ML17261A464
| ML17261A464 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/20/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17261A462 | List: |
| References | |
| 50-244-87-04, 50-244-87-4, NUDOCS 8704290230 | |
| Download: ML17261A464 (4) | |
Text
Appendix A NOTICE OF VIOLATION Rochester Gas 5 Electric Corporation R.
E. Ginna Nuclear Power Plant Docket No. 50-244 License No.
OPR-18 Ouring the inspection conducted on February 8, 1987 through March 14,
- 1987, and in accordance with the General Statement of Policy and Procedure for NRC Enforcement Actions 10 CFR Part 2, Appendix C (Enforcement Policy 1986), the following violations were identified:
A.
Technical Specification 4. 1.4 requires that Liquid Radioactive Waste Monitor R-18 be source checked monthly.
- Further, note 4 to Technical Specification Table 4. 1.5, "Radioactive Effluent Monitoring Surveillance Requirements" states:
"This check may require the use of an external source due to high background in sample chamber."
Contrary to the above, from March 1976 to January 1987 monthly source checks of radioactive waste monitor R-18 were not properly performed, in that, the check source position of the instrument front panel switch per-formed no function because no check source or check source solenoid has been installed since March 1976.
Additionally, no source check was performed with an external source when high background radiation existed.
This is a Severity Level IV violation.
(Supplement I)
B.
10 CFR 50.59 permits the licensee to make changes to the facility without prior Commission approval unless the proposed change involves an unreviewed safety question.
When making such changes the licensee shall maintain records which include a written safety evaluation that provides the bases for determining that these changes did not involve unreviewed safety "questions.
Contrary to the above.,
the licensee did not perform safety evaluations of lead shielding installations around a component cooling water pipe support and around the spent fuel pool heat exchanger when installing between 1970 and 1971.
Additionally, the licensee performed inadequate and inconclu-sive safety evaluations of these installations in 1986 when preexi stina lead shielding was evaluated as part of a temporary lead shielding review program.
This is a Severity Level IV violation.
(Supplement I)
Pursuant to the provisions of 10 CFR 2.201, Rochester Gas and Electric Corporation is hereby required to submit to this office within 30 days of the date, of. the letter transmitting -this Notice, a written statement or explanation in reply, including:
(1) the reason for the violation if admitted, (2) the corrective steps which have been taken and the results
- achieved, (3) the
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PDR OFFICIAL RECORD COPY IR GINNA 87"04 0003.0.0 04/13/87
Appendix A corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
Where good cause is shown, con-sideration will be given to extending the response time.
OFFICIAL RECORD COPY IR GINNA 87-04 0003.1.0 04/13/87