ML20207F033
| ML20207F033 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/04/1999 |
| From: | Doerflein L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20207F038 | List: |
| References | |
| 50-219-98-12, GL-89-10, GL-96-05, GL-96-5, NUDOCS 9903110139 | |
| Download: ML20207F033 (3) | |
See also: IR 05000219/1998012
Text
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March 4,1999
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Mr. Michael B. Roche -
._Vice President and Director
GPU Nuclear incorporated
Oyster Creek Nuclear Generating Station
P.O. Box 388 -
Forked River, New Jersey 08731
SUBJECT:
NRC ENGINEERING INSPECTION REPORT NO. 50-219/98-12
Dear Mr. Roche:
This refers to the engineering inspection conducted on December 14 - 18,1998,
January 6-7,1999, and January 20 - 22,1999, at your Oyster Creek Nuclear Generating
Station, and at your Parsippany, New Jersey, Office. The areas examined during this inspection
included the review of: 1) your self-assessment of Oyster Creek environmental qualification (EQ)
program; 2) your corrective actions for previously identified engineering open items; and 3) your
implementation of Generic Letter (GL) 89-10 motor-operated valve program. At the
February 4,1999, telephone exit meeting, the findings were discussed with you, Mr. Art Rone,
and others of your staff.
We determined you completed an in-depth self-assessment of the Oyster Creek EQ program.-
We noted your management was actively involved with the audit and provided appropriate
personnel to support the audit. We also found your corrective actions for the design control
issue of the Electromatic Relief Valve (EMRV) solenoids to be comprehensive.
We determined GPU has demonstrated the design basis capability of its safety-related motor
~ operated valves. Based on the reviews completed and open items closed, the NRC is closing
its review of the Generic Letter 89-10 Motor Operated Valve (MOV) Program at the Oyster
Creek Nuclear Generating Station. We understand that you will continue to address industry
raised MOV issues such as the performance prediction methodology, stem friction coefficient,
rate of loading, and those contained in Limitorque Technical Update 98-01, as part of your long
term penodic verification per GL 96-05, " Periodic Verification of Design Basis Capability of
Safety Related Motor-Operated Valves." The NRC will review your long-term Program at a later
date.
' No response to this letter is required, and your cooperation with us in this matter is appreciated.
9903110139 990304
PDR. ADOCK 05000219
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Mr. Michael B. Roche
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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its
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enclosure will be placed in the NRC Public Document Room.
Sincerely,
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Lawrence T. Doerflein, Chief,
Engineering Programs Branch
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Division of Reactor Safety
Docket No.-
50-219
. License No.
cc w/ encl:
M. Laggart, Manager, Licensing and Vendor Audits
G. Busch, Manager, Nuclear Safety and Licensing
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State of New Jersey
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Mr. Michael B. Roche'-
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Distribution w/ encl
Region i Docket Room (with concurrences)
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Nuclear Safety Information Center (NSIC)
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PUBLIC
NRC Resident inspector
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H. Miller, RA/J. Wiggins, DRA
W. Lanning, DRS
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' W. Ruland, DRS
L. Doerflein, DRS
. L. Cheung, DRS
P. Eselgroth, DRP '
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N. Perry, DRP
C. O'Daniell, DRP
DRS File
Distribution w/enci NIA E-MAIL):
G. Shear, OEDO
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C. Thomas, PD1-3, NRR
R. Eaton, PD1-3, NRR
T. Colbum, PDI-3, NRR
R. Correia, NRR
DOCDESK
Inspection Program Branch, NRR (IPAS)
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DOCUMENT NAME: G: PROGRAMS HEUNGOC9812.WPD
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DATE
02/17/99
02hf199 M' M 4 0;Fj4/99
03/3/99 "'M03/ /99
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OFFICIAL RECORD COPY
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