ML20207D800
ML20207D800 | |
Person / Time | |
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Issue date: | 07/15/1987 |
From: | Serkiz A NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
To: | Speis T NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
Shared Package | |
ML20195F793 | List: |
References | |
FOIA-87-652 NUDOCS 8808160088 | |
Download: ML20207D800 (4) | |
Text
i JUL iS DSI
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MEMORANDUM FOR: Therri s P. Speis, Deputy Director for Generic and Regulatory Issues C ice of Nuclear Regulatory Research FROM: M e:A W. Serkiz, Senior Task Manager Fea:to. and Plant Safety Issues Branch Di.ision of Rentu and Plant Systems, RES
SUBJECT:
SJ W ARY OF MEETING WITH NUCLEAR UTILITY GROUP 0% STATION BLACK 0UT (NUGSBO) ON USI A-44 Meeting Date: J.' 9, 1987 Location: 7920- Norfolk Avenue Betnesda, Maryland Purpose of Meeting: The purpose of this meeting was to continue discussions of guidelines and procedures dealing with NUMARC Initiative 2 previously discussed with NUGSB0 at the April 29, 1987 meeting. This was the 9th meeting held with the NUGSB0 group since the first meeting in July 1986.
Attendees: See attached attendee list
References:
(1) Letter to NRC Chairman Palladino from J. H. Miller, NUMARC, June 17, 1986.
(2) "Assuring the Adequacy of Station Blackout Response Procedures, Guidelines and Technical Bases," Rev. 0.0, April 24, 1987 (prepared by NUGSBO).
The principal topic discussed at this meeting was the station blackout coping analysis guidelines being developed by NUGSB0 for assuring that a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> coping capability would exists for all plants. However, NUGSB0 indicated that NUMARC has not endorsed a coping assessment as part of the industry initiatives, but they are considering doing so. NUMARC is reviewing these recently proposed guidelines and, upon approval from NUMARC, NUGSB0 will provide the NRC staff with a draft for review and comment. An estimated availability date of late July 1987 was set forth at this meeting.
The NUGSB0 attendees provided the staff with an overview of the coping analysis approach, calculational methodology, assumptions and views on incorporating the results of a coping analysis into plant operating procedures (i.e. , E0Ps). The coping guidelines provide a list of initial assumptions and a simplified procedure for as ,uring that sufficient cooling water, de battery capacity, and 8808160000 000711 PDR FOlA FDR .
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cors-essed air are available. Also, guidance to cope with the loss of )
ver.t lation is provided, but plant specific tests or calculations are not '
I ren. red to assure that equipment temperature limits are not exceeded. The staff questioned the lack of any plant-specific verification, and it was i agreed that this item would be discussed f uather. NUGSBC indicated that their prc;; sed coping procedure would provide a consistent assessment method and spec'fic step-by-step procedures to do the assessment that the draft ANS stancard 58.12 does not include.
NUGSEO reevaluated the coping categories foe the various plants using the stafs revised matrix that was adjusted to consider new hazard data and the ef fects of salt spray on expected loss of of f site power at coastal sites.
i NUG55 indicated that use of the new matr x resulted in a significant increase in the number of plants in the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> coping group. The staff, however, expected that use of the new matrix would result in only a few plants moving f rce the 4 to the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> category, and incicated that NUGSB0 might be misusing the revised hazard data. It was agreed that the staff and NUGSB0 would discuss this item separately to resolve the differences.
NUGSS3 staff also discussed revisions that have been made to Reference (2),
particularly changes in the definition of independent AC sources and incorporation of guidelines dealing with severe weather conditions (i.e.,
hurricane effects). NUGSB0 plans to provide the staf f with an updated copy of Reference 2 within the next several weeks.
The outcome of this meeting was agreement to continue such meetings with the understanding that draft copies of the technical aspects to be discussed should be provided in advance of such meetings, if possible.
SRisinalsiga,.,j; Aleck W. Serkiz, Senior Task Manager Reactor and Plant Safety Issues Branch Division of Reactor and Plant Systems, RES OFC :DRPS:RPSIB :DRPS:RHFB :DRP :RPSIB :DRPS:RPSIB :DRPS:DD : :
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NAME : ASer iz:jf :ARubin G M :PN n :KKniel :WMi rs : .
DATE :07/t4/87 :07/lf/87 :07//[/87 07//6/87 -
/ /87 : -
0FFICIAL RECORD COPY
n
, e Attendees 7-9-87 NUGSB0 Mto Name Affiliation Phone Al Serkiz RES/0RPS/RPSIB 301/492-7487 Paul Gill NRC/NRR/SELB 301/492-9474
- James E. Knight NRC/NRR/SELB 301/492-7456 Faust Rosa NRC/NRR/SELB 301/492-9466 Alan Rubin NRC/RES 301/492-8303 Karl Kniel RES/0RPS/RPSIB 301/492-4705 Stephen Maloney Devonrue - NUGSB0 Consultant 617/426-4550 Boro Malinovic Devonrue 617/426-4550 Mike Childers Northeast Utilities /NUGSB0 203/665-3472 Steve Floyd Carolina Power & Light /NUGSB3 919/836-6901 Mike McGarry BCP&R 202/857-9833 Pat Baranowsky NRC/NRR/EAB 301/492-8352 Warren Minners NRC/RES/0RPS 301/492-2787 Steve Crockett NRC/0GC 202/634-1465 Paul Norian RES/0RPS/RPSIB 301/492-7112 Jerry Jackson NRC/RES 301/492-8544
Ag '
,. . a :,yy DISTRIBUTION:
RES Circ RES Chron RPSIB R/F DRPS C/F BSheron WMinners ARubin ASerkiz MChilders, NU/NUGSB0 SMaloney, Devonrue HMcGarry, BCP&R NRC Participants POR O