ML20054J200
| ML20054J200 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/11/1982 |
| From: | Martin T Public Service Enterprise Group |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8206280281 | |
| Download: ML20054J200 (3) | |
Text
kJ Thomas J. Martin Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/4306316 Vice Presdent Ergineering ard Construction June 11, 1982 Mr. Ronald C. Haynes
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U.S.
Nuclear Regulatory Commission Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Haynes:
AUXILIARY BUILDING SEISMIC ANALYSIS POTENTIAL 10CFR50.55(e)
SIGNIFICANT DEFICIENCY HOPE CREEK GENERATING STATION We reference our letter to your office dated November 25, 1981 concerning a potential significant deficiency at Hope Creek Generating Station.
That letter provided an interim report concerning the effect of recent seismic re-analysis data upon the seismic qualification of certain equipment within the Auxiliary Building.
This letter serves as our final report on the subject.
Due to changes in general arrangement (a floor added to part of the Auxiliary Building), the Auxiliary Building was re-analyzed for seismic effects by EDS Nuclear, Inc. (EDS).
The results of the re-analysis, which was completed in October, 1981, indicated inconsistencies when compared to the results of the original analysis performed by EDS in 1975.
It appears that these inconsistencies were caused by the different methodologies used for the two analyses.
In the original (1975) seismic model for the Auxiliary Build-ing, EDS used input data from an uncoupled analysis of the Reactor Building basemat motion.
In the revised seismic model, EDS has usad a coupled analysis where the soil and structure have baen combined in one detailed model (incor-porating the revision to the general arrangement) speci-fically for the Auxiliary Building.
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8206280281 820611 PDR ADOCK 05000354 fg i
U PDR
s R. C. Haynes 6/11/82 In order to assess the impact of the inconsistencies in the design, the following evaluations were performed:
- Evaluated the effects of the revised results on the Auxiliary Building structures, mechanical and elec-trical components, and equipment, already designed.
- Recommended modifications, if necessary.
- Evaluated if similar inconsistencies could be present in the analysis of other Category I structures.
It should be noted that due to changes in the general ar-rangement, all affected structures, equipment, and compo-nents would have been re-analyzed for the new loadings.
The results of these evaluations based on the revised load-ings are as follows:
- The Auxiliary Building structures were found to be within the allowables specified in the design criteria.
- The cable trays and conduit supports were found to meet the design criteria when analyzed using conser-vative realistic 20% damping values based on testing.
- The HVAC ducts and duct supports were found to meet the design criteria.
- The pipes and pipe supports, evaluated based on a representative sampling, were found to meet the design criteria.
- It was not possible to evaluate representative samples of all equipment.
However, a large sample of different types of equipment was evaluated (approxi-mately 85% of equipment qualified / accepted to date) and found to meet the design critiera.
The original seismic analysis of the other Category I build-ings/ structures at Hope Creek Generating Station was re-viewed and found to be acceptable.
Therefore, based on the foregoing evaluation of the Aux-iliary Building structural components, representative piping systems, and available equipment data, there is a reasonable
R. C. Haynes 6/11/82 confidence level that the results of the original seismic analysis would not have adversely affected the safe opera-ti;n of the plant, had they gone ndetected.
Other Category I structures are not affected.
Furthermore, the revised seismic response spectra curves shall be used for all equip-ment previously qualified, presently being qualified, or yet to be procured.
Please advise if you require any additional information in this matter.
Very truly yours, f
CC:
Office of Inspection and Enforcement Division of Reactor Construction - Inspection Washington, D.C.
NRC Resident Inspector - Hope Creek P.O. Box 241 Hancocks Bridge, New Jersey 08038 B013 1-3
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