ML20137X995
| ML20137X995 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/19/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137X988 | List: |
| References | |
| TAC-57907, NUDOCS 8512100703 | |
| Download: ML20137X995 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 117 TO FACILITY OPERATING LICENSE NO. DPR-57 GEORGIA POWER COMPANY OGLETERHUT70VNT01FORTION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA EDWIN I. MATCH NUCLEAR PLANT, UNIT NO. 1 DOCKET NO. 50-321 Introduction and Evaluation By letter dated May 20, 1985, the licensee, Georgia Power Company (GPC) requested that plant Technical Specification (TS) 6.9.2 be revised to delete the special reporting requirements as listed in TS Table 6.9.2-1 for the secondary containment drawdown test (Item b) and for primary leakage to the drywell (Item c).
The first report, listed as Item "b" in Table 6.9.2-1, is a summary technical report of the secondary containment drawdown test which is required every refueling outage to measure the ability of the Standby Gas Treatment System to drawdown the secondary containment to negative one-quarter inch water gauge (-i"w.g.).
We do not currently require a report to be prepared after completion of this test and therefore there is no need for the reporting requirement listed in Technical Specification Table 6.9.2-1.
The second report, listed as Item "c" in Table 6.9.2-1, is a report of primary system leakage to the drywell which is required once every five years. The TS does not define or provide specific guidance on what should be included in this report, and we can identify no basis for the report.
(This special report is not included in current BWR Standard Technical Specifications).
It should also be noted that Item c has a typogra error in that it references TS 4.6.C (reactor head stud tensioning)phical rather thanTS4.6.G(reactorcoolantleakage).
Hatch TS 3.6.G and 4.6.G currently contain limiting conditions for operation and surveillance requirements for monitoring reactor coolant leakage into the drywell. Should the leakage limits be exceeded, it would be reported per the licensee event report requirements of 10 CFR 50.73. Thus, the special reporting requirement of item c is not necessary.
Accordingly, we conclude that the licensee's proposal to delete reporting requirements "b" and "c" of Table 6.9.2-1 is acceptable.
8512100703 851119 PDR ADOCK 05000321 P
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Environmental Considerations This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Coninission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: November 19, 1985 Principal Contributors:
J. Lane and D. Katze
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