ML20093K967
| ML20093K967 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/18/1995 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 95-514, NUDOCS 9510250122 | |
| Download: ML20093K967 (141) | |
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VIRGINIA ELECTRIC AND PowEn COMPANY l
Ricnxown, VIRGINIA 202M October 18, 1995 United States Nuclear Regulatory Commission Serial No.95-514 Attention: Document Control Desk NL&OS/EJW Washington, D. C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 License No. NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STAT!ON UNIT NOS.1 AND 2 INSERVICE TESTING PROGRAM ANOMAllES The NRC safety evaluation report for North Anna Power Station's ASME Section XI Inservice Testing (IST) Program was received by letter dated October 18,1994.
Appendix A to this report identified 10 anomalies in the program. Responses for each anomaly are provided in Attachment 1.
As a result of the anomalies identified in the NRC safety evaluation report, certain IST program changes have been made. IST program changes have also resulted from incorporating a sampling plan for nonintrusive testing of Safety injection check valves and from system configuration changes. These changes and the revised program pages are included in Attachments 2 and 3, for North Anna Units 1 and 2, respectively. These changes have been approved by the Station Nuclear Safety and Operating Committee.
If you have any questions concerning our response or IST program changes, please contact us.
Very truly yours, c
90H&
l James P. O'Hanlon l
Senior Vice President - Nuclear Attachments yk1 L$
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U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.
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L Mr. R. D. McWhorter L
NRC Senior Resident inspector North Anna Power Station l
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ATTACHMENT 1 NRC SAFETY EVALUATION OF NORTH ANNA UNITS 1 AND 2 INSERVICE TESTING PROGRAMS REVISION 7 RESPONSES TO IST PROGRAM ANOMALIES
ATI'ACHMENT 1 e
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RESPONSE TO IST PROGRAM ANOMALIES i
1.
SER Anomaly In TER section 2.1.1.1 Pump Relief Request P-13, the licensee requests relief from the flow rate and discharge pressure instrument accuracy requirements of Section XI, Paragraph IWP-4110, for pumps 1(2)-CH-P-1 A, -1B, and
-1C,1(2)-CC-P-1 A and -1B, and 1(2)-SW-P-1A, -1B, and -4. The service water pumps are the subject of other relief requests in this submittal; P-9, P-10, and P-12.
j Taken together, the reviewer does not have adequate information to fully assess the l
impact of the combination. We recommend that the proposed alternate be authorized pursuant to 10CFR50.55a(a)(3)(ii) with the following provision. The licensee should perform a complete assessment of the impact of the combination of this relief request and requests P-9, P-10, and P-12 as to their ability to assess the operational readiness of these pumps. The results of that assessment should be available for inspection at the facility.
Virginia Power Resoonse The assessment has been performed with the conclusion
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that the operational readiness of pumps 1(2)-CH-P-1 A, -1B, and -lC,1(2)-CC-P-1A and -1B, and 1(2)-SW-P-4 can be assessed given the relaxation of instrument i
accuracies requested by P-13 in combination with P-10 and P-12. The use of Code acceptable discharge pressure gauges has been implemented for pumps 1(2)-SW-P-1 A and B and these pumps were removed from P-13. However, an assessment on the impact of combining relief requests P-9 and P-12 was performed for pumps 1(2)-SW-P-1A and B in a manner similar for the other pumps in P-13.
The assessment for determining operational readiness included a review of normalized test data for each pump. North Anna has the ability to normalize the test data and trend the data from test to test. By knowing the polynomial equation that describes the reference pump curve discussed in P-12, a reference value can be calculated for the dependent variable using the value of the independent variable. The actual test result is divided by the reference value to yield a normalized test result which can then be used to trend the performance of the pump. This review showed that the test results were trendable and provide the ability to assess the operational readiness of these pumps.
2.
SER Anomaly In TER section 2.2.1.1, Pump Relief Request P-5, the licensee requests relief from the test frequency requirements of Section XI, Paragraphs 1
1 ATTACHMENT 1 IWP-3400(a)and -3500(a) for the RHR pumps. The licensee proposes to test them during refueling outages. However, the flow loop is equipped to measure individual pump inlet and discharge pressure, and combined system flow rate. This configuration l
should be conducive to the gathering of some meaningful test data during pump i
operation. It may not be prudent to arbitrarily extend the test interval to refueling l
outages if meaningful testing is practicable during cold shutdowns. We recommend that relief be granted pursuant to 10CFR50.55a(f)(6)(i) provided the licensee tests these pumps according to the Code test method requirements during cold shutdowns l
when heat loads are low and individual testing is practicable, and the licensee considers testing methods and acceptance criteria for assessing the operational readiness of these pumps during cold shutdowns when they can only be operated in parallel.
Virginia Power Resoonse The test frequency is being changed from every reactor refueling to every cold shutdown (but not more frequently than once every three j
months) for the RHR pumps.
l 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 the results will be compared to acceptance criteria based on that portion of the pump curve described above and the hydraulic acceptance criteria given in OM 3
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.
If vibration is found to vary significantly over the range of flow rates, flow rate versus vibration velocity data for at least five points will be taken, and a curve fit for these data points will be determined. Using the fitted curve and the acceptance criteria for vibration testing in OM Part 6, acceptance criteria dependent on flow rate will be determined.
3.
SER Anomalv In TER sections 2.3.1.1 and 2.3.1.2, Pump Relief Requests P-9 and P-10, the licensee requests relief from measuring pump inlet and d/p for service water pumps 1(2)-SW-P-1 A -1B, and -4 as required by Section XI, Paragraph IWP-3100.
2
A*ITACHMENT 1 The licensee proposes to monitor pump discharge pressure and use it in place of d/p to monitor for pump degradation. Inlet pressure will not be measured for these pumps. These pumps are the subject of other relief requests in this submittal; P-12 and P-13. The reviewer does not have adequate information to fully assess the impact of the combination of these requests. We recommend that the alternative be approved pursuant with 10CFR50.55a(a)(3)(ii) with the following provision. The licensee should perform a complete assessment of the impact of the combination of this relief request and requests P-12 and P-13 as to their ability to assess the operational readiness of these pumps. The results of that assessment should be available for inspection at the facility.
Virginia Power Resnonse The assessment described for Anomaly 1 applies to Anomaly 3. Refer to the response for Anomaly 1.
4.
SER Anomaly In TER section 2.4.1.1, Pump Relief Request P-12, the licensee requests relief from establishing fixed set (s) of reference values for component cooling water and service water pumps as required by Section XI, Paragraphs IWP-3100 and -3110. The licensee proposes to test these pumps in their as-found condition of flow rate and d/p and to compare the results to acceptance criteria based on a reference pump curve that is generated mathematically from the results of test data taken at least five points of operation. The service water pumps,1(2)SW-P-1A,
-1B, and -4 are also the subject of other relief requests in this submittal; P-9, P-10, and P-13. The reviewer does not have adequate information to fully assess the impact of the combination. Relief should be granted from this Code requirement pursuant to 10CFRS0.55a(f)(6)(i) with the following provisions. The licensee should follow the seven guidelines identified in section 2.4.1.1 for using reference curves, if practicable. Where it is not practicable to follow these guidelines, the licensee should identify the specifics of their alternative and justify the deviations and show the adequacy of their proposed testing. Also, for the service water pumps, the licensee should perform a complete assessment of the impact of the combination of this relief request and requests P-9, P-10, and P-13 as to their ability to assess the operational readiness of these pumps. The results of that assessment should be available for inspection at the facility.
Virginia Power Response The assessment described for Anomaly 1 applies to Anomaly 4. Refer to the response for Anomaly 1.
5.
SER Anomaly In Relief Request V-59 (see TER section 3.1.1.1), the licensee requests relief from assigning individual leakage rates to various valves as required by Section XI, Paragraph IWV-3426, and proposes to leak rate test these valves in groups.12ak rate testing in groups can be acceptable provided this testing does not 3
A'ITACHMENT 1 permit excessive leak through an individual valve in the group without taking appropriate corrective action. Therefore, the leakage limit for the group should be conservative considering the number and size of the valves in the group so that excessive leakage through any particular valve in the group results in appropriate corrective action.
Virginia Power Response The acceptance criteria are based on the diameter of the largest valve in the group. The groups are given below.
Group 1 Valve Size Ratio Groun 2 Valve Size Ratio 1-SI-MOV-1867C 3"
1 1-CH-402 0.75" 4
1.-SI-MOV-1867D 3"
1-CH-MOV-1380 3"
Group 3 Valve Size Batin Group 4 Valve Size Ratin 1-SI-MOV-1890C 10" 1
1-HV-MOV-100B 36" 2
1-SI-MOV-1890D 10" 1-HV-MOV-102 18" Group 5 Valve Size Ratio 1-HV-MOV-100D 36" 4.5 1-HV-MOV-101 8"
Although this method is not as conservative as basing the entire penetration leakage criterion on the smallest valve in the group, it still is adequately conservative to identify leakage from the smallest valve because the ratios between the largest and smallest valves are not that large. The largest ratio of 4.5 is for Group 5. The i
methodology is documented and available for NRC inspection.
6.
SER Anomaly In Relief Request V-42 (V-43), the licensee requests relief from the test frequency requirements of Section XI and proposes to exercise the accumulator i
discharge and cold leg injection check valves by performing a low pressure discharge of the accumulator each refueling outage and to verify a full-stroke using nonintrusive techniques on one valve from each group on a sampling basis. Use of nonintrusive techniques can be a positive means of verifying a full-stroke exercise as allowed by the Code, however, to use this technique on a sampling basis, the guidelines listed in the TER evaluation should be followed (see TER Section 3.2.2.3.3). The licensee's proposed alternate testing appears to comply with most of these guidelines, however, it is unclear from the submittal if all of these conditions are met. The licensee should verify that the testing of the subject valves complies with all of these guidelines. The 4
A'ITACHMENT 1 1
i proposed grouping in this request does not appear to comply with the GL 89-04 requirement that group valves have the same service conditions. Valve 1-SI-127 (2-SI-153) is the second check valve (closer to the RCS) in the injection line from the accumulator to the RCS while the other three group valves are the first check valves (closer to the accumulators). Differences in service conditions may affect the corrosion, erosion, wear, etc. for this valve such that it is not representative of the other valves in the proposed group. The licensee should justify the proposed grouping or bring it into compliance with the grouping criteria of GL 89-04.
Virginia Power Resoonse Anomaly 6 questions the placement of the check valve 1-SI-127 (2-SI-153) on the A loop in the same group as the three accumulator discharge check valves closest to the accumulator. It is assumed in the discussion that the valve closest to the RCS is the valve that normally seats against RCS pressure (i.e., valve 1-SI-127 (2-SI-153)), and is normally subject to RCS pressure, water chemistry, and possibly elevated temperatures, while the other valves in the group do not normally experience these conditions.
Valve 1-SI-127 (2-SI-153) in the A loop was originally placed with the valves closest to the accumulators because the valves closest to the RCS on B and C loops experience RHR flow during shutdowns, whereas the valve on the A loop does not.
Therefore, it was concluded that valve 1-SI-127 (2-SI-153) was subject to different service conditions.
However, if only normal operating conditions are considered, valve 1-SI-127 (2-SI-153) should be placed in the group with the other two valves closest to the RCS. The other two valves 1-SI-144 and 161 (2-SI-170 and 187) experience RHR flow only during shutdowns, which accounts for a small percentage of the total operating time.
l The other alternative would be to place 1-SI-127 (2-SI-153) in it's own group, which would require acoustic monitoring every outage. Numerous disassembly and inspections show that these check valves show virtually no degradation. Therefore, J
the difference in service conditions due to RHR flow during outages produces no additional detectable degradation in the valves in B and C loops. Given the lack of degradation observed in the valves during the disassembly and inspections, the added burden of acoustically monitoring valve 1-SI-127 (2-SI-153) every outage is not justified. Therefore, this valve will be placed in the same group as valves 1-SI-144 and 161 (2-SI-170 and 187). The testing of these valves complies with the provisions of GL 89-04, Position 2.
7.
SER Anomaly Several of the licensee's relief requests are approved by GL 89 04 and are not evaluated in this TER. The licensee indicates compliance with GL 89-04, but 5
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A'ITACHMENT 1 does not specifically address all aspects of the Generic letter provisions in the requests. In these cases, it is assumed that the licensee is complying with all of the I
requirements of the applicable GL 89-04 positions. Relief is not granted for the above relief requests for testing that deviates from that prescribed in GL 89-04. Whether the licensee complies with the provisions of GL 89-04 is subject to NRC inspection. If the licensee intends to deviate from a GL 89-04 position, a revised relief request specifically stating the deviation from GL 89-04 guidance must be submitted for review and approval prior to implementing the testing.
Virginia Power Resnonse Unless noted in the relief requests, North Anna complies with the provisions in GL 89-04.
8.
SER Anomaly Valve relief requests V-33,42 (-43), and -73 (-74) are for check valves that may not be practically verified closed using system pressure or flow or full stroke exercised open with flow per GL 89-04, Position 1. The licensee proposes to full-stroke exercise these valves by sample disassembly, inspection, and a manual i
exercise. The NRC considers valve disassembly and inspection to be a maintenance procedure and not a test equivalent to the exercising produced by fluid flow. This procedure has some risk, which make its routine use as a substitute for testing undesirable when some method of testing is possible. Disassembly and inspection, to verify the full-stroke open or closure capability of check valves is not a recommended option when exercising can be practically performed by system pressure, flow, or other positive means. Check valve disassembly is a valuable maintenance tool that can provide much information about a valve's internal condition and as such should be performed under the maintenance program at a frequency commensurate with the valve type and service.
Some test method may be feasible to full-stroke exercise these valves. The licensee should consider methods such as using nonintrusive techniques (e.g., acoustics, ultrasonics, magnetics, radiography, and thermography) to verify a full-stoke exercise of the subject check valves. This testing may only be practical at cold shutdowns or refueling outages. The licensee should perform their investigation and if a test method is found to be practicable, the IST requirements of the applicable valves should be satisfied by testing instead of disassembly and inspection. If testing is not practicable and disassembly and inspection is used, it must be performed in accordance with GL 89-04, Position 2. The licensee should respond to this concern.
Virginia Power Resoonse Relief request V-33 contains the casing cooling pump discharge check valves. These valves are downstream from the casing cooling pump test loop and do not experience flow when the pumps are tested. The casing cooling pump discharge lines connect to the suction lines of the outside recirculation spray 6
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ATTACHMENT 1 pumps at a point between the containment sump and the suction line motor operated isolation valve. Directing flow to the pump discharge valves would flood the containment sump and create a significant amount of contaminated water for disposal.
Therefore, the only practical means oflifting the valve disks is to disassemble the valves and manually lift the disks.
Nonintrusive techniques are being evaluated for testing the SI accumulator discharge -
check valves in relief request V-42 (43). The auxiliary service water pump discharge check valve in relief request V-73 (74) has a double disk design with springs that force the disks to the seat. An attempt was made to acoustically detect when the di:,ks strike the back seats. However, a strike could only be detected for one disk. The acceleration of the water when the pump was started was insufficient to force both disks to the back seats and create a detectable impact. Therefore, the test was inconclusive. Full flow testing of the check valves is not practical as described in the relief request. Therefore, the only practical means of exercising the valve disks is to disassemble the valves and manually exercise the disks. The testing of the valves in relief requests V-33,42 (-43), and -73 (-74) complies with the provisions of GL 89-04, Position 2.
l 9.
SER Anomaly V-69 (V-70) requests relief from the leak rate corrective action requirements of Section XI for all CIVs in the IST program and proposes to allow an evaluation of leakage rates above the allowable limits instead of repair or replacement as long as the overall containment leakage is less than 0.6L,. The licensee did not provide details about the evaluation that would be performed. The evaluations should be performed in a manner that provides a high level of assurance that delaying the repair or replacement of valves with high leakage rates will not result in exceeding the 0.612 limit before the next leakage rate tests. The licensee should document in the program plan how these evaluations will be performed and what will be included (see Section 3.1.2.1).
Virginia Power Resoonse An evaluation that returns a valve to service if it exceeds it's permissible leakage rate would typically include a determination of the cause for the leakage. The evaluation would also address the effect of the degradation mechanism for the valve on the ability of the containment to maintain overall leakage below 0.6L, during the subsequent 24 month interval. Evaluations are documented in the plant records and are available for review.
l 10.
SER Anomaly V-75 (V-76) requests relief from the leak rate corrective action requirements of Section XI for the RWST isolation valves and proposes to allow an evaluation of leakage rates above the allowable limits instead of repair or replacement as long as the overall containment leakage is less than the overall RWST leakage 7
ATTACHMENT 1 1
limit. The licensee did not provide details about the evaluation that would be performed. The evaluations should be performed in a manner that provides a high level of assurance that delaying the repair or replacement of valves with high leakage rates will not result in exceeding the overall RWST limit before the next leakage rate tests. The licensee should document in the program plan how these evaluations will be performed and what will be included (see Section 3.1.3.1).
Virginia Power Resnana An evaluation that returns a valve to service ifit exceeds it's permissible leakage rate would typically include a determination of the cause for the leakage. The evaluation would also address the effect of the degradation mechanism for the valve on the ability of the valve group to maintain overall leakage to the RWST below the overall allowable leakage rate during the subsequent 24 month interval. Evaluations are documented in the plant records and are available for review.
As a point of clarification, the NRC discussion given above refers to the overall containment leakage being less than the overall RWST leakage. Relief request V-75 (V-76) does not refer to overall containment being less than the overall RWST leakage but to the summed leakages of the RWST isolation valves being less than the overall RWST leakage.
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SUMMARY
OF CHANGES TO t
NORTH ANNA UNIT 1 IST PROGRAM i
REVISION 7 l
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SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 The following summary describes the changes to Revision 7 of the North Anna Unit 1 Inservice Testing (IST) Program Plan.
2.2.5 PUMP INSERVICE TESTING TABLE l
UNIT 1 PUMP NUMBER COMMENT / PROGRAM CHANGE 1-RH-P-1A Program change:
Test frequency was changed 1-RH-P-1B from every reactor refueling to every cold shutdown.
Refer to relief request P-5.
2.2.6 PUMP INSERVICE TESTING RELIEF REQUESTS UNIT 1 RELIEF REOUEST COMMENT / STATUS P-5 The test frequency for the RHR pumps was changed from every reactor refueling to every cold shutdown but not more frequently then every three months.
Also, the hydraulic acceptance criteria will be based on a portion of the pump curve instead of a i
specific reference value.
This change resulted from our response to Anomaly 2 in the NRC Safety Evaluation Report.
P-13 Service water pumps 1-SW-P-1A and B were deleted from this relief request.
The discharge pressures are measured using gauges that meet Section XI accuracy requirements.
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SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 i
2.3.4 VALVE INSERVICE TESTING TABLE i
Valves marked with an
- are being added to the IST Program.
UNIT 1 i
VALVE NUMBER COMMENT / PROGRAM CHANGE 4
i 1-CH-649' This check valve was installed on the header i
from the charging pump recirculation lines and the RCP seal water return line in response to the Westinghouse Nuclear Service Advisory Letter (NSAL)92-012.
This advisory identified the potential for leakage of contaminated sump water outside the containment via the RCP seal water heat exchanger relief valve to the volume control tank.
Program change:
The valve was added to the IST program to be leak tested and tested closed every reactor refueling (refer to Relief Request V-72), and to be tested open every cold shutdown (refer to Cold shutdown Justification CSV-38).
1-CH-MOV-1115B Relief Request V-75 was added for the RWST 1-CH-MOV-1115D isolation valves to allow for the use of an 1-SI-47 evaluation instead of repair or replacement 1-SI-MOV-1885A as corrective action if a valve exceeds it's 1-SI-MOV-1885B permissible leakage limit.
The relief 1-SI-MOV-1885C request was submitted to the NRC by letter 1-SI-MOV-1885D dated April 26, 1994.
Approval was granted by the NRC in the Safety Evaluation Repor.t for the IST program dated October 18, 1994.
Program change:
Relief request V-75 was added.
1-GN-229 Program change:
The valve number was changed from 1-GN-451 to 1-GN-229.
1-HC-5 This non-Code class check valve is on the discharge line for the containment purge blower.
The primary means of containment 2
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SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 hydrogen control is by operation of the recombiners.
Therefore, operation of the purge blowers is not critical to accident mitigation or recovery.
This valve was carried in the IST program because of a Technical Specification surveillance requirement that could be interpreted as requiring the testing of the blower.
This requirement has since been clarified.
There is no Technical Specification surveillance requirement.
Program change:- The valve was removed from the IST program.
1-HC-62 This hydrogen analyzer discharge check valve was removed from the system along with the analyzer.
Program change:
The valve was removed from the IST program.
1-MS-19 These decay heat release stop check isolation 1-MS-58 valves are now maintained closed with the 1-MS-96 stem on the disk.
In this configuration, the valve disk does not have to change position to fulfill it's isolation function.
Therefore, the Code does not require the valves to be tested.
Program change:
The valves were removed from the IST program.
R 1-QS-MOV-102A Testing valves quarterly presents a 1-QS-MOV-102B significant personnel hazard due to expos.ure to sodium hydroxide.
Program change:
These valves will be tested on a cold shutdown frequency instead of quarterly.
Refer to Cold Shutdown Justification CSV-44.
1-RH-7 Program change:
The test frequency for these 1-RH-15 RHR pump discharge check valves was changed from every reactor refueling to every cold shutdown but not more frequently then every three months.
Relief Request V-74 was 3
O
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 replaced by Cold Shutdown Justification CSV-46.
1-RH-FCV-1605 An engineering evaluation concluded that the 1-RH-HCV-1758 simultaneous failure of the RHR heat exchanger bypass and discharge valves to go to their fail-safe positions on loss of instrument air will not create a safety concern for achieving safe shutdown.
Therefore, these valves need not be included in the IST program.
Program change:- The valves were removed from the IST Program.
1-SI-83 Program change:
Reference to using 1-SI-86 nonintrusive techniques and a sampling plan 1-SI-89 for verifying full-stroke of the cold leg 1-SI-195 safety injection check valves was added to 1-SI-197 Relief Request V-41.
1-SI-199 1-SI-95 Program change:
Reference to using 1-SI-99 nonintrusive techniques and a sampling plan 1-SI-103 for verifying full-stroke of the hot leg 1-SI-209 safety injection check valves was added to 1-SI-211 Relief Request V-43.
1-SI-213 1-SI-125 Program change:
Reference to using a
1-SI-127 sampling plan with nonintrusive techniques 1-SI-142 for verifying full-stroke of the safety 1-SI-144 injection accumulator discharge check valves 1-SI-159 was added to R311ef Request V-42.
Also, the 1-SI-161 grouping of the valves was changed.
1-SI-MOV-1863B Program change:
The drawing reference was changed to 11715-CBM-096A.
1 1-SW-252 Further evaluation has shown that these 1-SW-255 service water header check valves can be full flow tested every three months.
Program change:
Cold shutdown Justification CSV-39 is being withdrawn and these check l
valves will be full flow tested every three months.
4
4 l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 3
IST PROGRAM, REVISION 7 I
1-SW-1067' These manual valves are normally open and are 1-SW-1070*
closed to isolate the service water chemical 1-SW-1139' addition system from the service water system.
A recent service water system review identified these valves as having to close to prevent loss of service water and recommended that they be included in the IST program.
Program change:
The valves were added to the IST Program to be tested to the full closed position every cold shutdown.
Refer to Cold Shutdown Justification CSV-45.
1-SW-MOV-102A Further evaluation resulting from the recent 1-SW-MOV-102B service water system review revealed that 1-SW-MOV-106A closing these service water cross-tie 1-SW-MOV-106B isolation valves is the preferred method for isolating an inoperable header.
Program change:
Closure testing was added to the IST program.
1-SW-MOV-108A These isolation valves are located in series 1-SW-MOV-108B on the service water supply to the component cooling heat exchangers.
Testing them every quarter creates a reduced flow condition for the service water pumps which in turn causes the pumps to experience harmful high-magnitude vibrations.
Program change:
These valves will be tested on a cold shutdown frequency instead of quarterly.
Refer to Cold Shutdown Justification CSV-43.
2.3.5 VALVE INSERVICE TESTING PROGRAM RELIEF REQUESTS UNIT 1 RELI"F REQUEST COMMENT / STATUS 1
V-38 The basis for relief was revised to indicate that the low head safety injection system must be isolated to perform closure testing on the check valves.
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SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1
-IST PROGRAM, REVISION 7 I
V-41 Reference to using nonintrusive techniques and a sampling plan for verifying full-stroke of the cold leg safety injection check valves was added.
The alternative method described for usir.g nonintrusive techniques described in NUREG 1482 will be followed.
According to NUREG 1482, " Relief is not required because this test method is 4
considered an acceptable 'other positive means,' even if used on a rotating basis.
However, if the recommended alternative methods of this section are implemented, the licensee must describe the implementation of this section in the IST program document."
Even though relief is not required, use of the sampling plan is described in this relief request to satisfy the documentation requirement described above.
V-42 Reference to using a sampling plan with nonintrusive techniques for verifying full-stroke of the safety injection accumulator discharge check valves was added.
Also, the grouping of the valves was changed from valves 1-SI-144 and 161 in one group, and 1-SI-125, 127, 142 and 159 in the other group, to 1-SI-125, 144 and 161 in one group, and 1-SI-127, 142 and 159 in the other group.
This change resulted from our response to Anomaly 6 in the NRC Safety Evaluation Report.
The explanation for why the grouping was changed i
is included in our response.
As described in j
the discussion for V-41, relief is not required for using the sampling plan.
V-43 Reference to using nonintrusive techniques and a sampling plan for verifying full-stroke of the hot leg safety injection check valves was added.
As described in the discussion I
for V-41, relief is not required for using the sampling plan.
V-50 Relief request is being withdrawn.
The only valve (1-HC-5) in this relief request was removed from the IST program.
6
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 V-72 Check valve 1-CH-649 was installed on the header from the charging pump recirculation lines and the RCP seal water return line in response to the Westinghouse Nuclear Service Advisory Letter (NSAL)92-012 and was added to this relief request for testing to the closed position.
During normal operation, this valve cannot be isolated to perform a back pressure test because normal letdown and charging flow, and reactor coolant pump seal flow would be interrupted.
Also, if the valve was isolated during normal operation, the charging pumps would have to be secured.
This valve is also subject to leak testing, which is performed every reactor refueling.
Verification of closure will be performed l
during the leak test every reactor refueling instead of every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify the burden of performing a leak rate test.
V-74 Relief request is being replaced by Cold Shutdown Justification CSV-46.
V-75 This relief reauest was added to the IST procram and applies to the RWST isolation valves.
In addition to replacement or repair as corrective actions, an evaluation can be
{
performed which demonstrates that even if a valve has exceeded its permissible leakage rate, the overall leakage rate to the RWS.T will be maintained below the overall allowable RWST leakage rate.
No repair or replacement is necessary if the evaluation is performed.
The relief request was submitted to the NRC by letter dated April 26, 1994.
Approval was granted by the NRC in the Safety Evaluation Report for the IST program dated October 18, 1994.
7 i
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 2.3.6 VALVE INSERVICE TESTING PROGRAM COLD SHUTDOWN JUSTIFICATIONS UNIT 1 COLD SHUTDOWN JUSTIFICATION COMMENT / STATUS l
CSV-20 Justification is being withdrawn because i
valves 1-RH-FCV-1605 and 1-RH-HCV-1758 were l
deleted from the IST Program.
i CSV-38 Check valve 1-CH-649 was installed on the header from the charging pump recirculation lines and the RCP seal water return line in I
response to the Westinghouse Nuclear Service Advisory Letter (NSAL)92-012 and was added to this cold shutdown justification for testing to the open position.
Full flow I
conditions have to be measured by using I
temporary ultrasonic flow instrumentation l
which is very labor intensive.
Also, reference to removing the ultrasonic flow instrumentation from the field after testing each valve wac deleted.
All four valves would be normally tested before the equipment is removed.
CSV-39 Justification is being withdrawn.
Further i
evaluation has shown that the service water header check valves 1-SW-252 and 255 can be full flow tested every three months.
1 CSV-43 Justification is beina added to the IST l
program.
Valves 1-SW-McV-108A and B are ~
located in series on the service water supply to the component cooling heat exchangers.
The component cooling heat exchangers carry a majority of the heat load for the service l
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 i
range from 7000 gpm to 6000 gpm.
These pumps cannot be stopped during the valve exercise 8
I
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 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.
CSV-44 Justification is beina added to the IST procram.
The normally closed six inch motor operated isolation valves 1-QS-MOV-102A and B 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 tha 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 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 9
l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 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.
CSV-45 Justification is beine added to the IST procram.
The normally open manual 1 inch (1-SW-1067 and 1070) and 1.5 inch (1-SW-1139) valves are closed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the accident as required by the abnormal i
operating procedures to prevent loss of service water in the event that the connected non-seismic pipe fails.
These valves are located in an expansion joint vault outside the service water pump house.
The vault is defined as a confined space due to possible consumption resulting from an expansion joint failure.
Entry into this confined space requires an entry permit, an air meter and two operators (buddy system).
Also, special tools are required to remove the manhole cover which weighs in excess of 300 lbs and is a missile barrier.
Closing these valves would require securing the service water addition system which could adversely affect 4
the biological agent concentration in the service water.
These manual valves remain in the open position during normal operation and are not subject to wear.
Closing these valves every three months to fulfill quarterly testing requirements creates an undue burden with no compensating benefit to quality and safety.
i Exercising these valves on a cold shutdown i
test frequency (but not more frequently then once every three months), is adequate to demonstrate that the valves can be closed in the case where service water isolation is required.
10
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 1 IST PROGRAM, REVISION 7 CSV-46 Justification is beina added to the IST program.
The 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 1-RH-P-1A and 1-RH-P-1B are running.
The low pressure pumps take suction from and discharge to the reactor coolant system which operates at 2235 psig.
This pressure is well above the operating pressure of the pumps, therefore, partial-stroke or full-stroke testing during normal operation is not practical.
2.3.7 ALTERNATIVE TESTING FOR NON-CODE VALVES UNIT 1 NON-CODE ALTERNATIVE TESTING COMMENT / STATUS VNC-1 Valve number for 1-GN-229 was changed from 1-GN-451.
l 11
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REPLACEMENT PAGES TO NORTH ANNA UNIT 1 IST PROGRAM REVISION 7
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RELIEF REQUEST P-5 I. IDENTIFICATION OF COMPONENTS System :
Residual Heat Removal Pump (s):
1-RH-P-1A
'l-RH-P-1B j
Class 2
?
II. IMPRACTICAL CODE REQUIREMENTS l
Frequency of Pump Test.
III. BASIS FOR RELIEF The low pressure pumps take suction from and discharge to the Reactor Coolant System (RCS)which operates at 2235 psig.
This pressure is well above the operating pressure of the pumps; therefore, testing during normal operation is not possible.
Also, the pumps are located inside containment and are inaccessible during normal operation.
As a result of industry experience and NRC guidance (Generic Letter 88-17) concerning the loss of decay l
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 gpa to 4000 gpa (depending on the system flow at the time of the test), and the results will be compared to acceptance criteria based on that portion of the pump curva 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.
2-19 1
N1PVR7 Revision 7 August 8, 1995
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 five points will be taken, and a curve fit for these data points will be determined.
Using the fitted curve and the acceptance
. criteria for vibration testing in ON Part 6, acceptance criteria dependent on flow rate will be determined.
IV. ALTERNATE TESTING 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 i
i 2-19a N1PVR7 Revision 7 August 8, 1995
.. _.m.
l l
RELIEF REQUEST P-13 I. IDENTIFICATION OF COMPONENTS System :
Component Cooling Chemical and Volume-Control Service Water
]
Pump (s):
1-CH-P-1A 1-CC-P-1A 1-CH-P-1B 1-CC-P-1B 1-CH-P-1C 1-SW-P-4 i
Class Class 2 for CH and Class 3 for CC and SW II. IMPRACTICAL CODE REQUIREMENTS i
Instrument Error III. BASIS FOR REQUEST Instruments used to measure certain pump parameters receive their signal at the equipment, which is transmitted to a process rack and then to a control room indicator.
The sensor and rack accuracy can be affected by drift, temperature, and calibration accuracy.
The indicator has a limit of accuracy.
The i
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 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 IWP 4110-1.
Instrument Component Parameter Accuracy FI-1122 1-CH-P-1A,B,C Flow 2.34'%
FI-CC-100A 1-CC-P-1A Flow 2.69%
FI-CC-100B 1-CC-P-1B Flow 2.69%
PI-SW-110 1-SW-P-4 Discharge Pressure 2.61%
i IV. ALTERNATE TESTING None C
2-29 N1PVR7 Revision 7 January 10, 1995 I
VIRGINIA POWER COMPANY PAGE:
9 OF 78 NORTH ANNA UNIT 1 REVISION: 07 SECONO INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NLMBER WlmBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1*CH 279 11715 CBM 0955 2 OF 2 06 CHECK VALVE 3.000 2 C
CV C
47 0
47 "C" CHARGING PUMP DISCHARGE CHECK VALVE 1-CH 322 11715 CSM-095C 1 0F 2 D4 CHECK VALVE 3.000 2 AC Civ CV C
10 LT C
MAIN CHARGING SUPPLY HEADER, INSIDE CONTAIN-MENT ISOLATION CHECK VALVE 1 CH-330 11715-CBM-095C 1 of 2 A6 CHECK VALVE 2.000 1 AC Civ CV C
10 LT C
............................~..............
CHARGlWG SUPPLY TO LOOP FILL HEADER, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CH-336 11715-CBM 095C 2 0F 2 58 CHECK VALVE 2.000 1 C
CV C
10 "A" RC PUNP SEAL W4TER SUPPLY, INSIDE CONTAINMENT ISOLATILs i, HECK VALVE 1-CH-358 11715-CBM-095C 2 OF 2 B7 CHECK VALVE 2.000 1 C
CV C
10 "B" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CH-380 11715-CBM-095C 2 OF 2 B5 CHECK VALVE 2.000 1 C
CV C
10 "C" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CH-402 11715 CBM-095C 2 0F 2 F4 CHECK VALVE
.750 2 AC Civ CV C
10 LT C
59 RC PUMP SEAL WATFt RETURN, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1-CH 649 11715-CBM 0958 1 0F 2 B6 CHECK VALVE 2.000 2 AC CV C
72 l
o 38 LT C
CHARGING PUMP RECIRC AND RCP SEAL WATER RETURN LINE !$0LATION CHECK VALVE 1-CH FCV-1113A 11715-CBM 095B 1 0F 2 C3 A0 GATE 1.000 3 B
EV 0
FS 0
ST 0
W K
l 1
ALTERNATE EMERGENCY BORATION LINE FLOW CONTROL VALVE 1-CH FCV-1114A 11715-CBM-0958 1 0F 2 D4 A0 GLOBE 1.000 3 B
EV C
FS C
ST C
VP OC i
4 PRIMARY GRADE WATER FLOW CONTROL VALVE lIbEibV55bb li755bEb95b i bi i 5~ b'bLbBb ""'55bbbi kE Ci I LT b
~ ~
vP OC
VIRGINIA POWER COMPANY PAGE:
10 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TA8LE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-CHARGING FLOW CONTROL TO LOOP FILL HEADER, OUTSIDE CONTAINMENT !$0LATION VALVE 1 CH-LCV 1460A 11715 CSM-095C 1 0F 2 F7 A0 GLOBE 2.000 1 B
EV C
5 FS C
5 ST C
VP OC LETDOWN ISOLATION VALVE 1-CH LCV-1460B 11715-CeM 095C 1 0F 2 F7 A0 GLOBE 2.000 1 B
EV C
5 FS C
5 ST C
VP OC LETDOWN ISOLATION VALVE 1-CH-MOV-1115B 11715 CeM-0959 2 0F 2 88 M0 GATE 8.000 2 A
EV C
6 0
6 LT C
75 ST C
6 0
6 VP OC CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TAWK 1-CH-MOV-1115C 11715 CBM-0955 1 0F 2 C6 M0 GATE 4.000 2 B
EV C
6 ST C
6 VP OC CHARGING PUMP SUPPLY ISOLATION FROM VOLUME CONTROL TANK 1 CH-MOV-1115D 11715-C8M-0958 2 0F 2 88 W GATE 8.000 2 A
EV C
6 0
6 LT C
75 ST C
6 0
6 VP OC CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 1 CH-Mov-1115E 11715-CSM 095B 10F 2 C6 M0 GATE 4.000 2 B
EV C
6 ST C
6 VP OC CHARGING PUMP SUPPLY ISOLATION VALVE FROM VOLUME CONTROL TANK 1*CH-MOV 1267A 11715 C8M-0958 2 0F 2 C7 MO GATE 6.000 2 E
VP OC "A" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 1-CH-MOV-1267B 11715-CBM 095B 2 OF 2 C7 MO GATE 6.000 2 E
VP OC l
l "A" CHARGING PUMP SUCTION ISOLATION FROM LHSI l
VIRGINIA POWER COMPANY PAGE:
11 0F 78 NORTH ANNA UNIT 1 REVisl0N: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM. VALVE TABLE i
NC 150 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NLMBER 1RMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1 CH-MOV 1269A 11715-CsM-0958 2 0F 2 C5 No GATE 6.000 2 E
VP OC "B" CHARGING PLMP SUCTION ISOLATION FROM RWST AND VCT 1 CN MOV 12698 11715 cam-0958 2 0F 2 C5 MO GATE 6.000 2 E
VP OC "S" CHARGING PLMP SUCTION ISOLATION FROM LHS!
1 CH-MOV-1270A 11715-CBM 0958 2 0F 2 C3 M0 GATE 6.000 2 E
VP OC "C" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 1*CH MOV-1270B 11715-CsM 0958 2 0F 2 C3 MO GATE 6.000 2 E
VP OC "C" CHARGING PUMP SUCTION ISOLATION FROM LHS!
1-CH MOV-1275A 11715-CBM-0958 2 0F 2 07 M0 GATE 2.000 2 B
EV C
0 ST C
0 VP OC "A" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE 1-CH-MOV-1275B 11715-cam 0958 2 0F 2 05 MO GATE 2.000 2 B
EV C
0 ST C
0 VP OC "B" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE 1 CH MOV 1275C 11715-C8M 0958 2 0F 2 D4 MO GATE 2.000 2 8
EV C
0 ST C
0 VP OC "C" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE 1 CH-MOV-1286A 11715-CBM 0958 2 0F 2 ET MO GATE 3.000 2 B
EV C
0 ST C
1 0
VP OC "A" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV-12868 11715-CBM-0958 2 0F 2 E6 M0 GATE 3.000 2 B
EV C
0 ST C
0 W
K i
VIRGINIA POWER COMPANY PAGE:
12 0F 78 WORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95
)
INSERVICE TESTING PROGRAM - VALVE TABLE
)
VALVE DRAWING
$NEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST 1
NUMBER BRMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-
)
"B" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1 CH MOV-1286C 11715-CBM 0958 2 0F 2 E4 M0 GATE 3.000 2 B
EV C
0 ST C
0 VP OC "C" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV 1287A 11715-CBM-0958 2 0F 2 D7 M0 GATE 3.000 2 B
EV C
0 i
ST C
1 0
VP OC "A" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 1 CH-MOV-1287B 11715-CBM-0958 2 0F 2 D6 M0 GATE 3.000 2 B
EV C
0 ST C
0 VP OC "B" CHARGlWG PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE i
i 1-CW-MOV-1287C 11715 CBM-0958 2 0F 2 D4 M0 GATE 3.000 2 B
EV C
0 ST C
0 VP OC "C" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 1 CH MOV-1289A 11715-CBM-095C 10F 2 D4 M0 GATE 3.000 2 A CIV EV C
7 i
LT C
ST C
7 w
M MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 CH MOV-12898 11715-CBM-095C 1 0F 2 B3 M0 GATE 3.000 2 B
EV C
7 ST C
7 VP OC l
MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE I
CONTAINMENT 1-CH-MOV-1350 11715-CBM-0958 1 0F 2 B5 MO GATE 2.000 2 8
EV O
4 ST 0
4 VP OC EMERGENCY BORATION TO CHARGING PUMP SUCTION 1 CH-MOV-1373 11715-CBM-095B 1 0F 2 A8 M0 GATE 3.000 2 E
VP OC i
4 1
1 l
VIRGINIA POWER COMPANY PAGE:
13 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-YCN-CHARGING PUMP RECIRCULATION HEADER !$0LATION VALVE 1-CH MOV 1380 11715-esM-095C 2 0F 2 F4 M0 GATE 3.000 2 A CIV EV C
9 LT C
59 ST C
9 VP OC REACTOR COOLANT PUMP SEAL WATER RETURN, INSIDE CONTAINMENT ISOLATION VALVE 1-CH-MOV 1381 11715-CsM-0958 1 OF 2 C8 MO GATE 3.000 2 A CIV EV C
9 LT C
ST C
9 VP OC REACTOR COOLANT PLMP SEAL WATER RETURN, OUT-SIDE CONTAINMENT ISOLATION VALVE 1-CH-RV-1203 11715-CBM 095C 1 0F 2 F4 RELIEF VALVE 2.000 2 C
SP 0
LETDOWN RELIEF VLV DOWNSTREAM OF REGEN HX, RV DISCHARGE To PRESSURIZER RELIEF TANK 1-CH-RV-1382s 11715-CBM 0958 10F 2 C7 RELIEF VALVE 2.000 2 C
SP O
SEAL WATER HEAT EXCHANGER RELIEF VALVE, RV DISCHARGE T0 VOLUME CONTROL TANK 1-CH-TV-1204A 11715 CDM 095C 1 0F 2 E3 A0 GLOBE 2.000 2 A CIV EV C
5 FS C
5 LT C
ST C
5 VP OC LETDOWN CONTROL FROM REGEN HX, INSIDE CONTAINMENT ISOLATION VALVE 1-CH-TV-12048 11715-cam-095A 4 0F 4 C3 A0 GLOBE 3.000 2 A CIV EV C
5 FS C
5 LT C
ST C
5 VP OC LETDOWN CONTROL FROM RcGEN HX, OUTSIDE CONTAINMENT ISOLATION VALVE l
l
VIR$1NIA PolElt CGUDANY PAGE:
27 0F 78 NORTN ANNA tal!T 1 REVISION: 07 SECOM INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAN - VALVE TABLE NC l
ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REQ JUST TEST j
laseER ELSWER NUISER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-l i
1 eN-225 11715 FM -105A 1 0F 3 E4 CNECK VALVE
.500 NC AC CV C
1 l
LT C
BOTTLED NITROGEN SUPPLY TO PORY ISOLATIDW CNECK VALVE 1-GN 229 11715 FM 105A 1 0F 3 E6 CNECK VALVE
.500 NC AC cv c
1 f
LT C
BOTTLED NITROGEN SUPPLY 70 PORY ISOLATION CNECK VALVE 1 GN RV 108A 1 11715 FM 105A 1 0F 3 E7 RELIEF VALVE
.750 NC C
SP 0
\\
1 BOTTLED NITROGEN SUPPLY 70 PORY RELIEF VALVE 1 GN-RV-108A 2 11715-FM -105A 1 0F 3 F6 RELIEF VALVE
.750 NC C
SP 0
BOTTLED N!TROGEN SUPPLY TO PORY RELIEF VALVE 1-GN RV 1084 3 tir15 FM -105A 1 0F 3 E6 RELIEF VALVE
.750 NC C
SP 0
BOTTLED NITROGEN SUPPLY 70 PORY RELIEF VALVE 1 GN-RV 1088 1 11715 FM -105A 1 0F 3 E3 RELIEF VALVE
.750 NC C
SP O
BOTTLED NITROGEN SUPPLY TO PORV RELIEF VALVE 1 GN-RV-1088-2 11715-FM 105A 1 0F 3 F5 RELIEF VALVE
.750 NC C
SP 0
j DOTTLED NITROGEN SUPPLY 70 PORY RELIEF VALVE j
j l
1-GN RV-1088 3 11715 FM 105A 1 of 3 E5 RELIEF VALVE
.750 NC C
SP O
80TTLED NITROGEN SUPPLY TO PORY RELIEF VALVE l
l J
VIRGINIA POWER COMPANY PAGE:
28 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERV!CE TESTING PROGRAM. VALVE TABLE l
MC 1
VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NLMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1-NC-014 11715 CeM-106A 10F 4 E8 CHECK VALVE 2.000 2 AC CIV CV C
20 0
20 LT C
UNIT 1 RETURN LINE FROM UNIT 1 HYDROGEN ANA-LYZERS & RECOMB, INSIDE CONT ISOL CHECK VALVE 1-NC-018 11715 CeM-106A 2 0F 4 E6 CHECK VALVE 2.000 2 AC CIV CV C
20 0
20 LT C
UNIT 1 RETURN LINE FROM UNIT 2 NYDROGEN ANA-LYZERS & RECOMS, INSIDE CONT ISOL CNECK VALVE 1 HC-063 11715-CSM 106A 1 0F 4 C7 CHECK VALVE
.375 NC C
CV 0
HYDROGEN ANALYZER DISCHARGE CHECK VALVE 1 NC TV-100A 11715 CeM-106A 10F 4 E8 So GLOBE
.375 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC UNIT 1 SAMPLE LINE TO UNIT 1 HYDROGEN ANA-LYZERS, INSIDE CONTAINMENT ISOLATION VALVE 1 HC TV 1008 11715 CBM-106A 10F 4 E7 So GLOBE
.375 2 A CIV EV C
C FS C
LT C
ST C
54 0
54 VP OC UNIT 1 SAMPLE LINE TO UNIT 1 HYDROGEN ANA-LYZERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-HC TV 101A 11715-CSM 106A 10F 4 07 50 GLOSE
.375 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC RETURN ISOLATION FROM UNIT 1 HYDROGEN ANA-LYZERS TO UNIT 1 CONT,0UTSIDE CONT ISOL VALVE 1 HC-TV-101B 11715 CBM 106A 1 0F 4 D7 SO GLOBE
.375 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC RETURN ISOLATION FROM UNIT 1 HYDROGEN ANA-LYZERS TO UNIT 1 CONT,0UTSIDE CONT ISOL VALVE 1-HC TV-102A 11715-CBM-106A 2 0F 4 E6 50 GLOBE
.375 2 A CIV EV C
VIRGINIA POWER COMPANY PAGE:
29 0F 78 WORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER WLMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1 HC TV 102A 11715 CSM 106A 2 0F 4 E6 SO GLOBE
.375 2 A CIV EV 0
FS C
LT C
ST C
54 0
54 VP OC UNIT 1 SAMPLE LINE TO UNIT 2 HYDROGEN ANA-LYZERS, INSIDE CONTAINMENT ISOLATION VALVE 1 HC-TV-1025 11715 cam-106A 2 0F 4 E7 So GLoeE
.375 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC UNIT 1 SAMPLE LINE TO UNIT 2 HYDROGEN ANA.
LYZERS, OUTSIDE CONTAINMENT ISOLATION VALVE l
1-HC-TV-103A 11715 cam-106A 2 of 4 D7 SO GLOSE
.375 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC RETURN ISOLATION FROM UNIT 2 NYDROGEN ANA-LYZERS TO UNIT 1 CONT,0UTSIDE CONT ISOL VALVE 1 HC-TV 1038 11715 cam 106A 2 0F 4 07 SO GLOSE
.375 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC RETURN ISOLATION FROM UNIT 2 HYDROGEN ANA-LYZERS To UNIT 1 CONT,0UTSIDE CONT ISOL VALVE 1 NC-TV-104A 11715 C8M-106A 4 0F 4 F6 A0 GLOSE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC SUPPLY ISOL FROM UNIT 1 CONT TO N1 HYDRO RE-COMB & N2 CONT BLOWER,0UTSIDE CONT ISOL VALVE 1-HC-TV-104B 11715 CBM 106A 4 0F 4 F6 A0 GLOBE 2.500 2 A Clv LV C
0 FS C
LT C
ST C
54 0
54 VP OC 1
l
VIRGINIA poler COMPANY PAGE:
30 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC
!$0 REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-SUPPLY ISOL FROM UNIT 1 CONT TO N1 NYDRO RE-COMB & N2 CONT BLOWER,00TSIDE CONT ISOL VALVE 1 NC-TV-105A 11715-COM 106A 1 0F 4 E6 A0 GLOSE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC RETURN ISOLATION FROM UNIT 1 NYDROGEN RECOMB
& ANAL TO UNIT 1 CONT, OUTSICE CONT 130L VALVE 1 HC-TV-1058 11715-CeM-106A 10F 4 E6 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC RETURN ISOLATION FROM UNIT 1 HYDR 0 GEN RECOMB
& ANAL TO UNIT 1 CONT, QUTSIDE CONT ISOL VALVE 1-HC-TV-106A 11715-CSM-106A 4 0F 4 F8 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE BLOW & N2 NYDRO RECOMS, OUTSIDE CONT ISOL VLV 1-HC-TV 1068 11715-cam-106A 4 OF 4 F8 A0 GLOSE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE BLOW & N2 NYDRO RECOMB, OUTSIDE CONT ISOL VLV 1 HC-TV-107A 11715 CBM-106A 2 0F 4 E7 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
54 0
54 VP OC RETURN !$0LATION FROM UNIT 2 HYDROGEN RECOMB
& ANAL TO UNIT 1 CONT, OUTSIDE CONT ISOL VALVE 1 HC-TV-107B 11715-CSM-106A 2 0F 4 E8 A0 GLOBE 2.500 2 A CIV EV C
i 0
FS C
LT C
ST C
54 J
1 1
4 VIRGINIA POWER COMPANY PAGE:
31 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SEC0kV INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TE5 TING PROGRAM - VALVE TABLE 1
NC ISO REL CS ALT VALVE DRAWING
$NEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST IRMBER BRMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1-NC TV-1075 11715 CsM-106A 2 0F 4 E8 AO GLOSE 2.500 2 A CIV ST o
54 VP OC RETURN ISOLATION FROM UNIT 2 NYDROGEN RECOMs
& ANAL 70 UNIT 1 CONT, OUTSIDE CONT ISOL VALVE 1 NC TV 108A 11715 CsM 106A 3 0F 4 E8 50 GLOBE
.375 2 A CIV EV C
FS C
LT C
ST C
54 VP OC UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, INSIDE CONTAINMENT !$0LATION VALVE 1-HC-TV 1088 11715 cam-106A 3 0F 4 E7 SO GLOSE
.375 2 A CIV EV C
FS C
LT C
ST C
54 VP OC UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, OUTSIDE CONTAINMENT ISOLATION VALVE 4
VIRGIN!A poler COMPANY PAGE:
60 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME !W VALVE TEST TEST REQ JUST TEST NUMBER NimBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1 MS-018 11715-CeM-070s 1 0F 3 C6 MANUAL GATE 3.000 2 B
EV C
MAIN STEAM TO AUXILIARY FEEDWATER TURSINE LINE ISOLATION VALVE 1-MS-057 11715 CsM-070s 2 0F 3 C6 MANUAL GATE 3.000 2 B
EV C
MA!N STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 1-MS 095 11715-COM 0708 3 0F 3 C6 MANUAL GATE 3.000 2 B
EV C
MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 1-MS-119 11715 cam-070A 3 0F 3 E7 CHECK VALVE 3.000 2 C
CV C
0 "A" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1 MS-122 11715-cam 070A 3 0F 3 F7 CHECK VALVE 3.000 2 C
CV C
0 "B" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1-MS-124 11715 CBM-070A 3 0F 3 F7 CHECK VALVE 3.000 2 C
CV C
0 "C" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1-MS-NRV-101A 11715-CBM-070s 1 0F 3 D3 CHECK VALVE 32.000 2 C
CV C
13 VP OC "A" MAIN STEAM HEADER NON-RETURN VALVE 1-MS NRV 1018 11715-CBM 0708 2 0F 3 D3 CHECK VALVE 32.000 2 C
CV C
13 VP OC "B" MAIN STEAM HEADER NON RETURN VALVE 1-MS NRV-101C 11715 CsM-070s 3 0F 3 D3 CHECK VALVE 32.000 2 C
CV C
13 VP OC "C" MAIN STEAM HEADER NON RETURN VALVE 1-MS PCV-101A 11715 CBM 0708 10F 3 E5 A0 ANGLE 6.000 2 8
EV C
0 FS C
ST C
0 VP OC "A" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE 1 MS PCV-101B 19715 cam 070s 2 QF 3 E6 A0 ANGLE 6.000 2 B
EV C
0 FS C
VIRGINIA POWER COMPANY PAGE:
41 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DAWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLMBER MUMBER COOR TYPE
$1ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1-MS-PCV-1015 11715 CBM 0708 2 0F 3 E6 Ao ANGLE 6.000 2 B
ST C
0 VP OC "S" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE 1-MS PCV-101C 11715-CsM 070s 3 0F 3 D3 AD ANGLE 6.000 2 B
EV C
0 FS C
ST C
0 VP OC "C" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE 1-MS SV 101A 11715 CeM-0700 10F 3 E6 SAFETY VALVE 6.000 2 C
SP O
"A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS-SV-101B 11715 CBM-0708 2 0F 3 E6 SAFETY VALVE 6.000 2 C
SP O
"B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE 10 ATMOS 1-MS SV-101C 11715-COM-070s 3 nr 3 D6 SAFETY VALVE 6.000 2 C
SP O
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS SV 102A 11715-CSM-0708 1 0F 3 E5 SAFETY VALVE 6.000 2 C
SP O
"A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS SV-102B 11715-CBM 0708 2 0F 3 E5 SAFETY VALVE 6.000 2 C
SP 0
......................t......................
"B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS SV-102C 11715-CsM 070s 3 or 3 D6 SAFETY VALVE 6.000 2 C
SP O
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS SV-103A 11715-C8M-070B 1 0F 3 E6 SAFETY VALVE 6.000 2 C
SP O
"A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE 10 ATMOS 1 MS SV-103B 11715 CBM-0708 2 0F 3 E5 SAFETY VALVE 6.000 2 C
$P O
"B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS SV 103C 11715 CBM 0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C
$P 0
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS-SV-104A 11715 CSM-0708 1 0F 3 E6 SAFETY VALVE 6.000 2 C
SP O
i VIRGINIA POWER COMPANY PAGE:
42 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER C00R TYPE
$!ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-l "A" MAIN STEAM NEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS SV-1648 11715 CBM 0708 2 0F 3 E6 SAFETY VALVE 6.000 2 C
SP 0
"B" MAIN STEAM NEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS-SV 104C 11715-CBM-0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C
SP O
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS-SV 105A 11715-CBM 0708 1 0F 3 E5 SAFETY VALVE 6.000 2 C
SP 0
"A" MAIN STEAM HEADER SAFETY VALVE, SV D!$ CHARGE TO ATMOS 1-MS-SV-105B 11715-CBM-0708 2 0F 3 E5 SAFETY VALVE 6.000 2 C
SP O
"B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1-MS-SV-105C 11715-CBM-0708 3 0F 3 D5 SAFETY VALVE 6.000 2 C
SP O
"C" MAIN STEAM NEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 1 MS TV-101A 11715-CBM-0708 1 0F 3 D4 A0 OISC 32.000 2 B
EV C
16 FS C
16 ST C
16 VP OC "A" MAIN STEAM HEADER TRIP VALVE 1-MS TV-1018 11715-CBM 0708 2 0F 3 C4 A0 DISC 32.000 2 B
EV C
16 FS C
16 ST C
16 VP OC "B" MAIN STEAM HEADER TRIP VALVE 1 MS-TV-101C 11715-CBM-0708 3 0F 3 C4 A0 DISC 32.000 2 B
EV C
16 FS C
16 '
ST C
16 VP OC "C" MAIN STEAM HEADER TRIP VALVE 1-MS-TV-109 11715-CBM 070A 1 0F 3 A8 A0 GLOBE 3.000 2 B
EV C
14 FS C
14 ST C
14 VP OC MAIN STEAM MIGH PRESSURE DRAIN ISOLATION To CONDENSER 1-MS-TV-110 11715-CBM 0708 3 0F 3 A4 A0 GLOBE 1.500 2 B
EV C
FS C
ST C
VIRGIN!A POLER COMPANY PAGE:
63 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER WUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1-MS-TV 110 11715 CBM-0708 3 0F 3 A4 A0 GLOBE 1.500 2 B
VP OC MAIN STEAM N!GN PRESSURE DRAIN HEADER 150-LATION TO STEAM GENERATOR BLone0WN SYSTEM 1 MS TV 111A 11715 CBM-070A 3 0F 3 E5 A0 GLOBE 3.000 2 5
EV C
0 FS O
ST C
0 VP OC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1-MS TV-1118 11715 CBM 070A 3 OF 3 E4 A0 GLOBE 3.000 2 B
EV C
0 FS 0
ST C
0 VP OC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 1-MS-TV 113A 11715-CBM-0708 1 OF 3 D4 A0 GLOBE 3.000 2 B
EV C
33 FS C
33 ST C
33 VP OC "A" MAIN STEAM TRIP BYPASS VALVE 1-MS-TV-1138 11715-CBM-0708 2 OF 3 D4 A0 GLOBE 3.000 2 8
EV C
33 FS C
33 ST C
33 VP OC "B" MAIN STEAM TRIP BYPASS VALVE 1-MS TV-113C 11715-CBM 0708 3 0F 3 D4 A0 GLOBE 3.000 2 B
EV C
33 FS C
33 ST C
33 VP OC "C" MAIN STEAM TRIP BYPASS VALVE 1 MS TV 115 11715 CBM 070A 3 0F 3 C4 MECH TRIP VLV 3.000 3 E
VP OC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AFW PUMP 1
i I
l
^
VIRGINIA POWER COMPANY PAGE:
44 0F 78 NORTN ANNA UNIT 1 REVISIDW: 07 SECOND INSPECT!DN INTERVAL DATE: 08/08/M 1
INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING
$NEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLMBER NUMBER COOR TYPE
$1ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-THIS PAGE IS INTENTIONALLY BLANK.
VIRGINIA poler IIBFAlff PAGE 45 0F 78 IIORTN AMA tal!T 1 REVISION: 07 SECCIS IllSPECTION liffERVAL DATE: 01/10/95 INSERVICE TESTIM PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWIIIG SNEET ORWG VALVE VALVE ASIE IW VALVE TEST TEST REQ JUST TEST lasetiR ItaSER IRSSER C00R TYPE SIZE CLA*S CAT TYPE TYPE POS V-CSV-VCN-1 08-011 11715-CBM-091A 2 0F 4 D6 WL CNECK VLV 8.000 2 AC CIV CV C
67 0
67 LT C
"A" REllCN SPN4T MAP INSIDE CONTAlleENT ISOLATION CUECL VALVE 1 08 019 11715-cam 091A 2 OF 4 E6 WL CNECK VLV 8.000 2 AC CIV CV C
67 0
67 LT C
"S" EERICN SPRAY MAP IIISIDE CONTAIIRENT ISOLATICII CIIECK VALVE 1-08 MOV 1004 11715-CSM-091A 2 0F 4 A3 100 GATE 10.000 2 E
VP OC "A" E ENCN SPRAY PLar SUCTION ISCLATION VAI.VE FRCpt REFLELIllG WATER STORAGE TANK 1 08 MOV 1005 11715 cam 091A 2 0F 4 A3 M0 GATE 10.000 2 E
VP OC "S" OUENCH SPRAY MaqP SUCTIosi ISOLATION VAL'd FROM RERELIIIG WATER STORAGE TANK 1 0$-It0V 101A 11715 cam-091A 2 of 4 05 MD GATE 8.000 2 A CIV EV C
0 LT C
ST C
0 VP OC "A" Gufl1CN SPRAY MSIP DISCilARGE ISOLATION VALVE, CUTSIDE CONTAINMENT ISOLATION VALVE 1-05-It0V 1018 11715-CDM 091A 2 0F 4 E5 000 GATE 8.000 2 A CIV EV C
0 LT C
ST C
0 VP OC "S" QUENCH SPRAY MaqP DISCNARGE ISOLATIcel VALVE, CUTSIDE CONTAIIDENT ISOLATICII VALVE 1 05-MOV-102A 11715 CSM 091A 1 0F 4 05 M0 GATE 6.000 2 8
EV 0
44 ST 0
44 VP OC CNEMICAL ADDITIcel TANC DISCNARGE ISOLATION VALVE 1-QS 600V 1028 11715 CSM-091A 1 0F 4 06 100 GATE 6.000 2 8
EV 0
44 ST C
44 VP OC CHEMICAL ADOITIcel TANK DISCMARGE ISOLATION VALVE
VIRGINIA POWER COMPANY PAGE:
69 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECONO INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWIWG SHEET DRWG VI.LVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBFR NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-
...................n.
1 RN-007 11715 CBM-094A 1 0F 2 E5 CHECK VALVE 10.000 2 C
CV C
46 0
46 "B" RHR PLMP DISCHARGE CHECK VALVE 1 RH 015 11715-CBM-094A 1 of 2 E7 CHECK VALVE 10.000 2 C
CV C
46 0
46 "A" RNR PUMP DISCHARGE CHECK VALVE I
1 RN-036 11715-CBM-094A 2 of 2 C4 MANUAL GATE 6.000 2 AE CIV LT C
RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, INSIDE CONTAINMENT I;OLATION VALVE 1-RH 037 11715-CBM-094A 2 0F 2 E3 MANUAL GATE 6.000 2 AE CIV LT C
RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, OUTSIDE CONTAlWMENT ISOLATION VALVE 1-kH-MOV-1700 11715-CBM 094A 1 0F 2 A5 Mo GATE 14.000 1 B
EV O
18 ST 0
18 Vo DC RHit PUMP SUPPLY ISCtATION FROM "A" HOT LEG, INS;DE MISSILE BARRIER 1 RM MOV-1701 11715-CBM-094A 1 0F 2 A4 MO GATE 14.000 1 B
EV 0
18 ST 0
18 VP OC RHR PUMP SUPPLY ISOLATION FROM "A" HOT LEG, DJTSIDE MISSILE BARRIER 1-RH-MOV-1720A 11715-CBM 094A 2 0F 2 C3 MO GATE 10.000 1 B
EV O
18 ST 0
18 VP OC i
RHR RETURN ISOLATION To "B" ACCUMULATOR DISCHARGE LINE l
1 RH-MOV 1720B 11715-CBM 094A 2 0F 2 B3 M0 GATE 10.000 1 B
EV O
18 ST C
18 VP OC RHR RETURN ISOLATION TO "C" ACCUMULATOR DISCHARGE LINE 1-RH RV-1721A 11715 CBM-094A 10F 2 E6 RELIEF VALVE 3.000 2 C
SP 0
RHR SYSTEM RELIEF VALVE AT "A" RNR PUMP SUC-TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK SIii$RhIifiiB'"lifi$I6Bi$694k'"i0F5'55"'R5Li5FELVi"" 3 666 E" " 6" " "' $P b' " ' " ' " ' " "
RHR SYSTEM RELIEF VALVE AT "B" RHR PUMP SUC-TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK l
VlasINIA PtBER OWNNY PAGE:
50 of 78 uCRTN Alma talli 1 REVISION: 07 SEC05 IIISPECTION INTERVAL.
DATE: 01/10/95 INSERVIM TESTillG PROGRAll
- VALVE TABLE NC ISO REL CS ALT VALVE DRAWIIIG SIEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST RE0 JUST TEST saseER meeER 1 RISER CDOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VEN-i 4
9 THIS PAGE IS INTENTIONALLY BLANK.
)
1 l
VIRGINIA Po6ER COMPANY PAGE:
56 0F 78 NORTH ANNA UNIT 1 REv!SION: 07 SECole INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTIM PROC 4AM
- VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS Va CSV-VCN-1-51-001 11715-COM-096A 1 0F 3 B7 CHECK VALVE 12.000 2 C
CV o
37 "A" LOW HEAD $1 PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 1 51-004 11715 CeM-096A 1 of 3 C7 CHECK VALVE
.750 2 AC CV C
53 LT C
"A" LOW HEAD SI PUMP SEAL WATER SUPPLY CHECK VALVE FROM RWST 1 51 009 11715-cam-096A 2 0F 3 B6 CHECK VALVE 10.000 2 C
CV C
38 i
0 38
\\
"A" LOW HEAD St PLMP DISCHARGE CHECK '!ALVE i
1 51-012 11715 CeM 096A 2 OF 3 B5 CHECK VALVE 2.000 2 C
CV 0
"A" LOW HEAD St PUMP MINIMUM FLOW /TIST LINE DISCHARGE CHECK VALVE 1-51-016 11715 CSM-096A 1 0F 3 B5 CHECK VALVE 12.000 2 C
CV 0
37
\\
"S" LOW HEAD $1 PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 1-51-018 11715-C8M 096A 1 0F 3 B3 CHECK VALVE 12.000 2 C
CV o
38 RWST SUPPLY CHECK VALVE TO "B" LOW HEAD SI J
PUMP SUCTION 1 SI-021 11715 CBM 096A 1 0F 3 c5 CHECK VALVE
.750 2 AC CV C
53 LT C
"B" LOW HEAD St PUMP SEAL WATER SUPPLY CHECK VALVE 1-SI-026 11715-C8M 096A 2 0F 3 B4 CHECK VALVE 10.000 2 C
CV C
38 0
38 l
I "B" LOW HEAD St PUMP DISCHARGE CHECK VALVE r
l 1-$1-029 11715-CBM-096A 2 0F 3 B4 CHECK VALVE 2.000 2 C
CV 0
"B" LOW HEAD $1 PUMP MINIMUM FLOW / TEST LINE DISCHARGE CHECK VALVE 1 SI-047 11715-CBM-096A 1 0F 3 E5 CHECK VALVE 8.000 2 AC CV C
39 0
39 LT C
75 RWST SUPPLY CHECK VALVE TO CHARGING PUMP SUCTION HEADER 1-S1-058 11715-CBM-0964 1 0F 3 E7 MANUAL GLOSE 1.000 2 AE CIV LT C
ACCUMULATOR MAKEUP LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 51-066 11715-CBM 096A 3 0F 3 D4 CHECK VALVE 1.000 2 C
CV C
l i
l
V!ROINIA POWER COMPANY PAGE:
60 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE
$!ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1 SI NCV 1936 11715-cam 0968 1 0F 4 E5 A0 GATE 1.000 2 A CIV EV C
FS C
LT C
ST C
VP OC WASTE GAS FROM ACCUMULATORS TO CHARCOAL FILTERS 1 SI-MOV-1836 11715-COM-096A 3 0F 3 CS MO GATE 3.000 2 A CIV EV C
23 0
23 LT C
ST C
23 0
23 VP OC HIGH HEAD $1 FROM CHARGING HEADER TO RCS COLD LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-S!-MOV-1860A 11715-CBM 096A 1 0F 3 B7 MO GATE 12.000 2 B
EV C
0 ST C
0 VP OC "A" LOW HEAD SI PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP 1-SI-MOV-18608 11715-CBM-096A 1 0F 3 B5 MO GATE 12.000 2 B
EV C
0 ST C
0 VP OC "B" LOW HEAD $1 PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP 1 S!-MOV-1862A 11715-CBM-096A 1 0F 3 m3 MO GATE 12.000 2 8
EV C
ST C
VP OC "A" LOW HEAD $1 PUMP SUCTION FROM RWST 1-SI MOV-1862B 11715-CsM 096A 1 0F 3 83 M0 GATE 12.000 2 B
EV C
ST C
VP OC "B" LOW HEAD St PUMP SUC?s0N FROM RWST 1-SI-Mov 1863A 11715-CsM-U96A ? 0F 3 C5 M0 GATE 8.000 2 B
EV C
0 ST C
0 VP OC "A" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 1 SI Mov-18638 11715 CBM-096A 2 0F 3 D4 MO GATE 8.000 2 8
EV C
0 ST C
0
VIRGIN!A POWER COMPANY PAGE:
61 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER C00R TYPE
$12E CLASS CAT TYPE TYPE POS V-CSV-VCN-I 1 St MOV 18638 11715-CSM 096A 2 0F 3 D4 M0 GATE 8.000 2 B
VP OC "B" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 1 SI-MOV-1864A 11715-CsM 096A 2 0F 3 C7 No GATE 10.000 2 B
EV C
0 ST C
0 VP OC "A" LOW HEAD SI PUMP COLD LEG DISCHARGE STOP l
VALVE 1-St-MOV-18648 11715-CeM-096A 2 0F 3 C6 MO GATE 10.000 2 B
EV C
0 ST C
0 VP OC "B" LOW HEAD St PUMP COLD LEG DISCHARGE STOP VALVE 1 SI-MOV-1865A 11715-CeM-0968'? 1 0F 4 C7 M0 GATE 12.000 2 8
EV C
24
)
0 24 y;
ST C
24 0
24 VP OC "A" ACCUMULATOR DISCHARGE ISOLATION VALVE TC.
2CS COLD LEG 1-SI MOV 1865B 11715-cam-0965 2 0F 4 c5 Mo CATE 12.000 2 8
EV C
24 0
24 ST C
24 0
24 VP OC "B" ACCUMULATOR DISCHARGE ISOLATION VALVE To RCS COLD LEG 1 SI Mov 1865C 11715 CBM 0968 3 0F 4 CS M0 GATE 12.000 2 B
EV C
24 0
24 ST C
24 0
24 VP OC "C" ACCUMULATOR DISCHARGE ISOLATION VALVC TO RCS COLD LEG l
l 1-SI-MOV-1867A 11715 CBM-096A 3 0F 3 D4 M0 GATE 3.000 2 B
EV C
0 ST C
0 VP OC BORON INJECTIOR TANK HIGH HEAD SI INLET VALVE 1 SI MOV 1867B 11715 COM 096A 3 0F 3 D4 MO GATE 3.000 2 B
EV C
0 ST C
0 VP OC i
j
VIRGINIA POWER COMPANY PAGE:
62 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLF NC ISO REL CS ALT VALVE DRAWING SHEET DRWG YALVE VALVE ASME IWV bALVE TEST TEST REQ JUST TEST NLBISER NLMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-BORON INJECTION TANK HIGH HEAD $1 INLET VALVE 1 SI-MOV 1867C 11715-cam-096A 3 0F 3 ET MO GATE 3.000 2 A CIV EV C
0 LT C
59 ST C
0 VP OC BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-MOV-1867D it715-CsM 096A 3 0F 3 D7 No GATE 3.000 2 A CIV EV C
0 LT C
59 ST C
0 VP OC BORON INJECTION TAWK OUTLET TO RCS COLD LEG, OUTS!DE CONTAINMENT ISOLATION VALVE 1-SI MOV 1869A 11715-CSM-096A 3 0F 3 C8 M0 GATE 3.000 2 A CIV EV C
23 0
23 LT C
ST C
23 0
23 VP OC HIGH HEAD $1 FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-MOV-18698 11715-COM-096A 3 0F 3 88 Mo GATE 3.000 2 A CIV EV C
23 0
23 LT C
ST C
23 0
23 VP OC HIGH HEAD SI FROM CHARGING HEADER To RCS NOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-51-MOV-1885A 11715-CSM 096A 2 0F 3 C3 Mo GlosE 2.000 2 A
EV C
LT C
75 ST C
W K
j "A" LOW HEAD SI PUMP MINIMUM FLOW / TEST LINE ISOLATION 1-SI-MOV 1885B 11715-CBM 096A 2 0F 3 B3 MO GLOSE 2.000 2 A
EV C
LT C
75 ST C
VP OC "B" LOW HEAD $1 PUMP MINIMUM FLOW / TEST LINE ISOLATION 1-SI MOV-1885C 11715-CBM-0964 2 0F 3 D3 M0 GLOSE 2.000 2 A
EV C
LT C
75 ST C
VP OC
VIRGINIA POWER COMPANY PAGE:
63 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST InsWER NUMBER NLMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-
"A" LOW HEAD $1 PUMr %!N19EJM FLOW / TEST LINE ISOLATION 1-SI Mov 1885D 11715-Cam-096A 2 0F 3 B3 MO GLOBE 2.000 2 A
EV C
LT C
75 ST C
VP OC "B" LOW HEAD SI PUMP MIN! MUM FLOW / TEST LINE ISOLATION 1 51-MOV-1890A 11715 CSM 096A 2 0F 3 D7 M0 GATE 10.000 2 A CIV EV C
23 0
23 LT C
ST C
23 0
23 VP OC "A" LOW NEAD SI PUMP NOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI MOV-1890s 117!5-CsM 096A 2 0F 3 D7 MO GATE 10.000 2 A CIV EV C
23 0
23 LT C
ST C
23 0
23 VP OC "B" LOW HEAD St PUMP MOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI-MOV-1890C 11715 CsM 096A 2 0F 3 C8 MO GATE 10.000 2 A CIV EV C
0 LT C
59 ST C
0 i
VP OC LOW HEAD $1 PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI MOV-18900 11715-CBM 096A 2 0F 3 C7 M0 GATE 10.000 2 A CIV EV C
0 LT C
59 ST C
0 VP OC LOW NEAD St PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1 SI RV-1845A 11715-cam-096A 2 OF 3 D6 RELIEF VALVE
.750 2 C
SP O
"A" LOW HEAD SI PLMP DISCHARGC RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 1 SI-RV-18458 11715-CeM-096A 2 0F 3 C7 RELIEF VALVE
.750 2 C
SP 0
LOW NEAD SI HEADER TO COLD LEG RELIEF VALVE, RV DISCHAar.E TO CAFEGJARDS AREA SUMP 1 SI-RV-1845C 11715-CBM-096A 2 0F 3 C6 RELIEF VALVE
.750 2 C
SP O
1
)
VIRGINIA poler COMPANY PAGE:
68 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER 1RMBER C00R TYPE
$1ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1 SW-0003 11715-CBM-078A 3 0F 4 D7 CHECK VALVE 20.000 3 C
CV C
63 0
63 UNIT 1 "A" SERVICE WATER PUMP DISCHARGE CHECK VALVE 1 SW-0010 11715-COM-078A 3 0F 4 D6 CHECK VALVE 20.000 3 C
CV C
63 0
63 UNIT 1 "B" SERVICE WATER PUMP DISCHARGE CHECK VALVE 1-$W-0022 11715-COM-078A 1 0F 4 C3 CHECK VALVE 24.000 3 C
CV C
0 73 UNIT 1 AUXILIARY SERVICE WATER PUMP DISCHARGE CHECK VALVE 1-SW-0114 11715-COM-078B 1 0F 4 F8 CHECK VALVE 24.000 3 C
CV 0
45 "A" SERVICE WATR HEADER SUPPLY CHECK VALVE TO RECIRC SPRAY HX UPSTREAM OF CROSS CONNECT 1-SW-0116 11715-COM-078B 1 0F 4 F8 CHECK VALVE 24.000 3 C
CV O
45 "B" SERVICE WATR HEADER SUPPLY CHECK VALVE TO RECIRC SPRAY HX UPSTREAM OF CROSS CONNECT 1-SW-0120 11715-COM-078B 1 0F 4 E3 CHECK VALVE 16.000 2 C
CV o
45 "A" RECIRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE 1-SW-0130 11715 COM-078B 1 0F 4 E4 CHECK VALVE 16.000 2 C
CV 0
45 "B" RECIRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE 1-SW-0140 11715-COM-078B 10F 4 E6 CHECK VALVE 16.000 2 C
CV 0
45 "C" REClRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE i
k$hh$bkhb~
kk7kh$bEbhbb k~b Uk~Eh bHEbK hkthh ibbbbh b"
bV b
kh "D" RECIRC SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY CHECK VALVE 1 SW 0251 11715-CBM 078C 2 0F 2 88 MANUAL GATE 4.000 3 8
EV C
SERVICE WATER SUPPLY MAUNAL ISOLATION VALVE 1-SW 0252 11715-CBM-078C 2 0F 2 58 CHECK VALVE 4.000 3 C
CV o
SERVICE WATER SUPPLY CHECK VALVE 1-SW-0254 11715-CBM 078C 2 0F 2 B8 MANUAL GATE 4.000 3 B
EV C
SERVICE WATER SUPPLY MAUNAL ISOLATION VALVE 1-SW 0255 11715 CBM-078C 2 0F 2 68 CHECK VALVE 4.000 3 C
CV 0
I
VIRGINIA POWER COMPANY PAGE:
69 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TEST!hG PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASE IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-SERVICE WATER SUPPLY CHECK VALVE 1-SW-0285 11715-cam-078C 2 OF 2 58 MANUAL GATE 4.000 3 8
EV C
SERVICE WATER RETURN MAUNAL ISOLATION VALVE 1 SW-0286 11715-CeM-078C 2 0F 2 B8 MANUAL GATE 4.000 3 B
EV C
SERVICE WATER RETURN MAUNAL ISOLATION VALVE 1 SW-0364 11715 CBS-0400 1 0F 3 E7 CHECK VALVE 4.000 NC C
CV 0
SERVICE WATER SUPPLY TO CONTROL ROOM CONDENSER WATER PUMPS 1 SW-0386 11715-Cas-040D 1 OF 3 CT CHECK VALVE 4.000 NC C
CV O
SERVICE WATER SUPPLY TO CONTROL ROOM CONDENSER WATER PUMPS 1-SW-0420 11715-Cas-0400 1 0F 3 A7 CHECK VALVE 4.000 NC C
CV 0
SERVICE WATER SUPPLY TO CONTROL ROOM CONDENSER WATER PUMPS 1 SW-0630 11715-COM 078G 1 0F 2 E8 CHECK VALVE 2.000 3 C
CV 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE 0!L COOLER CHECK VALVE 1-SW-0631 11715 CBM-078G 1 0F 2 E7 CHECK VALVE 2.000 3 C
CV 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE DIL COOLER CHECK VALVE 1 SW-0641 11715-CsM 078G 1 08 2 E6 CHECK VALVE 2.000 3 C
CV 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 1 SW 0644 11715-CBM-078G 1 0F 2 E7 CHECK VALVE 2.000 3 C
CV o
35 SERVICE WATER SUPPLY To CHARGING PUMP SEAL COOLER CHECK VALVE 1-SW 0647 11715-COM-078G 10F 2 E6 CHECK VALVE 2.000 3 C
CV o
35 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE OIL COOLER CHECK VALVE 1 SW 0648 11715 cam-078G 1 0F 2 E6 CHECK VALVE 2.000 3 C
CV o
35 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE CIL COOLER CHECK VALVE 1-SW-0658 11715-CBM 078G 1 of 2 E5 CHECK VALVE 2.000 3 C
cv 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE
VIRGINIA POWER COMPANY PAGE:
70 OF 78 NORTH ANNA UNIT 1 REVISION: 07 SECON0 INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE
$12E CLASS CAT TYPE TYPE POS V-CSV-VCN-1 1 SW-0661 11715-COM-078G 1 0F 2 E5 CHECK VALVE 2.000 3 C
CV 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CNECK VAL %i 1 SW-0664 11715-CBM-078G 1 (# 2 E4 CHECK VALVE 2.000 3 C
CV 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE OIL COOLER CHECK VALVE 1 SW-0665 11715 C8M-078G 1 0F 2 E4 CHECK VALVE 2.000 3 C
cv 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP LUBE DIL COOLER CHECK VALVE i
1-SW 0678 11715-CsM-078G 1 0F 2 A3 MANUAL GATE 4.000 3 B
EV C
SERVICE WATER RETURN MAUNAL ISOLATION VALVE 1 SW-0679 11715-cam 078G 1 0F 2 B3 MANUAL GATE 4.000 3 B
EV C
SERVICE WATER RETURN MAUNAL !$0LATION VALVE 1
1-SW 0681 11715 cam 078G 1 0F 2 F3 MANUAL GATE 4.000 3 B
EV C
SERVICE WATER SUPPLY MAUNAL ISOLATION VALVE j
1 SW-0686 11715-C8M-078G 1 0F 2 E3 CHECK VALVE 2.000 3 C
CV 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 1 SW-0689 11715-CBM 078G 1 0F 2 E3 CHECK VALVE 2.000 3 C
CV 0
35 SERVICE WATER SUPPLY TO CHARGING PUMP SEAL COOLER CHECK VALVE 1-SW-0694 11715-CBM-078G 1 0F 2 F3 MANUAL GATE 4.000 3 B
EV C
SERVICE WATER SUPPLY MAUNAL ISOLATION VALVE 1-SW-1067 11715-CBM 078A 3 OF 4 E7 MANUAL GATE 1.000 3 B
EV C
45 j
SERVICE WATER CHEMICAL ADDITION SYSTEM MANUAL ISOLATION VALVE 1 SW-1070 11715-CBM-078A 3 0F 4 F7 MANUAL GATE 1.000 3 B
EV C
45 SERVICE WATER CHEM ADDITION SYSTEM MANUAL ISOLAfl0N VALVE 1-SW-1139 11715 CDM-078A 3 0F 4 E7 MANUAL GATE 1.500 B
EV C
45 SERVICE WATER CHEM ADDITION SYSTEM MANUAL ISOLATION VALVE 1-SW-MOV-101A 11715 CBM 078A 4 0F 4 B3 M0 BFLY 24.000 3 B
EV O
34 ST 0
34 VP OC I
i
. ~
J l
VIRGINIA P0lER COMPANY PAGE:
71 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM VALVE TABLE
(
i NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER 1RMBER NLMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-l j
"A" SERVICE WATER NEADER SUPPLY ISOLATION T0 i
RECIRC SPRAY MEAT EXCHANGERS 1-SW-MOV 101B 11715 CMM-078A 4 of 4 53 No BFLY 24.000 3 s
EV 0
34 ST o
34 VP OC "A" SERVICE WATER NEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXLNANGERS 1 SW-MOV-101C 11715-CBM-078A 4 0F 4 53 M0 BFLY 24.000 3 B
EV o
34 j
ST 0
34 VP OC "B" SERVICE WATER NEADER SUPPLY ISOLATION To i
RECIRC SPRAY NEAT EXCHANGERS j
1 SW-MOV-101D 11715-CeM 078A 4 0F 4 C3 M0 BFLY 24.000 3 8
EV 0
34 ST 0
34 i
VP OC i
"S" SERVICE WATER NEADER SUPPLY ISOLATION TO j
RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-102A 11715-COM 078B 1 0F 4 F8 M0 BFLY 24.000 3 B
EV C
ST C
VP OC SERVICE WATER SUPPLY CROSS CONNECTS TO RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-1028 11715-CBM 0788 1 0F 4 F8 Mo BFLY 24.000 3 B
EV C
ST C
VP OC SERVICE WAIER SUPPLY CROSS CONNECTS TO RECIRC SPRAY HEAT EXCHANGERS
)
j 1-SW-MOV-103A 11715-cam-0788 1 0F 4 E3 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER SUPPLY 70 "A" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1 SW MOV 1038 11715-CSM 078B 1 0F 4 E4 M0 BFLY 16.000 2 A CIV EV C
O LT C
ST C
0 VP OC SERVICE WATER SUPPLY TO "B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE
(
1-SW MOV-103C 11715-C8M 078B 1 0F 4 E6 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0
VIRGINIA POWER COMPANY PAGE:
72 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING
$NEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1 SW MOV-103C 11715 CBM 0788 1 0F 4 E6 M0 BFLY 16.000 2 A CIV VP OC SERVICE WTER SUPPLY 70 "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV 1030 11715 CBM 0788 1 0F 4 E7 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER SUPPLY 70 "D" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1 SW-MOV-104A 11715-CBM-0788 1 OF 4 C3 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER RETURN FROM "A" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV 1048 11715-CBM-0788 1 0F 4 CS M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER RETURN FROM "B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-104C 11715-CBM-0788 1 0F 4 C6 MO BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER RETURN FROM "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT !$0LATION VALVE 1-SW-MOV-104D 11715-CBM-0788 10F 4 C7 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER RETURN FROM "D" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1 SW-MOV-105A 11715 CBM-078A 4 0F 4 C3 M0 BFLY 24.000 3 B
EV 0
34 ST 0
34 VP OC "B" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC SPRAY HEAT EXCHANGERS 1 SW-MOV 1058 11715+CBM-078A 4 0F 4 C3 M0 BFLY 24.000 3 B
EV o
34 ST 0
34 1
i I
J
VIRGINIA POWER COMPANY PAGE:
73 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM. VALVE TABLE l
NC 1
ISO REL CS ALT VALVE c1 AWING SNEET DRWG VALVE VALVE ASE IW VALVE TEST TEST REQ JUST TEST i
NUMBER JAMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-I i
1 SV Mov-sD5B 11715 CBM-078A 4 0F 4 C3 Mo BFLY 24.000 3 B
VP OC "B" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC SPRAY HEAT EXCHANGERS j
1 SW-MOV-105C 11715 CBM 078A 4 0F 4 C3 M0 BFLY 24.000 3 B
EV 0
34 i
ST 0
34 VP OC "A" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC SPRAY MEAT EXCHANGERS 1-SW-MOV-1050 11715-CBM-078A 4 0F 4 C3 M0 BFLY 24.000 3 B
EV 0
34 ST 0
34 l
VP OC "A" SERVICE WATER HEADER RETURN ISOLATION FROM RECIRC SPRAY HEAT EXCHANGERS 1 SW-MOV-106A 11715-CBM 0788 1 0F 4 B8 M0 BFLY 24.000 3 B
EV C
ST C
VP OC SERVICE WATER RETURN CROSS CONNECTS FROM RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-1068 11715-CBM-0788 1 0F 4 A8 M0 BFLY 24.000 3 8
EV C
ST C
VP OC SERVICE WATER RETURN CROSS CONNECTS FROM RECIRC SPRAY HEAT EXCHANGERS I
1-SW-MOV 108A 11715-CBM 078C 1 0F 2 B3 M0 BFLY 24.000 3 B
EV C
43 0
43 ST C
43 0
43 VP OC "A" SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1-SW MOV 108B 11715-CBM-078C 1 0F 2 B3 M0 BFLY 24.000 3 B
EV C
43 0
43 ST C
43 0
43 VP OC "A" SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1-SW-MOV-110A 11715-CBM 078A 4 0F 4 C4 M0 BFLY 8.000 3 E
VP OC SERVICE WATER HEADER SUPPLY TO RECIRCULATION AIR COOLERS 1 SW-Mov-110B 11715-CBM 078A 4 0F 4 C4 M0 BFLY 8.000 3 E
VP OC SERVICE WATER HEADER SUPPLY TO RECIRCULATION AIR COOLERS 1 SW MOV-113A 11715 CBM 078A 4 0F 4 87 M0 BFLY 10.000 3 E
VP OC
VIRGIN!A POWER COMPANY PAGE:
76 0F 78 WORTH ANNA UNIT 1 RFVISION: 07 SECOND INSPECTION INTERVAL DAiE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLMBER IAMBER COOR TYPE
$1ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-SERVICE WATER RETURN ISOLATION FROM FUEL PIT COOLERS 1 SW-MOV 1130 11715-CBM-078A 4 0F 4 B5 M0 SFLY 10.000 3 E
VP OC SERVICE WATER SUPPLY ISOLATION TO FUEL PIT COOLERS 1-SW-MOV 114A 11715-CBM-078A 4 0F 4 C4 M0 SFLY 8.000 3 E
VP OC SERVICE WATER NEADER RETURN FROM REclRCULATION AIR COOLERS 1-SW-MOV-1148 11715-CBM 07BA 4 0F 4 C4 M0 BFLY 8.000 3 E
VP OC SERVICE WATER NEADER RETURN FROM RECIRCULATION AIR COOLERS 1-SW-MOV 115A 11715-CBM 078A 1 0F 4 E7 M0 BFLY 24.000 3 8
EV 0
ST 0
VP OC SERVICE WATER NEADER SUPPLY ISOLATION VALVE FROM AUXILIARY SERVICE WATER PUMPS 1-SW-MOV-117 11715-CDM 078A 1 0F 4 C3 M0 BFLY 24.000 3 B
EV 0
ST 0
VP OC UNIT 1 AUXILIARY SERVICE WATER PUMP DISCHARGE ISOLATION VALVE 1-SW-MOV-118 11715 CBM-078A 10F 4 D4 M0 BFLY 24.000 3 E
VP OC AUXILIARY SERVICE WATER SUPPLY HEADER CROSS CONNECT VALVE 1-SW MOV-119 11715-CBM-078A 1 0F 4 D4 M0 BFLY 8.000 3 B
EV C
ST C
VP OC MAKEUP PUMP SUPPLY YALVE 1-SW-Mov-120A 11715-CBM 078A 4 0F 4 F3 M0 BFLY 10.000 NC E
VP OC AUXILIARY SERVICE WATER RETURN HEADER VALVE 1 SW-Mov 1208 11715-CBM 078A 4 0F 4 F3 M0 BFLY 10.000 NC E
VP OC AUXILIARY SERVICE WATER RETURN HEADER VALVE 1 SW MOV-121A 11715-CBM-078H 1 0F 1 B5 M0 BFLY 18.000 3 5
EV 0
ST 0
VP OC SERVICE WATER TO SPRAY ARRAYS STOP VALVE 1 SW-Mov-121B 11715 CBM-078H 1 0F 1 B7 M0 BFLY 18.000 3 B
EV O
ST 0
f-VIRGINIA POWER COMPANY PAGE:
75 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST 1EST REQ JUST TEST NUMBER NUMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1 SW-MOV-121B 11715-CBM-078N 1 0F 1 B7 MO BFLY 18.000 3 B
VP OC SERVICE WATER TO SPRAY ARRAYS STOP VALVE 1 SW-MOV 122A 11715-CBM 078N 1 0F 1 CS M0 SFLY 18.000 3 5
EV 0
ST 0
VP OC SERVICE WATER TO SPRAY ARRAYS STOP VALVE 1 SW-Mov-1228 11715 CBM-078N 1 0F 1 C6 M0 BFLY 18.000 3 5
EV 0
ST 0
VP OC SERVICE WATER 70 SPRAY ARRAYS STOP VALVE 1-SW-MOV 123A 11715-CBM-0784 1 0F 1 E4 M0 SFLY 24.000 3 B
EV C
ST C
VP OC SERVICE WATER BYPASS VALVE 1-SW-MOV-1238 11715 CBM 078N 1 0F 1 E8 M0 BFLY 24.000 3 S
EV C
ST C
VP OC i
SERVICE WATER BYPASS VALVE 1-SW-RV-100A 11715-CBM-078B 1 0F 4 E3 RELIEF VALVE
.750 2 C
SP O
"A" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1-SW-RV-1008 11715-CBM 078B 1 0F 4 E4 RELIEF VALVE
.750 2 C
SP 0
"B" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1-SW-RV 100C 11715 CBM 078B 1 0F 4 E6 RELIEF VALVE
.750 2 C
SP O
l "C" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1-SW RV-1000 11715-CBM 078B 10F 4 E7 RELIEF VALVE
.750 2 C
SP O
"D" RECIRC SPRAY MEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 1-SW TCV-102A 11715 CBM 078G 1 0F 2 C4 A0 GATE 2.000 3 B
EV 0
FS 0
ST 0
SERVICE WATER FROM CHARGING PUMP LUBE OIL COOLER TEMP CONTROL VALVE 1-SW-TCV 1028 11715 CBM 078G 1 0F 2 C6 A0 GATE 2.000 3 B
EV 0
FS O
ST 0
e
VIRGINIA POWER COMPANY PAGE:
750 0F 78 NORTH ANNA UNIT 1 REVISION: 07 SECONO INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-SERVICE WATER FROM CHARGING PUMP LUBE DIL C00 lek TEMP CONTROL VALVE 1 SW-TCV 102C 11715-CBM-078G 1 0F 2 C8 A0 GATE 2.000 3 B
EV 0
FS 0
ST 0
SERVICE WATER FROM CHARGING PLMP LUBE CIL COOLER TEMP CONTROL VALVE 2 SW MOV 2158 11715 CBM-078A 1 0F 4 E6 M0 BFLY 24.000 3 8
EV O
ST 0
VP DC SERVICE WATER HEADER SUPPLY ISOLATION VALVE FROM AUXILIARY SERVICE WATER PLMPS h
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RELIEF REQUEST V-38 I.
IDENTIFICATION OF COMPONENTS System Safety Injection Valve (s):
1-SI-9 1-SI-18 1-SI-26 Class 2
II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months i
III. BASIS FOR RELIEF Due to system design, check valves 1-SI-9 and 26 are not in the Low Head Safety Injection Pump test flowpaths.
They cannot be full or pe.-t-stroke tested during power operation because the LHSI pumps cannot overcome reactor coolant system pressure.
Valve 1-SI-18 can only be partial stroked every quarter because the quarterly test loop is a mini-flow loop.
During cold shutdown, the reactor coolant system pressure still prevents full flow testing of the check valves.
Partial stroke exercising the valves with flow could cause an overpressurization condition during cold shutdowns.
To verify closure of Valves 1-SI-9 and 26, the low head safety injection system must be isolated which can only be done at reactor refueling.
By isolating the system, the test boundary is established to demonstrate adequate seat tightness for the discharge valve to the non-running pump.
i IV. ALTERNATE TESTING I
Valves 1-SI-9 and 26 will be exercised to the full open and closed position every reactor refueling (not to exceed 24 months).
Valve 1-SI-18 will be partial j
stroke tested every quarter and full flow tested every reactor refueling.
2-63 N1PVR7 Revision 7 January 10, 1995
,4
RELIEF REQUEST V-41 I.
IDENTIFICATION OF COMPONENTS System Safety Injection Valve (s):
1-SI-83 1-SI-195 1-SI-86 1-SI-197 1-SI-89 1-SI-199 Class 1
l-II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These Safety Injection check valves must open and close to fulfill their safety functions.
They cannot be full 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 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.
With low head pump flow, the cold leg injection val.ves 1-SI-83, 86, 89, 195, 197 and 199 will be nonintrusively monitored using a sampling plan every reactor refueling.
The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.
Per this plan, the valves will be placed into two groups with valves 1-SI-83, 86 and 89 in one group, and valves 1-SI-195, 197 and 199 in the other group.
During initial testing using nonintrusive techniques, each valve in the group will be verified as operable.
2-66 N1PVR7 Revision 7 August 8, 1995
RELIEF REQUEST V-41 (Cont.)
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.
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.
IV. ALTERNATE TESTING 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.
2-66a N1PVR7 Revision 7 August 8, 1995 m
4 RELIEF REQUEST V-42 I.
IDENTIFICATION OF COMPONENTS 1
i System Safety Injection Valve (s):
1-SI-125 1-SI-144 1-SI-127 1-SI-159 1-SI-142 1-SI-161 Class 1
II. IMPRACTICAL CODE REQUIREMENTS 1
Exercise valves for operability every three' months j
III. BASIS FOR RELIEF These valves cannot be partial or full flow tested during normal operation because the accumulator pressure (600 to 650 psig) is below Reactor Coolant System pressure and the injection of borated water would upset the reactor coolant chemistry.
During cold shutdown, the RCS pressure may still prevent full flow testing.
Also, discharging the I
accumulators would challenge the Low Temperature Overpressure Protection System.
A partial flow test is not practical during cold shutdowns.
The flow from the accumulator is dependent on the pressure differential between the accumulator and the RCS.
The pressure differential cannot be controlled to the fine degree necessary to preclude dumping too much water into the pressurizer, thus making it difficult to control pressurizer level while pressure is being reduced during cooldown.
Also, the RCS temperature is high during short cold shutdowns.
Dumping cold accumulator water into the RCS could thermally shock the system.
The accumulators must be isolated to verify closure using back flow for valves 1-SI-127, 144 and 161.
The small increase in 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.
l 2-67 N1PVR7 Revision 7 August 8, 1995
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RELIEF REQUEST V-42 (Cont.)
'The use of nonintrusive monitoring techniques are being 3
evaluated for confirming full disk movement.
If nonintrusive techniques can provide a " positive means" for verifying obturator movement, a sampling program will be used as described below due to the burden of applying these techniques in the field.
IV. ALTERNATE TESTING i
During the first refueling outage where nonintrusive techniques are used, all valves in the group will be tested to verify that the techniques verify valve obturator movement.
During subsequent refueling outages, flow testing will be performed on all valves in the group, but the nonintrusive techniques will be applied only to one sample valve in each group, on a rotating basis, unless indications of problems are identified.
In this case, all valves in the group will be subjected to the nonintrusive techniques.
Valves 1-SI-127, 144 and 161 are closest to the reactor coolant I
system and will be in one group, and valves 1-SI-125, 142 and 159 will be in the other group.
This sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.
{
The flow test will consist of discharging the accumulator from an initial pressure that is less than 600 psig.
Discharging the accumulator at a lower initial pressure reduces the severity of the transient and the risk of adverse effects on the reactor coolant system.
The low pressure test should provide enough flow to force the disk to the full open position.
If full disk movement cannot be confirmed using nonintrusive monitoring during the initial verification of obturatar movement, these valves will be placed into two groups and one valve from each group will be disassembled and inspected every other reactor refueling.
The justification for the extended disassembly and inspection schedule is available at the
- station, j
Valves 1-SI-127, 144 and 161 will be confirmed closed every reactor refueling.
2-68 N1PVR7 Revision 7 August 8, 1995 t.
RELIEF REQUEST V-43 I.
IDENTIFICATION OF COMPONENTS System.:
Safety Injection valve (s):
1-SI-79 1-SI-185 1-SI-211 1-SI-90 1-SI-201 1-SI-213 1-SI-95 1-SI-206 1-SI-99 1-SI-207 1
1-SI-103 1-SI-209 i
Class 1 for 1-SI-90, 95, 99, 103, 201, 209, 211 and 213 2 for 1-SI-79, 185, 206, 207 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months
)
III. BASIS FOR RELIEF These Safety Injection check valves must open and close to fulfill their safety function.
They cannot be full or part-stroke exercised to the open position during power operation because this would cause safety s
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
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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 t'he lines.
With low head pump flow, the hot leg injection valves 1-SI-95, 99, 103, 209, 211 and 213 will be nonintrusively monitored using a sampling plan every reactor refueling.
The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.
2-69 N1PVR7 Revision 7 August 8, 1995
RELIEF REQUEST V-43 (Cont.)
t During subsequent testing, nonintrusive verification will be performed for only one valve of the group on a l
rotating schedule each time the testing is performed, and the balance of the group will be flow tested.
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.
IV. ALTERNATE TESTING Exercise to the open and closed positions every reactor refueling.
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l 2-69a N1PVR7 Revision 7 August 8, 1995
RELIEF REQUEST V-50 Relief Request Withdrawn F
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2-75 N1PVR7.
Revision 7 August 8, 1995
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RELIEF REQUEST V-72 I.
IDENTIFICATION OF COMPONENTS System Chemical & Volume control System Valve (s):
1-CH-215 1-CH-649 Class 2
II. IMPRACTICAL CODE REQUIREMENTS Exercise. valve closed every three months III. BASIS FOR RELIEF 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 t
isolated to 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 every reactor refueling.
Verification of closure will be performed during the leak test every reactor refueling instead of every cold shutdown l
because the small increase in safety gained by testing during cold shutdown does not justify the burden of performing a leak rate test.
~
IV. ALTERNATE TESTING Exercise to the closed position every reactor refueling.
2-99 N1PVR7 Revision 7 January 10, 1995 r.
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4 RELIEF REQUEST V-74 J
l Replaced by Cold Shutdown' Justification CSV-46 1
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2-101 N1PVR7 Revision 7.
August 8, 1995 1
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RELIEF REQUEST V-75 I. IDENTIFICATION OF COMPONENTS System Chemical and Volume control and Safety Injection Valve (s):
1-CH-HOV-1115B 1-SI-MOV-1885A 1-CH-MOV-1115D 1-SI-MOV-1885B 1-SI-47 1-SI-MOV-1885C 1-SI-MOV-1885D i
Class 2
II. IMPRACTICAL CODE REQUIREMENTS IWV-3427 (a) - Valves with leakage rates exceeding either the values specified by the Owner or those rates given in i
IWV-3426 shall be replaced or repaired.
]
III. BASIS FOR RELIEF l
Valves 1-CH-MOV-1115B and D, and 1-SI-47 are in the supply line to the charging pumps from the RWST.
Valves 1-SI-MOV-1885A, B.
C and D are on test lines that run from the discharge of the low head SI pumps to the RWST.
During recirculation mode transfer, the RWST is isolated and the low head SI pumps recirculate highly contaminated water from the containment sump to the reactor vessel.
The RWST isolation valves work as a system of valves to protect the RWST from the contaminated sump water.
Permissible valve leakage rates are based on each valve's possible contribution to the total allowable leakage rate to the RWST.
When the leakages from each valve have been measured and summed, an individual valve's permissible leakage rate may have been exceeded but the 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 performing adequately.
IV. ALTERNATE TESTING
?
I In addition to replacement or repair as corrective actions, an evaluation can be performed which demonstratas that even if a valve has exceeded its permissible leakage rate, the overall leakage rate to the RWST will be maintained below the overall allowable RWST leakage rate.
No repair or replacement is necessary if the evaluation is performed.
2-101a N1PVR7 Revision 7 January 10, 1995 e
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I COLD SHUTDOWN JUSTIFICATION CSV-20 Cold Shutdown Justification withdrawn i
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I 2-122 N1PVR7 Revision 7 January 10, 1995
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COLD SHUTDOWN JUSTIFICATION CSV-38 I. IDENTIFICATION OF COMPONENTS System Chemical and volume Control Valve (s):
1-CH-252 1-CH-264 1-CH-277 1-CH-649 Class 2
II. COLD SHUTDOWN JUSTIFICATION These check valves must open to allow charging pump 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 and their mounting carriages must be installed and the transducers referenced to a no flow condition before each test.
After each test, the equipment must be removed from the field and l
decontaminated if necessary.
Therefore, use of the ultrasonic flow instrumentation is very labor intensive and not practical for quarterly testing.
i Test experience has shown that the discharge pressure drop is undetectable when flow through the recirculation line is established in conjunction with normal charging.
Therefore, quarterly partial flow i
testing is not verifiable.
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l 2-135 N1PVR7-Revision 7 January 10, 1995 1
COLD SHUTDOWN JUSTIFICATION CSV-39 Cold shutdown Justification Withdrawn 2-136 N1PVR7 Revision 7 August 8, 1995 1
COLD SHUTDOWN JUSTIFICATION CSV-43 I.
IDENTIFICATION OF COMPONENTS t
System Service Water Valve (s):
1-SW-MOV-108A 1-SW-MOV-108B Class 3
II. COLD SHUTDOWN JUSTIFICATION These isolation valves are located in series on service water supply to the component cooling heat exchangers.
The component cooling heat exchangers carry a majority of the heat load for the service water system.
When the heat exchangers are isolated, service water flow decreases to less than 10% of normal flow.
Due to the design of the service water pumps, the pumps experience harmful high-magnitude vibrations as the service water flow decreases through a range from 7000 gpm to 6000 gpm.
These pumps cannot be stopped during the valve exercise test because they provide service water to other plant heat loads.
Therefore, performing the valve exercise test as frequently as once every three months should be avoided due to the harmful affects that the testing has on the service water pumps.
The valve controllers do not allow for a partial-stroke exercise test.
To reduce the harmful affects of high-magnitude vibrations on the service water pumps, the isolation valves will be full-stroke exercised on a cold shutdown frequency.
2-139a N1PVR7 Revision 7 August 8, 1995
1 COLD SHUTDOWN JUSTIFICATION CSV-44 I.
IDENTIFICATION OF COMPONENTS System Quench Spray i
Valve (s):
1-QS-MOV-102A 1-QS-MOV-102B Class 2
II. 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 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.
j 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.
2-139b N1PVR7 Revision 7 l
l January 10, 1995 i
COLD SHUTDOWN JUSTIFICATION CSV-45 I. IDENTIFICATION OF COMPONENTS System Service Water Valve (s) :
1-SW-1067 I
1-SW-1070 l
1-SW-1139 Class 3
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II. COLD SHUTDOWN JUSTIFICATION I
1 These normally open manual 1 inch (1-SW-1067 and 1070) and 1.5 inch (1-SW-1139) valves are closed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the accident as required by the abnormal operating procedures to prevent loss of service water in the event that the connected non-seismic pipe fails.
These valves are located in an expansion joint vault outside the service water pump house.
The vault is defined as a confined space due to possible consumption resulting from an expansion joint failure.
Entry into this confined space requires an entry permit, an air meter and two operators (buddy system).
Also, special tools are required to remove the manhole cover which weighs in excess of 300 lbs and is a missile barrier.
Closing these valves would require securing the service water addition system which could adversely affect the
+
biological agent concentration in the service water.
These manual valves remain in the open position during normal operation and are not subject to wear.
Closing these valves every three months to fulfill quarterly testing requirements creates an undue burden with no compensating benefit to quality and safety.
Exercising these valves on a cold shutdown test frequency (but not more frequently then once every three months), is adequate to demonstrate that the valves can be closed in the case where service water isolation is requir'ed.
2-139c
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N1P'/R7 Revision 7 January 10, 1995
COLD SHUTDOWN JUSTIFICATION CSV-46 j
I. IDENTIFICATION OF COMPONENTS System Residual Heat Removal i
Valve (s):
1-RH-7 l
1-RH-15 i
Class 2
II. 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 1-RH-P-1A and 1-RH-P-1B are running.
The low pressure pumps take suction from and discharge to the reactor coolant system which operates at 2235 psig.
This pressure is well above the operating pressure of the pumps, therefore, partial-stroke or full-stroke testing during normal operation is not practical.
These valves will i
be full-stroke exercised every cold shutdown but not more frequently then every three months.
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2-139d N1PVR7 Revision 7 August 8, 1995
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l NON-CODE ALTERNATIVE TESTING VNC-1 I. IDENTIFICATION OF COMPONENTS System Service Air 1
Valve (s):
1-GN-225 1-IA-2152 1-GN-229 1-IA-2153 1-IA-2154 1
1-IA-2155 1
Class NC II. IMPRACTICAL CODE REQUIREMENTS Exercise valves to the closed position every three months Exercise each valve individually III. BASIS FOR ALTERNATE TESTING Due to the plant configuration, these valves cannot be t
verified closed using flow.
l 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 j
required to be operable during normal operation.
- Also, l
these valves are located inside containment and are inaccessible during normal operation.
These valves are also subject to leak testing, which is performed every reactor refueling.
Verification of closure will be performed during the leak test every reactor refueling instead of every cold shutdown because the small increase in safety gained by test.ing during cold shutdown does not justify the burden of performing a back pressure test.
j Valves 1-IA-2152 and 2153 are in series and valves 1-IA-2154 and 2155 are in series.
There are no vents in between the two sets of valves; therefore, these valves cannot be individually back pressure tested or leak l
tested.
1 2-141 N1PVR7 Revision 7 January 10, 1995
NON-CODE ALTERNATIVE TESTING VNC-1 (Cont.)
IV. ALTERNATE TESTING Exercise to the closed position every reactor refueling.
i Valves 1-IA-2152 and 2153, and valves 1-IA-2154 and 2155 will be back pressure / leak tested in groups.
If the group of valves fails the test, both valves in the group will be subject to repair or replacement.
The leak test for valves 1-IA-2152, 2153, 2154 and I
2155, and 1-GN-225 and 229 will consist of recording the nitrogen bottle pressure, waiting a given period of time and then recording the bottle pressure again.
The results will be compared to appropriate acceptance criteria.
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i 2-142 N1PVR7 Revision 7 January 10, 1995
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.* 4 ATTACHMENT 3
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM REVISION 7
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 The following summary describes the changes to Revision 7 of the North Anna Unit 2 Inservice Testing (IST) Program Plan.
2.2.5 PUMP INSERVICE TESTING TABLE t
' UNIT 2 i
PUMP NUMBER COMMENT / PROGRAM CHANGE 2-RH-P-1A Program change:
Test frequency was changed 2-RH-P-1B from every reactor refueling to every cold shutdown.
Refer to relief request P-5.
2.2.6 PUMP INSERVICE TESTING RELIEF REQUESTS UNIT 2 RELIEF REQUEST COMMENT / STATUS i
P-5 The test frequency for the RHR pumps was changed from every reactor refueling to every t
cold shutdown but not more frequently then every three months.
Also, the hydraulic acceptance criteria will be based on a portion of the pump curve instead of a specific reference value.
This change resulted from our response to Anomaly 2 in the NRC Safety Evaluation Report.
P-13 Service water pumps 2-SW-P-1A and B were deleted from this relief request.
The discharge pressures are measured using gauges that meet Section XI accuracy rnqui.rements.
2 e
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SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 2.3.4 VALVE INSERVICE TESTING TABLE l
Valves marked with an
- are being added to the IST Program.
UNIT 2 VALVE NUMBER COMMENT / PROGRAM CHANGE 2-CH-495*
This check valve was installed on the header from the charging pump recirculation lines and the RCP seal water return line in response to the Westinghouse Nuclear Service Advisory Letter (NSAL)92-012.
This advisory identified the potential for leakage of contaminated sump water outside the containment via the RCP seal water heat exchanger relief valve to the volume control tank.
Program change:
The valve was added to the IST program to be leak tested and tested closed every reactor refueling (refer to Relief Request V-73), and to be tested open every cold shutdown (refer to Cold Shutdown Justification CSV-39).
2-CH-MOV-2115B Relief Request V-76 was added for the RWST 2-CH-MOV-2115D isolation valves to allow for the use of an 2-SI-18 evaluation instead of repair or replacement 2-SI-MOV-2885A as corrective action if a valve exceeds it's 2-SI-MOV-2885B permissible leakage limit.
2-SI-MOV-2885C 2-SI-MOV-2885D Program change:
Relief request V-76 was added.
2-HC-7 This non-Code class check valve is on the discharge line for the containment purge blower.
The primary means of containment hydrogen control is by operation of the recombiners.
Therefore, operation of the purge blowers is not critical to accident mitigation or recovery.
This valve was carried in the IST program because of a l
Technical Specification surveillance requirement that could be interpreted as requiring the testing of the blower.
This
4
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 requirement has since been clarified.
There is no Technical Specification surveillance requirement.
Deletion of this valve was approved by SNSOC on June 28, 1995.
Program change:
The valve was removed from the IST program.
2-HC-69 This hydrogen analyzer discharge check valve was removed from the system along with the analyzer.
Program change:- The valve was removed from the IST program.
L 2-MS-19 These decay heat release stop check isolation 2-MS-58 valves are now maintained closed with the 2-MS-96 stem on the disk.
In this configuration, the valve disk does not have to change position to fulfill it's isolation function.
Therefore, the Code does not require the valves to be tested.
Program change:
The valves were removed from the IST program.
j 2<-QS-MOV-202A Testing valves quarterly presents a 2-QS-MOV-202B significant personnel hazard due to exposure to sodium hydroxide.
Program change:
These valves will be tested on a cold shutdown frequency instead of j
quarterly.
Refer to Cold Shutdown i
Justification CSV-44.
I 2-RH-7 Program change:
The test frequency for t'hese 2-RH-15 RHR pump discharge check valves was changed from every reactor refueling to every cold shutdown but not more frequently then every three months.
Relief Request V-75 was replaced by Cold shutdown Justification CSV-45.
2-RH-FCV-2605 An engineering evaluation concluded that the 2-RH-HCV-2758 simultaneous failure of the RHR heat exchanger bypass and discharge valves to go to their fail-safe positions on loss of j
1 3
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SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 instrument air will not create a safety concern for achieving safe shutdown.
Therefore, these valves need not be included in the IST program.
Program change:
The valves were removed from the IST Program.
2-SI-91 Program change:
Reference to using 2-SI-99 nonintrusive techniques and a sampling plan 2-SI-105 for verifying full-stroke of the cold leg safety injection check valves was added to Relief Request V-42.
2-SI-92 Program chhnge:
Reference to using 2-SI-100 nonintrusive techniques and a sampling plan 2-SI-106 for verifying full-stroke of the cold leg safety injection check valves was added to Relief Request V-44.
2-SI-112 Program change:
Reference to using 2-SI-113 nonintrusive techniques and a sampling plan 2-SI-117 for verifying full-stroke of the hot leg 2-SI-118 safety injection check valves was added to 2-SI-124 Relief Request V-45.
2-SI-125 2-SI-151 Program change:
Reference to using a
2-SI-153 sampling plan with nonintrusive techniques 2-SI-168 for verifying full-stroke of the safety 2-SI-170 injection accumulator discharge check valves 2-SI-185 was added to Relief Request V-43.
Also, the 2-SI-187 grouping of the valves was changed.
2-SI-MOV-2863B Program change:
The drawing reference was changed to 12050-CBM-096A.
2-SW-MOV-202A Further evaluation resulting from the recent 2-SW-MOV-202B service water system review revealed that 2-SW-MOV-206A closing these service water cross-tie 2-SW-MOV-206B isolation valves is the preferred method for isclating an inoperable header.
Program change:
Closure testing was added to the IST program.
4 l
m
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 l
2-SW-MOV-208A These isolation valves are located in series 2-SW-MOV-208B on the service water supply to the component cooling heat exchangers.
Testing them every quarter creates a reduced flow condition for the service water pumps which in turn causes the pumps to experience harmful high-magnitude vibrations.
Program change:
These valves will be tested on a cold shutdown frequency instead of quarterly.
Refer to Cold Shutdown Justification CSV-43.
t 2.3.5 VALVE INSERVICE TESTING PROGRAM RELIEF REQUESTS UNIT 2 RELIEF r
REQUEST COMMENT / STATUS V-39 The basis for relief was revised to indicate that the low head safety injection system l
must be isolated to perform closure testing on the check valves.
V-42 Reference to using nonintrusive techniques and a sampling plan for verifying full-stroke of the cold leg safety injection check valves was added.
The alternative method described for using nonintrusive techniques described in NUREG 1482 will be followed.
According to NUREG 1482, " Relief is not required because this test method is considered an acceptable 'other positive means,' even if used on a rotating basis.
However, if the recommended alternative methods of this section are implemented, the licensee must describe the implementation of this section in the IST program document."
Even though relief is not required, use of the sampling plan is described in this relief request to satisfy the documentation requirement described above.
V-43 Reference to using a sampling plan with nonintrusive techniques for verifying full-5
1
SUMMARY
OF CHANGES TO NORTH-ANNA UNIT 2 IST PROGRAM, REVISION 7 stroke of the safety injection accumulator discharge check valves was added.
Also, the grouping of the valves was changed from valves 2-SI-170 and 187 in one group, and 2-SI-151, 153, 168 and 185 in the other group, to 2-SI-153, 170 and 187 in one group, and 2-SI-151, 168 and 185 in the other group.
This change resulted from our response to Anomaly 6 in the NRC Safety Evaluation Report.
The explanation for why the grouping was changed is included in our response.
As described in the discussion for V-42, relief is not i
required for using the sampling plan.
V-44 Reference to using nonintrusive techniques and a sampling plan for verifying full-stroke of the cold leg safety injection check valves was added.
As described in the discussion for V-42, relief is not required for using the sampling plan.
V-45 Reference to using nonintrusive techniques and a sampling plan for verifying full-stroke of the hot leg safety injection check valves was added.
As described in the discussion for V-42, relief is not required for using the sampling plan.
V-51 Relief request is being withdrawn.
The only valve (2-HC-7) in this relief request was removed from the IST program.
V-73 Check valve 2-CH-495 was installed on the header from the charging pump recirculation l i n e s a n d t h e R C P s e a l w a t e r r e t u r n l i n e -i n response to the Westinghouse Nuclear Service Advisory Letter (NSAL)92-012 and was added to this relief request for testing to the closed position.
During normal operation, this valve cannot be isolated to perform a back pressure test because normal letdown and charging flow, and reactor coolant pump seal flow would be interrupted.
Also, if the valve was isolated during normal operation, the charging pumps would have to be secured.
This valve is also subject to leak testing, 6
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7
-t F
which is performed every reactor refueling.
j Verification of closure will be performed during the leak test every reactor refueling instead of every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify the burden _of performing a leak rate test.
V-75 Relief request is being replaced by Cold Shutdown Justification CSV-45.
V-76 This relief reauest was added to the IST crogram and applies to the RWST isolation valves.
In addition to replacement or repair as corrective actions, an evaluation can be performed which demonstrates that even if a
)
valve has exceeded its permissible leakage rate, the overall leakage rate to the RWST will be maintained below the overall allowable RWST leakage rate.
No repair or replacement is necessary if the evaluation is performed.
The relief request was submitted i
to the NRC by letter dated April 26, 1994.
Approval was granted by the NRC in the Safety Evaluation Report for the IST program dated October 18, 1994.
2.3.6 VALVE INSERVICE TESTING PROGRAM COLD SHUTDOWN JUSTIFICATIONS UNIT 2 COLD SHUTDOWN i
JUSTIFICATION COMMENT / STATUS CSV-20 Justification is being withdrawn because valves 2-RH-FCV-2605 and 2-RH-HCV-2758 were deleted from the IST Program.
CSV-39 Check valve 2-CH-495 was installed on the header from the charging pump recirculation lines and the RCP seal water return line in response to the Westinghouse Nuclear Service Advisory Letter (NSAL)92-012 and was added to this cold shutdown justificaticn for testing to the open position.
Full flow conditions have to be measured by using 7
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 temporary ultrasonic flow instrumentation which is very labor intensive.
CSV-43 Justification is beina added to the IST procram.
Valves 2-SW-MOV-208A and B are located in series on the service water supply to the component cooling heat exchangers, i
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% cf 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 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 i
harmful affects of high-magnitude vibrations on the service water pumps, the isolation valves will be full-stroke exercised on a cold shutdown frequency.
CSV-44 Justification is beina added to the IST procram.
The normally closed six inch motor operated isolation valves 2-QS-MOV-202A and B 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.
[
8
l
SUMMARY
OF CHANGES TO NORTH ANNA UNIT 2 IST PROGRAM, REVISION 7 After the motor operated isolation valves are stroked open and closed, the piping between the motor operated valves and the downstream.
manual isolation valves must be drained of sodium hydroxide.
Approximately five gallons of highly caustic fluid are drained into a plastic container after each valve test.
Draining the piping presents a significant personnel hazard.
Sodium hydroxide causes severe burns if it comes in contact with the-skin.
The test personnel must wear rubber gloves, boots and face shields.
The drains are located outdoors and are near to the ground, which makes collection difficult.
Any soil that is contaminated with sodium hydroxide must be neutralized by the test personnel.
Partial stroke testing of these valves presents the same hazards as full stroke testing.
To reduce the number of times that test personnel are exposed to sodium hydroxide, the motor operated isolation valves will be tested on a cold shutdown frequency.
CSV-45 Justification is beina added to the IST proaram. The 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.
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A REPLACEMENT PAGES TO NORTH ANNA UNIT 2 IST PROGRAM REVISION 7
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RELIEF REQUEST P-5 I. IDENTIFICATION OF COMPONENTS System :
Residual. Heat Removal Pump (s) :
2-RH-P-1A 2-RH-P-1B Class 2
II. IMPRACTICAL CODE REQUIREMENTS Frequency of Pump Test.
III. BASIS FOR RELIEF The low pressure pumps take suction from and discharge to the Reactor Coolant System (RCS)which operates at 2235 psig.
This pressure is well above the operating pressure of the pumps; therefore, testing during normal operation is not possible.
Also, the pumps are located inside containment and are inaccessible during normal operation.
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 the results will be compared to acceptance criteria based on that portion of the pump curve described above and the hydraulic acceptance criteria given in OM Part 6.
The guidelines set forth in NUREG 1482, Section 5.2, "Use of Variable Reference Values for Flow Rate and Differential Pressure During Pump Testing," will be followed.
I 1
2-19 N2PVR7 Revision 7 August 8, 1995 i
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 five points will be taken, and a curve fit for these data points will be determined.
Using the fitted curve and the acceptance criteria for vibration testing in OM Part 6, acceptance criteria dependent on flow rate will be determined.
IV. ALTERNATE TESTING 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.
l i
i l
2-19a N2PVR7 Revision 7 August 8, 1995 J
RELIEF REQUEST P-13 I. IDENTIFICATION OF COMPONENTS System :
Component Cooling Chemical and Volume Control Service Water Pump (s):
1-CH-P-1A 1-CC-P-1A 1-CH-P-1B 1-CC-P-1B 1-CH-P-1C 1-SW-P-4 Class Class 2 for CH and Class 3 for CC and SW II. IMPRACTICAL CODE REQUIREMENTS Instrument Error III. BASIS FOR REQUEST Instruments used to measure certain pump parameters receive their signal at the equipment, which is transmitted to a process rack and then to a control room indicator.
The sensor and rack accuracy can be affected by drift, temperature, and calibration accuracy.
The indicator has a limit of accuracy.
The total loop accuracy is found by the root sum of the squares.
The only variables in this formula are the sensor calibration accuracy and the indicator accuracy.
^
Installing new sensors and indicators to reduce the j
accuracy by one percent is not warranted by the increase in safety obtained.
The following instrument loops exceed the 2% tolerance listed in Table IWP 4110-1.
Instrument Component Parameter Accuracy i
FI-1122 1-CH-P-1A,B,C Flow 2.34'%
FI-CC-100A 1-CC-P-1A Flow 2.69%
FI-CC-100B 1-CC-P-1B Flow 2.69%
PI-SW-110 1-SW-P-4 Discharge Pressure 2.61%
IV. ALTERNATE TESTING None
)
2-29 N1PVR7 Revision 7 January 10, 1995 i
i VIRGINIA P0bER COMPANY PAGE:
9 0F 79 NORTH ANNA UNIT 2 REVISION: 07 l
SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER-NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2 CH-208 12050-COM-0955 2 0F 2 D7 CHECK VALVE 3.000 2 C
CV C
48 0
M j
"C" CHARGING PUMP DISCHARGE CHECK VALVE 2-CH 260 12050-COM-095C 2 0F 2 58 CHECK VALVE 2.000 1 C
CV C
10 "A" RC PLMP SEAL WATER SUPPLY, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2 CH 284 12050-cam-095C 2 0F 2 B7 CHECK VALVE 2.000 1 C
CV C
10 l
"B" RC PtMP SEAL WATER SUPPLY, INSIDE l
CONTAINMENT ISOLATION CHECK VALVE 2-CH-308 12050-ceM 095C 2 0F 2 85 CHECK VALVE 2.000 1 C
CV C
10 "C" RC PUMP SEAL WATER SUPPLY, INSIDE CONTAINMENT !$0LATION CHECK VALVE 2-CH-331 12050-CBM 095C 2 0F 2 F4 CHECK VALVE
10 LT C
59 RC PUMP SEAL WATER RETURN, INSIDE CONTAINMENT ISOLAfl0N CHECK VALVE 2 CH-332 12050-C8M-095C 1 0F 2 AS CHECK VALVE 2.000 1 AC CIV CV C
10 LT C
CHARGING SUPPLY TO LOOP FILL HEADER, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-CH-335 12050-CBM-095C 10F 2 D4 CHECK VALVE 3.000 2 AC Civ CV C
10 LT C
)
MAIN CHARGING SUPPLY HEADER, INSIDE CONTAIN-MENT ISOLATION CHECK VALVE l
2-CH-495 12050-ceM 0958 10F 2 56 CHECK VALVE 2.000 2 AC CV C
73 0
39 CHARGING PUMP RECIRC AND RCP 'EAL WATER j
RETURN LINE ISOLATION CHECK VA JE 2-CH FCV 2113A 12050-CBM-0958 1 0F 2 C3 A0 GAL 1.000 3 B
EV O
FS 0
ST 0
VP OC ALTERNATE EMERGENCY SORATION LINE FLOW CONTROL VALVE 2 CH FCV-2114A 12050 CBM-0958 1 0F 2 D4 A0 GLOBE 1.000 3 B
EV C
FS C
ST C
VP OC 1
PRIMARY GRADE WATER FLOW CONTROL VALVE l
2-CH-FCV-2160 12050-CBM 095C 1 0F 2 A4 A0 GLOF 2.000 2 AE CIV LT C
VP OC l
l l
l i
i
__~ _. _.. _ _._
m _
m.
VIRGIN!A poler COMPANY PAGE:
10 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 180 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REQ JUST TEST NLBIBER NUMBER NUMBER C00R TYPE
$1ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-f CHARGING FLOW CONTROL TO LOOP FILL NEADER, OUTSIDE CONTAINMENT ISOLATION VALVE l
2-CH LCV-2460A 12050-ceM-095C 10F 2 F7 A0 GLOSE 2.000 1 B
EV C
5 FS C
5 ST C
5 I
VP OC I
l LETDOWN ISOLATION VALVE 2-CH LCV-2460s 12050-CeM-095C 1 0F 2 F7 A0 GLOBE 2.000 1 5
EV C
5 l
FS C
5 ST C
5 VP OC LETDOWN ISOLATION VALVE l
2-CH-MOV-21155 12050-COM 0958 2 0F 2 B8 M0 GATE 8.000 2 A
EV C
6 0
6 LT C
76 l
ST C
6 O
6 I
VP OC CHARGING PLS4P SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 2-CH-MOV-2115C 12050-CeM-0955 1 0F 2 C6 M0 GATE 4.000 2 B
EV C
6 ST C
6 VP OC CHARGING PUMP SUPPLY ISOLATION FROM VOLLSIE CONTROL TAWK 2-CH MOV-21150 12050-CeM-0958 2 0F 2 88 MO GATE 8.000 2 A
EV C
6 0
6 LT C
76 ST C
6 0
6 VP OC CHARGlWG PL84P SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TAhK 2 CH MOV-2115E 12050 CBM-0955 1 0F 2 C6 MO GATE 4.000 2 B
EV C
6 ST C
6 VP OC CHARGING PLSIP SUPPLY ISOLATION VALVE FROM VOLUME CONTROL TANK 2-CH MOV-2267A 12050 ceM-0958 2 0F 2 C3 M0 GATE 6.000 2 E
YP OC "A" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 2 CH-MOV-2267B 12050-COM 0958 2 0F 2 C3 M0 GATE 6.000 2 E
VP OC "A" CHARGING PUMP SUCTION ISOLATION FROM LMSI 9
VIRGINIA POWER COMPANY PAGE:
11 EF 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT
- VALVE DRAWING SHEET DRWG iVALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST i
NUMBER NUMBER WUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2-CH-MOV-2269A 12050-cam 0958 2 0F 2 C5 MO GATE 6.000 2 E
VP OC "B" CHARGING PUMP SUCTION ISOLATION FROM RWST AND VCT 2-CH-MOV 2269s 12050-ceM-0958 2 0F 2 C5 M0 GATE 6.000 2 E
VP OC "B" CHARGING PUMP SUCTION ISOLATION FROM LHS!
2-CH-MOV-2270A 12050-cam-0958 2 0F 2 C7 M0 GATE 6.000 2 E
VP GC "C" CHARGING PtMP SUCTION ISOLATION FROM RWST AND VCT 2-CH MOV-22708 12050 CeM-0958 2 0F 2 C7 M0 GATE 6.000 2 E
VP OC "C" CHARGING PUMP SUCTION !$0LATION FROM LHS!
2-CH-MOV-2275A 12050-CBM-0958 2 0F 2 D4 M0 GATE 2.000 2 B
EV C
0 ST C
0 VP OC "A" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE 2-CH-MOV-2275B 12050-cam-0955 2 0F 2 D5 MO GATE 2.000 2 8
EV C
0 ST C
0 VP OC "B" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE 2 CH-MOV-2275C 12050-CBM 0958 2 0F 2 D7 MO GATE 2.000 2 8
EV C
0 ST C
0 VP OC "C" CHARGING PUMP MINIMUM RECIRCULATION ISO-LATION VALVE 2 CH MOV-2286A 12050-CBM 0958 2 0F 2 E4 MO GATE 3.000 2 B
EV C
0 ST C
0 VP OC "A" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE I
2-CH-Mov 22868 12050 CBM 095B 2 0F 2 E6 M0 GATE 3.000 2 B
EV C
0 ST C
O VP OC
VIRGINIA POWER COMPANY PAGE:
12 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ABME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-1 "B" CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2-CH-MOV 2286C 12050-CBM-0958 2 0F 2 E7 MO GATE 3.000 2 B
EV C
0 ST C
0 VP OC "C" CHARGING PtMP MAIN DISCHARGE ISOL ATION VALVE 2-CH-MOV 2287A 12050 CBM-0958 2 rw ? n4 MO GATE 3.000 2 B
EV C
0 ST C
0 VP OC "A" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 2-CH-MOV-2287B 12050 CBM 0958 2 0F 2 D6 M0 GATE 3.000 2 B
EV C
0 ST C
0 VP OC "B" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 2-CH-MOV 2287C 12050-CBM-0958 2 0F 2 D7 MO GATE 3.000 2 B
EV C
0 ST C
0 VP OC "C" CHARGING PUMP ALTERNATE AND LOOP FILL DISCHARGE ISOLATION VALVE 2-CH-MOV-2289A 12050-CBM-095C 1 0F 2 D4 M0 GATE 3.000 2 A CIV EV C
7 LT C
ST C
7 VP OC MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1
1 2 CH-MOV-22898 12050-CBM 095C 1 0F 2 B3 M0 GATE 3.000 2 B
EV C
7 ST C
7 VP OC MAIN CHARGING HEADER !$0LAT10N VALVE, OUTSIDE i
CONTAINMENT 2-CH-MOV-2350 12050 CBM 0958 1 0F 2 B5 MO GATE 2.000 2 B
EV O
4 ST 0
4 VP DC EMERGENCY BORAT10N TO CHARGING PUMP SUCTION 2-CH-MOV 2373 12050-CBM 0958 1 0F 2 A8 MO GATE 3.000 2 E
VP OC i
VIRGIN!A POWER COMPANY PAGE:
13 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE A38E IW VALVE TEST TEST REQ JUST TEST NUMBER MUMBER NUMBER C0CR TTPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-CHARGING PUMP RECIRCULATION HEADER ISOLATION i
VALVE 2-CM-MOV-2380 12050-CBM-095C 2 0F 2 F4 MO GATE 3.000 2 A CIV EV C
9 LT C
59 ST C
9 VP OC REACTOR COOLANT PUMP SEAL WATER RETURN, INSIDE CONTAIMMENT ISCLATION VALVE 2-CH-MOV-2381 12050-cam 0958 1 0F 2 C8 MO GATE 3.000 2 A CIV EV C
9 LT C
ST C
9 VP OC REACTOR COOLANT PUMP SEAL WATER RETURN, OUT-
$1DE CONTAINMENT ISOLATION VALVE 2-CH RV-2203 12050-CBM-095C 1 0F 2 F3 RELIEF VALVE 2.000 2 C
SP 0
LETDOWN RELIEF VLV DOWNSTREAM OF REGEN HX, RV DISCHARGE TO PRESSURIZER RELIEF TANK 2 CH RV-23828 12050-cam-0958 1 0F 2 C7 RELIEF VALVE 2.000 2 C
SP 0
SEAL WATER HEAT EXCHANGER RELIEF VALVE, RV DISCHARGE TO VOLtmE CONTROL TANK 2 CH-TV-2204A 12050-cam-095C 1 0F 2 E3 A0 GLOBE 2.000 2 A CIV EV C
5 FS C
5 LT C
ST C
5 VP OC LETDOWN CONTROL FROM REGEN HX, INSIDE CONTAINMENT ISOLATION VALVE 2-CH TV 2204B 12050-CBM-095A 2 0F 2 C3 A0 CLOBE 3.000 2 A CIV EV C
5 FS C
5 LT C
ST C
5 VP OC LETDOWN CONTROL FROM REGEN HX, OUTSIDE CONTAINMENT !$0LATION VALVE I
L l
I t
l l
VIRGINIA POWER COMPANY PAGE:
28 0F 79 NORTH ANNA UNIT 2 REVISION: 07 I
SECOND INSPECT 10M INTERVAL DATE: 08/08/95 l
INSERVICE TESTING PROGRAM - VALVE TABLE l
NC
!$0 REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NLMBER NLMBER NLDSER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2 HC 015 11715-cam-106A 1 0F 4 E3 CNECK VALVE 2.000 2 AC CIV CV C
20 0
LT C
I UNIT 2 RETURN LINE FROM UNIT 1 HYDROGEN ANA-LYZERS & RECOMB, INSIDE CONT ISOL CNECK VALVE j
2-HC-020 11715-COM 106A 2 0F 4 E4 CHECK VALVE 2.000 2 AC CIV CV C
20 i
0 LT C
UNIT 2 RETURN LINE FROM UNIT 2 HYDROGEN ANA-LYZERS & RECOMB, INSIDE CONT ISOL CHECK VALVE 2 HC-068 11715 CeM-1064 2 0F 4 c5 CHECK VALVE
.375 NC C
CV o
HYDROGEN ANALYZER DISCHARGE CHECK VALVE 2-HC TV-200A 11715-CSM-106A 10F 4 E3 SO GLOSE
.375 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC UNIT 2 SAMPLE LINE To UNIT 1 HYDROGEN ANA-LYZERS, INSIDE CONTAINMENT ISOLATION VALVE
\\
2-HC-TV-200s 11715-CBM-106A 1 0F 4 E4 So GLOBE
.375 2 A CIV EV C
I O
j FS C
LT C
ST C
55 0
55 VP OC UNIT 2 SAMPLE LINE TO UNIT 1 HYDROGEN ANA-LYZERS, OUTSIDE C0hfAINMENT ISOLATION VALVE 2-HC-TV 201A 11715-CBM-106A 1 0F 4 04 $0 CLOBE
.375 2 A CIV EV C
0 FS C
LT C
i ST C
55 l
0 55 i
VP OC RETURN !$0LATION FROM UNIT 1 HYDROGEN ANA-
]
LYZERS TO UNIT 2 CONT,0UTSIDE CONT ISOL VALVE i
j 2-HC-TV-2018 11715 CeM-106A 1 0F 4 D4 SO GLOBE
.375 2 A CIV EV C
I O
FS C
LT C
ST C
55 0
55 VP OC RETURN ISOLATION FROM UNIT 1 HYDROGEN ANA-LYZERS TO UNIT 2 CONT,0UTSIDE CONT ISOL VALVE 2-HC TV-202A 11715 CsM 106A 2 0F 4 E4 50 GLOBE
.375 2 A CIV EV C
i
VIRGINIA POWER COMPANY PAGE:
29 0F 79 1
NORTH ANNA UNIT 2 REVISION: 07
)
SECOND INSPECTION INTERVAL DATE: 08/08/95 i
INSERVICE TESTING PROGRAM
- VALVE TABLE i
NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NLsqBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV* VCN-2-NC-TV 202A 11715 CBM-106A 2 0F 4 E4 50 GLOBE
.375 2 A CIV EV O
FS C
LT C
ST C
55 0
55 VP OC UNIT 2 SAMPLE LINE TO UNIT 2 HYDROGEN ANA-LYZERS, INSIDE CONTAINMENT ISOLATION VALVE 2-HC TV 2028 11715-CBM-106A 2 0F 4 E4 SO GLOBE
.375 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC UNIT 2 SAMPLE LINE To UNIT 2 HYDROGEN ANA-LYZERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2 HC-TV-203A 11715 C8M-106A 2 0F 4 D3 SO CLOBE
.375 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC RETURN ISOLATION FROM UNIT 2 HYDROGEN ANA-LYZERS TO UNIT 2 CONT,0UTSIDE CCM ISOL VALVE 2 HC-TV 2038 11715 CBM-106A 2 0F 4 D3 SO GLOBE
.375 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC RETURN ISOLATION FROM UNIT 2 HYDROGEN ANA-LYZERS To UNIT 2 CONT,00TSIDE CONT ISOL VALVE 2 HC TV 204A 11715-CBM-106A 4 0F 4 F4 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC SUPPLY ISOL FROM UNIT 1 CONT TO N1 HYDRO RE-COMB & N2 CONT BLOWER,0UTSIDE CONT ISOL VALVE 2-HC-TV 2048 11715-CBM 106A 4 0F 4 F5 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
i l
ST C
55 0
55 l
VP C'
i l
l r
l t
VIRGINIA POWER COMPANY PAGE:
30 CF 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NLMBER NLMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN*
SUPPLY ISOL FROM UNIT 1 CONT TO N1 HYDRO RE-COMs & N2 CONT BLOWER,0UTSIDE CONT ISOL VALVE 2 NC TV-205A 11715-cam 106A 1 0F 4 E4 A0 GLOSE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC RETURN ISOLATION FROM UNIT 1 NYDROGEN RECOMS
& ANAL TO UNIT 2 CONT, OUTSIDE CONT ISOL VALVE 2-NC-TV 2058 11715 CsM 106A 1 0F 4 E5 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC RETURN ISOLATION FROM UNIT 1 NYDROGEN RECOMB
& ANAL TO UNIT 2 CONT, OUTSIDE CONT ISOL VALVE 2 HC-TV-206A 11715-CsM 106A 4 0F 4 F3 A0 GLOSE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC UNIT 1 SUPPLY ISOLATION TO N1 CONT ATM0 PURGE BLOW & N2 NYDRO RECOMB, OUTSIDE CONT ISOL VLV 2-HC-TV 2068 11715 C8M-106A 4 OF 4 F3 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC 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 OF 4 E3 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
55 0
55 VP OC RETURN ISOLATION FROM UNIT 2 NYDROGEN RECOM8
& ANAL TO UNIT 2 CONT, OUTSIDE CONT ISOL VALVE 2 HC TV 207B 11715-CBM 106A 2 0F 4 E3 A0 GLOBE 2.500 2 A CIV EV C
0 FS C
LT C
ST C
55 1
~.
... ~... - -
VIRGINIA poler COMPANY PAGE:
31 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLAGER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2 NC TV 2075 11715-CBM 106A 2 0F 4 E3 A0 GLOBE 2.500 2 A CIV ST 0
55 VP OC RETURN ISOLATION FROM UNIT 2 HYDROGEN RECOMB
& ANAL TO UNIT 2 CONT, CUTSIDE CONT ISOL VALVE 2 NC-TV 208A 11715 CBM 106A 3 0F 4 E3 SO GLOBE
.375 2 A CIV EV C
FS C
LT C
ST C
55 VP OC UNIT 2 SAMPLE LINE TO AIR SAMPLE PANEL, INSIDE CONTAINMENT ISOLATION VALVE 2-HC TV-208B 11715-CBM-106A 3 0F 4 E4 SO GLOBE
.375 2 A CIV EV C
FS C
LT C
ST C
55 VP OC UNIT 2 SAMPLE LINE TO AIR SAMPLE PANEL, OUTSIDE CONTAINMENT ISOLATION VALVE r
1 1
l I
i l
VIRGINIA POWER COMPANY PAGE:
60 CF 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SHEET DAWG YALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLMBER NUMBER COOR TYPE SIZL CLASS CAT TYPE TYPE POS V-CSV-VCN-2-MS-018 12050-CBM-0708 1 0F 3 BT MANUAL GATE 3.000 2 B
EV C
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
MAIN STEAM TO AUXILIARY FEEDWATER TUR31NE LINE ISOLATION VALVE 2-MS-095 12050-CBM-0708 3 0F 3 BT MANUAL GATE 3.000 2 B
EV C
MAIN STEAM TO AUXILIARY FEEDWATER TURBINE LINE ISOLATION VALVE 2-MS 117 12050-CBM-070A 3 0F 3 F7 CHECK VALVE 3.000 2 C
CV C
0 "C" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PilMP 2 MS-119 12050 CBM 070A 3 0F 3 F7 CHECK VALVE 3.000 2 C
cv c
0 "B" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP M S-121 12050-CBM 070A 3 0F 3 E7 CHECK VALVE 3.000 2 C
cv C
0 "A" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 2-MS NRV-201A 12050-CBM 0708 1 0F 3 D3 CHECK VALVE 32.000 2 C
CV C
13 VP OC "A" MAIN STEAM HEADER NON-RETURN VALVE 2-MS-NRV 2018 12050-CBM-070B 2 0F 3 D3 CHECK VALVE 32.000 2 C
CV C
13 VP OC "B" MAIN STEAM HEADER NON RETURN VALVE 2-MS-NRV-201C 12050-CBM-0708 3 0F 3 D3 CHECK VALVE 32.000 2 C
CV C
13 VP OC "C" MAIN STEAM HEADER NON-RETURN VALVE 2-MS PCV 201A 12050-CBM 0708 1 0F 3 E5 AO ANGLE 6.000 2 B
EV C
0 FS C
ST C
0 s
W E
l "A" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE 2-MS-PCV 201B 12050 CBM 0708 2 0F 3 E6 A0 ANGLE 6.000 2 B
EV C
0 FS C
VIRGINIA POWCR COMPAW PAGE:
61 0F 79 WORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM. VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NLMBER IUSER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2-MS PCV 201B 12050 CsM-070s 2 0F 3 E6 A0 ANGLE 6.000 2 8
ST C
0 VP OC "B" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE PRES $URE CONTROL VALVE 2 MS-PCV-201C 12050-COM-0708 3 0F 3 D5 A0 ANGLE 6.000 2 B
EV C
0 FS C
ST C
0 VP OC "C" Math STEAM HEADER DISCHARGE TO ATMOSPHERE PRESSURE CONTROL VALVE 2-MS SV-201A 12050-CeM 0700 1 0F 3 E6 SAFETY VALVE 6.000 2 C
SP 0
"A" MAIN STEAM NEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-201B 12050 CSM-070s 2 0F 3 D6 SAFETY VALVE 6.000 2 C
SP 0
"B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS SV-201C 12050-CBM CTOB 3 0F 3 D6 SAFETY VALVE 6.000 2 C
SP O
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2 MS SV-202A 12050 cam-0 Q 1 0F 3 E5 SAFETY VALVE 6.000 2 C
$P O
"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 O
"B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-202C 12050-COM-0708 3 OF 3 D6 SAFETY VALVE 6.000 2 C
SP O
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS
...........................................................v.
2-MS SV 203A 12050 CBM 0708 1 OF 3 E6 SAFETY VALVE 6.000 2 C
SP O
"A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2 MS SV-2038 12050-CBM 070s 2 0F 3 D5 SAFETY VALVE 6.000 2 C
SP 0
"B" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2 MS-SV-203C 12050-CBM-070s 3 0F 3 D6 SAFETY YALVE 6.000 2 C
$P O
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV 204A 12050 cam-0708 1 0F 3 E6 SAFETY VALVE 6.000 2 C
SP O
VIRGINIA P0hER COMPANY PAGE:
42 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOW INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SNEET DeWC VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NLMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-
"A" MAIN STEAM NEADER SAFETY VALVE, SV DISCNARGE TO atmos 2-MS SV 2045 12050-cam-070s 2 0F 3 D6 SAFETY VALVE 6.000 2 C
SP 0
"B" MAIN STEAM NEADER SAFETY VALVE, SV DISCNARGE TO ATMOS 2 MS-SV 204C 12050-pSM-0708 3 0F 3 D6 SAFETY VALVE 6.000 2 C
SP O
"C" MAIN STEAM HEADER SAFETY VALVE, SV DISCNARGE TO ATMOS 2-MS SV 205A 12050 COM-0705 1 0F 3 E5 SAFETY VALVE 6.000 2 C
SP O
"A" MAIN STEAM NEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-2058 12050-CeM-070s 2 0F 3 D5 SAFETY VALVE 6.000 2 C
SP O
"O" MAIN STEAM NEADER SAFETY VALVE, SV DISCNARGE TO ATMOS 2-MS-SV-205C 12050 CsM-0708 3 0F 3 05 SAFETY VALVE 6.000 2 C
SP O
"C" MAIN STEAM NEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2 MS-TV 201A 12050-CBM 070s 1 0F 3 D4 A0 DISC 32.000 2 B
EV C
16 FS C
16 ST C
16 VP OC "A" MAIN STEAM NEADFR TRIP Vf.VE 2-MS-TV 2018 12050-CeM 070s 2 0F 3 C4 A0 DISC 32.000 2 B
EV C
16 FS C
16 ST C
16 VP OC "B" MAIN STEAM NEADER TRIP VALVE 2-MS-TV-201C 12050-CSM 070s 3 0F 3 C4 A0 DISC 32.000 2 B
EV C
16 FS C
16 '
ST C
16 VP OC "C" MAIN STEAM NEADEit TRIP VALVE 2 MS-TV 209 12150-CSM-070A 3 0F 3 D3 A0 GLOSE 3.000 2 B
EV C
14 FS C
14 ST C
14 VP OC MAIN STEAM NIGN PRESSURE DRAIN ISOLATION TO CONDENSER 2 MS-TV-210 12050-CBM-070s 3 or 3 A4 A0 GLOBE 1.500 2 B
EV C
FS C
ST C
i 1
i i
I
I VIRGINIA PGWR COMPANY PAGE:
43 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECONO INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SNEET ORWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NLMBER NUMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2-MS TV-210 12050-COM-0705 3 0F 3 A4 A0 GLOBE 1.500 2 B
VP OC MAIN STEAM MIGH PRESSURE DRAIN HEADER ISO-LATION TO STEAM GENERATOR BLOWOWN SYSTEM i
2-MS TV-211A 12050-CBM-070A 3 0F 3 E5 A0 GLOBE 3.000 2 8
EV C
O FS O
ST C
l 0
i VP OC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP I
2-MS-TV-2118 12050-cam 070A 3 0F 3 E4 A0 GLOBE 3.000 2 8
EV C
1 0
FS 0
ST C
0 VP OC l
i MAIN STEAM SUPPLY TRIP VALVE TO TURBINE
)
DRIVEN AUXILIARY FEEDWATER PUMP
]
2 MS-TV-213A 12050-CBM-0708 10F 3 D4 A0 GLOBE 3.000 2 B
EV C
34 FS C
34 ST C
34 VP OC "A" MAIN STEAM TRIP BYPASS VALVE 2-MS TV 213B 12050-CsM 070s 2 0F 3 04 A0 GLOBE 3.000 2 B
EV C
34 FS C
34 ST C
34 i
VP OC "B" MAIN STEAM TRIP BYPASS VALVE 2 MS TV 213C 12050-CBM-070s 3 0F 3 D4 A0 GLOBE 3.000 2 B
EV C
34 FS C
34 ST C
34 VP OC "C" MAIN STEAM TRIP BYPASS VALVE 2 MS-TV 215 12050-CBM 070A 3 0F 3 C4 MECH TRIP VLV 3.000 3 E
VP OC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AFW PLMP
VIRGINIA POWER COWANY PAGE:
44 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TASLE NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST IRRIBER 1RMBER NUMBER COOR TYPE
$!ZE CLAS3 CAT TYPE TYPE POS V-CSV-VCP-THIS PAGE IS INTENTIONALLY BLANK.
1 1
1 l
VIABINIA PGER CIBFANY PAGE:
45 0F 79 ulkTN AleIA tallT 2 REVISION: 07 SECINS IllSPECTIluf INTERVAL DATE: 01/10/95 I M RVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REQ JUST TEST 1RsWER 845SER 1RaeBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2 et 011 12050-tam 091A 2 0F 4 D6 WL CNECK VLV 8.000 2 AC CIV CV C
68 G
68 LT C
"A" MEllCN SPRAY PLar INSIDE CCIfTAIIDENT ISOLATICIf CNECK VALVE 2-08 022 12050 CeM-091A 2 0F 4 E6 WL CNECK VLV 8.000 2 AC CIV CV C
68 0
68 LT C
"9" EEIICN SPRAY PLSF INSIDE CONTAlleENT ISOLATICII CIECK VALVE 2-et le0V 200A 12050-tam-091A 2 0F 4 A3 No GATE 10.00 2 E
VP OC "A" EEIICal SPRAY Pulp SUCTICIf 180LATICIf VALVE FROM REF1ELING WATER STORAGE TAIIK u..
2-08-le0V-200s 12050-tam 091A 2 0F 4 A3 IID GP~~
10.000 2 E
VP OC "0" alENCN SPRAY PLDP !IUC'!".'t IPT eICII VALVE FRGI REFLELIIIG WATER STtcAGE Tt 2-03-MOV 201A 12050-Can 091A 2 0F 4 D5 18 0 ATE 8.000 2 A CIV EV C
C LT C
ST C
0 VP OC "A" 9'ANCH SPRAY PLSF DISCliARGE ISOLATION VALVE, GUTS!DE CONTAlletENT ISOLATION VALVE 2-QS-le0V-2015 12050 CBM 091A 2 0F 4 E5 M0 GATE 8.000 2 A CIV EV C
0 LT C
ST C
0 W
K "B" QUENCH SPRAY PLDIP DISCNARGE ISOLATI0lt 1
VALVE, GJTSIDE CONTAll#ENT ISOLATICII VALVE 2-OS-n0V 202A 12050-C8M 091A 1 0F 4 05 M0 GATE 6.000 2 B
EV O
44 ST 0
44 VP DC CHEMICAL ADDITION TANK DISCHARGE ISOLATION VALVE 2-OS-le0V 2028 12050-Can 091A 1 0F 4 D6 1e0 GATE 6.000 2 B
EV 0
44 ST 0
44 VP OC
............ u................................
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Cc!! CAL ADDIUCII TAIIK DISCNARGE ISOLATIDW VRW l
l
l i
VIRGINIA POWER COMPANY PAGE:
69 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM VALVE TABLE NC ISO REL CS ALT VALVE DRAWINC SNMT DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NLMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2-RN-007 12050-CsM-094A 10F 2 E7 CHECK VALVE 10.000 2 C
CV C
45 0
45 "A" RNR PUMP DISCHARGE CHECK VALVE 2-RN-015 12050-CBM-094A 1 0F 2 E5 CHECK VALVE 10.000 2 C
cv C
45 0
45 "B" RNR PLMP CISCHARGE CHECK VALVE
$ RM-037 12050-CBM 094A 2 0F 2 C4 MANUAL GATE 6.000 2 AE CIV LT C
RNR SUPPLY ISOLATICN TO REFUEL WATER STORAGE TANK, INSIDE CONTAINMENT ISOLATION VA.YE 2-RN-038 12050-ceM-094A 2 0F 2 D3 MANUAL GATE 6.000 2 AE CIV LT C
RNR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, OUTSIDE CONTAINMENT ISOLATION VALVE 2 RN-MOV-2700 12050-CBM-094A 1 0F 2 A5 MO GATE 14.000 1 A PlV EV O
18 LT C
ST C
18 VP OC RHR PUMP SUPPLY ISOLATION FROM "A" HOT LEG, INSIDE MISSILE BARRIER 2-RN-Mov-2701 12050-cam-094A 1 0F 2 A4 MO GATE 14.000 1 A PlV EV 0
18 LT C
ST C
18 VP OC RHR PUMP SUPPLY ISOLATION FROM "A" HOT LEG, OUTSIDE MISSILE BARRIER 2-RM-MOV-2720A 12050 CBM-094A 2 0F 2 C3 M0 GATE 10.000 1 A PlV EV 0
18 LT C
ST C
18 VP OC l
I RHR RETURN' ISOLATION TO "B" ACCUMULATOR I
DISCHARGE LINE 1
2 RH-MOV-27208 12050-CBM-094A 2 0F 2 B3 MO GATE 10.000 1 A Plv EV 0
18 '
LT C
ST 0
18 VP OC RHR RETURN ISOLATION 70 "C" ACCUMULATOR DISCHARGE LINE 2 RH RV4721A 12050 CBM-094A 1 0F 2 E6 RELIEF VALVE 3.000 2 C
SP 0
RHR SYSTEM RELIEF VALVE AT "A" RHR PLMP SUC-TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK 2-RN-RV-2721B 12050 CBM-094A 10F 2 E4 RELIEF VALVE 3.000 2 C
SP 0
RHR SYSTEM RELIEF VALVE AT "B" RHR PUMP SUC-TION, RV DISCHARGE TO PRESSURIZER RELIEF TANK
VIRGlulA PERER IXBFANY PAGE:
50 0F 79 NIRTN AdelA LAl!T 2 REVISION: 07 i
SEC0 5 INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM a VALVE TABLE NC ISO REL CS ALT VALVE DRAMNG SNEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REG #if TEST IRSSER ENER 1RSSER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-THIS PAGE IS INTENTIONALLY BLANK.
VIRGINIA POWER COMPANY PAGE:
56 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER C00R TYPE
$!ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2-51 001 12050-CBM-096A 1 0F 3 56 CHECK VALVE 12.000 2 C
cv 0
38 "A" LOW HEAD St PLMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 2 51 006 12050-CBM-096A 1 0F 3 C7 CHECK VALVE
.750 2 AC CV C
54 LT C
"A" LOW HEAD $1 PLMP SEAL WATER SUPPLY CHECK VALVE FROM RWST 2-SI-009 12050-CBM-096A 2 0F 3 B6 CHECK VALVE 10.000 2 C
CV C
39 l
0 39 "A" LOW HEAD St PUMP DISCHARGE CHECK VALVE 2-SI-012 12050-CBM-096A 2 0F 3 B5 CHECK VALVE 2.000 2 C
CV 3
"A" LOW HEAD SI PUMP MINIMUM FLOW / TEST LINE DISCHARGE CHECK VALVE 2-$1 018 12050 CBM-096A 1 0F 3 E5 CHECK VALVE 8.000 2 AC CV C
40 0
40 LT C
76 RWST SUPPLY CHECK VALVE To CHARGING PUMP SUCTION HEADER 2-51-019 12050-CBM-096A 1 0F 3 83 CHECK VALVE 12.000 2 C
CV O
39 RWST SUPPL) CHECK VALVE T0 "B" LOW HEAD S1 PUMP SUCTION 2 51-021 12050 CBM 096A 1 0F 3 B5 CHECK PALVE 12.000 2 C
CV O
38 "B" LOW HEAD SI PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 2 SI-029 12050-CBM-096A 1 0F 3 c5 CHECK VALVE
.750 2 AC CV C
54 LT C
"B" LOW HEAD $1 PUMP SEAL WATER SUPPLY CHECK VALVE 2-51-032 12050 CBM-096A 2 0F 3 84 CHECK VALVE 10.000 2 C
CV C
39 0
39 1
"B" LOW HEAD SI PUMP DISCHARGE CHECK VALVE
'" "'" E6565ba5I6 s "" 5"6f 5 Y "5HibK hILhi""" $$666 E"" 6" ""' 6h"~ 6"~
i 5Iii!b55 "B" LOW HEAD SI PUMP MINIMUM FLOW / TEST LINE DISCHARGE CHECK VALVE 2 51-047 12050-CBM-096A 1 0F 3 E7 MANUAL CLOBE 1.000 2 AE CIV LT C
ACCUMULATOR MAKEUP LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-51-070 12050 CbM 096A 3 0F 3 D4 CHECK VALVE 1.000 2 C
CV C
l i
VIRGINIA POWER COMPANY PAGE:
61 0F 79 WORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST RE0 JUST TEST NUMBER NUMBER NUMBER C00R TYPE S!ZE CLASS CAT 1(PE TYPE POS V-CSV-VCN-
"B" LOW NEAD SI PUMP SUCTION FROM RWST 2 SI-MOV-2863A 12050 tam 096A 2 0F 3 C5 M0 GATE 8.000 2 B
EV C
0 ST C
0 VP OC "A" LOW HEAD SAFETY IhJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 2-St-MOV-28638 12050-CBM-096A 2 0F 3 04 M0 GATE 8.000 2 B
EV C
0 ST C
0 VP OC "S" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 2-SI-MOV 2864A 12050 CSM 096A 2 0F 3 C7 M0 GATE 10.000 2 B
EV C
0 ST C
0 VP OC "A" LOW HEAD $1 PUMP COLD LEG DISCHARGE STOP VALVE 2-SI Mov-28648 12050 CBN-096A 2 0F 3 C6 MO GATE 10.000 2 B
EV C
0 ST C
0 VP OC "B" LOW HEAD $1 PUMP COLD LEG DISCHARGE STOP VALVE 2 SI Mov 2865A 12050-CeM 0968 10F 4 C7 Mo GATE 12.000 2 B
EV C
24 0
24 ST C
24 0
24 VP OC "A" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2 SI-Mov-2865B 12050 CBM-0968 2 0F 4 C5 MO GATE 12.000 2 B
EV C
24 0
24 ST C
24 0
24 VP OC "B" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2-SI-MOV 2865C 12050-CsM-0968 3 0F 4 c5 M0 GATE 12.000 2 B
EV C
24 0
24 ST C
24 0
24 VP OC
VIRGINIA POWER COWANY PAGE:
62 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TTPE TYPE POS V-CSV-VCN-
"C" ACCUBRJLATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2 SI-MOV 2867A 12050-CsM 096A 3 0F 3 04 M0 GATE 3.000 2 B
EV C
0 ST C
0 VP OC BORON INJECTION TANK HIGH HEAD $1 INLET VALVE 2-SI-MOV 2867B 12050-ceM-096A 3 0F 3 04 M0 GATE 3.000 2 B
EV C
0 ST C
0 VP OC BORON INJECTION TANK HIGH HEAD S! INLET VALVE 2 SI-MOV-2867C 12050-CSM-096A 3 0F 3 E7 M0 GATE 3.000 2 A C&P EV C
37 0
37 LT C
59 ST C
37 0
37 VP OC BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV 2867D 12050-CBM 096A 3 0F 3 D7 M0 GATE 3.000 2 A C&P EV C
37 0
37 LT C
59 ST C
37 0
37 VP OC BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLAT!0N VALVE 2-SI MOV 2869A 12050 cam 096A 3 0F 3 C8 MO GATE 3.000 2 A C&P EV C
35 0
35 LT C
ST C
35 0
35 VP OC HIGH HEAD SI FROM CHARGING HEADER TO RCS NOT LEGS, OUTSIDE CONTAIMMENT ISOLATION VALVE 2 $1 MOV-2869s 12050-CeM 096A 3 0F 3 88 MO GATE 3.000 2 A C&P EV C
35 0
35 LT C
ST C
35 0
35 l
VP OC 1
HIGH HEAD SI FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 2 SI-MOV-2885A 12050-C8M-096A 2 0F 3 C3 M0 GLOBE 2.000 2 A
EV C
LT C
76 1
I I
VIRGINIA POWER CIMPANY PAGE:
63 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 01/10/95 INSERV!CE TESTING PROGRAM - VALVE TABLE NC
!$0 REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TIPE POS V-CSV-VCN-2-SI-MOV 2885A 12050-CBM-0 6 2 0F 3 C3 No GLOBE 2.000 2 A
ST C
VP OC "A" LOW NEAD $1 PUMP MINIMUM FLOW / TEST LINE ISOLATION 2-SI-MOV-28858 12050 CBM-096A 2 0F 3 B3 M0 GLOBE 2.000 2 A
EV C
LT C
76 ST C
VP OC "B" LOW HEAD SI PLMP MINIMLM FLOW / TEST LINE ISOLATION 2-$1-MOV-2885C 12050-CBM-096A 2 0F 3 D3 MO GLOBE 2.000 2 A
EV C
LT C
76 ST C
VP OC "A" LOW NEAD $1 PUMP MINIMLM FLOW / TEST LINE ISOLATION 2 SI-MOV 28850 12050-CBM 096A 2 0F 3 B3 NO GLOBE 2.000 2 A
EV C
LT C
76 ST C
l VP OC "B" LOW HEAD S1 PUMP MINIMUM FLOW / TEST LINE ISOLATION 2 SI-MOV-2890A 12050-CBM-096A 2 0F 3 D7 M0 GATE 10.000 2 A C&P EV C
35 0
35 LT C
ST C
35 0
35 VP OC "A" LOW NEAD St PUMP NOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2 SI-MOV 28908 12050-CBM 096A 2 0F 3 D7 M0 GATE 10.000 2 A C&P EV C
35 0
35 LT C
ST C
35 0
35 VP OC "B" LOW HEAD St PUMP NOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2 SI-Mov 2890C 12050-CBM-096A 2 0F 3 C8 M0 GATE 10.000 2 A C&P EV C
37 1
0 37 i
LT C
59 ST C
37 0
37 VP OC LOW HEAD 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
37 0
37 LT C
59 ST C
37
VIRGINIA POWER COMPANY PAGE:
71 0F 79 NORTM ANNA UNIT 2 REVISION: 07 SEcole INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT 1
VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE
$1ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-2-SW-627 11715-CBM 078G 2 0F 2 E3 CHECK VALVE 2.000 3 C
CV 0
36 l
SERVICE WATER SUPPLY TO CHARGING PLMP SEAL COOLER CNECK VALVE 2-SW-MOV 201A 11715 CBM-078A 4 GF 4 ET M0 BFLY 24.000 3 5
EV 0
35 ST o
35 VP OC "A" SERVICE WATER NEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2 SW-MOV-201B 11715-CBM-078A 4 0F 4 E7 M0 BFLY 24.000 3 B
EV 0
35 ST 0
35 VP OC i
)
"A" SERVICE WATER HEADER SUPPLY ISOLATI E TO RECIRC SPRAY MEAT EXCNANGERS 2-SW-Mev-201C 11715 CBM-07BA 4 0F 4 E7 Mo BFLY 24.000 3 B
EV o
35 ST o
35 VP OC "B" SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2-SW-MOV 2010 11715 CBM 078A 4 0F 4 E7 MO BFLY 24.000 3 8
EV 0
35 ST 0
35 VP OC j
"B" SERVICE WATER NEADER SUPPLY !$0LATION TO RECIRC SPRAY HEAT EXCHANGERS 2 SW-MOV 202A 11715 CBM-0788 3 0F 4 F8 M0 BFLY 24.000 3 8
EV C
ST C
VP OC SERVICE WATER SUPPLY CROSS CONNECTS TO RECIRC SPRAY HEAT EXCHANGERS 2-SW MOV 202B 11715 CBM 0785 3 0F 4 F8 M0 BFLY 24.000 3 5
EV C
ST C
VP OC SERVICE WATER SUPPLY CROSS CONNECTS TO RECIRC SPRAY HEAT EXCHANGERS 2 SW-MOV-203A 11715-CBM 0788 3 0F 4 E7 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER SUPPLY TO "A" RECIRC SPRAY HEAT EXCNANGER, OUTSIDE CONT ISOLATION VALVE 2 SW-MOV 2038 11715 CBM-0788 3 0F 4 E6 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC
VIRGINIA poler COMPANY PAGE:
72 0F 79 WORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-SERVICE WATER SUPPLY TO "S" RECIRC SPRAY MEAT EXCHANGER, QUTSIDE CONT ISOLATION VALVE 2 SW-MOV-203C 11715 COM-0788 3 0F 4 E4 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER SUPPLY TO "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE j
2-SW-MOV-2030 11715 CBM-0788 3 0F 4 E3 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER SUPPLY TO "0" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-M09-204A 11715-CsM-0788 3 0F 4 C7 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
l 0
W K
i SERVICE WATER RETURN FROM "A" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2 SW-MOV-2048 11715 cam 0788 3 0F 4 C6 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER RETURN FROM "B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2 SW MOV 204C 11715 CBM 078s 3 0F 4 C5 M0 BFLY 16.000 2 A CIV EV C
0 LT C
ST C
0 VP OC SERVICE WATER RETURN FROM "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2 SW MOV-204D 11715 COM-0788 3 0F 4 C3 M0 BFLY 16.000 2 A CIV EV C
O LT C
ST C
0 VP OC SERVICE WATER RETURN FROM "D" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE
VIRGINIA PCER COMPANY PAGE:
73 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST ' REQ JUST TEST IRMBER NLMBER NUMBER COOR TYPE SI2E CLASS CAT TYPE TYPE POS V*
CSV-VCN-2 SW MOV-205A 11715-cam-078A 4 0F 4 Er No BFLY 24.000 3 B
EV 0
35 ST 0
35 VP OC "B" SERVICE WATER NEADER RETURN ISOLATION FROM RECIRC SPRAY MEAT EXCHANGERS 2-SW MOV-2058 11715 C8M-078A 4 0F 4 E7 M0 BFLY 24.000 3 8
EV 0
35 ST 0
35 VP OC l
"B" SERVICE WATER NEADER RETURN !$0LATION 1
FROM RECIRC SPRAY NEAT EXCNANGERS i
I 1
2-SW MOV 205C 11715-CSM-078A 4 0F 4 E6 No BFLY 24.000 3 8
EV 0
35 ST 0
35 VP OC j
"A" SERVICE WATER NEADER RETURN ISOLATION l
1 FROM RECIRC SPRAY HEAT EXCHANGERS 2-SW-MOV-2050 11715-COM-078A 4 0F 4 E7 Mo BFLY 24.000 3 5
EV 0
35 ST 0
35 VP OC "A" SERVICE WATER NEADER RETURN ISOLATION FROM RECIRC SPRAY NEAT EXCHANGERS 2-SW-MOV-206A 11715 CBM-0788 3 0F 4 53 M0 BFLY 24.000 3 B
EV C
ST C
VP OC SERVICE WATER RETURN CROSS CONNECTS FROM RECIRC SPRAY MEAT EXCHANGERS 2 SW-MOV 2068 11715-COM 0788 3 0F 4 A3 M0 BFLY 24.000 3 5
EV C
St C
VP OC SERVICE WATER RETURN CROSS CONNECTS FROM RECIRC SPRAY HEAT EXCHANGERS 2 SW MOV 208A 11715 CeM-078C 1 0F 2 53 M0 BFLY 24.000 3 8
EV C
43 0
43 ST C
43 0
43
)
VP OC "A" SERVICE WATER NEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2 SW MOV-2088 11715 cam 078C 1 0F 2 B3 M0 BFLY 24.000 3 8
EV C
43 0
43 ST C
43 0
43 VP OC "A" SERVICE WATER NEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2 SW MOV 210A 11715-CBM-078A 4 0F 4 E8 M0 BFLY 8.000 3 E
VP OC i
I
1 VIRGINIA poler COMPANY PAGE:
76 0F 79 i
i NORTH ANNA UNIT 2 REVISION: 07 i
l SECONO INSPECTION INTERVAL DATE: 08/08/95
{
INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-SERVICE WATER HEADER SUPPLY TO RECIRCULATION l
AIR COOLERS 2 sW-Mov 210B 11715 CBM-078A 4 0F 4 F8 M0 BFLY 8.000 3 E
VP OC SERVICE W TER NEADER SUPPLY TO RECIRCULATION AIR COOLERS 2-SW MOV-213A 11715-CBM-078A 4 0F 4 B7 M0 BFLY 10.000 3 E
VP OC SERVICE WATER RETURN ISOLATION FROM FUEL PIT COOLERS 2 SW-MOV-2138 11715 CBM-078A 4 0F 4 B5 M0 BFLY 10.000 3 E
VP OC SERVICE WATER SUPPLY ISOLATION TO FUEL PIT COOLERS 2-SW MOV-214A 11715 CBM-078A 4 0F 4 F8 M0 BFLY 8,000 3 E
VP OC SERVICE WATER NEADER RETURN FROM RECIRCULATION AIR COOLERS 2-SW-MOV-2148 11715-CBM-078A 4 0F 4 F8 M0 BFLY 8.000 3 E
VP OC SERVICE WATER NEADER RETURN FROM RECIRCULATION AIR COOLERS 2-SW Mov 215A 11715 CBM-078A 1 0F 4 07 No BFLY 24.000 3 8
EV O
ST 0
VP OC SERVICE WATER NEADER SUPPLY ISOLATION VALVE FROM AUXILIARY SERVICE WATER PUMPS 2 SW MOV-217 11715 CBM 078A 1 0F 4 D6 M0 BFLY 24.000 3 B
EV 0
ST 0
VP OC UNIT 2 AUXILIARY SERVICE WATER PUMP DISCHARGE ISOLATION VALVE 2 SW-Mov-219 11715 CBM-078A 1 OF 4 05 M0 BFLY 8.000 3 B
EV C
ST C
VP OC MAKEUP PUMP SUPPLY VALVE 1
2 SW Mov-220A 11715-CBM 078A 4 0F 4 F3 M0 BFLY 10.000 NC E
VP OC AUXILIARY SERVICE WATER RETURN HEADER VALVE l
2-SW-Mov-2208 11715-CBM 078A 4 OF 4 F3 No BFLY 10.000 NC E
VP OC 1
AUXILIARY SERVICE WATER RETURN HEADER VALVE l
I 2-SW-Mov 221A 11715-CBM 078N 1 0F 1 C8 M0 BFLY 18.000 3 8
EV 0
l ST 0
i VP OC i
1
VIRGINIA POWER COMPANY PAGE:
75 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS ALT
- VALVE DILAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NLMBER C00R TYPE
$!ZE CLASS CAT TYPE TYPE POS V-CSV-VCN-SERVICE WATER TO SPRAY ARRAYS STOP VALVE 2-SW-MOV-221B 11715 CBM-078H 1 0F 1 C4 M0 BFLY 18.000 3 B
EV 0
ST 0
VP OC SERVICE WATER TO SPRAY ARRAYS STOP VALVE 2-SW-MOV 222A 11715-CBM 078H 1 0F 1 C7 M0 BFLY 18.000 3 B
EV 0
ST 0
VP OC SERVICE WATER TO.0tAY ARRAYS STOP VALVE 2 SW-MOV-2228 11715-CBM-078H 1 0F 1 C4 M0 BFLY 18.000 3 B
EV 0
ST 0
VP OC SERVICE WATER TO SPRAY ARRAYS STOP VALVE 2 SW-MOV 223A 11715-CBM-078H 1 0F 1 D8 M0 BFLY 24.000 3 B
EV C
ST C
VP OC SERVICE WATER BYPASS VALVE 2-SW MOV-2238 11715 CBM-078H 1 0F 1 D4 M0 BFLY 24.000 3 8
EV C
ST C
YP OC SERVICE WATER BYPASS VALVE 2 SW RV-200A 11715-CBM-0788 3 0F 4 ET RELIEF VALVE
.750 2 C
SP 0
"A" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 2 $W RV 2008 11715 CBM 0788 3 0F 4 E6 RELIEF VALVE
.750 2 C
SP 0
"B" REC!RC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 2 SW RV-200C 11715-CBM 0788 3 0F 4 E4 RELIEF VALVE
.750 2 C
SP 0
"C" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE To CONT SLMP 2-SW RV-2000 11715-CBM-0788 3 0F 4 E3 RELIEF VALVE
.750 2 C
SP O
"D" RECIRC SPRAY HEAT EXCHANG SERVICE WATER RELIEF VALVE, RV DISCHARGE TO CONT SUMP 2 SW-TCV 202A 11715 CBM 078G 2 0F 2 C4 A0 GATE 2.000 3 8
EV O
FS 0
ST 0
1 VIRGIN!A P0hER CCMPANY PAGE:
76 0F 79 NORTH ANNA UNIT 2 REVISION: 07 SECOND INSPECTION INTERVAL DATE: 08/08/95 INSERVICE TESTING PROGRAM - VALVE TABLE NC 150 REL CS ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST TEST NUMBER NUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-VCN-SERVICE WATER FROM CHARGING PLMP LUBE DIL COOLER TEMP CONTROL VALVE 2-SW TCV 202B 11715 CBM 078G 2 0F 2 C6 A0 GATE 2.000 3 B
EV 0
FS O
ST 0
SERVICE WATER FROM CHARGING PUMP LUBE OIL COOLER TEMP CONTROL VALVE 2 SW TCV-202C 11715 CBM-078G 2 0F 2 C8 A0 GATE 2.000 3 B
EV 0
FS 0
ST 0
SERVICE WATER FROM CHARGING PUMP LUBE OIL COOLER TEMP CONTROL VALVE O
-.. --- -.-..-._.-- ~
RELIEF REQUEST V-39
-I.
IDENTIFICATION OF COMPONENTS System Safety Injection Valve (s):
2-SI-9 2-SI-19 2-SI-32 Class 2
II. IMPRACTICAL Ct SE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF 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.
During cold shutdown, the reactor coolant system pressure still prevents full flow testing of the check valves.
Partial stroke exercising the valves with flow could cause an overpressurization condition during cold shutdowns.
To verify closure of Valves 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 established to demonstrate adequate seat tightness for the discharge valve to the non-running pump.-
IV. ALTERNATE TESTING Valves 2-SI-9 and 32 will be exercised to the full open and closed position every reactor refueling (not to exceed 24 months).
Valve 2-SI-19 will be partial stroke tested every quarter and full flow tested every reactor refueling.
2-65 N2PVR7 Revision 7 January 10, 1995
--.. ~
~...
.. - _ ~ _ - -.. -.... -.. - -. - - -.-...
l l
RELIEF REQUEST V-42 I. IDENTIFICATION OF COMPONENTS System Safety Injection i
Valve (s):
2-SI-85 2-SI-107 2-SI-91 2-SI-119 2-SI-93 2-SI-126 2-SI-99 2-SI-128 2-SI-105 Class 1 for 2-SI-91, 99, 105, 107 and 119 2 for 2-SI-85, 93, 126 and 128 II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These Safety Injection check valves must open and close to fulfill their safety functions.
They cannot be full 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 l
overpressurization of the Reactor Coolant System and i
force a safety system to function.
These valves can only be tested to the closed position by draining the lines and performing a back seat leak 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.
With low head pump flow, the cold leg injection valves 2-SI-91, 99, and 105 will be nonintrusively monitored using a sampling plan every reactor refueling.
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 one t
group.
During initial testing using nonintrusive techniques, each valve will be verified as operable.
i 2-68 N2PVR7 Revision 7 August 8, 1995
RELIEF REQUEST V-42 (Cont.)
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.
If t
1 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 flow rate can be measured for the remaining valves in this relief request.
IV. ALTERNATE TESTING Exercise to the open position every reactor refueling.
Exercise to the closed position every reactor refueling per Technical Specification 4.4.6.2.2.
I 2-68a N2PVR7 Revision 7 August 8, 1995 l
_ ~. ~. _ _
RELIEF REQUEST V-43 I. IDENTIFICATION OF COMPONENTS System Safety Injection Valve (s):
2-SI-151 2-SI-170 2-SI-153 2-SI-185 2-SI-168 2-SI-187 Class 1
II. IMPRACTICAL CODE REQUIREMENTS Exercise valves for operability every three months III. BASIS FOR RELIEF These valves cannot be partial or full flow tested during normal operation because the accumulator pressure (600 to 650 psig) is below Reactor Coolant System pressure and the injection of borated water t
would upset the reactor coolant chemistry.
During cold shutdown, the RCS pressure may still prevent full flow testing.
Also, discharging the accumulators would challenge the Low Temperature Overpressure Protection System.
A partial flow test is not practical during cold shutdowns.
The flow from the accumulator is dependent on the pressure differential between the accumulator and the RCS.
The pressure differential cannot be controlled to the fine degree necessary to 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 l
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.
2-69 N2PVR7 Revision 7 August 8, 1995
~
.~.
- -.-~- - --. -. _.-- -
RELIEF REQUEST V-43 (Cont.)
The use of nonintrusive monitoring techniques are being evaluated for confirming full disk movement.
If nonintrusive techniques can provide a " positive means" for verifying obturator movement, a sampling program will be used as described below due to the burden of 1
applying these techniques in the field.
IV. ALTERNATE TESTING During the first refueling outage where nonintrusive techniques are used, all valves in the group will be tested to verify that the techniques verify valve obturator movement.
During subsequent refueling outages, flow testing will be performed on all valves in the group, but the nonintrusive techniques need be applied only to one valve in each group, on a rotating basis, unless indications of problems are identified.
In this case, all valves in the group will be subjected to the nonintrusive techniques.
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 i
will be in the other group.
This sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.
The flow test will consist of discharging the i
accumulator from an initial pressure that is less than 600 psig.
Discharging the accumulator at a lower initial pressure reduces the severity of the transient and the risk of adverse effects on the reactor coolant i
system.
The low pressure test should provide enough flow to force the disk to the full open position.
If full disk movement cannot be confirmed using nonintrusive monitoring, these valves will be placed into two groups and one valve from each group will be disassembled and inspected every other reactor refueling.
The justification for the vtended disassembly and inspection schedn' s.vailable at the station.
Valves 2-SI-153, 170 and 187 will be confirmed closed every reactor refueling.
2-70
'N2PVR7 Revision 7 August 8, 1995
-. - ~
i 4
i RELIEF REQUEST V-44 I.
IDENTIFICATION OF COMPONENTS System Safety Injection Valve (s):
2-SI-92 2-SI-100 2-SI-106 Class 1
II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These Safety. Injection check valves must open and close to fulfill their safety function.
They cannot be full or part-stroke exercised to the open position during power operation because this would 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 I
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.
With low head pump flow, these cold leg injection valves will be nonintrusively monitored using a sampling plan every reactor refueling.
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 one group.
During initial testing using nonintrusive techniques, i
each valve will be verified as operable.
2-71 N2PVR7 Revision 7 l
August 8, 1995
RELIEF REQUEST V-44 (Cont.)
During subsequent testing, nonintrusive verification a
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.
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.
IV. ALTERNATE TESTING Exercise to the open and closed positions every reactor i
refueling.
)
i l
2-71a N2PVR7 Revision 7 August 8, 1995
7 RELIEF REQUEST V-45 I. IDENTIFICATION OF COMPONENTS System Safety Injection Valve (s):
2-SI-90 2-SI-117 2-SI-98 2-SI-118 2-SI-104 2-SI-124 2-SI-112 2-SI-125 2-SI-113 Class 1
II. IMPRACTICAL CODE REQUIREMENTS Exercise valves every three months III. BASIS FOR RELIEF These safety Injection check valves must open and close to fulfill their safety function.
They cannot be full or part-stroke exercised to the open position during power operation because this would thermally shock the injection system and cause unnecessary plant transients.
During cold shutdown, the Reactor Coolant System pressure still prevents full design flow.
Also, a partial or full stroke test could cause an overpressurization of the Reactor Coolant System and force a safety system to function.
The only test methods to individually back seat these valves are to perform leak tests or to use downstream pressure provided by the low head safety injection pump tests.
Either test can only be performed during reactor refueling.
With low head pump flow, 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.
The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.
2-72 N2PVR7 Revision 7 August 8, 1995
RELIEF REQUEST V-45 (Cont.)
Per this plan, the valves will be placed into two groups with valves 2-SI-113, 118 and 125 in one group, and valves 2-SI-112, 117 and 124 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.
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.
IV. ALTERNATE TESTING Exercise to the open and closed positions every reactor refueling.
2-72a N2PVR7 Revision 7 August 8, 1995
l 1
l RELIEF REQUEST V-51 Relief Request Withdrawn l
l l
l
~
N2PVR7 Revision 7 August 8, 1995
RELIEF REQUEST V-73 I. IDENTIFICATION OF COMPONENTS System Chemical & Volume Control System Valve (s):
2-CH-153 2-CH-495 Class 2
l II. IMPRACTICAL CODE REQUIREMENTS Exercise valve closed every three months III. BASIS FOR RELIEF 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 perform a back pressure test because normal letdown and charging flow, and reactor coolant pump i
seal flow would be interrupted.
Also, if the valves were isolated during normal operation, the charging pumps would have to be secured.
1 These valves are also subject to leak testing, which is l
performed every reactor refueling.
Verification of I
closure will be performed during the leak test every reactor refueling instead of every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify the burden of performing a leak rate test.
IV. ALTERNATE TESTING Exercise to the closed position every reactor refueling.
1 2-101 N2PVR7 Revision 7 January 10, 1995
m_
~.-.. - -. -
RELIEF REQUEST V-75 Replaced by Cold Shutdown Justification CSV-45 f
V r-h I
1 i
l
[
i 2-103 N2PVR7 Revision 7 August 8, 1995 i
E l
RELIEF REQUEST V-76 I.
IDENTIFICATION OF COMPONENTS 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 f:
2-SI-18 2-SI-MOV-2885C i
2-SI-MOV-2885D Class 2
II. IMPRACTICAL CODE REQUIREMENTS IWV-3427 (a) - Valves with leakage rates exceeding either the values specified by the Owner or those rates given in i
IWV-3426 shall be replaced or repaired.
i III. BASIS FOR RELIEF 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 diacharge of the low head SI pumps to the RWST.
During recirculation mode transfer, the RWST is italated and the low head SI pumps recirculate highly contaminated water from the containment sump to the reactor vessel.
The RWST isolation valves work as a system of valves to protect the RWST from the contaminated sump water.
Permissible valve leakage rates are based on each valve's possible contribution to the total allowable leakage rate to the RWST.
When the leakages from each valve have been measured and summed, an individual valve's permissible leakage rate may have been exceeded but the 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 j
be performing adequately.
IV. ALTERNATE TESTING In addition to replacement or repair as corrective actions, an evaluation can be performed which demonstrates that even if a valve has exceeded its permissible leakage rate, the overall leakage rate to the RWST will be maintained below the overall allowable RWST leakage rate.
No repair or replacement is necessary if the evaluation is performed.
2-103a
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N2PVR7 Revision 7 January 10, 1995
COLD SHUTDOWN JUSTIFICATION CSV-20 Cold Shutdown Justification withdrawn ca i
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2-124 N2PVR7 Revision 7 January 10, 1995
COLD SHUTDOWN JUSTIFICATION CSV-39 I. IDENTIFICATION OF COMPONENTS System Chemical and Volume Control l
Valve (s):
2-CH-176 2-CH-191 j
2-CH-206 2-CH-495 Class 2
II. COLD SHUTDOWN JUSTIFICATION These check valves must open to allow charging pump recirculation.
There is no permanently mounted instrumentation to measure full flow in the racirculation flow path.
Therefore, full flow conditions will have to be measured by using temporary ultrasonic flow instrumentation.
The ultrasonic flow transducers and their mounting carriages must be installed and the transducers referenced to a no flow condition before each test.
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 for quarterly testing.
J Test experience has shown that the discharge pressure drop is undetectable when flow through the recirculation line is established in conjunction with normal charging.
Therefore, quarterly partial flow testing is not verifiable.
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2-136 N2PVR7 Revision 7 January 10, 1995 i
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COLD SHUTDOWN JUSTIFICATION CSV-43 I. IDENTIFICATION OF COMPONENTS System Service Water
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Valve (s):
2-SW-MOV-208A 2-SW-MOV-208B Class 3
II. COLD SHUTDOWN JUSTIFICATION These isolation valves are located in series on service water supply to the component cooling heat exchangers.
E The component cooling heat exchangers carry a majority j
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 i
harmful high-magnitude vibrations as the service water i
flow decreases through a range from 7000 gpa to 6000 i
gpa.
These pumps cannot be stopped during the valve i
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.
j The valve controllers do not allow for a partial-stroke l
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
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cold shutdown frequency.
1 2-139a N2PVR7 Revision 7 August 8, 1995
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W COLD SHUTDOWN JUSTIFICATION CSV-44 I.
IDENTIFICATION OF COMPONENTS System Quench Spray Valve (s):
2-QS-MOV-202A 2-QS-MOV-202B Class.
2 II. 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 horic acid solution in the RWST.
After the motor operated isolation valves are stroked open and closed, the piping between the motor operated i
valves and the= downstream manual isolation valves must be drained of sodium hydroxide.
Approximately five l
gallons of highly caustic fluid are drained into a l
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.
2-139b N2PVR7 Revision 7 January 10, 1995
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COLD SHUTDOWN JUSTIFICATION CSV-4r3 i
I.
IDENTIFICATION OF COMPONENTS
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System Residual Heat Removal Valve (s):
2-RH-7 2-RH-15 l
Class 2
II. COLD SHUTDOWN JUSTIFICATION These RHR pump discharge check valves e tn 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 cperation is not practical.
These valves will be full-stroke exercised every cold shutdown but not mere frequently then every three months.
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i 2-139c N2PVR7 Revision 7 August 8, 1995 l
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