ML18153A934
| ML18153A934 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 04/26/1994 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-223, TAC-M86645, TAC-M86646, NUDOCS 9405020379 | |
| Download: ML18153A934 (10) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 26, 1994 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 SUBMITTAL OF 1ST RELIEF REQUESTS Serial No.
NL&P/GSS Docket Nos.
License Nos.94-223 R1 50-338 50-339 50-280 50-281 NPF-4 NPF-7 DPR-32 DPR-37 Pursuant to 1 O CFR 50.55a(f)(5), Virginia Electric and Power Company hereby requests relief from the lnservice Testing requirements of Section XI, 1986 Edition, paragraph IWV-3427(a) for the North Anna Power Station and of Section XI, 1989 Edition, OM Part 10, paragraph 4.2.2.3(f) for the Surry Power Station. These paragraphs state that for valves with leakage rates exceeding the values specified by the Owner, the valves shall be replaced or repaired. Relief is requested to provide additional flexibility in returning certain isolation valves to service following leak testing. The basis for each relief request is provided in the Attachments of this letter.
The relief requests pertain to the system of isolation valves that prevent leakage of contaminated containment sump water to the Refueling Water Storage Tanks (RWST) from the discharge side of the low head safety injection pumps during recirculation mode transfer phase of safety injection. Relief requests V-75 (North Anna Unit 1 ), V-76 (North Anna Unit 2), V-52 (Surry Unit 1 ), and V-52 (Surry Unit 2) state that in addition to replacement or repair as corrective actions, an evaluation can be performed. The evaluation is to demonstrate 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. Therefore, no repair or replacement is necessary if the evaluation is performed and the overall allowable leakage is maintained.
These relief requests are similar to the relief requests that have been submitted for the containment system isolation valves at the North Anna and Surry Power Stations.
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Relief requests V-69 (North Anna Unit 1) and V-70 (North Anna Unit 2) allow for the use of an evaluation in addition to replacement or repair for the containment system isolation valves and were approved for use by the NRC Safety Evaluation dated September 17, 1993 (TAC Nos. M86645 and M86646). Relief requests V-51 (Surry Unit 1) and V-51 (Surry Unit 2) were submitted for the Surry containment system isolation valves by letter dated October 19, 1993 as part of the Third Ten Year 1ST Program update.
These relief requests have been reviewed by the Station Nuclear Safety and *Operating Committees.
If you have questions regarding this information, please co11tact us.
Very truly yours,
{ar W. L. Stewart Senior Vice President - Nuclear Attachments
- 1. North Anna Units 1 and 2 Relief Requests
- 2. Surry Units 1 and 2 Relief Requests cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident Inspector North Anna Power Station Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station North Anna Power Station Units 1 and 2 1ST Relief Requests
NORTH ANNA UNIT 1 RELIEF REQUEST V-75 I. IDENTIFICATION OF COMPONENTS System Chemical and Volume Control and Safety Injection Valve(s):
1-CH-MOV-1115B 1-CH-MOV-1115D 1-SI-47 Class 2
II. IMPRACTICAL CODE REQUIREMENTS 1-SI-MOV-1885A 1-SI-MOV-1885B 1-SI-MOV-1885C 1-SI-MOV-1885D IWV-3427 (a) - Valves with leakage rates exceeding either the values specified by the Owner or those rates given in IWV-3426 shall be replaced or repaired.
III. BASIS FOR RELIEF 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 Dare 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 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.
e e
NORTH ANNA UNIT 2 RELIEF REQUEST V-76 I. IDENTIFICATION OF COMPONENTS System Chemical and Volume Control and Safety Injection Valve(s):
2-CH-MOV-2115B 2-CH-MOV-2115D 2-SI-18 Class 2
II. IMPRACTICAL CODE REQUIREMENTS 2-SI-MOV-2885A 2-SI-MOV-2885B 2-SI-MOV-2885C 2-SI-MOV-2885D IWV-3427 (a) - Valves with leakage rates exceeding either the values. specified by the Owner or those rates given in IWV-3426 shall be replaced or repaired.
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 Dare 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 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.
Surry Power Station Units 1 and 2 1ST Relief Requests
SURRY UNIT 1 RELIEF REQUEST V-52 system Chemical and Volume Control and Safety Injection Valve(s):
1-CH-LCV-1115B 1-CH-LCV-1115D 1-SI-25 category:
A and A/C Class 2
1-SI-MOV-1885A 1-SI-MOV-1885B 1-SI-MOV-1885C 1-SI-MOV-1885D Function:
RWST Isolation Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.2.2.3(f) - Valves or valve combinations with leakage rates exceeding the values specified by the Owner in (e) above shall be declared inoperable and be either repaired or replaced.
Basis For Request Valves 1-CH-LCV-1115B and D, and 1-SI-25 are in the supply line to the charging pumps from the RWST.
Valves 1-SI-MOV-1885A, B, c and Dare 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.
SURRY UNIT 1 RELIEF REQUEST V-52 (Cont.)
Alternate Testing Proposed In addition to repair or replacement as corrective actions, an evaluation can be performed which demonstrates that even if a valve has exceeded its permissible leakage rate, the overall leakage rate to the RWST will be maintained below the overall allowable RWST leakage rate.
No repair or replacement is necessary if the evaluation is performed.
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SURRY UNIT 2 RELIEF REQUEST V-52 system Chemical and Volume Control and Safety Injection Valve(s):
2-CH-LCV-2115B 2-CH-LCV-2115D 2-SI-25 category:
A and A/C Class 2
2-SI-MOV-2885A 2-SI-MOV-2885B 2-SI-MOV-2885C 2-SI-MOV-2885D Function:
RWST Isolation Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.2.2.3(f) - Valves or valve combinations with leakage rates exceeding the values specified by the Owner in (e) above shall be declared inoperable and be either repaired or replaced.
Basis For Request Valves 2-CH-LCV-2115B and D, and 2-SI-25 are in the supply line to the charging pumps from the RWST.
Valves 2-SI-MOV-2885A, B, C and Dare 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.
SURRY UNIT 2 RELIEF REQUEST V-52 (Cont.)
Alternate Testing Proposed In addition to repair or replacement as corrective actions, an evaluation can be performed which demonstrates that even if a valve has exceeded its permissible leakage rate, the overall leakage rate to the RWST will be maintained below the overall allowable RWST leakage rate.
No repair or replacement is necessary if the evaluation is performed.