ML20212N426
| ML20212N426 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/09/1987 |
| From: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20212N429 | List: |
| References | |
| NUDOCS 8703130020 | |
| Download: ML20212N426 (3) | |
See also: IR 05000219/1986039
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DESIGNATED ORIGIN /G
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MAR 0 91987
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Docket No. 50-219
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GPU Nuclear Corporation
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ATTN: Mr. P. B. Fiedler
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Vice President and Director
Oyster Creek Nuclear Generating Station
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P. O. Box 388
Forked River, New Jersey 08731
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Gentlemen:
Subject:
Inspection No. 50-219/86-39
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This refers to the routine safeguards inspection conducted by Mr. W. Madden of
this office on December 8-11, 1986 at Oyster Creek Nuclear Generating Station
of activities authorized by NRC License No. DPR-16 and to the discussions of our
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findings held by Mr. Madden with Mr. J. Barton and other members of your staff
at the conclusion of the inspection, and to subsequent telephone discussions
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between Mr. Madden and Mr. D. Long, Security Supervisor, on December 17 and
Mr. J. Knubel, Director of Security, on December 19, 1986.
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Areas examined during this inspection are described in the NRC Region I
Inspection Report which is enclosed with this letter. Within these areas, the
inspection consisted of selective examinations of procedures and representative
records, interviews with personnel, and observations by the inspector.
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Within the scope of this inspection, no violations were observed.
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During the inspection, our inspector questioned certain aspects of your protec-
tion program for safety related equipment. As a r;sult, members of your staff
inquired about the Vital Area Analysis of Oyster Creek conducted by the Los
Alamos National Laboratory (LANL).
The results of that analysis will be vali-
dated by NRC during the Regulatory Effectiveness Review (RER) which is currently
being scheduled for Oyster Creek. You will be advised shortly, by separate
correspondence, of the date. However, to assist you in reviewing your protec-
tion program, we are enclosing the assumptions developed by LANL and used by
the NRC during RER's (Enclosure 2). This information, in combination with your
Final Safety Analysis Report and physical protection program criteria contained
in 10 CFR 73.1(a),10 CFR 73.55 and Appendices "B" and "C" of 10 CFR 73, should
facilitate your review.
Paragraphs 5 and 6 of the inspection report (Enclosure 1) and Enclosure 2 have
been deternined to be exempt from public disclosure in accordance with 10 CFR 73.21(SafeguardsInformation). Therefore, they will not be placed in the NRC's
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Public Document Room and will receive limited :fistribution. This letter and
0FFICIAL RECORD COPY
IR SG OYC 86-39 - 0001.0.0
03/06/87
07031
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the remaining portions of the inspection report will be placed in the Public
Document Roo.a. in accordance with 10 CFR 2.790(a).
No reply to this letter is required. Your cooperation with us is appreciated.
Sincerely,
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Original Signed By:
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Richard R. Keinig
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Thomas T. Martin, Director
Division of Radiation Safety
and Safeguards
Enclosures:
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1.
NRC Region J Inspection Report No. 50-219/86-39
(Contains Safeguards Information (SG1) in Paragraphs 5 and 6)
2.
Assumptions used by RER for Identifying Vital Areas
(Contains Safeguards Information)
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cc w/ enc 1 (w/o SGI):
M. Laggart, BWR Licensing Manager
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Licensing Manager, Oyster Creek
Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector (w/SGI)
State of New Jersey
bec w/ enc 1 (w/o SGI):
Region I Docket Room (with concurrences)
Haragement Assistant, DRMA (w/o enc 1)
'Section Chief, DRP
Robert J. Bores, DRSS
Robert Dube, NMSS (w/SGI)
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03/ 6 /87
03/6 /87
03/4/87
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OFFICIAL RECORD COPY
IR SG OYC 86-39 - 0002.0.0
03/06/87
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ENCLOSURE 2
ASSUMPTIONS USED BY RER FOR' IDENTIFICATION OF VITAL AREAS
ALL OF ENCLOSURE 2 CONTAINS
SAFEGUARDS INFORMATION AND
IS NOT.FOR PUBLIC DISCLOSURE
IT IS INTENTIONALLY LEFT
BLANK