ML20030C817
| ML20030C817 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 08/18/1981 |
| From: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| To: | Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, QA-1472, NUDOCS 8108280197 | |
| Download: ML20030C817 (2) | |
Text
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TIIE CINCINNATI GAS & ELECTRIC COMPANY egg CINCINN ATi, OHIO 45201 August 18, 1981 c.4.sonow4uu sc ~,o. v,c c
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U.S. Nuclear Regulatory Commission
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Region III
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799 Roosevelt Road AUG 2 71981 *,L -
Glen Ellyn, Illinois 60137
""&lsy 1,1 Attention:
Mr.
R.
C.
Knop, Acting Chief Reactor Construction and 4
p Engineering Support Branch g
RE:
WM.
H.
ZIMMER NUCLEAR POWER STATION UNIT 1 10CFR50.55(e) E-14, GENERAL ELECTRIC CO. SUPPLIED IN-CORE POWER RANGE SENSOR - ELECTRICAL PLUG CONNECTOR, CONSTRUCTION PERMIT CPPR88, DOCKET NO.
50-358, W.O.
- 57300-957, JOB E-5590 Gentlemen:
On April 6, 1981, the NRC Site Senior Resident Inspector was notified by phone of a possible 10CFR50.55(e) condition regarding environmental discrepancies between the Wm.
H.
Zimmer Nuclear Power Station FSAR, Para. 7.6.1.9.5.2 and the General Electric Company Standard Catalog information for the LPRM In-Core Power Range Sensor Electrical Connector, Cat. No. X901-200.
Subsequently, formal notification was transmitted by CG&E letter QA-1423 dated May 6, 1981.
Environmental tests performed by the General Electric Company on the LPRM Connectors indicate that they will perform satisfactorily during and af ter exposure to 390oF for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> followed by 3250F for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
Paragraph 7.6.1.9.5.2 of the Wm.
H.
Zimmer Station - Unit 1 FSAR will be rovised to reflect the new design criteria from General Electric Company.
This revision is expected to be complete by August 31, 1981.
Based on this information, the connectors in use are capable of withstanding those conditions expected in the con-tainment area and will not advursely affect the safe operation of the plant.
Therefore, this item is considered not to be reportable under 10CFR50.55(e).
s 4 8108280197 810918 N
PDR ADOCK 05000358 Mb'31 S
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i Mr. Dick Knop U.S. Nuclear Regulatory Commission Region III August 18, 1981 QA-1472 Page #2
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We trust that the above will be found acceptable i
as a final report under the requirements of 10CFR50.55(e).
Yours very truly, f h ayd =^ -
E. A. Borgmann i
EAB:mjl cc:
NRC Resident Inspector Attn:
F. T. Daniels NRC Office of Inspection and Enforcement Washington, D.C.
20555 1
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