ML19345G502
| ML19345G502 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/01/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | James Keppler, Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, SLNRC-81-22, NUDOCS 8104070396 | |
| Download: ML19345G502 (2) | |
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SNUPPS Stenderdized Nuclear Unst Power Plant System Nicholes A. Petrick s choke cherry Reed Reekedk. Marviend 20050 Executive Director (301) assecto April 1, 1981 SLNRC 81-22 FILE: 0491.10.2 SUBJ:
Interim Reports on 10CFR 50.55(e) Matters Mr. James G. Keppler Director, Region III Office of Inspection and Enforcement f~(fijf]n U. S. Nuclear Regulatory Comission w
799 Roosevelt Road
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Glen Ellyn, Illinois 60137 g;
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Mr. Karl Seyfrit virector, Region IV
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U. S. Nuclear Regulatory Comission
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Suite 1U0U, Parkway Central Plaza
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Arlington, Texas 76012
References:
1.
SLNRC 80-45, dated September 15, 1980: Centrifugal Charging Pump Operation Following Secondary Side High Energy Line Rupture 2.
SLNRC 80-64, dated November 26, 1980: Failure of l
Containment Isolation Valves Gentlemen:
l Reference 1 provided information on a potential deficiency involving centrifugal charging pump operation following a secondary side line rupture.
It was estimated that design changes to correct the situa-tion would be completed by the first quarter of 1981. However, the changes are still being evaluated by Bechtel Power Corporation, West-ingnouse and the SNUPPS Utilities. When the evaluations are complete, a final report will be submitted.
It is anticipated that this will occur in late sumer of this year.
Reference 2 reported a potential deficiency involving the failure to close of valves that are identical to containment iso'ation valves planead for use at the SNUPPS plants. Reference 2 alsc, st-ted that a final or follow-up report would be submitted during the first quarter d
[g g/d of 1981. The valves in question were tnree-inch gate valves manufac-tured by Westingnouse Electro-Mechanical Divisior. (EMD). In addition 3
sing o,tfo gagves specifically mentioned (location nos. 810s and 810 t
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9 SLNRC 81-22 Page Two has been determined that valve location numbers 8000A and B are active, safety-related valves of this type. Westinghouse has informed SNL'PPS that four-inch EMD valves (models 4GM87 and 4GM88) also fail to close against equipment specification differential pressure requirements.
In the SNUPPS design such valves are planned for use at valve location numbers 8801 A/B, 8802 A/B, 8803 A/B, 8821 A/B and 8835. Larger West-inghouse EM0 valves (10 and 12 inch) are under review for similar problems.
Modifications considered for the three-inch valves include changing the operator gear ratio, changing the operator control and changing the oper-ator type.. Modifications for the four-inch valves are under evaluation.
A schedule for complete resolution of this matter has not been established.
However, SNUPPS will continue to keep the NRC informed and will, at mini-mum, provide an additional report on this matter in September 1981.
Very truly yours, p.
\\ CNT\\C Nicholas A. Petrick RLS/srz cc:
G. L. Koester KGE D. T. McPhee KCPL J. K. Bryan UE W. Hansen NRC/Callaway T. Vandel NRC/ Wolf Creek
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Victor Stello, Jr.
Director, Office of I & E, USNRC, Washington, D. C./
J. Konklin NRC, Region III
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