ML20236P538
| ML20236P538 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/09/1987 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20236P541 | List: |
| References | |
| NUDOCS 8711180040 | |
| Download: ML20236P538 (4) | |
See also: IR 05000219/1987024
Text
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- Docket 1No.:50-219.
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.GPU Nu' clear Corporation
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. ATTN: ; Mr; P..c B. Fiedler
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Vice' President and Director'
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Oyster Creek Nuclear Generation Station.
P/ 0. Box 388
Forked River; New Jersey .08731
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Gentlemen:
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Subject:
Inspection Report.No.'50-219/87-24
During the' period from to. August 10, 1987,- to August 21, 1987, an Integrated
Performance Assessment Team inspection was conducted at the Oyster Creek
. Nuclear Generating 1 Station.
Details of the inspection and findings are
,
provided in the enclosed report.
The purpose of this inspection was-to evaluate the level of your performance in
various functional ~ areas and to determine the underlying reasons for that
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performance. . During the period of the inspection, .the' plant operated routinely
and provided few opportunities.to' observe performance associated with off-normal
-conditions. Within the scope of this inspection, however, the
~ team concluded that there is capable management and staff.at.the' plant.
The
various programscin place, as well as your performance in implementing the
programs,1are adequate.to reasonably assure nuclear safety of the plant and
radiological safety'of-both the workers and the public.-lFurther,' your
organizati.on exhibited a positive attitude'toward self-im'provement.
The team identified a number of areas needing management attention, in par-
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ticular,-(1) overall coordination of ALARA efforts, (2) certain aspects of
plant engineering activities, and (3) control of temporarily stored equipment .
in the plant. Also, despite a generally good safety perspective among the
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staff relative to avoiding plant trips and transients and toward meeting
Technical Specification requirements, the team concluded that improvement was
.needed in the areas of risk perspective and understanding the design basis of
the plant.
In order to assist us in evaluating your actions in response to this
inspection, ya are requested to provide, within 45 days of the date of this
' letter, a written response detailing your evaluation of inspection team
findings and your plans for improvement relative to the following items:
.(1) definition and. coordination of your ALARA program (inspection report
. paragraph 3.3);
,
(2) appreciation of the need for clear and effective administrative controls
for plant engineering activities (paragraph 6.3.1);
0FFICIAL RECORD COPY
IR OC 87-24 - 0001.0.0
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ADOCK 05000219 :_
11/06/87
8711180040 871109
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'(3) control-of temporarily stored equipment in plant, including' gas bottles,
ladders, and equipment on rollers; and
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(4):
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Enhancement of' facility staff's risk perspective and comprehension of-
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design' bases. (paragraphs 2.2.3 and 7.0).
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NRC Region I.will follow up on your evaluations and actions, in response to'
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- these ' items and others identified in-the . inspection, as described Lin paragraph
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8 of.the report,
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JTwo operational events took place at your. facility recently which resulted.in
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significant1 safety. concerns. The first involved blocking open drywell _ and
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torus vacuum breakers in April, 1987.
The second was-the violation'of e. safety
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, limit in September 1987.
Both of these events resulted from personnel. errors.
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Personnel performance associated with these events contrasts significantly
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iwith the performance observed during this in'spection. We recognize that you
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have' assessments under way to understand the' reasons for'the inconsistency
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in ~ personnel performance that has occurred during recent months. Your efforts
to determine the underlying reasons for this inconsistency and to develop
appropriate corrective actions will be a major focus of our future inspection
. activities at your. facility.
Thank you for your. cooperation in these matters.
Sincerely,
William.F. Kane, Director
Division of Reactor Projects
Enclosure: NRC Region I Inspection Report No. 50-219/87-24
cc w/ enc 1:
.M. Laggart, BWR Licensing Manager
Licensing Manager, Oyster Creek
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear . Safety Information Center (NSIC)
NRC Resident ~ Inspector
State of New Jersey
D. Scott, New Jersey DEP (3)
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0FFICIAL RECORD C0pY
IR OC 87-24 - 0002.0.0
11/29/80
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Region 1 Docket' Room (with concurrences)
Management ' Assistant, DRMA (w/o enc 1)
DRP Section Chief
Robert J. Bores, DRSS
B. Clayton, EDO
W. Bateman, RI
A. Blough, RI
R. Brady, RI
T. Dragoun, RI
D. Florek RI
D. Hickman, NRR
C. Hinson, NRR
D. Johnson, RI
J. Kaucher, RI
G. Kelly, RI
R. Pederson, NRR
J. Sharkey, NRR
A. Dromerick, NRR
J. Stolz, NRR
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0FFICIAL RECORD COPY
IR OC 87-24 - 0003.0.0
10/30/87
See previous concurrences
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W. Bateman, RI
A. Blough, RI
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R. Brady, RI
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T. Dragoun, RI
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D. Florek. RI
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D. Hickman, NRR
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C. Hinson, NRR
D. Johnson, RI
J. Kaucher, RI
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G. Kelly, RI
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R. Pederson, NRR
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J. Sharkey, NRR
A. Dromerick, NRR
J. Stolz, NRR
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0FFICIAL RECORD COPY
IR OC 87-24 - 0003.0.0
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10/28/87
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