ML20055A334
| ML20055A334 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/14/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TASK-***, TASK-RR LSO5-82-07-030, LSO5-82-7-30, NUDOCS 8207160170 | |
| Download: ML20055A334 (4) | |
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July 14,1982 Docket tio. 50-219 LS05 07-030 Mr. P. B. Fiedler Vice President and Director - Oyster Creek Oyster Creek tiuclear Generating Station Post Office Box 388 Forked River, flew Jersey 08731
Dear Mr. Fiedler:
SUBJECT:
AGEtiDA FOR SEP TOPIC ttEETItiGS TO BE HELD DURING JULY 1982; PROPOSED PROCEDURE FOR FORMALIZIt4G TOPIC RESOLUTI0tt The purpose of this letter is two-fold.
First, it presents a proposed procedure for fomalizing topic resolutions.
Second, it presents the sug-gested agenda of topics to be discussed during the July SEP topic neetings.
The SEP topic meetings planned during July 1982 are aimed at the resolution of identified differences.
You will be expected to formally respond to all of the identified differences.
In addition, where it appears that added licensee information and/or a proposed course of action are sufficient to support a topic resolution, these actions should also be formally submitted to the f4RC.
Included in your submittal should be copies of procedures and drawings used to support the topic resolution. This submittal should be made within 30 days after the topic discussion meeting.
The enclosed topic agendas are presented in support of our July 13, 1982, and July 20 - 21, 1982 meetings to discuss the differences identified in the topic reviews, as corrected in the enclosures. Please note that the proce-dures formalizing topic resolution will be discussed during the July 13, 1982 meeting.
Sincerely,
jdd:
OSiginal 31 "ed by 7
bN' g g' Dennis M. Crutchfield, Chief g ggg gy p
Operating Reactors Branch tio. 5 r
Division of Licensing
Enclosure:
As stated cc w/ enclosure:
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' Mr. P. B. Fiedler Revised 3/30/82 7
cc G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U. S. NRC 1800 M Street', N. W.
Post Office Box 445 Washington, D. C.
20036 Forked River, New Jersey 08731 J. B. Lieberman, Esquire Commiss'ioner Berlack, Israels & Lieberman New Jersey Department of' Energy 26 Broadway 101 Commerce Street New York, New-York 10004 Newark, New Jersey 07102 Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsyl.vania 19406 J.. Knubel BWR Licensing Manager GPU 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 Jersey 08625
' Mayor Lacey Township 818 Lacey Road Farked 3iver, New Jersey 08731 U. S. Environmental Protection Agency Region II Office ATTN:
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 3
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AGENDA FOR OULY 13, 1982 MEETING AT hRC BETHESDA, MARYLAND TOPIC TITLE III-1 QUALITY GROUP CLASSIFICATIONS OF COMPONENTS AND SYSTEMS III-5.A EFFECTS OF PIPE BREAK ON STRUCTURES, SYSTEMS AND COMPONENTS INSIDE CONTAINMENT 111-5.8 EFFECTS OF PIPE BREAK OUTSIDE CONTAINMENT III-6 SEISMIC DESIGN CONSIDERATIONS III-7.B DESIGN CODES, DESIGN CRITERIA AND LOADING CONDITIONS O
DISCUSS THE PROCEDURE TO FORMALIZE RESOLUTION OF SEP TOPICS.
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i AGENDA FOR JULY 20 - 21, 1982 MEETING
^
GPU PARSIPPANY, NEW JERSEY July 20,1982 7
TOPIC TITLE II-3.A FLOODING P0TENTIAL AND PROTECTION REQUIREMENTS II-3.C CAPABILITY OF OPIRATING PLANTS TO COPE WITH DESIGN BASIS FLOODING CONDITIONS II-3.C SAFETY-RELATED WATER SUPPLY (ULTIMATE HEAT SINK)
III-2 WIND AND TORNADO LOADINGS III-3.A EFFECTS IF HIGH WATER ON STRUCTURES III-3.C INSERVICE INSPECTION OF WATER CONTROL STRUCTURES III-4.A TORNADO MISSILES III-4.B TURBINE MISSILES 111-4.D SITE PR0XIMITY MISSILES July 21,1982 TOPIC TITLE IV-2 REACTIVITY CONTROL SYSTEMS INCLUDING FUNCTIONAL DESIGN AND PROTECTION AGAINST SINGLE FAILURES VI-4 CONTAINMENT ISOLATION SYSTEMS VI-7.A.4 CORE SPRAY N0ZZLE EFFECTIVENESS IX-5 VENTILATION SYSTEMS XV-1 DECREASE IN FEEDWATER TEMPERATURE, INCREASE IN FEEDWATER FLOW AND INCREASE IN STEAM FLOW l
l)GI,16 RADIOLOGICAL CONSEQUENCES OF FAILURE OF SMALL LINES CARRYING REACTOR COOLANT OUTSIDE CONTAINMENT XV-18 RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE BREAK XV-19 RADIOLOGICAL CONSEQUENCES OF LOSS OF COOLANT ACCIDENT l
REVIEW STATUS OF SEP TOPICS DISCUSSED DURING MAY 17 -20, 1982 MEETING AT OYSTER CREEK PLANT.
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