C RR 27 0 RR 27 VP OC 24 BORON INJECTION TANK HIGN HEAD SI INLET VALVE 2 S! MOV-28678 12050-CBM-096A 3 0F 3 D4 M0 GATE 3.000 2 B EV C RR 27 0 RR 27 ST C RR 27 0 RR 27 OC 24
( ,_, .............................................
VP BORON INJECTION TANK HIGH HEAD $1 INLET VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... I 2 SI-MOV 2867C 12050 CBM-096A 3 0F 3 E7 Mo GATE 3.000 2 A C&P EV C RR 8 0 RR 8 LT C 24 ST C RR 8 0 RR 8 VP DC 24 BORON INJECTION TANK OUTLET 70 RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV 28670 12050 CBM-096A 3 0F 3 D7 MO GATE 3.000 2 A C&P EV C RR 8 0 RR 8 LT C 24 ST C RR 8 0 RR 8 VP OC 24 BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2869A 12050-CBM 096A 3 0F 3 C8 M0 GATE 3.000 2 A C&P EV C RR 7 0 RR 7 LT C 24 ST C RR 7 0 RR 7 VP DC 24 HIGH HEAD $1 FROM CHARGING HEADER TO RCS HOT p LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE q
s
~
l l
l j
VIRGIN!4 POWER COMPANT PAGE: 67 0F 84 NORTH ANNA UNIT 2 REVISION: 8 (s SECOND 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 DM VALV TEST TEST TEST RES JUST JUST TEST NLMBER NUMBER NUMBER COOR TTPE $1ZE CLAS CAT TTPE TTPE POS FRE0 V- CSV RRV- VCN-2 SI MOV 2869B 12050-CBM-096A 3 0F 3 88 M0 GATE 3.000 2 A C&P EV C RR 7 0 RR 7 LT C 24 ST C RR 7 0 RR 7 VP OC 24 HIGH HEAD SI FROM CHARGING HEADER TO RCS NOT LEGS, QUTSIDE CONTAINMENT ISOLATION VALVE 2 SI MOV 2885A 12050-CBM-096A 2 0F 3 C3 M0 CLDBE 2.000 2 A EV C 03 LT C 24 76 ST C 03 VP OC 24 "A" LOW HEAD $1 PUMP MINIMUM FLOW / TEST LINE ISOLAT!DN 2 St MOV-2885B 12050-CBM 0964 2 0F 3 B3 M0 GLOBE 2.000 2 A EV C 03 LT C 24 76 ST C 03 VP DC 24 "B" LOW HEAD St PUMP MINIMUM FLOW / TEST LINE ISOLATION J 2-SI MOV-2885C 12050 CBM D96A 2 0F 3 D3 M0 GLOBE 2.000 2 A EV C 03 sd LT C 24 76 ST C 03 VP OC 24 "A" LOW HEAD SI PUMP MINIMUM FLOW / TEST LINE ISOLAfl0N 2-SI-MOV-2885D 12050 CBM D96A 2 0F 3 B3 M0 GLOBE 2.000 2 A EV C 03 i LT C 24 76 i ST C 03 VP OC 24 i "B" LOW HEAD S1 PUMP MINIMUM FLOW / TEST LINE ISOLAT10N 2 SI MOV 2890A 12050 CBM 096A 2 0F 3 D/ M0 GATE 10.000 2 A C&P EV C RR 7 0 RR 7 LT C 24 ST C RR 7 0 RR 7 VP OC 24 "A" LOW HEAD St PUMP HOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-RI-MOV 28908 12050 CBM-D96A 2 0F 3 D7 MO GATE 10.000 2 A C&P EV C RR 7 0 RR 7 LT C 24 ST C RR 7 0 RR 7 VP OC 24 A
is
r VIRGINIA POWER COMPANT PAGE: 68 0F 84 (VA) NORTH ANNA UNIT 2 SECOND INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM VALVE TABLE REVISION: 8 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 COOR TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-
"B" LOW HEAD St PUMP HOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV 2890C 12050-CsM-096A 2 0F 3 C8 MO GATE 10.000 2 A C&P EV C RR 8 0 RR 8 LT C 24 ST C RR 8 0 RR 8 VP OC 24 LOW NEAD St PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2 SI-MOV-28900 12050-CBM 096A 2 0F 3 C7 M0 GATE 10.000 2 A C&P EV C RR 8 0 RR 8 LT C 24 ST C RR 8 0 RR 8 VP OC 24 LOW HEAD SI PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... i 2 SI-RV-204 12050-cam 096A 2 0F 3 F7 RELIEF VALVE 3 C SP O 120 !
CONTAINMENT PENETRATION 106 RELIEF VALVE
\
2 SI RV-2845A 12050-CBM-096A 2 0F 3 D6 RELIEF VALVE .750 2 C SP O 120
............................................. I "A" LOW HEAD St PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 2 SI-RV 28458 12050-CBM 096A 2 0F 3 C7 RELIEF VALVE .750 2 C SP O 120 1 1
1 LOW HEAD $1 HEADER TO COLD LEG RELIEF VALVE, '
RV DISCHARGE TO SAFEGUARDS AREA SUMP 2-SI RV-2845C 12050-CBM-096A 2 OF 3 E7 REL*EF VALVE .750 2 C SP O 120 "B" LOW HEAD $1 PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 2 SI RV-2857B 12050-CsM-096A 3 0F 3 E7 RELIEF VALVE .750 2 C SP 0 120 BORON INJECTION TANK RELIEF VALVE, RV DISCHARGE TO FLOOR DRAIN 2 51 RV 2858A 12050-CBM 0968 10F 4 D7 RELIEF VALVE 1.000 2 C SP O 120 j ............................................. ,
"A" ACCUMULATOR RELIEF VALVE 2 51 RV 28588 12050-CBM-0968 2 0F 4 05 RELIEF VALVE 1.000 2 C SP O 120 "B" ACCUMULATOR RELIEF VALVE p 2-SI-RV-2858C 12050-CBM 0968 3 OF 4 D5 RELIEF VALVE 1.000 2 C SP O 120 i
\
F I
l i
l VIRGINIA POWER COMPANY PAGE: 69 0F 84
-%s NORTH ANNA UNIT 2 REVISION: 8 l SECONO INSERVICE TESTING INTERVAL DATE: 08/17/98
,, INSERVICE TESTING PROGRAM - VALVE TABLE l
NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REO JUST JUST TEST MUISER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-
"C" ACCUMULATOR RELIEF VALVE 2-SI-TV-200 12050-CBM 0965 1 0F 4 F3 A0 GLOBE 1.000 2 A CIV EV C 03 FS C 03 LT C DPS ST C 03 VP OC 24 NITROGEN SUPPLY TO ACCUMULATORS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI TV 201 12050-CBM 0968 1 0F 4 E4 A0 GLOBE 1.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 55 VP OC 24 ACCUMULATOR $ TO WASTE GAS CHARCOAL FILTERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2 SI TV 2842 12050 CBM 0965 1 0F 4 D4 A0 GLOBE .750 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 VP OC 24 ACCUMULATOR TEST LINE, INSIDE CONTAINMENT ISOLATION VALVE 2 SI TV 2859 12050-CBM 096A 2 0F 3 F7 A0 CLDBE .750 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 l VP OC 24 !
ACCUMULATOR TEST LlhE, OUTSIDE CONTAINMENT ISOLATION VALVE 2 SI-TV-2884A 12050 CBM 096A 3 0F 3 F4 A0 GLOBE 1.000 2 B EV C 03 FS C 03 l ST C 03 55 l
VP DC 24 BORON INJECTION TAWK RETURN ISOLATION TO BORIC ACID STORAGE TANK 2 $1 TV-28848 12050-CBM-096A 3 0F 3 E4 A0 GLOBE 1.000 2 B EV C 03 FS C 03
% VP OC 24 h
i
(
~
VIRGINIA POWER COMPANT PAGE: 70 or 84 NORTH ANNA UNIT 2 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 OM VALV TEST TEST TEST REO JUST JUST TEST NUMBER NUMBER NUMBER C00R TTPE $12E CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN- '
...... ....... ...... .... ..... ..... .... ... .... .... l BORON INJECTION TANK SUPPLY ISOLATION FROM BORIC ACID TRANSFER PUMPS
, i l
l i
1 l
l l
l I
\ \
1 1
I 1
I l
l VIRGINIA POWER COMPANY PAGE: 71 0F 84 NORTN ANNA UNIT 2 REVISION: 8 i
SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 I
INSERVICE TESTING PROGRAM - VALVE TABLE
, NC i
ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST ImmBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FRE0 V- CSV- RRV VCN-l 2 SS TV 2004 12050-COM-0898 1 0F 1 F6 - A0 GLOSE .375 1 A CIV EV C 03 l FS C 03 I LT C OPS ST C 03 VP OC 24 PRESSURIZER LIQUID SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE l 2 SS TV 2005 12050-CBM-0898 1 0F 1 F6 A0 GLOSE .375 1 A CIV EV C 03 l FS C 03 l LT C OPS
- ST C 03
! VP OC 24 l PRESSURIZER LIQUID SPACE SAMPLE LINE, OUTS!DE i CONTAINMENT ISOLATIDW VALVE 2 SS TV-201A 12050-COM-0895 1 0F 1 E6 A0 GLOBE .375 1 A CIV EV C 03 FS C 03 l LT C OPS l ST C 03 55 l VP OC 24 l
l PRESSURIZER VAPOR SPACE SAMPLE LINE, INSIDE
! CONTAINMENT ISOLATION VALVE I
2 SS TV 2018 12050-CSM-0898 1 0F 1 E6 A0 GLOBE .375 1 A CIV EV C 03 FE C 03 LT C OPS ST C 03 VP OC 24 l PRESSURIZER VAPOR SPACE SAMPLE LINE, GUTSIDE l CONTAINMENT ISOLATION VALVE j ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
2 SS TV 202A 12050-CSM 0898 1 0F 1 D6 SO GLOSE .375 1 A CIV EV C 03 l FS C 03 l LT C OPS i ST C 03 55 l VP OC 24 l REACTOR COOLANT COLD LEGS SAMPLE HEADER,
! INSIDE CONTAINMENT ISOLAT!DN VALVE l
l 2 SS TV 202B 12050 C M 0898 1 0F 1 D6 So CLOBE .375 1 A CIV EV C 03 FS C 03 LT C OPB ST C 03 55 VP OC 24
............................................. 2 i
REACTOR COOLANT COLD LEGS SAMPLE HEADER, QUTSIDE CONTAINMENT ISOLAfl0N VALVE 2-SS TV 203A 12050-CBM 0898 1 0F 1 F6 So GlosE .375 2 AE CIV LT C OPS l VP OC 24
............................................. 4 RNR SAMPLE HEADER, INSIDE CONTAINMENT ISOLA-T10N VALVE 2 SS TV 2035 12050-CBM-089s 1 0F 1 F6 80 GLOBE .375 2 AE CIV LT C DPS
l VIRGINIA POWER COMPANT PAGE: 72 0F 84 je- s NORTH AbkA UNIT 2 REVISION: 8 4
SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 l\ INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV RRV- VCN-2-SS TV-2038 12050-CBM-0895 1 0F 1 F6 SO GLO6E .375 2 AE CIV VP OC 24 RHR SAMPLE HEADER, OUTSIDE CONTAINMENT ISOLA-TION VALVE 2 SS TV 204A 12D50-CBM-0898 1 0F 1 C6 A0 GLOBE .375 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 55 VP OC 24 PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 2 SS TV-204B 12050-CBM-0898 1 0F 1 C6 A0 GLOBE .375 2 A CIV EV C 03 FS C 03 LT C DPB ST C 03 55 VP DC 24 PRESSUR!ZER RELIEF TANK GAS SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2 SS-TV-206A 12050-CBM 0898 1 OF 1 E6 50 GLOBE .375 1 A CIV EV C 03 FS C 03 A I LT C OPS (j
\
OC 24 03 55 REACTOR COOLANT NOT LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATION VALVE 2 SS TV 2068 12050 CBM-089B 1 0F 1 E6 SO GLOBE .375 1 A CIV EV C 03 FS C 03 l LT C OPB ST C 03 55 VP OC 24 REACTOR COOLANT NOT LEGS SAMPLE HEADER, OUT-SIDE CONTAINMENT ISOLATION VALVE 2 SS TV-212A 12050 CBM 089A 3 of 4 D3 A0 GLOBE .375 2 A CIV EV C 03 FS C 03 LT C OPB ST C 03 55 VP OC 24
! STEAM GENERATORS SAMPLE HEADER, INSIDE CON-l TAINENT ISOLATION VALVE 2-SS-TV-2125 12050-CBM-089A 3 0F 4 C3 A0 GLOBE .375 2 A CIV; EV C 03 FS C 03 LT C DPB ST C 03 55 VP DC 24 STEAM GENERATORS SAMPLE HEADER, OUTSIDE CON-TAINMENT ISOLATION VALVE I
\s I
l l VIRGINIA P0lER COMPANY PAGE: 73 0F 84 NORTN ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/98 INSERVICE TESTING PROGRAM - VALVE TABLE NC 180 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME QM VALV TEST TEST TEST REG JUST JUST TEST IRMBER NUMBER NLMBER C00R TYPE SIZE CLAS CAT TYPE TYPE Pos FRE0 V- CSV RRV VCN-l ...... ....... ...... .... ..... ..... .... ... .... .... .... .... ... .... .... ....
2 SV TV 202 1 12050-CBM-072A 2 0F 3 C3 A0 GLoeE 6.000 2 B EV C 03 FS C 03 ST C 03 VP OC 24 CONDENSER AIR REMOVAL DISCHARG TO CONTAIN-MENT, QUTSIDE CONTAIN ISOLATION W
...................................................'.VE .......... ..... .... ... .... .... .... .... ... .... .... ....
2-SV TV 203 12050 CBM-072A 2 0F 3 D3 A0 GLOBE 6.000 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 VP OC 24 C0tCENSER AIR REMOVAL DISCHARGE TO CONTAIN-MENT, OUTSIDE CONTAINMENT ISOLATION VALVE l
l
- s
(~
7 1
VIRGIN!A POWER COMPANY PAGE: 74 0F 84
, DO)
NORTH ANNA UNIT 2 SECOND INSERVICE TESTING INTERVAL REVISION: 8 DATE: 02/25/99 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SKEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NLMBER NUMBER NUMBER COOR TYPE SIZE CLAS CAT TYPE TYPE POS FREO V- CSV- RRV- VCN-1 SW-MOV 115B 11715-CDM-078A 1 0F 4 D7 M0 BFLY 24.000 3 B EV O 03 l
ST 0 03 VP OC 24 SERVICE WATER HEADER SUPPLY ISOLATION VALVE FROM AUXILIARY SERVICE WATER PUMPS 2 SW 003 11715 CBM-078A 3 0F 4 D4 CHECK VALVE 20.000 3 C CV C RR 21 0 RR 21 PO 03 UNIT 2 "A" SERVICE WATER PUMP DISCHARGE CHECK VALVE 2 SW-010 11715-CBM-078A 3 0F 4 D3 CHECK VALVE 20.000 3 C CV C RR 21 0 RR 21 PO 03 UNIT 2 "B" SERVICE WATER PUMP DISCHARGE CHECK VALVE i
2 SW-024 11715-CBM-078A 1 0F 4 C6 CHECK VALVE 24.000 3 C CV C 03 '
O RR 26 PO 03 j
l . '\ UNIT 2 AUXILIARY SERVICE WATER PUMP DISCHARGE
/ CHECK VALVE s_-
s ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
l 2 sW 068 11715-CBM-0788 3 0F 4 F8 CHECK VALVE 24.000 3 C CV 0 RR 16 "A" SERV!CE WATR HEADER SUPPLY CHECK VALVE TO RECIRC SPRAY HX UPSTREAM OF CROSS CONNECT 2 SW 070 11715 CBM-0788 3 0F 4 F8 CHECK VALVE 24.000 3 C cv 0 RR 16 "B" SERVICE WATR HEADER SUPPLY CHECK VALVE TO i I
RECIRC SPRAY HX UPSTREAM OF CROSS CONNECT 2 SW 074 11715-CBM 07B8 3 0F 4 E7 CHECK VALVE 16.000 2 C CV 0 RR 16 "A" REclRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE 2-SW-084 11715 CBM-0788 3 0F 4 E6 CHECK VALVE 16.000 2 C CV 0 ER 16 "B" RECIRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE 2 SW 094 11715 CBM 0788 3 0F 4 E4 CHECK VALVE 16.000 2 C CV O RR 16 I "C" RECIRC SPRAY HEAT EXCHANGER SERVICE WATER "'
SUPPLY CHECK VALVE 2-SW 104 11715-CBM-0788 3 0F 4 E3 CHECK VALVE 16.D00 2 C CV 0 RR 16 "D" RECIRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE 2 SW-580 11715 CBM-078G 2 0F 2 E7 CHECK VALVE 2.000 3 C CV C RR 77 ed I]
/
d 0
PO 03 RR 77 I2L V
r-VIRGINIA poler COMPANY PAGE: 75 0F 84 NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 02/25/99
, _ , INSERVICE TESTING PROGRAM - VALVE TABLE
(
5 NC
!$0 REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME DM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER WUMBER 000R TYPE SIZE CLAS CAT TYPE TYPC POS FREQ V- CSV- RRV- VCN-SERVICE WATER SUPPLY TD CHARGING PUMP LUBE DIL COOLER CHECK VALVE 2 SW-581 11715 CBM-078G 2 0F 2 E7 CHECK VALVE 2.000 3 C CV C RR 77 0 RR 77 PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE OIL COOLER CHECK VALVE 2 SW-591 11715-CBN 078G 2 0F 2 E6 CHECK VALVE 2.000 3 C CV C PR 77 0 RR 77 PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 2 SW 592 11715-CBM 078G 2 0F 2 ET CHECK VALVE 2.000 3 C CV C RR 77 0 RR 77 PO 03 :
............................................. l SERVICE WATER SUPPLY TO CHARG!hG PUMP SEAL COOLER CHECK VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 2-SW 597 11715 CBM-078G 2 0F 2 E6 CHECK VALVE 2.000 3 C CV C RR 77 l 0 RR 77
~('~~ .............................................
SERVICE WATER SUPPLY TO CHARGING PUMP LUBE CIL COOLER CHECK VALVE C'l 2 SW 598 11715-CBM 078G 2 0F 2 E6 CHECK VALVE 2.000 3 C CV C RR 77 ;2 '
O RR 77 g PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE DIL COOLER CHECK VALVE 2 SW 608 11715-CBM 078G 2 0F 2 E5 CHECK VALVE 2.000 3 C CV C RR 77 0 RR 77 PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 2 SW 600 11715-CBM 078G 2 OF 2 E5 CHECK VALVE 2.000 3 C CV C RR 77 0 RR 77 PO C3 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 2 SW 615 11715 CBM 078G 2 0F 2 E4 CHECK VALVE 2.000 3 C CV C RR 77 0 RR 77 i PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE Olt COOLER CHECK VALVE 2-SW 616 11715-CBM-078G 2 0F 2 E4 CHECK VALVE 2.000 3 C CV C RR 77 O
(
w l
r 1 VIRGINIA POWER COMPANY PAGE: 76 0F 84 i NORTH AWMA UNIT 2 REVIS10N: 8 J SECONO INSERVICE TESTING INTERVAL DATE: 02/25/99 INSERVICE TESTING PROGRAM - VALVE TABLE
,D t NC
\'- ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER WUMBER WUMBER C00R TYPE $!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN-2-SW-616 11715-CBM-078G 2 0F 2 E4 CHECK VALVE 2.000 3 C CV o RR 77 PO 03
, SERVICE WATER SUPPLY TO CHARGING PUMP l LUBE DIL COOLER CHECK VALVE 2-SW-626 11715 CBM-078G 2 0F 2 E3 CHECK VALVE 2.000 3 C CV C RR 77 0 RR 77 PO 03 h, SERVICE WATER SUPPLY TO CHARGING PUMP [2, SEAL COOLER CHECK VALVE g
2-SW-627 11715-CBM-078G 2 0F 2 E3 CHECK VALVE 2.000 3 C CV C RR 77 1 0 RR 77 PO 03 SERVICE WATER SUPPLY TO CHARGING PUMP ,
SEAL COOLER CHECK VALVE l 2-SW-MOV 201A 11715-CBM-078A 4 0F 4 E7 Mo BFLY 24.000 3 B EV O CS 35 ST 0 CS 35 l VP OC 24 I
............................................. 4 "A" SERVICE WATER HEADER SUPPLY !$0LAT10N TD RECIRC SPRAY HEAT EXCHANGERS
,,_m 2-SW-Mov 201B 11715-CBM-078A 4 0F 4 E7 M0 BFLY 24.000 3 B EV O CS 35 l
"A" SERVICE WATER HEADER SUPPLY ISOLAT10N TD RECIRC SPRAY HEAT EXCHANGERS 2 SW Mov-201C 11715 CBM-07BA 4 0F 4 E7 M0 BFLY 24.000 3 B EV O CS 35 ST 0 CS 35 ,
"B" SERVICE WATER HEADER SUPPLY ISOLAT!DN TO RECIRC SPRAY HEAT EXCHANGERS 2-SW-MOV 201D 11715-CBM-07BA 4 0F 4 E7 Mo BFLY 24.000 3 8 EV 0 CS 35 ST 0 CS 35 VP DC 24 "B" SERVICE WA1ER HEADER SUPPLY !$0LATION TO RECIRC SPRAY HEAT EXCHANGERS l
2 SW-MOV 202A 11715-CBM 0788 3 0F 4 F8 M0 BFLY 24.000 3 B EV C 03 ST C 03 VP OC 24 SERVICE WATER SUPPLY CROSS CONNECTS TO RECIRC SPRAY HEAT EXCHANGERS 2-SW MOV 202B 11715 CBM 0788 3 0F 4 F8 M0 BFLY 24.000 3 B EV C 03 ST C 03 VP DC 24 s
1
VIRG',NIA POE R COMPANY PAGE: 77 of 84 NORTH ANNA UNIT 2 REVISIDW: 8 SECOND INSERVICE TESTING INTERVAL DATE: 02/25/99
,_ INSERVICE TESTING PROGRAM - VALVE TABLE
(\s, NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ABME DM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE $3ZE CLAS CAT TYPE TYPE P05 FRE0 V- CSV RRV- VCN-SERVICE WATER BUPPLY CROSS CONNECTS TO RECIRC SPRAY HEAT EXCNANGERS
............................................................. ..... .... ... .... .... .... .... ... .... .... .... i 2 BW-MOV-203A 11715-cam 078B 3 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 "A" RECIRC SPkAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW MOV 2038 11715-CBM-0788 3 0F 4 E6 M0 BFLY 16.000 2 A CIV EV C 03 0 03 LT C DPB ST C 03 0 03 VP OC 24 SERVICE WATER SUPPLY TO "B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j 2 SW MOV-203C 11715 CBM-078B 3 0F 4 E4 M0 BFLY 16.000 2 -A CIV TV C 03 0 03 LT C OPB j rss ST C 03 j
( O 03 '
y} .............................................
VP OC 24 ]
1 SERVICE WATER SUPPLY TO "C" RECIRC SPRAY HEAT l EXCHANGER, DUTSIDE CONT ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... l 2 SW MOV 203D 11715-CBM 0788 3 0F 4 E3 Mo BFLY 16.000 2 A CIV EV C 03 0 03 LT C DPB ST C 03 0 03 VP DC 24 SERVICE WATER SUPPLY TO "D" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2 SW Mov 204A 11715 CBM 0788 3 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 "A" RECIRC SPRAY HEAT EXCHANGER, DUTSIDE CONT ISOLATION VALVE .
2 SW-Mov 2048 11715-CBM 0788 3 0F 4 C6 M0 BFLY 16.000 2 A CIV EV C 03 0 03 LT C DPB ST C 03 0 03 VP OC 24 s
I' VIRGINIA POWER COMPANY PAGE: 78 0F 84 NORTH ANNA UNIT 2 REV!$10N: 8 SECOND INSERVICE TESTING INTERVAL DATE: 02/25/99
<-- INSERVICE TESTING PROGRAM - VALVE TABLE
'\s_, NC ISO REL CS RR ALT VALVE DRAWING SMEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER DOOR TYPE $!2E CLAS CAT TYPE TYPE PDS FRE0 V- CSV RRV. VCN-SERVICE WATER RETURN FROM "B" RECIRC SPRAY MEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... )
2-SW M0V-204C 11715 CBM 0785 3 0F 4 c5 M0 BFLY 16.000 2 A CIV EV C 03 l 0 03 LT C DPB ST C 03 0 03 VP DC 24 SERVICE WATER RETURN FROM "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE
............................................................. ..... .... ... .... .... .... .... ... .... .... .... j 2 SW MOV 2040 11715 CBM-0785 3 0F 4 C3 M0 BFLY 16.000 2 A Civ EV C 03 l 0 03 1 1
LT C DPS ST C 03 0 03 VP DC 24 SERVICE WATER RETURN FROM "D" RfCIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLAT!DN VALVE 2 SW-MOV 205A 11715 CBM-076A 4 0F 4 E7 M0 BFLY 24.000 3 8 EV 0 CS 35 <
~s .............................................
"B" SERVICE WATER HEADER RETURN ISOLAfl0N k.s FROM RECIRC SPRAY HEAT EXCHANGERS 2 SW-MOV 2058 11715 CBM 078A 4 0F 4 E7 M0 BFLY 24.000 3 B EV 0 CS 35 ST 0 CS 35 VP OC 24 "B" SERVICE WATER HE ADER RETURN ISOLAT!DN FROM RECIRC SPRAY HEAT EXCHANGERS 2 SW Mov-205C 11715 CBM 078A 4 0F 4 E6 M0 BFLY 24.000 3 8 EV 0 CS 35 ST 0 CS 35 VP OC 24 "A" SERVICE WATER HEADER RETURN ISOLAT10N FROM RECIRC SPRAY MEAT EXCHANGERS 2-SW MOV 205D 11715 CBM 078A 4 of 4 ET M0 BFLY 24.000 3 B EV 0 CS 35 ST 0 CS 35 VP DC 24 "A" SERVICE WATER HEADER RETURN ISOLAfl0N FROM RECIRC SPRAY HEAT EXCHANGERS 2 SW-MOV-206A 11715-CBM 078B 3 0F 4 B3 M0 BFLY 24.000 3 B EV C 03 ST C 03 VP DC 24 SERVICE WATER RETURN CRDSS CONNECTS FROM RECIRC SPRAY HEAT EXCHANGERS 2 SW Mov-2065 11715 CBM 0788 3 0F 4 A3 M0 BFLY 24.000 3 B EV C 03 ST C 03 m
/ T U
VIRGINIA POW R COMPANY PAGE: 79 0F 84 NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 02/25/99
,,ss INSERV!CE TESTING PROGRAM - VALVE TABLE k WC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE $!ZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV- VCN.
2-SW-MOV 2068 11715 CBM-078B 3 OF 4 A3 M0 BFLY 24.000 3 B VP OC 24 SERVICE WATER RETURN CROSS CONNECTS FROM RECIRC SPRAY HEAT EXCHANGERS 2-SW MOV.208A 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 ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2 SW-MOV-208B 11715 CBM-078C 1 0F 2 B3 M0 BFLY 24.000 3 B EV C CS 43 0 CS 43 ST C CS 43 O CS 43 VP OC 24 "A" SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2-SW-MOV-210A 11715-CBM 078A 4 0F 4 E8 MO BFLY 8.000 3 E VP DC 24 SERVICE WATER HEADER SUPPLY TO RECIRCULATION AIR COOLERS 2 SW-MOV 2108 11715-CBM-07BA 4 0F 4 F8 MO BFLY 8.000 3 E VP DC 24 SERVICE WATER HEADER SUPPLY TO RECIRCULATION %
AIR COOLERS 2 SW MOV-213A 11715-CBM-07BA 4 0F 4 B7 M0 BFLY 10.000 3 E VP OC 24 SERVICE WATER RETURN ISOLATION FROM FUEL PIT COOLERS 2 SW MOV-2138 11715-CBM-078A 4 0F 4 85 M0 BFLY 10.000 3 E VP OC 24 SERVICE WATER SUPPLY ISOLATION TO FUEL P!T COOLERS 2 SW MOV 214A 11715 CBM 07BA 4 0F 4 F8 MO BFLY 8.000 3 E VP DC 24 SERVICE WATER HEADER RETURN FROM RECIRCULATION AIR COOLERS 2 SW MOV 2148 11715 CBM 07&A 4 0F 4 F8 M0 SFLY 8.000 3 E VP DC 24 SERVICE WATER HEADER RETURN FROM RECIRCULATION AIR COOLERS 24.000 3
~' 0 03 2-SW-MOV 215A 11715 CBM 078A 10F 4 07 MO BFLY B EV ST 0 03 VP OC 24 l SERVICE WATER HEADER SUPPLY ISOLATION l l
VALVE FROM AUXILIARY SERVICE WATER PUMPS i 2 SW MOV-217 11715 CBM 078A 1 0F 4 D6 M0 BFLY 24.000 3 B EV O 03 A
s VIRGINIA POWER COMPANY PAGE: 80 0F 84 i NORTH ANNA UNIT 2 REVISION: 8 SEC04D INSERV!CE TESTING INTERVAL DATE: 02/25/99
- s INSERVICE TESTING PROGRAM - VALVE TABLE l
s NC
~'
t ISO REL CS RR ALT i VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST l NUMBER WUMBER WUMBER 000R TYPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV- RRV VCN-2 SW-M0V-217 11715-CsM-078A 1 of 4 D6 M0 BFLY 24.000 3 8 ST 0 03 i
VP OC 24 l .......... ..................................
l UNIT 2 AUXILIARY SERVICE WATER PUMP DISCMARGE ISOLATIDW VALVE 2-SW-MOV-219 11715-COM-078A 1 0F 4 D5 M0 BFLY 8.000 3 B EV C 03 ST C 03 VP DC 24 MAKEUP PUMP BUPPLY VALVE 2-SW MOV-220A 11715-CBM-078A 4 0F 4 F3 Mo BFLY 10.000 NC E VP OC 24 AUXILIARY SERVICE WATER RETURN HEADER VALVE 2 SW-Mov-2208 11715 CBM-078A 4 0F 4 F3 M0 BFLY 10.000 NC E VP DC 24 AUXILIARY SERVICE WATER RETURN HEADER VALVE 2-SW MOV 221A 11715-CBM 078H 1 0F 1 C8 M0 BFLY 18.000 3 B EV O 03 ST 0 03 VP OC, 24 SERVICE WATER TO SPRAY ARRAYS STOP VALVE
\- 2-SW-MOV 2218 11715-CBM 078H 10F 1 C4 M0 BFLY 18.000 3 B EV 0 03 ST C 03 VP OC 24 SERVICE WATER TO SPRAY ARRAYS STOP VALVE 2 $W MOV 222A 11715-CBM-078H 1 0F 1 C7 M0 BFLY 18.000 3 B EV 0 03 ST C 03 VP DC 24 SERVICE WATER TO SPRAY ARRAYS STOP VALVE 2 SW MOV-2228 11715 CBM-078H 1 0F 1 C4 M0 BFLY 18.000 3 B EV O 03 ST 0 03 VP DC 24 SERVICE WATER TO SPRAY ARRAYS STOP VALVE 2 SW-MOV 223A 11715-CBM-078H 1 0F 1 D8 M0 BFLY 24.000 3 8 EV C 03 ST C 03 VP DC 24 SERVICE WATER BYPASS VALVE 2-SW-MOV-2238 11715-CBM-078H 1 0F 1 04 M0 BFLY 24.000 3 8 EV C 03 ST C 03 1
\
\
J
r-i r
VIRGINIA poler COMPANY PAGE: 81 0F 84 NORTH ANNA UNIT 2 REVISION: 8
, SECOND INSERVICE TESTING INTERVAL DATE: 02/25/99 INSERVICE TESTING PROGRAM VALVE TABLE O
l g NC ISO REL CS RR All VALVE DRAWING SHEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REQ JUST JUST TEST NUleER NUMBER NLMBER C00R TTPE SIZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV- VCN-l ...... ....... ...... .... ..... ..... .... ... .... .... .... .... ... .... .... ....
SERVICE WATER BYPASS VALVE 2 SW-RV 200A 11715-CeM-07Be 3 0F 4 E7 RELIEF VALVE .750 2 C SP O 120 "A" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 2 SW-RV 200s 11715 COM-078B 3 0F 4 E6 RELIEF VALVE .750 2 C SP O 120 "O" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 2 SW-RV 200C 11715-cam-078s 3 OF 4 E4 RELIEF VALVE .750 2 C SP 0 120 "C" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 2 SW-RV 2000 11715-COM-0788 3 0F 4 E3 RELIEF VALVE .750 2 C SP 0 120 "D" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 2-SW RV-201A 11715 CBM-07BC 1 0F 2 E7 RELIEF VALVE .750 3 C SP 0 120
............................................. i UNIT 2 "A" COMPONENT COOLING HEAT EXCHANGER I SERVICE WATER RELIEF VALVE i l
g ............................................................. ..... .... ... .... .... .... .... ... .... .... ....
2-SW-RV-201B 11715-CBM-078C 1 0F 2 E8 RELIEF VALYE .750 3 C SP 0 120
,v f UNIT 2 "B" COMPONENT COOLING HEAT EXCHANGER SERVICE WATER RELIEF VALVE 2 SW-TCV-202A 11715-CBM-078G 2 0F 2 C4 A0 GATE 2.000 3 B EV 0 03 FS 0 03 ST 0 03 SERVICE WATER FROM CHARGING PUMP LUBE CIL I COOLER TEMP CONTROL VALVE l l
I 2 SW TCV 2028 11715 CBM-078G 2 of 2 C6 A0 GATE 2.000 3 B EV 0 03 l FS 0 03 ST C 03 SERVICE WATER FROM CHARGING PUMP LUBE OIL COOLER TEMP CONTROL VALVE
.............................................................. ..... .... ... .... .... .... .... ... .... .... .... l l
2 SW-TCV 202C 11715 CSM-078G 2 0F 2 C8 A0 GATE 2.000 3 8 EV O 03 '
FS 0 03 ST C 03 I
SERVICE WATER FROM CHARGING PUMP LUBE CIL -
l COOLER TEMP CONTROL VALVE e
k r
i
VIRGINIA POWER COMPANY PAGE: 82 0F 84 NORTH ANNA UNIT 2 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 OM VALV TEST TEST TEST RE0 JUST JUST TEST NUMBER NLMBER NUMBER C00R TYPE $1ZE CLAS CAT TYPE TYPE POS FREQ V- CSV RRV VCN-
, 2-VG TV-200A 12050-CBM 090A 1 0F 3 F3 A0 GLOBE 1.500 2 A CIV EV C 03 FS C 03 LT C OPS ST C 03 55 VP OC 24 VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, OUTSIDE CONT ISOL 2 VG TV 2005 12050 CSM 090A 1 0F 3 D3 A0 GLOBE 1.500 2 A CIV EV C 03 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
yy ) gg pgyi .y-------.i-- -- - - - -
VIRGINIA POE R COMPANY PAGE: 83 of 84 NORTH ANNA UNIT 2 REVISION: 8 SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING $NEET DRWG VALVE VALVE ASME OM VALV TEST TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE $!ZE CLAS CAT TYPE TYPE POS FRE0 V- CSV RRV VCN-2-VP-024 12050-can 072A 2 0F 3 E3 CHECK VALVE 6.000 2 AC CIV CV C 24 17 LT C OPS CONDENSER AIR REMOVAL DISCHARG TO CONTAINMENT INSIDE CONTAIN ISOLATION CHECK VALVE "f
g
VIRGINIA POE R COMPANY PAGE: 84 0F 84
'-'s NORTH ANNA UNIT 2 REVISION: S SECOND INSERVICE TESTING INTERVAL DATE: 08/17/96
\<~ ')
INSERVICE TESTING PROGRAM VALVE TABLE NC 180 REL C5 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-2 WT D41 12050-CBM-102A 2 0F 2 F7 CHECK VALVE .750 2 C CV C D3 "A" STEAM GENERATOR CHEMICAL FEED SUPPLY CHECK VALVE 2-WT-053 12050 CBM 102A 2 0F 2 ET CHECK VALVE .750 2 C CV C 03 "B" $ TEAM GENERATOR CHEMICAL FEEI) SUPPLY i
l CHECK VALVE 2-WT 069 12050 CBM 102A 2 0F 2 D7 CHECK VALVE .750 2 C CV C 03 l "C" STEAM GENERATOR CHEMICAL FEED SUPPLY CHECK VA.VE 2 WT 437 12050-CBM-102B 1 OF 1 E6 MANUAL GATE 3.000 2 AE Civ LT C OPS WET LAY UP RETURN FROM "A" $ TEAM GENERATOR, INSIDE CONTAINMENT ISOLATION VALVE 2 WT 438 12050-CBM-102B 1 0F 1 D6 MANUAL GATE 3.000 2 AE CIV LT C OPB 4............................................
WET LAY UP RETURN FROM "B" $ TEAM GENERATOR, INSIDE CONTAINMENT ISOLATION VALVE 2 WT 439 12050 CBM 1028 1 0F 1 B6 MANUAL GATE 3.000 2 AE Civ LT C DPB i/'~) .............................................
d WET LAY UP RETURN FROM "C" STEAM GENERATOR, INSIDE CONTAINMENT ISOLAfl0N VALVE 2 WT 446 12050-CBM-1028 1 0F 1 ES MANUAL GATE 3.000 2 Al CIV LT C OPB WET LAY UP RETURN FROM "A" STEAM r.ENERATOR, OUTSIDE CONTAINMENT l$0LATION VALVE 2 WT 447 12050 CBM-1028 1 0F 1 D5 MANUAL GATE 3.000 2 AE CIV LT C OPB WET LAY UP RETURN FROM *B" STEAM GENERATOR, OUTSIDE CONTAINMENT ISOLATION VALVE 2 WT 448 12050 CBM-102B 1 0F 1 B5 MANUAL GATE 3.000 2 AE CIV LT C OPB WET LAY UP RETURN FROM "C" $ TEAM GENERATOR, DUTSIDE CONTAINMENT ISOLATION VALVE l
l i ;
I
[h
\
s l
l
1 4.5 VALVE INSERVICE TESTING PROGRAM RELIEF REQUESTS Relief requests identify those Section XI Code i requirements considered to be impractical. The basis for the relief request and the alternate testing to be performed is given.
l l
l l
lO 1
l l
n !
1 1
O 4-8 N2PVI2R8 Revision 8 August 17, 1998
I l i
l l
l l
() 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 i
RELIEF REQUEST V-4 Replaced by Cold Shutdown Justification CSV-5 RELIEF REQUEST V-5 l 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 RELIEF REQUEST V-8 Replaced by Cold Shutdown Justification CSV-8 j l
RELIEF REQUEST V-9 4
Replaced by Cold Shutdown Justifica2 ion CSV-47 i ,
o i
r~N U 4-9 N2PVI2R8 Revision 8 December 1, 1998 .
l l
p l
(~) RELIEF REQUEST V-10 i (_ /
l 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. l RELIEF REQUEST V-14 Relief Request withdrawn.
f%
(_) 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 Oi V 4-10 N2PVI2R8 Revision 8 August 17, 1998
[~ ,
(~)
V RELIEF REQUEST V-19 Relief Request withdrawn.
1 RELIEF REQUEST V-20 Replaced by Reactor Refueling Justification RRV-4 j l
1 RELIEF REQUEST V-21 Replaced by Reactor Refueling Justification RRV-5 RELIEF REQUEST V-22 Replaced by Cold Shutdown Justification CSV-13 RELIEF REQUEST V-23 Replaced by Cold Shutdown Justification CSV-14
,n
\-)
~ RELIEF REQUEST V-24 1
Replaced by Cold Shutdown Justification CSV-15 i 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 r~
l 4_11 N2PVI2R8 Revision 8 August 17, 1998
RELIEF REQUEST V-28 Replaced by Reactor Refueling Justification RRV-6 RELIEF REQUEST V-29 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 O
t l
l l 4-12 N2PVI2R8 Revision 8 August 17, 1998
I l
[ RELIEF REQUEST V-33 System : Recirculation Spray I
i Valve (s)': 2-RS-103 2-RS-118 I
Category: C Class : 2 l 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 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 I These check valves must open in order to' perform their safety
(- /~') functions. Due to system design, they are not in the Casing Cooling Pump test flowpath. Partial or full stroke exercising these valves with flow would flood the containment sump.
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.
o i
O 4-13 l N2PVI2R8 Revision 8 )
August 17, 1998 l i
i
RELIEF REQUEST V-34
[
Replaced by Cold Shutdown Justification CSV-22 1
RELIEF REQUEST V-35 1
Replaced by Reactor Refueling Justification RRV-7 RELIEF REQUEST V-36 Replaced by-Cold Shutdown Justification CSV-24 1 ,
RELIEF REQUEST V-37 Replaced by Reactor Refueling Justification RRV-8
~>
i O 4-14 ,
N2PVI2RB Revision 8 August 17, 1998 L_
[) RELIEF REQUEST V-38 V
System : Safety Injection Valve (s) : 2-SI-1 2-SI-21 Category: 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 ksl To partial or. full flow test these check valves requires taking suction from the reactor containment sump which is normally empty. Water would have to be added to the sump. However, the ,
water would pick up contaminants from the sump. This untreated '
water should not be 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.
l r
\~.j 4-15 N2PVI2R8 Revision 8 August 17, 1998
I l
- Q RELIEF REQUEST V-39 l V Replaced by Reactor Refueling Justification RRV-9 i
RELIEF REQUEST V-40 Replaced by Reactor Refueling Justification RRV-10 RELIEF REQUEST V-41 Replaced by Reactor Refueling Justification RRV-11
^
4-16 l N2PVI2R8 Revision 8 '
August 17, 1998 !
RELIEF REQUEST V-42_
(}
l
~ System : Safety Injection Valve (s):- 2-SI-91 2-SI-100 2-SI-92. 2-SI-105 2-SI-99 2-SI-106 Category: AC i
Class : 1
-Function: -RCS Cold Leg SI~ Admission 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 O 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 Th'ere is no installed instrumentation that can measure individual flow rates for these valves. The alternate testing described below will be used, i 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 i
analyzed to show that the disk struck the back seat, which
! verifies that the disk stroked to the full open position.
.i l- 4-17 !
N2PVI2R8' Revision 8 August 17, 1998
E 1 1
i RELIEF REQUEST V-42 (Cont.)
[}
1 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 2-SI-91, 99 and 105 in one group, and valves.2-SI-92, 100 and 106 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.
i l
4-18 N2PVI2R8 Revision 8 4 August 17, 1998 l
RELIEF REQUEST V-43
(}
System : Safety Injection Valve (s): 2-SI-151. 2-SI-170 l 2-SI-153 2-SI-185 l 2-SI-168 2-SI-187 Category: C Class : 1 Punction: 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 pe.rt 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 kT) s 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 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 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 verifies that the disk stroked to the full open position.
l 0
x) 4-19 N2PVI2R8 Revision 8 August 17, 1998 l
I-RELIEF REQUEST V-43 (Cont )
(}
The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2. Valves 2-SI-153, 170 and 187 are closest to the reactor coolant system and will be '
in one group, and valves 2-SI-151, 168 and 185 will be in the other group. During initial testing using nonintrusive techniques, each valve in the group will be verified as operable.
During subsequent ter; ting, 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.
O l
1 r
1 l
i l
l l
O 4-20 N2PVI2R8 Revision 8 August 17, 1998 f
l RELIEF REQUEST V-44 Relief Request withdrawn.
I i
j l
i l
l l
l I
I 4-21 N2PVI2R8 Revision 8 August 17, 199g
RELIEF REQUEST V-45
(}
System .: Safety Injection -
Valve (s) : 2-SI-112 2-SI-118 2-SI-113 2-SI-124 2-SI-117 2-SI-125 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
/~. 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 flow rates for these valves. The alternate testing described below will be used. )
Alternate Testing Proposed l ,
With low head pump flow, the hot leg injection valves will be i acoustically monitored using a sampling plan for the disk j striking the back seat every reactor refueling,, The data will be i analyzed to show that the disk struck the back seat, which verifies that the disk stroked to the full open position.
4-22 !
I N2PVI2R8 Revision 8 August 17, 1998 L
l
f RELIEF REQUEST V-45 (Cont.)
L 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 2-SI-112, 117 and 124 in one group, and valves 2-SI-113, 118 and 125 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 per' ormed, l 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 I 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.
> n l
l l
l 4-23 N2PVI2R8 Revision 8 August 17, 1998 i
p l- ,
5 l-
[ } ' RELIEF REQUEST V-46 i Replaced by Reactor Refueling Justification RRV-16 l
RELIEF REQUEST V-47 l
f Replaced by Reactor Refueling Justification RRV-17 RELIEF REQUEST V-48 Replaced by' Reactor Refueling Justification RRV-18 RELIEFiREQUEST V-49
! Relief Request Withdrawn RELIEF REQUEST V-50 Relief Request Withdrawn RELIEF REQUEST V-51 L
l- Relief Request Withdrawn l
! RELIEF REQUEST V-52 Relief Request Withdrawn RELIEF REQUEST V-53 1
Relief Request Withdrawn
]
l l
n
[
4 i
l 4-24 N2PVI2R8 Revision 8 August 17, 1998 t- .
RELIEF REQUEST V-54
}
Replaced by Reactor Refueling Justification RRV-19 RELIEF REQUEST V-55 Relief Request Withdrawn ,
I RELIEF REQUEST V-56 Replaced by Non-Code Alternative Testing Description VNC-4 RELIEF REQUEST V-57 Relief Request Withdrawn RELIEF REQUEST V-58 Replaced by Cold Shutdown Justification CSV-48 2 U
RELIEF REQUEST V-59 Relief Request Withdrawn RELIEF REQUEST V-60 Relief Request Withdrawn RELIEF REQUEST V-61 Relief Request Withdrawn RELIEF REQUEST V-62 Relief Request Withdrawn
5
' )
4-25 I N2PVI2R8 Revision 8 December 1, 1998 L
r I-L RELIEF REQUEST-V-63
[
Replaced by Reactor Refueling Justification RRV-20 l l
RELIEF REQUEST V-64 Replaced by Reactor-Refueling Justification RRV-21 I
RELIEF REQUEST V-65 j Replaced by Non-Code Alternative Test Description VNC RELIEF REQUEST V-66 Replaced by Reactor Refueling Justification RRV-22 RELIEF REQUEST V-67 Relief Request Withdrawn
( RELIEF REQUEST V-68 j Replaced by Reactor Refueling Justification RRV-23 RELIEF REQUEST V-69 Relief Request Withdrawn i
l l
n O 4-26 N2PVI2R8 Revision 8 August 17, 1998 i
1
i l
[ RELIEF REQUEST V-70
}
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
{
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 i possible contribution to the total leakage rate for the I 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.
Also, there may be plant conditions, or schedule constraints, that preclude repair or replacement of a valve when the individual leakage limit is exceeded, but the overall leakage limit for the Type C-tested valves is met. In these cases, imposing the Code requirements of repair or replacement would create an undue burden with no compensating benefit to quality and safety when the bases for leakage limits is met for the overall limit necessary to ensure containment 4ntegrity.
,-~,
(,)
l 4-27 N2PVI2R8 Revision 8 August 17, 1998
r-l i
(' ; RELIEF REQUEST V-70 (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 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.
L.
lO i
l l i O 4-28 l N2PVI2R8 Revision 8 August 17, 1998 i
n 1 I
RELIEF REQUEST V-71 Replaced by Reactor Refueling Justification RRV-24 4
RELIEF REQUEST V-72 l Relief Request Withdrawn RELIEF REQUEST V-73 Replaced by Reactor Refueling Justification RRV-25 RELIEF REQUEST V-74 Replaced by Reactor Refueling Justification RRV-26 RELIEF REQUEST V-75 Replaced by Cold Shutdown Justification CSV-45 O
l l
l l
I l-0 4-29 l N2PVI2R8 Revision 8 August 17, 1998 L
RELIEF REQUEST V-76
[}
System : Chemical and Volume Control and Safety Injection.
Valve (s) : '2-CH-MOV-2115B 2-SI-MOV-2885A 2-CH-MOV-2115D 2-SI-MOV-2885B 2-SI-1B 2-SI-MOV-2885C 2-SI-MOV-2885D-Category: A for 2-CH-MOV-2115B and D, and 2-SI-MOV-2885A-D AC for 2-SI-18 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 l Valves 2-CH-MOV-2115B and D, and 2-SI-18 are in the supply line to the charging pumps from the RWST. Valves 2-SI-MOV-2885A, 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. Pennissible 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 overall allowable leakage to the RWST may not,have been exceeded.
In these cases, a repair or replacement may not be necessary because_the system of isolation valves has been verified to be i performing adequately.
I
() 4-30 N2PVI2R8 Revision 8 :
August 17, 1998 i
ri
() RELIEF REQUEST V-76 (Cont.)
Alternate' Testing Proposed In addition to repair or replacement as corrective actions, an evaluation can be performed which~ demonstrates that even if a i valve has exceeded its permissible leakage rate, the overall i leakage rate to the RWST will be maintained below the overall.
I allowable RWST leakage rate. No repair or replacement is l necessary if the' evaluation is performed.
l l
l LO 1
L >
l 0 4-31 ,
N2PVI2R8 Revision 8 August 17, 1998 l
r, l'
D J RELIEF REQUEST V-77 System .: Service Water zValve (s) : 2-SW-580 2-SW-597 2-SW-615 2-SW-581 2-SW-598 2-SW-616 2-SW-591 2-SW-608 2-SW-626 2-SW-592 2-SW-609 2-SW-627 i 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 l every refueling outage to verify operability of check valves may j be used." This sentence implies that each valve in the group j given above must be disassembled every refueling outage.
Basis For Request l
l These check valves must open to supply service water to the charging pump lube oil and gear box coolers and close if one of l 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. ,
l l Due to the 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 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 l plant through a major evolution to depressurize one header.
l n
4-32 N2PVI2R8 Revision 8 August 17, 1998 e
() RELIEF REQUEST V-77 (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.
t i
i i
n O 4-33 N2PVI2R8 Revision 8 August 17, 1998
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 the valves cannot be exercised during normal operation.
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 cold shutdown justifications identify and provide the technical basis for valves exercised during cold shutdown but not during normal operation.
O n
O 4-34 N2PVI2R8 Revision 8 August 17, 1998 L - . . . .
l COLD SHUTDOWN JUSTIFICATION CSV-1 l
1 l System :- Component Cooling l
Valve (s): 2-CC-TV-201A 2-CC-TV-202E 2-CC-TV-201B 2-CC-TV-202F 2-CC-TV-202A 2-CC-TV-204A 2-CC-TV-202B 2-CC-TV-204B l 2-CC-TV-202C 2-CC-TV-204C 2-CC-TV-202D Category: A Class : 2
- Function
- Reactor Coolant Pump CC Supply and Return Containment l
isolation Valves l
Failure of these valves in the closed position would result in a loss of component cooling flow to the Reactor Coolant Pumps l thermal barriers, lube oil, stator and/or shroud coolers. The l
i Q
\_/
increased level of safety gained from exercising these valves during power operation does not justify the operational consequences should they fail in the closed position. The valve controllers do not allow for a part-stroke exercise test.
-Testing' Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
l !
l l
l l
l i
l l
4-35 l N2PVI2R8 Revision 8 August 17, 1998
l l
1 I
i COLD SHUTDOWN JUSTIFICATION CSV-2 Replaced by Relief Request V-63 O
l t
l n
l 1
i l
O 4-36 N2PVI2R8 Revision 8 August 17, 1998
r--
l
() COLD SHUTDOWN JUSTIFICATION CSV-3 l System : CH Valve (s): 1-CH-118.
1-CH-133 Category: C l
Class : 3 Function: Boric Acid Transfer Pump Discharge Check Valves Cold Shutdown Justification l
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 l O These valves will be partial stroke exercised every quarter and full stroke exercised every cold shutdown but not more frequently
.than once every three months.
1 4
l' O 4-37 N2PVI2R8 Revision 8 August 17, 1998
COLD SHUTDOWN JUSTIFICATION CSV-4
(}
System : Chemical & Volume Control System Valve (s) : 2-CH-MOV-2350 2-CH-155-2-CH-156 2-CH-157 2-CH-159 l
Category: B for 2-CH-156 and 2-CH-MOV-2350 C for 2-CH-155, 157 and 159 Class : 2 for 2-CH-157, 159 and 2-CH-MOV-2350 3 for 2-CH-155 and 156 Function: Emergency Boration Line and Alternate Boration Line Valves Cold Shutdown Justification Full or part-stroke exercising these valves during power operation would cause a sudden increase in reactor coolant system O boron inventory by providing flow from the emergency and alternate boration paths to charging pump suctions. Also, the valve controller for 2-CH-MOV-2350 does not allow for a part-stroke exercise test. The increased level of safety gained from full or part-stroke exercising these valves during power operation does not justify the operational consequences associated with reactivity transients.
Testing Frequency i
These valves will be full stroke' exercised every cold shutdown l but not more frequently than once every three months. Manual valve 2-CH-156 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 i the manual valve.
n l
O 4-38 N2PVI2R8 Revision 8 August 17, 1998 l
E ,
COLD SHUTDOWN JUSTIFICATION CSV-5 System : Chemical & Volume Control System Valve (s): 2-CH-TV-2204A 2-CH-LCV-2460A 2-CH-TV-2204B 2-CH-LCV-2460B
' Category: B for 2-CH-LCV-2460A and B A for 2-CH-TV-2204A and B Class : 2 Function: Letdown Line Isolabion Valves 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 I control valve so that the charging input flow to the RCS and k--) reactor coolant pump seal injection flow into the RCS matches letdown flow.
Also, exercising these valves during normal operation will interrupt letdown flow through the regenerative heat exchanger.
-This flow interruption would allow a slug of relatively cool charging water to thermal shock the nozzle connecting the 3" charging line to the 27" loop 2 cold leg injection line. The valve controllers do not allow for a part stroke exercise test.
Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
n l
l 4-39 N2PVI2R8 Revision 8 August 17, 1998
s I COLD SHUTDOWN JUSTIFICATION CSV-6 System : ' Chemical & Volume Control System Valve (s) : 2-CH-MOV-2115B 2-CH-MOV-2115C 2-CH-MOV-2115D 2-CH-MOV-2115E Category: A for 2-CH-MOV-2115B and D 1B for 2-CH-MOV-2115C 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
(, 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.
1 i "1 1
1 0 4-40 N2PVI2R8 Revision 8 August 17, 1998 L.
s l ?
f
/\ COLD SHUTDOWN' JUSTIFICATION CSV-7 l0 l
l System : Chemical & Volume Control System i Valve (s): 2-CH-MOV-2289A
( 2-CH-MOV-2289B l Category: A for 2-CH-MOV-2289A B for 2-CH-MOV-2289B 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 desirable since decreased charging temperatures result in
, reactivity increases and thermal stress on the piping and heat
- exchanger.
Full or part-stroke exercising these valves during power operation would isolate the normal charging flow path from the I
O' charging pumps to the Reactor Coolant System. Also, the valve controllers do not allow for a part-stroke exercise test. The sma11' 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.
I
'A l
i
^l 4-41 N2PVI2R8 Revision 8 i August 17, 1998 )
> COLD SHUTDOWN JUSTIFICATION 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 (D
U l
4-42 N2PVI2R8 Revision 8 August 17, 1998
r I I
I i
I~' COLD SHUTDOWN JUSTIFICATION CSV-ll I
\ ,)T l
System : Feedwater j Valve (s): 2- FW-FCV-24 7 8 2- FW-MOV-254A 2- FW- FCV-247 9 2-FW-MOV-254B i 2- FW- FCV-24 8 8 2- FW-MOV-2 54 C ;
2-FW-FCV-2 4 8 9 i 2- FW-FCV-2 4 98 2-FW-FCV-2499 i
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 l reactor trip. The main feedwater regulating valves 2-FW-FCV- .
2478, 2488 and 2498 move during normal operation as they perform )
(~'T their regulating function. In order to perform a partial stroke ]
(_s/ test during normal operation, the plant would have to reduce j power to cause the valve disks to move. Reducing power for the i 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 2-FW-FCV-2479, 2489 and 2499 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 2-FW-MOV-254A, 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.
l p)
\.
4-43
! N2PVI2R8 Revision 8 l
August 17, 1998
9 T l
.. COLD SHUTDOWN JUSTIFICATION CSV-12
. System .: Feedwater
- Valve (s):. 2-FW-62 l 2-FN L 2-FN-126 Category: C Class : 2 Function: Main Feedwater Supply Isolation Check Valves Cold Shutdown Justification These check valves must seat upon reversal of flow to' fulfill their safety functions. The only method to verify this actuation l
is to perform a back pressure test. Since the valves must be open to sustain power operation, they cannot be tested every three months.
Testing Frequency L These' check valves will be tested in the closed position every ,
cold shutdown but not more frequently than once every three l months.
l j
- l. 1 l
l I i "b
- l i
4-44 N2PVI2R8 Revision 8 August 17, 1998
/
r f
COLD SHUTDOWN JUSTIFICATION CSV-13 System : Main Steam Valve (s): 2-MS-NRV-201A 2-MS-NRV-201B 2-MS-NRV-201C Category: C Class : 2 Function: Main Steam Header Non-return Valves Cold Shutdown Justification l Valve Description The main steam non-return valves (.N RVs) 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 l
O piston and the whole assembly is free to move about 25 vertical inches within the valve body. cylinder. The disk measures 25.5 inches across and the disk and piston assembly weighs approximately 1,200 lbs. When the main steam system is not inservice, a motor operator is used to run the valve stem down l 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 l generator for any break location, even if one valve fails to close. For example, for a break upstream of the trip valve in l one line, the closure of either the non-return valve in that line l or the trip valves in the other lines prevents the blowdown of j the other steam generators.
Method of Testing i 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.
4-45 N2PVI2R8 Revision 8 August 17, 1998 I l
l
[ )
F r l
COLD SHUTDOWN JUSTIFICATION CSV-13 (Cont.)
(}
t 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 st'eam flow.
l l After the main steam trip valve is closed, the Valve Operation Test and Evaluation System (VOTES) can be used to determine the position of the disk of'the~NRV. After the main steam flow is stopped, the non-return valve stem is run down onto the disk after the disk returns to the seat. A change in 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 l travels to the seated disk with nominal changes in the running l 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 l 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 l running force. The test can be performed either at the valve by I 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 !
l l in the stem load which would indicate a stuck or binding valve disk. The second and more sensitive method monitors a single phase of the motor current. The motor current information is used to generate motor power and power factor signatures which are very sensitive to changes in stem load. Changes in motor load would again indicate a stuck or binding valve disk. In both ;
l 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 l course of stem travel. The second method is preferred.
l Testing Frequency Discussion y Full stroke or part stroke exercising of these valves during power operation would result in a turbine and reactor trip.
U 4-46 N2PVI2R8 Revision 8 August 17, 1998
/ COLD SHUTDOWN JUSTIFICATION CSV-13 (Cont.)
V)
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 i 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 that a valve has stuck in the partial open position. The piston-disk assembly is not attached to any other internal part, the 1,200 lb piston-disk assembly is maintained parallel within the valve body cylinder 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.
I J ,
i O 4-47 N2PVI2R8 Revision 8 l August 17, 1998
r l
L
/\ COLD SHUTDOWN JUST FICATION CSV-14 C/
System : Main Steam Valve (s): 2-MS-TV.209 Category: B Class : 2 Function: Main Steam High Pressure Drain to Condenser Isolation Valve Cold Shutdown Justification Full or part-stroke exercising this. valve during power operation would cause undesirable pressure transients in the High Pressure Secondary Drains System. Also, the valve controller does not allow for 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 This valve will be full stroke exercised every cold shutdown but not more frequently than once every three months.
l
~s f)
U 4-48 N2PVI2R8 Revision 8 August 17, 1998 t.
r lO COLD SHUTDOWN JUSTIFICATION CSV-15 Cold Shutdown Justification withdrawn l
l
- O l l
l 1
I i l
n i
O 4-49 N2PVI2R8 Revision 8 August 17, 1998
e k
COLD SHUTDOWN JUSTIFICATION CSV-16 System : Main Steam Valve (s) : 2-MS-TV.201A 2-MS-TV-201B 2-MS-TV-201C Category: B l: . Class : 2 l
Function: Main Steam Header Trip Valves Cold Shutdown Justification
, These valves are in positions required to sustain power L operation.- Ebll or part-stroke exercising these valves during i 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
i
\s-) These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
l l^
1 l
l l %
l l
l O 4-50 N2PVI2R8 Revision 8 August 17, 1998 1
1 i
i COLD SHUTDOWN JUSTIFICATION CSV-17 Replaced by Relief Request V-68 l
i I
O i
l l
~s O 4-51 N2PVI2R8 Revision 8 August 17, 1998
p 1
\
() COLD SHUTDOWN JUSTIFICATION CSV-18 System : Residual Heat Removal l Valve (s): 2-RH-MOV-2700 2-RH-MOV-2701 2-RH-MOV-2720A 2-RH-MOV-2720B Category: B Class : 'l Function: RHR Supply and Return Isolation Valves Cold Shutdown Justification These valves isolate the Residual Heat Removal System, which is a 600 lb class system, from the Reactor Coolant System during power l operation. These valves are normally closed and cannot be opened l when Reactor Coolant System pressure is above 418 psig due to l system interlocks.- Therefore, the valves cannot be full or part-stroke exercised during power operation. Also, the valve l[ controllers do not allow for a part-stroke exercise test.
l Testing Frequency l
These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
l l
i l
- s O 4-52 i N2PVI2R8 Revision 8 August 17, 1998 L
D 1 i
COLD SHUTDOWN JUSTIFICATION CSV-19
(}
Replaced by Relief Request V-75 COLD SHUTDOWN JUSTIFICATION CSV-20 Cold Shutdown Justification withdrawn COLD SHUTDOWN JUSTIFICATION CSV-21 Replaced by Relief Request V-68 i
COLD SHUTDOWN JUSTIFICATION CSV-22 Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-23 l
l Replaced by Relief Request V-35
!O i
i i
l l vs t
i 1
4-53 N2PVI2R8 Revision 8 August 17, 1998 L_
f-() COLD SHUTDOWN JUSTIFICATION CSV-24
' System : Safety Injection Valve (s):_ 2-SI-MOV-2865A 2-SI-MOV-2865B 2-SI-MOV-2865C
-Category: B Class : 2 Function: .I S Accumulator Discharge Isolation Valves Cold Shutdown Justification The Accumulator Discharge Isolation Valves are in their safety positions with power removed from the valve actuators during 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 O' 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.
n O 4-54 ,
N2PVI2R8- Revision 8 l August 17, 1998
o i
l l
I COLD SHUTDOWN JUSTIFICATION CSV-25 Cold Shutdown Justification Withdrawn 1
COLD SHUTDOWN JUSTIFICATION CSV-26 Cold Shutdown Justification Withdrawn l
( COLD SHUTDOWN JUSTIFICATION CSV-27 l
l Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-28
- Replaced by Relief Request V-37 i
COLD SHUTDOWN JUSTIFICATION CSV-29 l Replaced by Relief Request V-71 l
O 1
l O 4-55 N2PVI2R8 Revision 8 August 17, 1998 r
L
F.
l COLD SHUTDOWN' JUSTIFICATION CSV-30
}
. System : Auxiliary-Feedwater Valve (s): 2-FW-63 2-FW-97 2-FW-65 2-FW-127 Category: C Class : 3 Function: Auxiliary Fe'edwater 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 O- but not more frequently than once every three months.
n 4-56 N2PVI2R8 Revision 8 August 17, 1998
1 l
l I
COLD SHUTDOWN JUSTIFICATION CSV-31
)
System : Instrument Air l Valve (s): 2-IA-504 2-IA-531 2-IA-510 2-IA-537 2-IA-516 2-IA-543 2-IA-525 2-IA-549 Category: AC Class : NC i Function: Air Accumulator Isolation Check Valves Cold Shutdown Justification i
Check valves 2-IA-504, 510 and 516 isolate the normal instrument i air supply from the backup bottled air supply for the main steam !
pressure control valves 2-MS-PCV-201A, B and C. Valves 2-IA-525, 1 531 and 537 isolate the normal instrument air supply to the auxiliary feedwater valves 2-FW-HCV-200A, B and C. Valves 2-IA- l 543 and 549 isolate the normal instrument air supply to the l auxiliary feedwater valves 2-FW-PCV-259A and B. l
()N
\_ !
To back seat test check valves 2-IA-504, 510 and 516, the instrument air system must be isolated to all three main steam ,
pressure control valves and the lines vented. To back seat test l check valves 2-IA-525, 531, 537, 543 and 549, 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.
Testing Frequency These check valves will be tested in the closed position every cold shutdown but not more frequently than once every three months.
l O
V 4-57 N2PVI2R8 Revision 8 August 17, 1998
r 11 l
{' COLD SHUTDOWN JUSTIFICATION CSV-32 System : . Auxiliary Feedwater Valve (s) : 2-FW-HCV-200A 2- FW-HCV-2 00B 2-FW-HCV-200C
' Category: B
[ Class : 3 l
Function: Standby Auxiliary Feedwater Supply Valves l
Cold Shutdown Justification Stroke time is dependent on how quickly the operator can turn the l i
l
! knob to the potentiometer which controls valve position. Several l turns of the knob are necessary to full stroke the valve.
Isolating. instrument air and electrical power to the valve during i
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
/)
s/
because these valves must 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.
l l
l 9 !
l.
i
() 4-58 ;
N2PVI2R8 Revision 8 I August 17, 1998 L
p i
)
COLD SHUTDOWN JUSTIFICATION CSV-33 System.-: Auxiliary Feedwater i
l -Valve (s): 2-FW-PCV-259A i 2-FW-PCV-259B
-Category: B Class. : 3-Function: ' Auxiliary Feedwater Pressure Control Valves Cold Shutdown Justification
'During. normal operation, these valves control auxiliary feedwater-headerLpressure 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 l
I l
i
~s i O '4-59
- N2PVI2RB- Revision 8 August 17, 1998
?
l t
/~ COLD SHUTDOWN-JUSTIFICATION CSV-34 System : Main Steam Valve (s): 2-MS-TV.213A 2-MS-TV-213B 2-MS-TV-213C i
l . 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 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
/~N 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 5s 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 E
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 but not more frequently than once every three months.
l n
4-60
! N2PVI2R8 Revision 8
! August 17, 1998 L
["'j COLD SHUTDOWN JUSTIFICATION CSV-35
\ /
l System : Service Water Valve (s): 2-SW-MOV-201A 2-SW-MOV-205A 2-SW-MOV-201B 2-SW-MOV-205B 2-SW-MOV-201C 2-SW-MOV-205C 2-SW-MOV-201D 2-SW-MOV-205D Category: B Class : 3 Function: Recirculation Spray Heat Exchanger Service Water Supply and Discharge Isolation Valves Cold Shutdown Justification During normal operation, the lines between the Service Water supply and return header isolation valves given above and the recirculation heat exchanger isolation valves (2-SW-MOV-203A, B, C and D, and 2-SW-MOV-204A, B, C and D) are maintained dry to ensure that no service water enters the heat exchangers. Full or I
(~N' partially stroking the header isolation valves described above
\m / 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.
n i
Y*%
4-61 N2PVI2R8 Revision 8 August 17, 1998 l \
l
C's COLD SHUTDOWN JUSTIFICATION CSV-36 0
Replaced by Relief Request V-77 COLD SHUTDOWN JUSTIFICATION CSV-37 Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-38 Cold Shutdown Justification Withdrawn O 4-62 N2PVI2R8 Revision 8 August 17, 1998
i i
l' COLD SHUTDOWN JUSTIFICATION CSV-39 )
l l System : Chemical and Volume' Control l
l Valve (s): 2-CH-176.
2-CH-191 2-CH-206 2-CH-495 l
Category: C Class : 2-Function: Charging Pump Recirculation Line Check Valves Cold Shutdown Justification l These check valves must open to allow charging pump l recirculation. There is no permanently mounted instrumentation to measure full flow in the recirculation flow path. Therefore, full flow conditions will have to be measured by using temporary ultrasonic flow instrumentation. The ultrasonic flow transducers l and their mounting carriages must be installed and the l
transducers referenced to a no flow condition before each test.
After each test, the equipment must be removed from the. field and decontaminated if necessary. Therefore, use of the ultrasonic flow instrumentation is very labor intensive and not practical j for# quarterly testing.
Test experience has shown that the discharge pressure drop is undetectable when flow through the recirculation line is established in conjunction with normal charging. Therefore, l 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 l .,
I l
l l
4-63 N2PVI2R8 Revision 8 August 17, 1998
I"
-( COLD SHUTDOWN JUSTIFICATION CSV-40
)
System : Auxiliary Feedwater Valve (s): 2- FN- 0 64 2-FW-157 2-FW-066 2-FW-173~
2-FW-096 2- FW-17 4 2- FW-098 2-FW-193 2-FW-128 2- FW-194 2-FW-130- 2-FW-317 -
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 O positioned to provide these dedicated flow paths. During a main feed line break or steam line break, no credit is taken for operator action during 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 pumps are realigned using the manual valves. Therefore, the manual valves must be known to be operable.
However, exercising the valves during normal operation would
! violate the technical specifications and reduce plant safety without a corresponding increase in component reliability. These valves remain in their aligned positions during normal operation and~are not subject to wear. Exercising the valves during each ,
cold shutdown is adequate to demonstrate that these valves can be l l manipulated in case the auxiliary feedwater paths need to be ,
L changed. !
Testing Frequency .,
l These valves will be full stroke exercised every cold shutdown !
but~not more frequently than once every three months.
N2PVI2R8 Revision 8 August 17, 1998
COLD SHUTDOWN JUSTIFICATION CSV-41 O]
\_
System : Auxiliary Feedwater Valve (s): 2- FW- 14 7. 2- FW-182 2-FW-164 2-FW-202 Category: B Class : 3 Function: Auxiliary Feedwater Pump Alternate Supply Manual Valves Cold Shutdown Justification These normally locked closed manual valves are opened as required by the abnormal operating procedures to provide service water to the auxiliary feedwater pumps in the event of an accident where all normal auxiliary feedwater pump supplies have been exhausted.
Opening these valves every three months to fulfill quarterly testing requirements would accelerate the buildup of sludge in
/}
'ws' 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 but not more frequently than once every three months.
I l
O) 4-65 N2PVI2R8 Revision 8
, August 17, 1998 l
mi
~)
l
[~'N COLD SHUTDOWN JUSTIFICATION CSV-42 b
l System : Reactor Coolant i
Valve (s) : 2-RC-PCV-2455C 2-RC-PCV-2456 I
Category: BC Class : 1 Function: Pressurizer Power Operated Pressure Control Valves 1
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 !
l this differential pressure, cycling would eventually degrade the j l block valves seating capability, thus decreasing plant safety. l l Also, the valve controllers do not allow for a part-stroke i i exercise test.
l
[)
V' Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
i l
t
(
%.J 4-66 N2PVI2R8 Revision 8 August 17, 1998
r-l
( COLD SHUTDOWN JUSTIFICATION CSV-43
\
System : Service Water Valve (s) : 2-SW-MOV-208A 2-SW-MOV-20SB Category: B Class : 3 i
Function: Component Cooling Heat Exchanger Service Water Supply )
Isolation Valves Cold Shutdown Justification I 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 flow decreases through a range from 7000 gpm to 6000 gpm. These
(S
(_jl 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.
l 4-67 N2PVI2R8 Revision 8 August 17, 1998
1
()
(/
COLD SHUTDOWN JUSTIFICATION CSV-44 System : Quench Spray )
Valve (s) : 2-OS-MOV-202A 2-OS-MOV-202B Category: B Class : 2 Function: Chemical Addition 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.
)
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 l 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.
1
/T V 4-68 N2PVI2R8 Revision 8 August 17, 1998
1
[ ,
COLD SHUTDOWN JUSTIFICATION CSV-44 (Cont.)
Testing Frequency These valves will be full stroke exercised on a cold shutdown frequency but not more frequently'than once every three months.
o)
(
)
4-69 N2PVI2R8 Revision 8 August 17, 1998 i
i COLD' SHUTDOWN JUSTIFICATION CSV-45
(}
System : Residual Heat Removal Valve (s): 2-RH-7 2-RH-15 Category: C Class : 2 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 RHR pumps 2-RH-P-1A and 2-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.
C_s Testing Frequency I c
These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.
y i
I O 4-70 N2PVI2R8 Revision 8 August 17, 1998
COLD SHUTDOWN JUSTIFICATION CSV-46 Replaced by Reactor Refueling Justification RRV-27 i
l O
i l
s O 4-71 N2PVI2R8 Revision 8 August 17, 1998
COLD SHUTDOWN JUSTIFICATION CSV-47
(}
System : Chemical & Volume Control Valve (s): 2-CH-MOV-2380 2-CH-MOV-2381
. 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 at all times while the pumps are in operation. Failure of one of these valves in the closed position could result in damage to the reactor coolant pump seal, thus placing the plant in an unsafe condition. Also, the valve controllers do not allow for a part-stroke exercise test. The reactor coolant pumps must be secured and reactor coolant pressure must be above 100 psig to perform the -
.Q D
exercise tests.
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.
J' i
I O 4-72 N2PVI2R8 Revision 8 l
August 17, 1998 i
. 1 l
~
P l.
COLD SHUTDOWN JUSTIFICATION CSV-48 System : Reactor Coolant
. Valve (s): 2-RC-SOV-201A-1 2-RC-SOV-201A-2 2-RC-SOV-201B-1 2-RC-SOV-201B-2 Class : 1 Function: Reactor Vessel Vent Line Isolation Valves Cold Shutdown Justification l
These valves are the Reactor Vessel Head Vent Valves. Full or part-stroke exercising these valves at power could release l reactor coolant into the reactor vessel refueling cavity.
l 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 O boundary. However, these valves should not be stroked while the Reactor Coolent System is pressurized. These valves will be exercised during each cold shutdown when the Reactor Coolant System is depressurized. 1 1
Testing Frequency Exercise for operability during cold shutdown when the Reactor Coolant System is depressurized but not more frequently than once per three months. I l
,, 3 4-73 N2PVI2R8 Revision 8 August 17, 1998
4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the 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.
l l
t 0
l I
t i +
O 4-74 N2PVI2R8 Revision 8 August 17, 1998 J
4
REACTOR REFUELING JUSTIFICATION RRV-1 System : Component Cooling Valve (s): 2-CC-78 2-CC-115 2-CC-152 Category: C Class : 2 Function: CC Supply to Reactor Coolant Pump Containment Isolation Check Valve l 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 refueling outages because the small increase in safety gained by O' 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.
l n
4-75 N2PVI2R8 Revision 8 August 17, 1998
1
[]
V REACTOR REFUELING JUSTIFICATION RRV-2 System : Chemical & Volume Control 1
Valve (s): 2-CH-260. 2-CH-308 2-CH-332 }
2-CH-284 2-CH-331 2-CH-335 I I
Category: AC for 2-CH-331, 332 and 335 C for 2-CH-260, 284 and 308 Class : 1 for 2-CH-260, 284, 308 and 332 2 for 2-CH-331 and 335 Function: Charging Supply Inside Containment Isolation Check Valves (2-CH-332, 335), RC Pump Seal Water Supply Isolation Check valves (2-CH-260, 284 and 308), and RC Pump Seal Water Return Containment Isolation Check Valve (2-CH-331)
Reactor Refueling Justification These check valves must seat upon reversal of flow in order to j fulfill their safety functions. The only method to verify this
/~N 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. 2-CH-335 is in the normal charging line to the RCS.
-These lines cannot be drained during short cold shutdowns because charging flow is often maintained. 2-CH-260, 284, and 308 are in the RCP seal water supply lines, and 2-CH-331 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. 2-CH-332 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 2-CH-332.
The valves will be exercised only during refueling outages because the small increase in safety gained by testing during cold shutdown does not justify the burden of draining lines and performing leak rate tests.
n Testing Frequency Exercise for operability each reactor refueling.
l0 v 4-76 N2PVI2R8 Revision 8 August 17, 1998 i
c.
l REACTOR REFUELING JUSTIFICATION RRV-3 i ' System :. Fire Protection Valve (s): 2-FP-79 i
! Category: AC l
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 fulfill its safety function. The only method to verify this actuation is to perform a leak rate /back pressure test. Since the l valve is located inside containment, it cannot be tested every
! three months. 2-FP-79 i;s in the containment fire protection system. Testing this valve will render the fire protection system i inoperable. It will be exercised only during refueling outages l because the small increase in safety gained by testing during cold O 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."
i Testing Frequency l
l Exercise for operability each reactor refueling.
l l
t l
n
(~%
U 4-77 N2PVI2R8 Revision 8 August 17, 1998
(O REACTOR REFUELING JUSTIFICATION RRV-4 O
l System : Post Accident Hydrogen. Removal l Valve (s) : 2-CV-8 2-HC-15 2-CV-15 2-HC-20
)
Category: AC for 2-HC-15 and 20 C for 2-CV-8 and 15 l l
Class : 2 l Class : 2 4 Function: Containment Vacuum System Isolation Check Valves and ;
Hydrogen Analyzer /Recombiner Containment Isolation Check Valves Reactor Refueling Justification Check valves.2-CV-8 and 15, 2-HC-15 and 20 must open to sample hydrogen to fulfill their safety functions. To test valves 2-HC-15 and 20 either partially or full open, and to test valves 2-CV-8
('_N and 15 full open requires a significant manipulation of the
(-) hydrogen recombiner system. In addition, should a containment !
pressurization event occur while operating the hydrogen ,
recombiners, there is a possibility of exceeding the design l pressure of the recombiner system, which may result in a loss of j recombiner function. The hydrogen recombiner is a low pressure system intended for use after the containment depressurizes.
Valves 2-CV-8 and 15 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 frequent basis.
l Check valves 2-HC-15 and 20 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 verify closure is to perform a leakage /back pressure test.
I
(~'#
\'s 4-78 l N2PVI2R8 Revision 8 August 17, 1998 L
l l
REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)
d l
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 2-HC-15 and 20 will be exercised to the closed position every reactor refueling. Check valves 2-CV-8 and 15, 2-HC-15 and 20 will be exercised to the full open position at least once every 18 months. Valves 2-CV-8 and 15 will be exercised to the partially open position once every three months.
( )
~
4-79 N2PVI2R8 Revision 8 August 17, 1998
r; i-
!~' REACTOR REFUELING JUSTIFICATION RRV-5 System : Instrument Air Valve (s): 2-IA-250.
, 2-IA-428 .
l Category: AC l
l Class : 2 i-Function: Instrument Air Supply Containment Isolation Check Valves
- Reactor Refueling Justification These check valves must seat upon reversal ~of flow in order to i 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 2-IA-250 is in the instrument air supply line to containment. Testing this valve renders the instruments and
, components supplied by instrument air inside containment inoperable.
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 of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing."
Testing Frequency Exercise for operability each reactor refueling.
t )
l 0 4-80 !
N2PVI2R8 Revision 8 Rugust 17, 1998 ;
REACTOR REFUELING JUSTIFICATION RRV l System : Reactor Coolant l
l l . Valve (s) : 2-RC-162 Category: AC l
Class : 2 l Function: Primary Grade Water Supply Containment Isolation Check Valves Reactor Refueling JustificatiGn 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. 2-RC-162 is in the primary grade water to pressurizer l relief tank and the #2 seal stand pipes. This line cannot be drained during short cold shutdowns because the PRT is required l during normal cold shutdowns. Standpipe level must be maintained when the'RCS is pressurized to control leakage. The valve will be' exercised only during refueling. outages because the small increase in safety gained by testing during cold shutdown does I 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. ->
4-81 N2PVI2R8 Revision 8 August 17, 1998
[T u
l-l -' O W REACTOR REFUELING JUSTIFICATION RRV-7 System . : Safety Injection Valve (s): 2-SI-MOV-2836 2-SI-MOV-2869A 2-SI-MOV-2869B 2-SI-MOV-2890A l
2-SI-MOV-2890B Category: A.
Class : 2 Function: High Head (2-SI-MOV-2836, 2869A and B) and Low Head (2-SI-MOV-2890 A and B) SI to RCS Containment g Isolation Valves Reactor Refueling 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 l .
the valve actuators during Modes 1, 2, and 3. Full or part-stroke exercising these valves during power operation would be in l violation of Technical Specifications. Also, the valve '
! controllers do not allow for a part-stroke exercise test.
l l
l Technical Specification 4.4.6.2.2 requires that these valves be ;
leak tested following valve actuation. 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.
Testing Frequency Exercise for operability each reactor refueling.
1 O 4-82 N2PVI2R8 Revision 8 August 17, 1998 L
REACTOR REFUELING JUSTIFICATION RRV-8 Na System : Safety Injection Valve (s) : 2-SI-MOV-2867C 2-SI-MOV-2867D 2-SI-MOV-2890C 2-SI-MOV-2890D Category: A Class : 2 Function: Boron Injecrtion Tank Discharge Line to RCS Cool Legs (2-SI-MOV-2867C and D), and Low Head SI Discharge to RCS Cool Legs (2-SI-MOV-2890C and D) Containment Isolation Valves Reactor Refueling Justification Technical Specification 4.4.6.2.2 requires that these valves be leak tested following valve actuation. 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
, ()x
%_ of performing leak rate terts.
Testing Frequency Exercise for operability each reactor refueling.
l n
(
{
n U 4-83
( N2PVI2R8 Revision 8 l
August 17, 1998
[
i
I 3
[g- REACTOR REFUELING JUSTIFICATION RRV-9
-System : Safety Injection Valve (s): 2-SI-9 2-SI-19 2-SI-32 Category: C Class : 2 Function: Low Head SI Pump Discharge Check Valves Reactor Refueling Justification Due to system design, check valves 2-SI-9 and 32 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 2-SI-19 can only be partial stroked every quarter because the quarterly test loop is a mini-flow loop.
i During cold shutdown, the reactor coolant system pressure still )
prevents full flow testing of the check valves. Partial stroke
]
exercising the valves with flow could cause an overpressurization !
condition during cold shutdowns, i To verify closure of Valves 2-SI-9 and 32, 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 l established to demonstrate adequate seat tightness for the discharge valve to the non-running pump.
Testing Frequency j Valves 2-SI-9 and 32 will be exercised to the full open and closed position every reactor refueling. Valve 2-SI-19 will be l partial stroke tested every quarter and full flow tested every 4 reactor refueling.
u 4-84 N2PVI2R8 Revision 8 ;
August 17, 1998 L.
r REACTOR REFUELING JUSTIFICATION RRV-10 System .:. Safety Injection Valve (s): 2-SI-18 1
Category: AC Class : 2
! 1 l Function: RWST Supply to Charging Pump Suction Header Check l . Valves Reactor Refueling Justification Full or part-stroke axercising 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 flow for the charging system can only be established during reactor refueling when the RCS is depressurized. j
! To verify valve closure, the refueling water storage tank must be
("'\ isolated which is a violation of Technical Specification 3.1.2.1.b during normal operation.
The only method to verify closure other than disassembly and inspection is to perform a leak rate /back pressure test. This l valve is also subject to lesk testing, which is performed every ;
reactor refueling. Verification of closure will be performed l during the leak test every reactor refueling instead of every 1
- cold shutdown because the small increase in safety gained by l 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."
l Testing Frequency l
l Exercise to the partially open position during' cold shutdown, exercise to the full open and closed positions every reactor refueling.
O b 4-85 N2PVI2R8 Revision 8 August 17, 1998
I }
L )
l l
O REACTOR REFUELING JUSTIFICATION RRV-11 System :- Safety Injection Valve (s): 2-SI-132 l
2-SI-136 Category: AC l
Class : 2 Function: Nitrogen Supply to Accumulators Containment Isolation Check Valves l
Reactor Refueling Justification i
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 i valves are located inside containment, they cannot be tested every three months. .These valves will be exercised only during l refueling outages.because the-small increase in safety gained by ,
testing during cold shutdown does not justify the burden of I
, performing a leak rate test. This technical basis is consistent l( with the NRC position on this subject that is described in NUREG-l 1482, Section 4.1.4, entitled " Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak l l
Testing."
1 1 Testing Frequency Exercise for operability every reactor refueling.
l l
?
i O
V 4-86 N2PVI2R8 Revision 8 August 17, 1998
l l
l l
l REACTOR REFUELING JUSTIFICATION RRV-12 1
System : Safety Injection Valve (s):
2-SI-91 2-SI-100 2-SI-92 2-SI-105 2-SI-99 2-SI-106 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.
/~ ' During cold shutdown, the Reactor Coolant System pressure still prevents full design flow. Also, a partial or full stroke test could cause an overpressurization of the Reactor Coolant System and force a safety system to function.
These valves can only be tested to the closed position by i 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 i nonintrusively monitored using a sampling plan every reactor l refueling as described in Relief Request V-41.
l 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.
4-87 N2PVI2R8 Revision 8 August 17, 1998 f
1 L
i i
[]
V REACTOR REFUELING JUSTIFICATION RRV-13 System : Safety Injection Valve (s): 2-SI-151 2-SI-170 l 2-SI-153 2-SI-185 2-SI-168 2-SI-187 ;
I Category: C Class : 1 Function: SI Accumulator Discharge Check Valves Reactor Refueling Justification I
These valves cannot be partial or full flow tested during normal !
operation because the accumulator pressure (600 to 650 psig) is ;
below Peactor Coolant System pressure and the injection of borated water would upset the reactor coolant chemistry.
l During cold shutdown, the RCS pressure may still prevent full )
flow testing. Also, discharging the accumulators would challenge
) the Low Temperature Overpressure Protection System.
(~^J L
A partial flow test is not practical during cold shutdowns. The flov from the accumulator is dependent on the pressure differential between the accumulator and che RCS. The pressure differential cannot be controlled to the fine degree necessary to preclude dumping too much water into the pressurizer, thus making it difficult to control pressurizer level while pressure is being reduced during cooldown. Also, the RCS temperature is high during short cold shutdowns. 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 2-SI-153, 170 and 187. The small increase in 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-43.
g I 4 LJ _
N2PVI2R8 Revision 8 August 17, 1998 1
i
i REACTOR REFUELING JUSTIFICATION..RRV-13 (Cont.)
!- Testing' Frequency i
Exercise to the open position using nonintrusive techniques'every l
reactor refueling. Valves 2-SI-153, 170 and 187 will be confirmed closed every reactor refueling. l l
i L
l I
lO 1
l O 4-89 N2PVI2R8 Revision 8 August 17, 1998 t ..
r i
l I
l O
J REACTOR REFUELING JUSTIFICATION RRV-14 i
System -: Safety Injection Valve (s): 2-SI-85 2-SI-117 2-SI-126 2-SI-93 2-SI-118 2-SI-128 2-SI-107 2-SI-119 2-SI-112 2-SI-124 2-SI-113- 2-SI-125 Category: AC for 2-SI-85, 93, 107, 119, 126 and 128 C for 2-SI-112, 113, 117, 118, 124 and 125 Class : 1 for 2-SI-107, 112, 113, 117, 118, 119, 124 and 125 2 for 2-SI-85, 93, 126, 128 Function: High Head SI to RCS Cold Legs Check Valves (2-SI-85 and 93), High Head SI to RCS Hot Legs Check Valves (2-SI-107 and 119), SI to RCS Hot Legs Check Valves (2-SI-113, 118 and 125), Low Head to RCS Hot Legs Check Valves (2-SI-112, 117, 124, 126 and 128)
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 and cause unnecessary plant transients. Flow cannot be established in the low head injection lines during normal plant operation.
During cold shutdown, the Reactor Coolant System pressure still prevents full design flow. Also, a partial or full stroke test could cause an overpressurization of the Reactor Coolant System
'and force a safety system to function.
These valves 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 2-SI-112, 113, 117, 118, 124 and 125 will be nonintrusively :
monitored using a sampling plan every reactor refueling as !
described in Relief Request V-45. The remaining check valves can '
be full flow tested using installed instrumentation. ,
(~% l
\_) 4-90
\
N2PVI2R8 Revision 8 August 17, 1998
REACTOR REFUELING JUSTIFICATION RRV-14 (Cont.)
Testing Frequency Exercise valves 2-SI-85,-93, 107, 119, 126 and 128 to the open position using flow every reactor' refueling. Exercise valves 2-l SI-112, 113, 117, 118, 124 and 125 to the open position using nonintrusive techniques every reactor refueling. Exercise each valve to the closed position every reactor refueling.
v O i l
i 4-91 N2PVI2R8 Revision 8 August 17, 1998
(^j REACTOR REFUELING JUSTIFICATION RRV-15 G'
System : Safety Injection Valve (s) : 2-SI-90
]
2-SI-98 '
2-51-104 4
Category: C Class : 1 Function: High Head SI to RCS Cold Legs Check Valves ,
i Reactor Refueling Justification i 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 i because this would thermally shock the injection system and cause '
unnecessary plant transients.
During cold shutdown, the Reactor Coolant System pressure still
('~T 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.
,. ~
4-92 N2PVI2R8 Revision 8 August 17, 1998
O REACTOR REFUELING JUSTIFICATION RRV-16 System : Service Water Valve (s): 2-SW-68 2-SW-94 2-SW-70 2-SW-104 2-SW-74 2-SW-84 Category: C Class : 2 for 2-SW-74, 84, 94, 104 3 for 2-SW-68, 70 Function: Recirculation Spray Heat Exchanger Service Water Supply Check Valves j
Reactor Refueling Justification Full or part-stroke exercising these valves would flow Service Water into the Recirculation Spray Heat Exchangers. Per FSAR Section 6.2.2.2.5, in order to ensure long term reliability of the heat exchangers, following each periodic test the heat
(N exchangers are drained, purged with air and maintained in dry
\s l 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 operability every reactor refueling.
/
4-93 N2PVI2R8 Revision 8 August 17, 1998 c . ..
REACTOR REFUELING JUSTIFICATION RRV-17 System : Vacuum Priming Valve (s): 2-VP-24 Category: AC
' Class : 2 Punction: 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 O- " Extension of Test' Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing."
Testing Frequency i Exercise for operability every reactor refueling.
i I
l I
b I
O 4-94 N2PVI2R8 Revision 8 August 17, 1998 L
1 l
REACTOR REFUELING JUSTIFICATION RRV-18 System : CH Valve (s): 2-CH-178 2-CH-193 2-CH-208 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.
(J)
Testing Frequency Exercise closed every three months and exercise full open every
- reactor refueling. Valves are partial exercised open during l normal operation when the charging train is in service.
l i
i l
l 1
/"' ,
ks _)s ' I 4-95 N2PVI2R8 Revision 8 August 17, 1998 i t.
o
_ REACTOR REFUELING JUSTIFICATION RRV-19
~ System : SI Valve (s): 2-SI-6 2-SI-29 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.
i i
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 l 1s consistent with the NRC position on this subject that is ;
described in NUREG-1482, Section 4.1.4, entitled " Extension of l Test Interval to Refueling Outage for Check Valves Verified f Closed by Leak Testing." .
4-96 N2PVI2R8 Revision 8 August 17, 1998 l
l
'J i-
' REACTOR REFUELING JUSTIFICATION RRV-19 (Cont.)
. Testing Frequency Exercise'to the closed position every reactor refueling.
1 1
O l-O 4-97 N2PVI2R8 Revision 8 August 17, 1998 i
i l
REACTOR REFUELING JUSTIFICATION RRV-20 System- : Component Cooling Valve (s) : 2-CC-276.
2-CC-289 2-CC-302 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 involve isolating the containment air cooling coils. The containment recirculation air cooling coils are required for normal operation to maintain containment
/~
temperature below technical specification limits. Therefore, 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 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."
i Testing Frequency l
l Exercise to the closed position every reactor gefueling.
t O 4-98 ,
N2PVI2R8 Revision 8 !
I August 17, 1998 l
l' l
1 1
REACTOR REFUELING JUSTIFICATION RRV-21 4
System .: Service Water Valve (s): 2-SW-3 2-SW-10 Category: C Class : 3 Function: Service Water Pump Discharge Check Valves Reactor Refueling Justification These check valves cannot be full flow tested during normal operation or cold shutdown because the Recirculation Spray Heat Exchangers must be included in the flow path in order for full flow conditions to be established. As described in Reactor Refueling Justification RRV-16, introduction of service water to the Recirculation Spray Heat Exchangers is prohibited without subsequently draining the heat exchangers. This requirement makes testing during normal operation or cold shutdowns
)
(V impractical.
Monitoring the discharge pressure gauge of the non-running pump would reveal gross failure of the check valve. However, this ;
test may not detect leakage past the valve due to a partially stuck open disk. The service water pumps are deep draft pumps with enough tolerance between the impellers and the pump casing to pass significant flow without pressurizing the discharge piping to a detectable degree.
The verification of full disk closure using back flow can only be performed when design flow is achieved during the service water pump tests. Verification of design flow for the running pump demonstrates adequate back seating for the discharge check valves of the non-running pumps. However, the observation of the non-running pump discharge gauge to detect gross failure can and should be performed every three months. ,
Testing Frequency 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.
l 4_gg N2PVI2R8 Revision 8 August 17, 1998
(3 REACTOR REFUELING JUSTIFICATION RRV-22 LJ' System : Component Cooling Valve (s): 2-CC-107.
2-CC-144 2-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.
( \
V Testing Frequency Exercise to the closed position every reactor refueling.
l s*%
'~'
4-100 N2PVI2R8 Revision 8 August 17, 1998
W L
l l
l l
REACTOR REFUELING JUSTIFICATION RRV-23 System : Recirculation Spray Valve (s): 2-RS 2-OS-11 2-RS-30 2-OS-22 Category: AC Class : 2 l
' Function: Quench Spray'and Outside Recirculation Spray l 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 l and saturate containment. These valves can be mechanically l exercised to the open and closed positions. However, the valves are located inside containment and require the construction of
- scaffolding before they can be exercised. The small increase in O safety gained by exercising the valves during cold shutdown does not_ justify the burden of constructing the scaffolding.
These valves are also' subject to leak testing, which is performed l 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 i leak test every refueling outage is an alternative that provides l an acceptable level of quality and safety. This technical basis l is consistent with the NRC position on this subject that is
! described in NUREG-1482., Section 4.1.4, entitled " Extension of i Test Interval to Refueling Outage for Check Valves Verified i Closed.by Leak Testing."
l Testing Frequency These valves will be exercised to the open and, closed positions every reactor refueling.
l 1
4-101' N2PVI2R8 Revision 8 i August 17, 1998
IL I
p REACTOR REFUELING JUSTIFICATION RRV-24 l
System _ : Component Cooling Valve (s) : 2-CC-194.
2-CC-199 l
l Category: AC Class : 2 Function: CC Water Supply to the RHR Heat Exchangers Containment l- Isolation Check Valves Reactor Refueling Justification These check valves are in the component cooling lines to the RHR heat exchangers and must close for isolation and open to allow l
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.
l O To establish full flow through the valves 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 l
by reducing the RCS temperature.. This reduction in volume can be l large enough as to cause excessive makeup demands to the RCS.
l Therefore, the full flow test should be performed during reactor refueling when the vessel is defueled. The vessel is defueled every refueling outage.
l l Testing Frequency Exercise for closure and full open every reactor refueling.
Partial stroke open every quarter.
l l
O 4-102
{ N2PVI2R8 Revision 8 August 17, 1998
n -
l REACTOR REFUELING JUSTIFICATION RRV-25 V('
System : Chemical & Volume Control System Valve (s) : 2-CH-153.
2-CH-495 Category: AC l
Class : 2 Function: Charging Pump Supply from the VCT (2-CH-153) and Charging Pump Recirculation and Seal Water Return (2-CH-495) Containment Isolation Check Valves 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 leak rate /back pressure test on each valve.
During normal operation, these valves cannot be isolated to O perform a back pressure test because normal letdown and charging flow, and reactor coolant pump seal flow would be interrupted.
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 refueling. A leak test provides more information I
concerning the condition of the valve seats then just a back
- pressure test. When compared to the Code requirements for a i backseat test performed every cold shutdown, the performance of a l 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."
Testing Frequency y Exercise to'the closed position every reactor refueling.
m 4-103 N2PVI2R8 Revision 8 August 17, 1998
r .-
REACTOR REFUELING JUSTIFICATION RRV-26 System : Service Water Valve (s): 2-SW-24.
Category: C 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.
{
l Testing Frequency l( }
This valve will be disassembled and inspected on a reactor refueling test frequency and partial flow tested every three months. i i
t
/"'T (g
4-104 N2PVI2R8 Revision 8 August 17, 1998
E 1 l
l l
[VD REACTOR REFUELING JUSTIFICATION RRV-27 System : Safety Injection Valve (s) : 2-SI-MOV-2867A 2-SI-MOV-2867B 2-SI-70 Category: B (2-SI-MOV-2867A and B)
C (2-SI-70)
Class : 2-Function: Boron Injection Tank Inlet Isolation valves (2-SI-MOV-2867A and B) and Boric Acid Recirculation Line Check Valve (2-SI-70)
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 2-SI-MOV-2867A and B and the outlet isolation valves 2-SI-MOV-2867C and D. These valves open upon
/' safety injection initiation. As shown in Figure RRV-25, the ,
i inlet valves are located on parallel paths. The normal operating pressure just upstream of the isolation valves is between 2600 and 2650 psig which is the discharge pressure of the charging pumps. The downstream pressure is approximately 40 psig. The reason for this low pressure is that the BIT boric acid solution is constantly circulated by the relatively low pressure boric acid transfer pumps. l I
Tests have revealed that when either 2-SI-MOV-2867A or B is l 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 I 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 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.
4-105 N2PVI2R8 Revision 8 August 17, 1998
r-1
(~ T REACTOR REFUELING JUSTIFICATION RRV-27 (Cont.)
LJ l
In the past, the BIT volume was pressurized slowly by manually cracking one of the inlet isolation valves, thus avoiding the 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." l 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 valves with a l 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 the charging system is secured.
In the past, the BIT recirculation line isolation check valve 2-SI-70 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 of the inlet isolation valves and manually cracking the valve open so as to slowly pressurized the BIT. However, this method of testing disables the BIT inlet 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 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 equipment is adequate justification to defer back flow testing of a check valve until a refueling outage."
Testing Frequency ,
The BIT inlet isolation valves will be full stroke exercised and the BIT recirculation line check valve will be backseat tested every reactor refueling.
p b 4-106 N2PVI2R8 Revision 8 August 17, 1998
7 REACTOR REFUELING JUSTIFICATION RRV-27 (Cont.)
(Y x x 2*av assra dok1 1 "o"%
K 2-88-MOV-2867D TO RCs 2-CSMOV-2289A 2OW-2867C 24h<aOV-22698 m
RC'S 2-St-MOV-20678 w t- -
2 OV-2867A 2<,*MOV-2206A 2N-2m FRN BOR 244Wov-2287A b\_
"uT5^E.
2-CnHCV 2186
."c, =
n RCP SEAL 2 CHA1A FIGURE RRV-27
)
l
' Is 1
i O
4-107 N2PVI2R8 Revision 8 August 17, 1998 l
E 4.8 ALTERNATIVE TESTING FOR NON-CODE 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 o.f components covered by the Code. For other components important to' safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a
' request for relief' to be submitted to the staff.
Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.
North Anna Power Station has elected to include certain non-Code components in the ASME IST program. Where the Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability. The alternate testing is described in this section. There may be other deviations from Code provisions that are not described in this section. For these cases, documentation is available at the plant site.
As indicated in the minutes of public meeting on Generic Letter 89-04, a ' request for relief' need not be submitted for non-Code components. Therefore, the alternative tests described in this section are not
' requests for relief' but are provided for information.
O 4-108 N2PVI2R8 Revision 8 August 17, 1998
c i-I NON-CODE ALTERNATIVE TESTING VNC-1 System : Service Air Valve (s): 2-GN-101. 2-IA-2130 L 2-GN-102' 2-IA-2131 i 2-IA-2132 l 2-IA-2133 Category: AC Class : NC Function: ' Bottled Air System Supply to PORV Isolation Check Valves i OM Part 10 Code Requirements Which Will Not Be Met l 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 obturat6r travel to the closed, full-open or partially open position required to fulfill its function.
Basis For Alternate Testing 4 L Valves 2-IA-2130 and 2131 are in series and valves 2-IA-2132 and 2133 are in series. There are no vents in between the two sets of valves; therefore,.these valves cannot be individually back
( pressure tested or. leak tested. l
[ l Reactor Refueling Justification l Due to1the plant configuration, these valves cannot be verified closed using flow.
6 1
- 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.
l 4-109 N2PVI2R8 Revision 8 August 17, 1998 L:
[ NON-CODE ALTERNATIVE TESTING VNC-1 These valves are also subject to leak testing, which is performed every teactor-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.
l Alternate Testing proposed Valves 2-IA-2130 and 2131, and valves 2-IA-2132 and 2133 will be back pressure / leak tested in groups. If the group of valves
- l. fails the test, both valves in the group will be subject to repair or replacement.
The leak test for valves 2-IA-2130, 2131, 2132 and 2133, and 2-GN-101 and 102 will consist of recording the nitrogen bottle i pressure, waiting a given period of time and then recording the l bottle pressure again. The results will be compared to j appropriate acceptance criteria.
Testing Frequency Exercise to the closed position every reactor refueling.
t O
lU N2PVI2R8 4-110 Revision 8 August 17, 1998
r l
NON-CODE ALTERNATIVE TESTING VNC-2
. System : Instrument Air i Valve (s): . 2-IA-396 l 2-IA-397 l 2-IA-405 l 2-IA-406 Category: AC l
Class : NC l
Function: Safeguard Area Fans Air Receiver Isolation Check Valves OM Part 10 Code Requirements Which Will Not Be Met i
OM Part 10, Section 4.3.2.2 (b) - During plant operation, each check valve shall be exercised or examined in a manner which i verifies obturator travel to the closed, full-open or partially-open position required to fulfill its function.
() Basis For Alternate Testing Back seating these valves requires that the lines upstream of the valves be vented. The 2-IA-396 and-397 valves are in series with !
no vent valves in between, as are 2-IA-405 and 406. Therefore, i there is'no way to individually leak test or back seat these valves.
l 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
-disassembled, inspected and repaired if necessary. ;
i O 4-111 ,
N2PVI2R8 Revision 8 August 17, 1998
DO NON-CODE ALTERNATIVE TESTING VNC-3 System : Instrument Air Valve (s): 2-IA-504 '2-IA-531 2-IA-510 2-IA-537 2-IA-516 2-IA-543 2-IA-525 2-IA-549 Category: AC Class : NC Function: Main Steam Pressure Control and Auxiliary Feedwater Valves Air Accumulators Isolation Check Valves OM 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.
Basis For Alternate Testing
{}
l Check valves 2-IA-504, 510 and 516 isolate the normal instrument air supply from the backup bottled air supply for the main steam pressure control valves 2-MS-PCV-201A, B and C. Valves 2-IA-525, 531 and 537 isolate the normal instrument air supply to the auxiliary feedwater valves 2-FW-HCV-200A, B and C. Valves 2-IA-543 and 549 isolate the normal instrument air supply to the !
auxiliary feedwater valves 2-FW-PCV-259A and B. l The purpose of the bottled air supplies is to ensure that the 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 l
of times over a predetermined period in order to meet their i design requirements. In lieu of a leakage test for the isolation i check valves given above, the main valves will be cycled the required number of times over the required period with the normal air. supply isolated and vented. This test provides verification that the isolation" check valves are leak tight enough to allow
! the main valves to perform their safety functions.
l 4-112 N2PVI2R8 Revision 8 August 17, 1998
..~
l NON-CODE ALTERNATIVE TESTING VNC-3 (Cont.)
' Alternate Testing proposed 1
l' '
l In lieu of a leakage test forfthe isolation check valves given l 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.
l l
1 fO l
l
?
I 1
I l
l s
I i
l 4-113 l N2PVI2R8 Revision 8 August 17, 1998 lj l
E l
l
, l NON-CODE ALTERNATIVE TESTING VNC-4 System : Emergency Diesel Air Services i Valve (s): 2-EG-SOV-700HA 2-EG-SOV-700JA 2-EB-15 2-EG-SOV-701HA 2-EG-SOV-707JA 2-EB-34 2-EG-SOV-700HB 2-EG-SOV-700JB 2-EB-61
, 2-EB-78 Category: B for 2-EG-SOV-600HA, HB, JA and JB and 601HA and 607JA C for.2-EB-15, 34, 61 and 78 Class : NC Function: Diesel Air Receiver Tank Discharge Check Valves and
- Diesel Air Start Solenoid Valves OM Part 10 Code Requirements i
~Which Will Not Be Met OM Part 10, Section 4.2.1.4 (b) - The stroke time of all power-
- operated valves shall be measured to at least the nearest second.
l()
l \_/ 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.
Basis For Alternate Testing The solenoid valves have actuation times considerably under a second and there is no visual reference on the solenoid valve to l 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 l recorded to. verify a decrease in pressure, which confirms that l the air banks discharged properly.
I Flow through check valves 2-EB-15, 34, 61 and 78 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
{ a full stroke test for the check valves. The test to start the 4-114 N2PVI2R8 Revision 8 August 17, 1998 t
y i
l NON-CODE ALTERNATIVE TESTING VNC-4 (Cont.)
s_/
diesels on one air bank is performed on a rotating basis once "
, every six months. Based on this rotation, each check valve will be full flow tested once every 18 months.
Alternate Testing proposed The solenoid valve'will be full stroke exercised and check valves will be partial stroke exercised monthly by observing that the valves perform their intended function (if the diesel starts, the air bank pressures decrease and the air supply manifold maintains l its integrity, then the solenoid and check valves were stroked successfully).
Every'18 months, the check valves will be full stroke tested by discharging only one air bank to start the diesel. The failure l
of either the solenoid or check valves to open will promptly give a diesel alarm. Further investigation would identify problems with the operability of these valves. The diesel start time will l
~
be recorded and compared to a maximum allowable start time during this test.
iO l
l l
l i
l 4-115 N2PVI2R8 Revision 8 August 17, 1998 l
(;
I
- ( '
NON-CODE' ALTERNATIVE TESTING VNC-5
[ Gr System : Service Air
. Valve (s) : 2-IA-497.
2-IA-499 Class : NC Category: A Class : NC Function: Bottled Air Supply to Hydrogen Recombiner Containment Isolation Valves Extended Test Frequency Justification These non-Code check valves close in the event of a loss of l
pressure in the respective instrument air supply header to prevent blowdown of the nitrogen reserve volume tank which supplies.the hydrogen recombiner system isolation valves.
lf}
l (_/
Testing the check valves to the closed position requires that the instrument air supply be isolated to both Units 1 and 2 hydrogen t
recombiner isolation valves, the high-radiation sampling subsystem, and various liquid waste and boron recovery system components. Isolating the instrument air supply to these systems ,
every three months to perform the back pressure test would be disruptive to normal plant operation. Therefore, these valves should not be closure tested every three months.
l The check valves are also subject to leak testing at least once l L every 24 months. These check valves will be closure tested at '
l least once every 24 months during the leak test because the small increase in safety gained by performing the back pressure test every cold shutdown does not justify the disruption of normal
, operating activities of the opposite unit or the added burden of performing the back pressure-test on the more frequent schedule.
Testing Frequency ,,
Exercise these-valves to the closed position at least once every 24 months.
O 4-116 N2PVI2R8 Revision 8 August 17, 1998
= ,
I
/~'T 5.0 REPORTING OF INSERVICE TEST RESULTS O
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, (D
(_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, f 6) comparisons with allowable ranges of test values l- and analysis of deviations, L'
5-1 N2PVI2R8 Revision 8 August 17, 1998
F.
l-
- 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 accordance with OM Part 6, Section 7.4 that includes a summary of the corrections made, the subsequent I inservice tests and confirmation of operation adequacy,
! and the signature of the individual responsible for the 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 l serial or other unique identification number, 1
- 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.
l A record of test results will be maintained in l l accordance with OM Part 10, Section 6.3 that includes i the following: 1
- 1) valve identification,
- 2) date of test, 1 O 5-2 N2PVI2R8 Revision 8 August 17, 1998 i
- 3) reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.),
I 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
- 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 surveillance test procedures and results will be kept Os at North Anna Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC.
n
!O
! 5-3 N2PVI2R8 Revision 8 August 17, 1998
- 6. 0' QUALITY ASSURANCE PROGRAM
-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.
O 1,
O 6-1 N2PVI2R8 Revision 8 August 17, 1998 L-