ML19260A490
| ML19260A490 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/13/1979 |
| From: | Olshan L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911210340 | |
| Download: ML19260A490 (5) | |
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'o UNITED STATES NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555 a
NOVEMBER 1 3 1979 Docket Nos. 50-295 and 50-304 LICENSEE:
COMMONWEALTH EDISON COMPANY FACILITY:
ZION STATION, UNITS 1 AND 2
SUBJECT:
SUMMARY
OF NOVEMBER 8,1979 PHONE CONVERSATION REGARDING LESSONS LEARNED IMPLEMENTATION During a phone conversation on Novenber 8,1979 the NRC Lessons Learned Implementation Team discussed with the licensee, its October 18, 1979 response to our September 13, 1979 letter.
The team informed the licensee of those lessons learned items for which the licensee's proposed schedule for implementation is unacceptable.
These items, along with the proposed and required completion dates, are listed in Attachment 1.
The team informed the licensee of those items for which the proposed action does not appear to comply with the lessons learned requirement.
These items and their associated deficiencies are listed in Attachment 2.
The team also informed the licensee of those items for which further clarification of the licensee's commitment is necessary to demonstrate compliance with the lessons learned requirements.
These items and the associated team questions are listed in Attachment 3.
By letter dated October 30, 1979 we provided additional clarification of the lessons learned requirements to all licensees. We also requested that within 15 days licensee's justify proposed actions not in complete agreement with the staff's requirements and improve the implementation schedule where it differed from the staff's requirements.
During this phone conversation we informed the licensee that those items listed in Attachments 1 and 2 should be addressed in their response.
In addition, the licensee agreed to provide the information requested in Attachment 3 in its response to our October 30, 1979 letter or as soon thereafter as possible, gf 0[4 L. N. Olshan, Project Manager Operating Reactors Branch #1 Division of Operating Reactors Attachments:
As Stated 1380 1
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cc: w/ attachments See next page i 911210 M O
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i Meeting Summary for NOVEMBER 1 19N Zion 1 and 2 Docket Files NRC POR Robert J. Vollen, Esquire Local POR 109 North Dearborn Street ORBI Reading Chicago, Illinois 60602 NRR Reading H. Denton Dr. Cecil Lue-Hing E. Case Director of Research and Development D. Eisenhut Metropolitan Sanitary District R. Tedesco of Greater Chicago G. Zech 100 East Erie Street B. Grimes Chicago, Illinois 60611 W. Gammill L. Shao Zion-Benton Public Library District J. Miller 2600 Emmaus Avenue R. Vollmer Zion, Illinois 60099 T. J. Carter A. Schwencer Mr. Phillip P. Steptoe D. Ziemann Isham, Lincoln and Beale P. Check Counselors at Law G. Lainas One First National Plaza D. Crutchfield 42nd Floor B. Grimes Chicago, Illinois 60603 T. Ippolito R. Reid Susan N. Sekuler, Esquire V. Noonan Assistant Attorney General
.G. Knighton Environmental Control Division D. Brinkman 188 West Randolph Street, Suite 2315 Project Manager Chicago, Illinois 60601 OELD OI&E (3)
C. Parrish/P. Kreutzer ACRS (16)
NRC Participants NSIC M TERA Licensee Short Service List 1380 I56 e
k ATTACHMENT 1 ITEMS THAT DO NOT MEET LESSONS LEARNED IMPLEMENTATIOu SCHE _DULE NONE 1380 157
i ATTACHMENT 2 PROPOSED ACTIONS DO NOT APPEAR TO COMPLY WITH LESSONS LEARNED REQUIREMENTS e
NONE 1380 158
ATTACHMENT 3 CLARIFICATION OF PROPOSED ACTIONS ARE NEEDED IN ORDER TO VERIFY CONFORMANCE TO LESSONS LEARNED REQUIREMENTS l.
Section 2.1.3.b Instrumentation for Detection of Inadequate Gas __ Cooling The additional information on the subcooling meter requested in the October 30, 1979 Harold R. Denton letter to all operating nuclear power plants should be addressed.
2.
Section 2.1.6.a Systems Integrity Your rescanse should address providing a program summary report, submitting leak rate data, and establishment of a test program.
3.
Section 2.1.6.b Shielding Review Your submittal should address vital areas and dose criteria.
4.
Sec tion .1.8.a Post-Accident Sampling Your response should address measurement of hydrogen in the containment atmosphere and dissolved gases in the primary coolant.
5.
Section 2.2.1.b Shift Technical Advisor Additional clarification of how the operating experience assessment function will be accomplished and how this knowledge is assimilated by the Shift Technical Advisors should be addressed.
6.
Section 2.2.2.b Onsite Technical Support Center It is noted that you intend to provide a permanent onsite technical support center adhering to Atomic Industrial Forum position requirements.
You should describe and justify differences between the AIF requirements and the requirements of NUREG-0578 and the Harold R. Denton October 30, 1979 letter to all operating nuclear power plants.
1380 l59 4