ML20031G029
| ML20031G029 | |
| Person / Time | |
|---|---|
| Issue date: | 09/22/1981 |
| From: | Brickley R, Hale C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20031G019 | List: |
| References | |
| REF-QA-99900404 NUDOCS 8110200665 | |
| Download: ML20031G029 (12) | |
Text
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ORGANIZATION: WESTINGHOUSE ELECTRIC CORPORATION, NUCLEAR TECHNOLOGY DIVISION, MONR0EVILLE, PENNSYLVANIA REPORT NO.: 99900404/81-03 INSPECTION DATE(Sl: 8/17-21/81 INSPECTION ON-SITE HOURS: 29 l
CORRESPONDENCE ADDRESS: Westinghouse Electric Corporation Nuclear Technology Division Attn:
Dr. R. J. Slember General Manager Post Office Box 355 Pittsburgh, Pennsylvania 51230 ORGANIZATION CONTACT:
Mr. P. T. McManus, Manager, Product Assurance TELEPHONE:
(412) 273-6268 PRINCIPAL PRODUCT: Nuclear Steam Supply Systems NUCLEAR INDUSTRY ACTIVITY: The Nuclear Technology Division of Westinghouse Electric Corporation employs approximately 2,212 people,100% of which are assigned to domestic nuclear power plant activities.
l ASSIGNED INSPECTOR: I k. h 9
/
j R. H. Brickley, R$ tor Systems Section (RSS)
Date t
i OTHER INSPECTORiSl: None APPROVED BY:
Cd M 'h /
C. J.J ale, Chief, RSS Date i
INSPECTION BASES AND SCOPE:
A.
BASES:
10 CFR Part 50, Appendix B, and Topical Report No. WCAP-8370.
B.
SCOPE: A Regional request concerning Volume Control Tank level transmitters, audits, and status of previous inspection findings, t
i Certified By__
8110200665 810928 PDR GA999 EMVWEST 99900404 PDR
ORGANIZATION: WESTINGHOUSE ELECTRIC CORPORATION, NUCLEAR TECHNOLOGY DIVISION, MONROEVILLE, PENNSYLVANIA RE90RT NO.: 99900404/81-03 INSPECTION RESULTS:
PAGE 2 of 3 A.
VIOLATIONS None.
B.
NONCONFORMANCES None.
C.
UNRESOLVED ITEMS None.
U.
STATUS OF PREVIOUS INSPECTION FINDINGS (Closed) Follow-Up Item (81-02): Calculation No. CN-RPA-76-53, part of the verification package for cycle 2 (version) of computer program MARVEL, could not be located during the inspection.
Calculation No. CN-RPA-76-53 could not be located, therefore, Westinghouse performed another calculation, No. CN-PP-81-174.
E.
OTHER FINDINGS OR COMMENTS 1.
Volume Control Tank Level Transmitter - Westinghouse had informed the licerisee (North Anna 1 & 2) of a 10 CFR Part 21 report involving the Volume Control Tank (VCT) level instrumentation.
If one of the two VCT level transmitters fails high, letdown flow would be diverted to the Boron Recovery System. The VCT level would continue to decrease but automatic makeup would not be initiated from the Refueling Water Storage Tank because of the failed level channel.
Both level channels are required.
This particular scenario was not one of the analyses required for plant licensing.
It was postulated as a result of a continuing study by Westinghouse involving failure modes and effects analyses involving system interactions.
These studies were in response to the issues addressed in Generic Task A-17 of the NRC Program for Resolution of Generic Issues and Recommendation 59 of NUREG-0585, TMI-2 Lessons Learned Task Force Final Report.
The inspector examined the records maintained on Safety Review Committee (SRC) Item ID 81-177.
It was determined that this item was initially identified as Potential Item (PI) 80-85 on March 27, 1980. This item was submitted to the SRC on April 9,1981.
The SRC met on May 19, 1981, and concluded that this scenario couTd lead to a loss in redundancy in the high head safety injection system and may not meet the intent of the regulations with respect to separation of protection and control systems and single failure criteria. A 10 CFR Part 21 report was submitted to the NRC on May 21, 1981, and a meeting was held on this item with NRC:NRR repre-
ORGANILATH3N: WESTINGHOUSE ELECTRIC CORPORATION, NUCLEAR TECHNOLOGY DIVISION, MONROEVILLE, PENNSYLVANIA REPORT NO.: 99900404/81-03 INSPECTION RESULTS:
PAGE 3 of 3 sentatives on May 27, 1981. At this meeting, Westinghouse presented their position that timely operator action could negate this scenario and recommended that plant procedures be reviewed to assure that the operator would be properly alerted and take appropriate action.
NRR had not responded to the Westinghouse position at the time of this inspection. A proper evaluation appears to have been performed, QA program and applicable reporting requirements followed and all affected licensees notified.
2.
Audits - Topical Report WCAP-8370 and the applicable implementing procedures were examined to determine that Westinghouse commitments had been translated into procedural requirements.
The records maintained on six internal audits and the training and qualifica-tions of seven auditors were examined to determine that procadural requirements had been followed.
It was determined that audits had been conducted in accordance with commitments and applicable pro-cedural requirements.
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