ML20041F679
| ML20041F679 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/08/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Fiedler P JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-03-07.D, TASK-3-7.D, TASK-RR LSO5-82-03-037, LSO5-82-3-37, NUDOCS 8203170292 | |
| Download: ML20041F679 (4) | |
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4 March 8,1982 Docket No. 50-219 LS05 03-037 i
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Mr. P. B. Fiedler
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Dyster Creek Nuclear Generating Station gg M 'P % >o Post Office Box 388 D
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Forked River, New Jersey 08731 d
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Dear Mr. Fiedler:
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SUBJECT:
SEP TOPIC III-7.D, CONTAINMENT STRUCTURAL INTEGRITY TEST -
OYSTER CREEK NUCLEAR GENERATING STATION Enclosed is a copy of our final evaluation of SEP Topic III-7.D. " Containment Structural Integrity Test." This evaluation was developed using the Safety Analysis Report provided by you on November 4,1981, and other information on Docket No. 50-219.
This evaluation concludes that the structural integrity test performed at Oyster Creek was satisfactory and provides assurance that the containment is
- capable of performing its intended safety function.
This evaluation will be a basic input to the integrated safety assessment of your facility unless you identify changes needed to reflect the as-built con-ditions at your facility.
This assessment may be revised in the future if your facility design is changed or if NRC criteria is changed prior to the start of the integrated safety assessment.
Sincerely,
-w Amt Dennis M. Crutchfield, Chief g,, Syc7 Operating Reactors Brech No. 5 Division of Licens*:9
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Enclosure:
As stated cc w/ enclosure:
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PDR ADOCK 05000219 FICIAL RECORD COPY usemisu-m wo Nncroni P
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3 Oyster Creek Docket N). 50-219 Rev. 2/8/82 Mr. P. B. Fiedler CC Resident Inspector G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge c/o U. S. NRC Post Office Box 445 1800 M Street, N. W.
Forked River, New Jersey 08731 Washington, D. C.
20036 Commissioner J. B. Lieberman, Esquire New Jersey Dep'artm' nt of Energy Berlack, Israels & Liebernan 101 Commerce Street 26 Broadway Newark, New Jersey 07102 New York, New York 10004 Natural Resources Defense Council Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I 917 15th Street, N. W.
Of fice of Ihspection and Enforcement Washington, D. C.
20006 631 Park Avenue King of Prussia, Pennsylvania 19406 J. Knubel BWR Licensing Manager GGPU Nuclear 100 Interplace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety.
36 West State Street - CN 112 Trenton, New Jersy 08625 Ms. Phyllis Haefner 101 Washington Street Toms River, New Jersey 08753 Mayor Lacey Township 818 Lacey Road Forked River, New Jersey 08731 U. S. Environmental Protection Agency Region II Office ATTH: Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Licensing Supervisor Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 i
ENCLOSURE 1 OYSTER CREEK NUCLEAR PLANT SEP TOPIC III-7.D ASSESSMENT OF CONTAINMENT STRUCTURAL INTEGRITY TEST I.
INTRODUCTION The structural integrity test procedure and test results for the Oyster Creek containment were evaluated in comparison to current criteria for such tests.
The purpose of the evaluation was to verify that the contain-ment structural integrity test was in compliance with the current require-ments of 10 CFR 50 thus providing assurance that the structure will perform its intended safety function.
II.
REVIEW CRITERIA
References:
A.
ASME Boiler and Pressure Vessel Code,Section III, Division I, Subsection NE, Article NE6000.
C.
NRC Standard Review Plan Section 3.8.2 D.
Oyster Creek SAR for SEP Topic III-7.D References A, B, and C outline current criteria for conducting and evaluating containment structural integrity tests.
Reference D describes the tests actually conducted at the Oyster Creek plant.
III. RELATED TOPICS AND INTERFACES SEP Topic VI-3 " Containment Pressure and Heat Removal Capability" will provida an assessment of the adequacy of the original design pressure for this containment.
The evaluation described herein is based on the original design and test pressure loading for the containment as described in reference D.
IV.
REVIEW GUIDELINES The test procedure and results were compared with current NRC criteria for such tests in order to determine if any significant deviations existed.
V.
EVALUATION The Oyster Creek Containment is a MKI (inverted " light bulb" drywell and torus suppression pool) containment.
The original design pressures were 62 psig for the drywell and 35 psig for the suppression pool.
The drywell was subjected to a test pressure of 71.3 psig (1.15 times design) and the torus was subjected to a test pressure of 40.25 psig (1.15 times design).
Current ASME Code requirements (reference B) for steel containment tests are 1.1 times design pressure which would be 68.2 psig for the drywell and38.5 psig for the suppression pool.
Thus, the test pressures are conservative by current standards.
It is not known how the test pressure was applied.
Also, the range of the gages used in the original test are not in conformance with current criteria.
These are not considered to be significant deviations.
VI.
CONCLUSIONS Based on the review of the original structural integrity test (as outlined above) in comparison with current test criteria it is considered that the test was satisfactory and thus demonstrated that the structure is capable of performing its intended safety function.
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