ML20212L091
| ML20212L091 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Diablo Canyon |
| Issue date: | 07/15/1977 |
| From: | Allison D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20150F500 | List:
|
| References | |
| FOIA-86-391 NUDOCS 8608250200 | |
| Download: ML20212L091 (6) | |
Text
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JUL 151977 DOCKET NOS. 50-275 AND 50-323 APPLICNIT: PACIFIC GAS AND ELECTRIC C01@N4Y (PG&E)
FACILITY:
DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 (DIABLO CANYON)
SUBJECT:
SUMIMRY OF ADVISORY C0lWITTEE Ott REACTOR SAFEGUARDS (ACRS)
SUBC0lWITTEE MEETING ON JUNE 21, JUNE 22 AND JUNE 23, 1977 10 DISCUSS DIABLO CANYON SEISMIC DESIG4 The ACRS Subconunittee for Diablo Canyon met with PGt.E and the NRC staff on June 21, 22 and 23,1977 in Los Angeles, California to discuss Diablo Canyon seismic design. A partial list of attendees is included in the Enclosure.
BACKGROUNO Diablo Canyon had originally been designed to withstand an earthquake l
with a horizontal gmund acceleration of 0.4g, based on the geological investigations that had been conducted in connection with the construction permit myiew. During the operating license review, which was in progress, we had requested that PG&E mevaluate the plant's seismic capabilities to determine what modifications ufght be necessary to ensure that the plant could withstand a som severe earthquake with a horizontal gmund acceleration of 0.75g, based on newer geological infomation. Although PG&E did not agree with our evaluation of the Hosgri fault's earthquake potential, PG&E was perfoming such a reanalysis.
PG&E had also expressed its intention to apply for an interim operating i
license for Diablo Canyon to allow plant operation while the seismic reevaluation was being completed. The unterial needed to justify such an interim license application had previously been outlined by the NRC staff as follows:
(1) A demonstration of the need to consider such an action, and gg, S O 8608230200 860801 I
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. JUL 151977 (2) Infomation and analyses to demonstrate that the requisite level of safety would be assumd during the period of the interim license. This infomation should include all available msults of the seismic reassessment program, supported by:
(a) a realistic assessment of the pmbability of large earthquakes in the site environs and the pmbability of the plant to withstand such earthquakes without failums of structures and equipment sufficient to i
lead to unacceptable radiological consequences to the public; 1
(b) a casesitzent to make any changes to the design datamined to be necessary on.the basis of the i
continuing seismic reassessment program; and (c) an evaluation of the practicality of making the needed changes to a plant which has been in operation during the tem of the interim license.
In Supplement 4 to the Safet;y Evaluation Report (SER), issued in May 1976 and Supplement 5 to the SER, issued in September 1976, the NRC staff had approved the principal criteria and procedures to be used in reevaluating the plaat. These criteria and pmcedures had been discussed with the ACRS in 1976 but they were still open items in the ACRS review.
Since the last meeting with the ACRS, in November 1976, PGEE had been proceeding with the reanalysis based on the principal criteria and,,
1 procedures that had been approved by the NRC staff and had been pren3 ng responses to numsmus comments and concerns regarding these criteriMhat had been raised by the ACRS and its consultants. On June 5.1977 PG&E' had submitted an extensive amendment (Amendment 50) to the Final Safety i
Analysis Report (FSAR) which documented the following:
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(1) Results of a major part of the reanalysis including the major structums, the mactor coolant system and a minimue amount of systems and equipment needed to effect a safe shutdown.
(2) The first part of a probability study to quantify seismic risks, and i
i (3) Responses to comments and concerns raised by the ACRS and its consultants.
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3-JUL 151977 NRC STAFF REVIEW STATUS The NRC staff had not yet reviewed Anendment 50 so most of the discussions consisted of PG&E pmsenting its views. The staff intended to complete its myiew of non-seismic items and publish SER supplement on thoso items about July 11 and would request ACRS full committee review in August 1977.
This schedule would support public hearings on non-seismic issues which were scheduled to begin on October 18, 1977.
The schedule for completing the remainder of the NRC staff review was uncertain. With regard to an interim operating license. PG&E's apolication and some of the necessary technical infonnation remained to be submitted.
With regard to the reanalysis to justify a full term operating license, considerable work remained to be done and submitted by PG&E before the staff myiew and audit could be completed.
DISCUSSIONS PG&E made presentations concerning geology, seismicity, probability studies, reanalysis results and msponses to the ACRS comments. Several members of the public also made statements. A full transcript of the discussions is available in the Public Document Room.
PLANT K)DIFICATIONS The reanalysis had indicated that substantial modifications to the tuttine building structure would be needed to demonstrate the building's adequacy for.75g. PGAE described the modifications which included i
adding massive concate shear walls and buttresses.
Original Signed By l
l Dennis P. Allison l
D. P. Allison, Project Manager Light Water Reactors Branch No.1 Division of Project Management Enclosum:
Partial Attendance List i
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Pacific Gas & Electric Company.
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ces: Pacific Gas & Electric Company N. M. Newmark ATTN: Mr. John C. Morrissey Consulting Engineering Services Vice President & General 1211 Civil Engineering Building Counsel University of Illinois 77 Beale Street Urbana, Illinois 61801 San Francisco, California 94106 Mr. John Forster Philip A. Crane, Jr., Esq.
985 Palm Street Pacific Gas & Electric Company San Luis Obispo, California 93401 77 Beale Street San Francisco, California 94106 Mr. William P. Cornwell P. O. Box 453 Andrew J. Skaff, Esq.
Morro Bay, California 93442.
California Public Utilities Cosedssion Mr. James 0. Schuyler 350 McAllister Street Nuclear Project Engineer San Francisco, California 94102 Pacific Sas & Electric Company 77 Beale Street Mr. Frederick Eissler, President San Francisco, California 94106 EiiiilWiiiilll Scenic Shomline Preservation s
Conference, Inc.
Mrs. Thelma Hirdler 4623 More Mesa Drive 811 Fair Oaks Avenue Santa Barbara, California 93105 Arroyo Grande. California 94420 Ms. Sandra A. Silver Mr. W. C. Gangloff Mr. Gonion A. Silver Westinghouse Electric Corporation 5055 Radford Avenue P. O. Box 355 North Hollywood, California 91607 Pittsburgh, Pennsylvania 15230 Paul C. Valentine Esq.
Yale I. Jones Esq.
400 Channing Avenue 100 Van Ness Avenue Palto Alto, California 94301 19th Floor San Francisco, California 94102 Neil Goldberg, Esq.
Wilmer, Cutler & Pickering David F. Fleischaker. Esq.
1666 K Street, N. W.
102515th Street, N. W.
Washington, D. C.
20006 Washington, D. C.
20005 Ms. Elizabeth E. Apfelber9 1415 Cazadero San Luis Obispo, California 93401 GF FSC E &
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c ENCLOSURE 3
PARTIAL LIST OF ATTENDEES
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ACRS SUBC099GTTEE EETING ON DIABLO CANYON.
JUNE 21, 22123,1977 ACRS Subcosarittee Members NRC Staff Consultants D. Okmnt - Subcouarittee Chairman M. Neuumrk C. Siess W. Hall J. Ebersole A. Ang S. Lawrowski (June 21)
P. Showson (June 21 & 22)
M. Plessett (June 22 & 23)
PG&E J. Hoch ACRS Staff J. Schuyler M. Furbush
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J. McKinley R. Bettinger dn
V. Ghio F. Mouty P., Devin.
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p ACRS Consultants Crane T. Pickel G. Lenfesty G. Thompson H. Gormly, et al M. White M. Trifunac J. Luco U. S. Geological Survey B. Page J. Devine (June 23) )
J. Wilson S. Brockman (June 23 F. McKeown (June 23)
HRC Staff D. Allison Public J. Stolz J. Knight Several members of the public D. Jeng were present, including the R. Hofunnn following who made statements:
E. Sullivan P. T. Kuo J. Anderson G. Bagchi R. Curry T. Young J. Brune P. Johnson R. Hubbard R. Goddard J. C. Stepp (June 22 & 23) orrics >
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PGAE Consultants J. Blume H. Seed A. Cornell D. Ray L. Edgar A. Gehr B. Norton, et al Westinghouse W. Gangloff T. Esselman G. Fidler, et al MiliEE l
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