ML20155G503
| ML20155G503 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 05/26/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155G493 | List: |
| References | |
| NUDOCS 8806170333 | |
| Download: ML20155G503 (2) | |
Text
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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION P' LATED TO AMENDMENT NO. g TO FACILITY OPERATING LICENSE NO DPR-61 CONNECTICUT YAhKEE ATOMIC POWER COMPANY 10DAMNECKPLANT DOCKET NO. 5_0,213
1.0 INTRODUCTION
Pursuant to 10 CFR 50.90, Connecticut Yankee Atomic Power Company (CYAPCO) proposes to amend the Operating License No. OPR-61 for the Haddam Neck Plant.
By letter dated February 25, 1988. CYAPC0 proposed to renumber the manual high pressure safety injection (HPSII throttle valves in Technical Specification 3.6.B.2 to be consistent with the plant loop nunbering scheme. Also the applicability statement for Technical Specification 3.6.B.2 has been changed to be more concise and PODE specific and the Basis for Technical Specification 3.6 has been clarified.
2.0 DISCUSSIO,N Manual valves SI-V-905, 906, 907 and 908 have been renumbered to be consistent with the plant loop numbering scheme. Specifically, the proposed change would renunber valves currently designated as SI-V-907, 908, 906 and 905 to SI-V-905, 906, 907 and 908 respectively.
The proposed change would associate valves SI-V-905, 906, 907 and 908 with loops 1, 2, 3 and 4 respectivel3 The valves are identical and their throttle positions have been established by test for the proper loop.
In order to be more concise and PODE specific, the applicability statement for Technical Specification 3.6.B.? has been changed from "Prior to startup from cold shutdown (MODE 5)" to "On startup prior to entering MODE 4".
In both cases this statement requires the valves to be in their correct position prior to making the transition from MODE 5 to MODE 4 The basis has been revised to describe more accurately the safety limits that must not be exceeded during a loss of coolant accident. Specifically, the Basis 3.6 has been changed from "Based on the loss of coolant accident analysis melting of the cladding is prevented with only one high pressure safety injection pump and one low pressure safety injection (core deluge) purp in operation" to "Based on the loss of coolant accident analysis, exceeding the Interim Acceptance Criteria clad temperature safety limit (2300*F) is prevented with only one high pressure safety injection pump and one low pressure safety injection (core deluge) pump in operation."
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3.0 EVALUATION Manual valves, SI-V-905, 906, 907 and 908 were renumbered to be consistent with the plant loop numbering scheme. Therefore, the change does not change the ECCS configuration, diminish ECCS LOCA mitigation capability or affect the nonnal operating condition of the plant.
The proposed change in the applicability statement for Technical Specification 3.6.B.2 maintains the current requirerents that valves SI-V-905, 906, 907, 908 and 873 are in the correct position prior to niaking the transition from MODE 5 to MODE 4 The HPSI throttle valves (SI-Y-905 through 908) are not required to be operable until the plant is in MODE-3 while the core deluge valve (SI-V-873) is required for MODE-4 operation. While both statements ensure that the above valves are properly positioned and secured before they are requested to be OPERABLE, the NRC staff agrees that the propcsed char.ge is more concise and PCDE specific.
The proposed revisier to the basis describes more accurately the safety limits that must not be exceeded during a loss of coolant accident. The staff has reviewed this change and egrees that the change in the basis is more descriptive.
4.0 ENVIRONFENTAL CONSIDERA110N This amendment involves changes which are administrative in nature. Accordingly, the avendment ineets the eligibility criteria for categorical exclusien set forth in 10 CFR 551.22(c)(10).
Pursuant to 10 CFR 951.22(b), no environmental impact statement or enviror.ner.tal assessnent need be prepared in connection with the issuance of the amendment.
5.0 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 Connission's regulations, and the issuance of the amendment will not be inimical to the connon defense and security or to the health and safety of the public.
Dated:
May 26,1988 Principal Contributor:
Alan Wang
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