ML20205P483
| ML20205P483 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/31/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205P470 | List: |
| References | |
| TAC-63572, NUDOCS 8704030287 | |
| Download: ML20205P483 (3) | |
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. UNITED STATES NUCLEAR REGULATORY COMMISSION y,
.p WASHINGTON. D. C. 20556
,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.135 TO FACILITY OPERATING LICENSE NO. DPR-57 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 DOCKET N0. 50-321
1.0 INTRODUCTION
Hatch Nuclear Plant Unit I was licensed in 1974 and the plant Technical Specifications are in the old format.
The Unit 2 Technical Specifications are in the new format since the plant was licensed in 1978. Due to the differences in the format, as well as in the content of the specifications, there are some differences between the Units 1 and 2 Technical Specifications.
In a submittal dated September 9, 1986, the Georgia Power Company (the licensee) has requested changes to the Unit 1 Technical Specifications in the area of the refueling interlocks surveillance requirements. The proposed change would clarify the Unit 1 Technical Specifications and make them conform more closely to the Unit 2 Technical Specifications. The specification being changed, Technical Specification 3/4.10.A, is related to the reactor moc'e switch, the fuel grapple hoist load setting interlock, and the auxiliary hoists load setting interlock. This evaluation is concerned with the surveillance requirements associated with the aforementioned components.
2.0 EVALUATION The current Technical Specification 3.10.A (limiting conditions for operation) has three subsections which deal with the reactor mode switch (3.10.A.1), the fuel grapple hoist load setting interlocks (3.10. A.2),
and the auxiliary hoists load setting interlocks (3.10.A.3). The corresponding surveillance requirements are specified on a single generic section (4.10. A) which deals with refueling interlocks. This surveillance requirements specification states that " prior to any fuel handling with the head off the reactor vessel, the refueling interlocks shall be functionally tested.
They shall be tested at weekly intervals thereafter until no longer required. They shall also be tested following any repair work associated with the interlocks."
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. The licensee has proposed to revise the surveillance requirements, such that there is a specific surveillance requirement section to correspond to the section on limiting conditions for operation. The proposed revision would have Sections 4.10.A.1, 4.10.A.2, and 4.10.A.3 correspond to Sections 3.10. A.1, 3.10. A.2, and 3.10. A.3, respectively. The original i
surveillance Section 4.10.A has been proposed as Section 4.10 A.1.
With respect to surveillance of the reactor mode switch, the first line of the paragraph has been revised to read:
" Prior to any core alterations, the reactor mode switch refueling interlocks..." (The revised words are underlined). The licensee has not proposed any revision to the corresponding limiting condition for operation. Since the revision for Section 4.10.A.1 clarifies and makes the surveillance requirements more specific, the proposed revision of this section is acceptable.
The licensee has proposed two new sections in the surveillance requirements, namely Sections 4.10. A.2 and 4.10. A.3, relating to the fuel grapple and the auxiliary hoists load setting interlocks, respectively.
Both new proposed paragraphs state that " prior to any movement of fuel assemblies or control rods within the reactor pressure vessel, this l
refueling interlock shall be functionally tested.
It shall be tested at weekly intervals thereafter until no longer required and following any repair work associated with this interlock." This proposed modification of the plant Technical Specifications places the surveillance requirements in a one to one relationship with the appropriate limiting l
conditions for operation.
Furthermore, there is no proposed deviation from the original intent of the refueling interlock surveillance requirements. On the basis of the abon, we conclude that the addition of these two new sections of surveillance requirements is acceptable.
The licensee has proposed modifications to the Unit 1 Technical Specifications which clarify the surveillance requirements for the refueling interlocks and make the Technical Specifications similar to the Unit 2 Technical Specifications. On the basis that the proposed Technical Specification clarifies the surveillance requirements and, thereby, tends to reduce the potential for operator error, we conclude that the proposed modifications to the Unit 1 Technical Specifications 3/4.10.A are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
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This amendment changes surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the. types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessnent need be prepared in connection with the issuance of the amendment.
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4.0 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 Commission'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.
4 Principal Contributor:
J. Ridgely Dated:
March 31, 1987 4
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