ML20207F033

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Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted
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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( (.k . 2 March 4,1999

.

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 2

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its i

enclosure will be placed in the NRC Public Document Room.

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Sincerely, l

.

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I

Lawrence T. Doerflein, Chief, l

Engineering Programs Branch i

Division of Reactor Safety

Docket No.- 50-219

. License No. DPR-16

cc w/ encl:

M. Laggart, Manager, Licensing and Vendor Audits

G. Busch, Manager, Nuclear Safety and Licensing i

State of New Jersey l

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Mr. Michael B. Roche'- 3 ,

Distribution w/ encl

Region i Docket Room (with concurrences)  !

Nuclear Safety Information Center (NSIC) ,

PUBLIC

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NRC Resident inspector

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 ,

C. Thomas, PD1-3, NRR i

R. Eaton, PD1-3, NRR

T. Colbum, PDI-3, NRR

R. Correia, NRR

DOCDESK  !

> Inspection Program Branch, NRR (IPAS)

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