ML20216H148
| 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: |
| 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
SUBJECT: SPECIAL INSPECTION REPORT NO. 50-219/98-04 AND NOTICE OF
VIOLATION
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
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for tritium vapor. The enclosed report presents the results of this inspection. Our
preliminary findings were discussed at the exit meeting on March 18,1998.
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
this inspection report. The radiological assessment was performed by NRC radiation
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specialists, as described in Section R1 of this inspection report. This inspection consisted
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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
(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
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in order to demonstrate compliance with the dose limits for individuals members of the
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public, as required by Technical Specification 6.8.4.a.3.These violations are of concern
since the issue involving the design basis description was previously identified by your
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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
in February 1998. These violations are discussed in Sections O.3 and R.1 of this report,
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respectively.
9804210071 980415
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M. Roche
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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
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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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