ML20137Q362
| ML20137Q362 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/31/1986 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Muller D Office of Nuclear Reactor Regulation |
| References | |
| 0250C, 250C, GL-83-28, SL-74, NUDOCS 8602060185 | |
| Download: ML20137Q362 (2) | |
Text
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Georga Power Company 333 Piedmont Avenue Atianta. Georg:a 30308 Taiannnna an4 orW6 Ma:hng Address:
Post Office Box 4545 Atlanta, Georgf a 30302 GeorgiaPower L T.Gucwa P ' u d* """'vM'
Manager Nuclear Safety and Licensing Department SL-74 0250C January 31, 1986 Director of Nuclear Reactor Regulation 7
Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
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NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 i
GENERIC LETTER 83-28 (SALEM REQUIREMENTS) 4 CONFIRMATION OF TEl. ECON RELATED T0 c'U@RE OF SECTIONS 3.1.3 and 3.2.3 Gentlemen:
During the subject telcon on November 25, 1985, Mr. George Rivenbark and Mr. Don Lasher of the NRC staff, requested certain information needed for closure of the Generic Letter 83-28 f tems related to post-maintenance test requirements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety (Sections 3.1.3 and 3.2.3).
This letter provides the requested information.
Post-maintenance testing is controlled administrative 1y under the maintenance work order (MWO) procedures.
Our review of the Hatch Unit 1 and Unit 2 Technical Specifications identified only a few specific requirements for post-maintenance testing.
None of these requirements is perceived to degrade the reliability of the systems, nor adversely impact the safety of the plant Accordingly, no further action is required for Plant Hatch and, therefore, the requirements can be considered closed for Plant Hatch Units 1 and 2.
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N GeorgiaPower d Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 January 31, 1986 Page Two During our review, we did not discover any post-maintenance testing requirements in the Technical Specifications for equipment required to trip the reactor (section 3.1.3 of the Generic Letter), and additionally, we did not find any adverse post-maintenance requirements for the remaining safety-related equipment (Section 3.2.3 of the Generic Letter).
Accordingly, no further action is required for Plant Hatch and, therefore, the requirements can be considered closed for Plant Hatch Units 1 and 2.
Please contact this office if you have any questions or comments.
Very truly yours,
- d. [ 6Hml L. T. Gucwa PLS/lc c: Mr. J. T. Ceckham, Jr.
Mr. H. C. Nix,
Dr. J. N. Grace (NRC-Region II) l Senior Resident Inspector GO-NORMS 70071$