ML20081F112
| ML20081F112 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 10/25/1983 |
| From: | Williams J CINCINNATI GAS & ELECTRIC CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, LOZ-83-0193, LOZ-83-193, M-91, NUDOCS 8311020352 | |
| Download: ML20081F112 (3) | |
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TIIE CINCINNATI GAS & ELECTitIC COMPANY M
. CINCINNATI. OHIO 45201 October 25, 1983 LOZ-83-0193 J. WILlJ AMS, JR -
)
ermion vice pan.ocar nuctw, oesamous Docket No. 50-358 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attention:
Mr. J.G. Keppler Regional Administrator Gentlemen:
j RE:
WM. H. ZIMMER NUCLEAR POWER STATION - UNIT 1 10CFR50.55 (e), ITEM M-91, OVERPRESSURIZATION OF HIGH PRESSURE CORE SPRAY (HPCS) RELIEF VALVE lE22F035 W.O. 57300, JOB E-5590, FILE NO. 956C, M-91 l
This letter constitutes an interim report concerning the subject condition initially reported to the commission on August 18, 1983.
CG&E has determined that this condition is a reportable deficiency under 50.55 (e).
i The condition identified a design deficiency in the piping system such that the. discharge outlet'of relief valve lE22-F035 could be' exposed-to' pressure in excess of the vendor pressure limit of,230-_ psi.- An engineering evaluation of this condition j'
has been completed and is as follows:
Based on the. assumption that the HPCS pump motor is sprayed following a postulated failure of'the relief valve discharge outlet during plant operations, and a subsequent inoperability of the HPCS' pump motor due to its proximity to the relief valve, the HPCS system is therefore assumed to be not available. -Then, assuming the worst case single failure (from an ECCS availability standpoint) of a~1oss of emergency diesel generator A or B, the ECCS availability' requirements were reviewed for various line breaks.
For small line breaks and large line breaks (other than DBA), the requirements laid out on pages 6.3-12 and 13 of the i.
FSAR can be met.
However, for a large line break (DBA) the requirements cannot be met if diesel generator A fails because i
three LPCI loops will not be operable.
Therefore, this item is considered to be reportable.
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8311020352 831025 un PDR ADDCK 05000358
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L Mr. J.G.
Keppler Regional Administrator i
October 25, 1983 LOZ-83-0193' Page 2
't When the design deficiency was detected in 1981, an Engineering Change Request (ECR) 1195 was initiated to reroute the relief valve discharge piping path to the Suppression Pool rather than to the High Pressure Core Spray (HPCS) pump discharge line, to preclude the overpressure condition.
Construction work 4
to ECR-1195 was completed in September 1982.
ECR-1195 was reviewed by CG&E auditors during Audit 83-19 of Sargent & Lundy in July 1983, and was then identified as the subject of this report.
CG&E NR C-QAD-83-1862-E has been initiated to identify that relief valve lE22-F035 underwent an overpressure condition (1200 PSI) during an HPCS' system test in 1979.
Audit Finding Report (AFR) 83-19-05 has been initiated to identify.and resolve Sargent
& Lundy's programmatic deficiencies and Corrective Action Request (CAR) 83-83 was issued to resolve CG&E's programmatic deficiencies with regard to this matter.
CG&E has resolved the deficiencies identified in CAR 83-83 and the CAR is now closed.
A follow-up report detailing the corrective actions taken with respect to NR C-QAD-83-1862-E and AFR 83-19-05 along with our actions taken to prevent its recurrence will be submitted by
(
May 18, 1984.
We trust the above will be found acceptable as an interim i
report under 10CFR50.55(e).
Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY By M
ILLIAMS, J SENIOR VICE P SIDENT BLT/sfr
em -.
4 Mr. J.G. Keppler Regional Administrator October 25, 1983 LOZ-83-0193 Page 3 cc:
NRC Office of Inspection & Enforcement Washington, D.C.
20555 NRC Resident Site Supervisor ATTN:
W.M. Hill NRC Zimmer Project Inspector, Region III ATTN:
E. R. Schweibinz i
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