ML20140C981
| ML20140C981 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 08/17/1984 |
| From: | Houston R Office of Nuclear Reactor Regulation |
| To: | Lainas G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20140C940 | List:
|
| References | |
| FOIA-85-136 TAC-55439, NUDOCS 8408270556 | |
| Download: ML20140C981 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION e
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WASHWGTON, D. C. 20555 g
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August 17, 1984 t
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MEMORANDUM FOR:
G. Lainas, Assistant Director
~l for Operating Reactors Division of Licensing FROM:
R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration
SUBJECT:
OR ACTION:
REQUEST FOR EXEMPTION FROM APPENDIX J; ZION GENERATING STATION, UNIT 1,-
Plant Name:
Zion Generating Station, Unit 1 Docket No.:
50-295 Responsible Branch:
ORB #1 Project Manager: Jan Norris Review Branch:.CSB: DSI Review Status:
Complete In response to Technical Assistance Recuest TACS 55439, the Containment Systems Branch (CSB) has reviewed the licensee's submittals of July 19, 1984, for Zion Generating _ Station, Unit 1.
In the above cited submittals, the licensee requested an exemption from Paragraph III.A.3(b) of Appendix J, which specifies that the verification test result shall be within 25%
of the Type A test result. The basis for the request for exemption is that although the acceptance criterion was not met during the 1983 Type A test, the test could still be found acceptable on some other technical basis. However, based on our review, we find that the requested exemption from the verification test acceptance criterion should not be granted.
Moreover, based on a review of the licensee's submittals and certain l
additional information provided by the licensee, we have identified several additional concerns regarding the acceptability of the 1983 l
Type A test for Zion, Unit 1.
These additional concerns are:
1.
The verification test was not conducted in the manner prescribed by Appendix J.
A_ppendix J requires that a.
verification test be performed following an acceptable Tvoe_A i
test. The purpose of the verification test is to verify the functional capability of the instrumentation system and the stability of the test conditions.
For the 1983 Type A test, the verification test was performed before an acceptable Type A test result was obtained; also, the ultimately succes f 1 Type A test was of short duration.
Both of the abo
@ ci N factors tend to increase the level of uncertainty in the final calculated containment leak e.
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G. Lainas.
2.
Based on the infotmation provided by.Jhe licensee,iit appears that the containment t'st condition's were n'ot g abilized, except,
e over the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; i.e., the tim,e over which an acceptable Type A test result was obtained.' Since the f
calculated containment leakage rate was continually changing during the early part of the test, it is not appropriate to
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base the success of the verification test on the early test results. Therefore, we have a concern as to whether the 1983 verification test met the acceptance criteria, and whether the verification test was conducted in a valid manner.
3.
The 1983 Type A test was a short duration test (about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />); the only approved methodology for conducting short duration tests and analyzing the associated test data is contained in BECHTEL Topical Report BN-TOP-1.
In applying this methodology to the 1983 test data, the staff calculated a higher leak rate relative to that obtained by the licensee's methodology.
Therefore, we are unable to accept the
' lower leak rate calculated by the licensee, which used a comonly accepted method in the industry for longer duration tests.
Based on the above discussion, we conclude that the request for exemption from the requireinents 'of Appen' dix J sh'ould be denied, and that the 1983 Zion Type A test was not an acceptable test in terms of demonstrating the containment leakage rate to be within the prescribed limits.
A brief SALP is also enclosed. This completes our review as called for in TACS 55439.
J R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration
Enclosure:
As stated cc:
R. Bernero D. Eisenhut S. Varga J. Norris R. Capra CONTACT:
Y. S. Huang, CSB: DSI g
x29493
i EtlCLOSURE i
SALP prepared by the Containment Systems Branch Evaluation 210N GENERATING STATION, UNIT l' Criteria Ca tego ry Narra tive Description
! anagement Invol Emeidl' M
s N/A
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'Appraacno kesoTiIlon of Technical Issues 2
The licensee's proposed resolution to the subject issue is found to be l
unacceptable.
Responsivenes.s i
Enforcement Ilistory e
, Reportable Events N/A l
Ttaffing N/A Training N/A
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s 98 400
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