ML20030C768
| ML20030C768 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/20/1981 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8108280118 | |
| Download: ML20030C768 (3) | |
Text
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-Dunu-PoWEH COMPANY PowEn Unismixo 42e SouTri Csicucu STREET, CIIAHIDTTE, N. C. 20242
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t W I L LI AM G. PA R M E R, J R.
V,cr Parsierwr TELCPMONE: Anta 704 S'""""
August 20, 1981 f'(y[r*k'fsh((g</
Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission y
6 6;J.,1 b' f Region II
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101 Marietta Street, Suite 3100
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Atlanta, Georgia 30303 9
AUG 2 71981
- Re: Catawba Nuclear Station E u.L g b 7 '
Units 1 & 2
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Docket Nos. 50-413 & -414
Dear Mr. O'Reilly:
Pursuant to 10 CFR 50.55e, please find attached Significant Deficiency Report IE-79/05-SDD-413/414 (Fins' Deport).
Very truly yours, M/
t.
Willin 0. Parker, Jr.
ROS/php Attachment i
l cc: Director Resident Inspector Office of Inspection and Enforcement Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Catawb6 Nuclear Station Washington, D. C. 20555 l
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8108280118 810820 t
PDR ADOCK 05000413 L
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j REPORT NUMBER:
!E-79/05-SDD-413/414 (Final)
REPURT DATE: July 30, 1981 FACILITY:
Catawba Nuclear Station Units 1 & 2 t
IDENTIFICATION OF DEFICIENCY:
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Steam Generator (Main Steam) Power Operated Relief Valves-Doghouse Environmental Qualification INITIAL REPORT:
See original Report No. IE-79/05-SDD-413/414 dated December 26, 1979 SUPPLIER AND/OR COMPONENT:
The Steam Generator Power Operated ReIIef Valves (Duke Tag Numbers 1 & 2 SV 1, 7,13, and 19) are active, air cylinder operated, ASME Section ill Class 2 relief control valves manufactured by Control Components, international of Irvine, California.
l DESCRIPTION OF DEFICIENCY:
f The Steam Generator Power Operated Relief Valves were not designed to fall j
close during the postulated feedwater or main steam. line break accider.t j
environment.
ANALYSIS OF SAFETY IMPLICATIONS:
Worst case safety consequence consists of a secondary line break in the doghouse creating an accident environment which causes the Steam Generator Power Operated Relief Valves to fail in the open position.
This would cause both steam generators associated with the main steam lines in the affected doghouse to depressurize.
Each Steam Generator Power Operated Relief Valve is backed up by an active, ASME Section 111 Class 2, electric motor operated isolation valve qualified for the doghouse accident environment.
CORRECTIVE ACTION:
i The Steam Generator Power Operated Relief Valves have been r(designed to fall close in the doghouse accident environment. The following materials in the air cylinder were replaced to correct this deficiency:
1.
The black analgum cylinder material was replaced with SA 312 Type 304 j
stainless steel material.
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Page 2 of 2 REPORT NUMBER:
IE-79/05-SDD-413/414 (Final)
REPORT DATE:
July 30, 1981 2.
All of the static and dynamic seals in the air cylinder were changed from Buna-N material to fluorocarbon compound, V747-75 (Trade name: Viton-A) material.
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