ML20134Q036
| ML20134Q036 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/26/1996 |
| From: | Rainsberry J SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M93558, TAC-M93559, NUDOCS 9612020077 | |
| Download: ML20134Q036 (4) | |
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f[5 Southem Califomia Edison Company P. O. BOX 128 SAN CLEMENTE. CALIFORNIA 92674-0128 J. L. RAINSBERRY TELEPHONE I
m o~O"7EE$~o'EU'017~7.m au November 26, 1996 l
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Response to Information Requested in the NRC's Review of Responses 1
.to Anomalies for San Onofre Nuclear Generating Station, Units 2 and 3, Inservice Testing Program (TAC Nos. M935C8 and M3559)
San Onofre Nuclear Generating Station Units 2 and 3
References:
1)
Letter from Mel B. Fields (NRC) to Mr.. Harold B. Ray (Edison) dated April 22, 1996;
Subject:
Review of Responses to Anomalies for San Onofre Nuclear Generating Station, Units 2 and 3, Inservice Testing Program (TAC Nos. M93558 andM3559) 4 2)
Letter from Walter C. Marsh (Edison) to the Document Control Desk (NRC) dated August 28, 1995;
Subject:
ASME Code Update for the Second Ten Year Interval, Inservice Testing Program, San Onofre Nuclear Generating Station, Units 2 and 3 3)
Letter from Theodore R. Quay (NRC) to Harold B. Ray (Edison) dated August 31, 1994;
Subject:
Second 10-Year Interval for Inservice Testing of Pumps and Valves - San Onofre Nuclear Generating Station, Unit No. 2 (TAC M87283) and Unit No. 3 (TAC No. M87284)
This letter is to inform the NRC of changes to the Inservice Testing (IST) program. These changes resulted from Southern California ~ Edison's (Edison's) l[
evaluation following the receipt of the April 22, 1996, letter (Reference 1).
By the August 28, 1995, letter (Reference 2) Edison responded to seven e
anomalies which the NRC identified in the August 31, 1994, letter (Reference
/hd, 3). The April 22, 1996, letter (Reference 1) provided the results of the
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NRC's review of Edison's response. Reference 1 closed out the NRC review of Edison's second ten-year IST program. However, reference 1 did contain two comments that have now been addressed by Edison's IST program.
9612020077 961126 PDR ADOCK 05000361 G
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Comment 1:
In the NRC review of Anomaly 3, which addressed several Alternate Testing Justifications (ATJs), the NRC stated:
4 "The anomaly indicated that there were several ATJs which did not adequately demonstrate the impracticality of testing the subject valves l
t quarterly during power operation or during cold shutdowns if testing is i
deferred to refueling outages. Each listed ATJ was reviewed by the j
licensee and, using the guidance in NUREG-1482, " Guidelines for j
Inservice Testing at Nuclear Power Plants," April 1995, the testing frequency was adjusted or additional justification was incorporated into i
the basis for deferral.
(Note, however, that in the resolution description for ATJ 14.0, Part 3, S2(3)2423MU017, the licensee states i
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that "the close exercise test has been removed from the Inservice Testing Program Requirements," while the basis states that "the basis document calls only for a close verification." The statements appear to j
contradict each other and that it is rather the open function that has i
been deleted from the IST program.)"
Response
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-S2(3)2423MU017 is a normally closed check valve. The IST basis document and the Program document have been revised to show that the only test required is an Appendix J 1eak test.
Comment 2:
Under "Other Comments" the NRC stated the following_concerning Position IndicationTesting(PIT):
"In reviewing the changes to the IST program plan, an item was noted that may require action by-the licensee.- Revised Note 23 states that, contrary to the SONGS-2/3 IST basis document and because the subject valves are locked in position, "no actual PIT [ position indication verification] test is required..."The licensee should evaluate the consistency of Revised Note 23 with the ASME OH-10 provisions and inform us of any changes to the IST Program plan resulting from the evaluation."
Response
Edison has removed Note 23 from its program and will perform PITS on the affected valves (four per unit) by the end of the Cycle 9 refueling outage for each unit. Additionally, the IST basis document was reviewed, and an additional 6 valves per unit (listed in the enclosed table) were identified that used this same logic for excluding PITS. Testing of these valves will also be completed by the end of the Cycle 9 refueling outage for each unit.
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Document Control Desk !
Please let me know if you have any questions.
Very truly yours, 7~D, /9/15 i
4 36. %
i Enclosure b
i cc:
L. J. Callan, Regional Administrator, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3-i
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Tests added to the Inservice Testing Program F
Valve Name Description Test Added Test Inten al S2(3)2423MUO55 Service Air Containment Isolation Valve Position Indication Test Refueling S2(3)1204MUO99 Safety Injection Tank to Refueling Water Tank (RWT)
Position Indication Test Refueling Containment Isolation Valve S2(3)1204MUO22 Isolation Valve, RWT-005 to LSPI P015 Suction Position Indication Test Refueling S2(3)1204MUO23 Isolation Valve, RWT-006 to LSPI P016 Suction Position Indication Test Refueling S2(3)120lMU015 Isolation Valve, Shut Down Cooling to LPSI P015 Position Indication Test Refueling Suction 4
S2(3)120lMU018 Isolation Valve, Shut Down Cooling to LPSI P016 Position Indication Test Refueling Suction
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