ML20216H148

Forwards Insp Rept 50-219/98-04 on 980226-0318 & NOV Re Failure to Conduct Written Safety Evaluation to Provide Bases for Determination That Use of make-up Water Source for IC Sys Did Not Involve Unreviewed Safety Question

ML20216H148
Person / Time
Site:	Oyster Creek
Issue date:	04/15/1998
From:	Jason White NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Roche M GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20216H154	List: ML20216H148 ML20216H170 ML20216H191
References
50-219-98-04, 50-219-98-4, EA-98-198, NUDOCS 9804210071
Download: ML20216H148 (3)

See also: IR 05000219/1998004

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April 15, 1998

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EA 98-198

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

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SUBJECT: SPECIAL INSPECTION REPORT NO. 50-219/98-04 AND NOTICE OF l

VIOLATION i

Dear Mr. Roche:

This refers to the special inspection conducted on February 26-March 18,1998, at the

Oyster Creek Generating Station. The purpose of this specialinspection was to review the

circumstances related to the licensee's identification that continuous steaming of one of  !

the two isolation condensers, constituted an unmonitored radioactive effluent release path ,

for tritium vapor. The enclosed report presents the results of this inspection. Our l

preliminary findings were discussed at the exit meeting on March 18,1998. l

The operations, maintenance and material condition of the isolation condenser (IC) system  !

were inspected by the NRC resident inspector, as described in Sections 02,03, and M2 of l

this inspection report. The radiological assessment was performed by NRC radiation j

specialists, as described in Section R1 of this inspection report. This inspection consisted )

of selective examinations of procedures and representative records, interviews with

personnel, and observations by the inspectors.

Based on the results of this inspection, the NRC has determined that violations of NRC

requirements occurred. These violations are cited in the enclosed Notice of Violation l

(Notice) and the circumstances surrounding them are described in detail in the subject

inspection report. One violation involved failure to conduct a written safety evaluation, as

required by 10 CFR 50.59, to provide the bases for the determination that the use of a

make-up water source for the IC system, that was different than described in design bases

documents, did not involve a unreviewed safety question. A second violation involved

failure of your radioactive effluents control program to provide for the monitoring,

sampling, and analysis of tritium that was released to the atmosphere from the IC system ,

in order to demonstrate compliance with the dose limits for individuals members of the

public, as required by Technical Specification 6.8.4.a.3.These violations are of concern

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since the issue involving the design basis description was previously identified by your

l staff in March 1997, but was not followed-up sufficiently to assure regulatory compliance

until the potential radioactive release pathway from the isolation condenser was discovered

i in February 1998. These violations are discussed in Sections O.3 and R.1 of this report,

respectively.

9804210071 980415 n

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M. Roche 2

Notwithstanding these violations of NRC regulatory requirements, our review determined

that the dose consequence to members of the public and onsite workers, relative to the

release of tritium vapor to the atmosphere from the IC system, was insignificant with

respect to criteria and limits specified in the applicable regulatory requirements, including

10 CFR 20. Accordingly, no health and safety consequence to members of the public or

plant workers is expected as a result of this release pathway.

You are required to respond to this letter and should follow the instructions specified in the

enclosed Notice of Violation when preparing your response. The NRC will use your

response, in part, to determine whether further enforcement action is necessary to ensure

compliance with regulatory requirements,

in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,

its enclosures, and your response will be placed in the NRC Public Document Room (PDR).

Sincerely,

ORIGINAL SIGNED BY:

John R. White, Chief

Radiation Safety Branch

Division of Reactor Safety

Docket No: 50-219

License No: DPR-16

Enclosure: NRC Inspection Report No. 50-219/98-04

cc w/ encl:

G. Busch, Manager, Site Licensing, Oyster Creek

M. Laggart, Manager, Corporate Licensing

State of New Jersey

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M. Roche 3

Distribution w/ encl:

Region 1 Docket Room (with concurrences)

Nuclear Safety information Center (NSIC)

PUBLIC

NRC Resident inspector

J. Schoppy, SRI-Oyster Creek

N. Perry, DRP

D. Haverkamp, DRP -

J. Yerokun, DRS

H. Miller, RA/W. Axelson, DRA

A. Linde, DRP

C. Miskey, DRS

Distribution w/ encl: (VIA E-MAIL)

B. McCabe, OEDO

P. Milano, NRR, PD1-3

C. Thomas, NRR, PD1-3

R. Correia, NRR

F. Talbot, NRR

DOCDESK

Inspection Program Branch, NRR (IPAS)

D. Screnci, PAO

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DOCUMENT NAME: G:\RSB\JANG\0C9804. INS -

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'N' = Qo copy

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