ML20214E977
| ML20214E977 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/17/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214E958 | List: |
| References | |
| TAC-55543, NUDOCS 8611250154 | |
| Download: ML20214E977 (3) | |
Text
[ancob UNITED STATES
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NUCLEAR REGULATORY COMMISSION 6
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 69 TO
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FACILITY OPERATING LICENSE N0.
NPF-5 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA EDWIN I. HATCH NUCLEAR PLANT, UNIT N0t 2 DOCKET N0. 50-366
1.0 INTRODUCTION
By letter dated July 18,1986 (Reference 1), the Georgia Power Company (GPC) requested changes to the Hatch Plant Unit 2 Technical Specifications that (1) would add and/or clarify operability and surveillance requirements pertaining to the Anticipated Transient Without Scram (ATWS) Recirculation Pump Trip (RPT) instrumentation as previously proposed in GPC's submittal of April 23, 1984 (Reference 2) and (2) add a new section to provide explicit operability and surveillance requirements for the End-of-Cycle (E0C) RPT function in place of footnotes.
2.0 EVALUATION The ATWS RPT instruments are designed to trip the recirculation pump motor-generator set drive motor breakers to reduce reactivity during postulated ATWS events.
Presently these instruments are identified by footnote "j" to Table 3.3.1-1, " Reactor Protection System Instrumentation." None of the operability and surveillance requirements are provided; those actions and surveillance requirements provided in Tables 3.3.1-1 and 4.3.1-1 are applicable only to the Reactor Protection System (RPS) instrumentation. Because of this situation, the Hatch Unit 2 Plant Procedures now implement requirements similar to those in the i
l Hatch Unit 1 Technical Specifications, which do provide explicit i
operability and surveillance requirements for the RPT instrumentation.
The proposed change 1 adds a new section 3/4.3.9.1, "ATWS Recirculation Pump Trip Actuation Instrumentation," providing operability requirements, l
action statements, instrument setpoints, and surveillance requirements for the ATWS RPT instruments. These requirements are consistent with those in the Hatch Unit 1 Technical Specifications already implemented in the Unit 2 procedures.
The proposed change 2 adds a new section 3/4.3.9.2, "End-of-Cycle Recirculation Pump Trip System Instrumentation," providing explicit h
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operability and surveillance requirements for the E0C RPT function. The purpose of the E0C RPT is to recover the loss of thermal margin occurring at the end of cycle. Each E0C RPT system trips both recirculation pumps, reducing coolant flow in order to reduce the void collapse in the core during a limiting pressurization transient near the end of cyc,le.
Presently, these instruments are identified by footnote "k" to Table 3.3.1-1, " Reactor Protection System Instrumentation." Similar to change 1 described above, none of the operability and surveillance requirements are provided. The proposed change 2 will provide explicit requirements for the E0C RPT instrumentation.
These changes add explicit operability and surveillance requirements for instrumentation which provides the ATWS RPT and the E0C RPT functions.
These instruments are presently footnoted in the Technical Specifications, but no surveillance requirements are provided. The changes are administrative in nature, since the proposed requirements are already being met procedurally.
On the basis of the above discussion we conclude that these proposed changes are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
S This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and adds 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 should be no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public coment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 20 CFR 51.22(b), no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
On the basis of the considerations discussed above, the staff has concluded 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.
Principal Contributor:
D. Yue Dated:
November 17, 1986 L
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5.0 REFERENCES
1.
Letter from J. T. Beckham, Jr., Georgia Power Company, to D. Muller, NRC, July 18, 1986..
2.
Letter from J. T. Beckham, Jr., Georgia Power Company, to J. F. Stoltz, NRC, April 23, 1984.
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