ML19345E777
| ML19345E777 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/15/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345E775 | List: |
| References | |
| NUDOCS 8102060092 | |
| Download: ML19345E777 (3) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 34 TO FACILITY OPERATING LICENSE NO. DPR-64 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 Introduction By letter of July 7,1979, we identified sections of the Indian Point 3 Technical Specifications that needed upgrading to be at least as stringent We under-as the Standard Technical Specifications for Westinghouse plants.
took this effort in accordance with Item F.l(f)(3) of the Zion / Indian Point Task Action Plan (Enclosure 4 of our April 5,1980 letter). By letter 29, 1980, the Power Authority of the State of New York dated September (the licensee) proposed Technical Specifications to satisfy parts of our Jt.ly 7, 1979 letter.
By letter dated October 31, 1980, the licensee proposed a change to the Technical Specification definition of " surveillance interval." Also, in a second letter dated October 31, 1980 the licensee proposed a chan'ge to the Technical Specifications to assure a minimum of 23 feet of water over the top of the reactor pressure vessel flange during movement of fuel This proposal was in response to our letter of August 15, assemblies.
1980 to "All Westinghouse Pressurized Water Reactor Licensees."
By letter dated November 7, 1980, the licensee proposed a change to the Technical Specifications to require valves 1870 and 743 be open and the power supplies de-energized. This proposal is in response to our letter of September 22, 1980.
Finally, the license condition which deals with steam generator inspection is being revised to eliminate the requirement for a mid-cycle inspection of one steam generator.
This inspection was conducted in October 1980 and approved by our letter dated November 20, 1980.
Evaluation l
The proposed Technical Specifications submitted by letter of July 7,1980 are, in all cases, more restrictive than the current Technical Specifica-Our objective to upgrade the Indian Point 3 Technical Specifications, tions.
as discussed in Item F.l(f)(3) of the Zion / Indian Point Task Action Plan, has been met in these proposed Technical Specifications and we therefore find them acceptable.
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. However, the licensee still has to propose changes to the following Sections of the Technical Specifications to completely satisfy our 3.1. A.1. b, 3.1. A.1.c, 3. 5. 3.6. c. 4. 5. A.4, 4. 5. A. 5, July 7,1979 letter:
4.5.A.6, 4.6.B, 4.6.X, 4.8.1, and appropriate Limiting Conditions for Operation and Surveillance Requirements for remote shutdown instrumentation, post-accident instrumentation, chlorine detection instrumentation, turbine overspeed, and electrical equipment protection devices.
31, 1980 letters proposes to change the definition One of the October of " surveillance interval" to that which is in the Standard Technical Specifications. We find the change acceptable.
The other letter dated October 31, 1980 was sent in response to our 15, 1980 letter. The proposed change assures a minimum of 23 August feet over the top of the reactor pressure vessel flange during movement i
of fuel assemblies. This, in turn, assures that the minimum level of water over the fuel assemblies is approximately 33 feet which is sufficient depth to prevent inadvertent exposure of a fuel assembly during transfer.
We find this proposed change acceptable.
The November 7,1980 letter proposes a change to the Technical Specifications which keeps valves 1870 and 743 open and their power supplies de-energized.
This is required to prevent a spurious closing of either of these valves following a safety injection signal. These valves are in the Residual Heat Removal (RHR) System miniflow line, and a spurious closing of either valve could result in damage to the RHR pumps if the reactor coolant system pressure is still high.
Finally, the updated license condition for the steam generator inspection requires the inspection of all four steam generators within twelve The mid-cycle equivalent months of operation from the mid-cycle inspection.
l inspection of #32 Steam Generator was performed after slightly more Thus, with the new license l
than eight equivalent months of operation.
condition, the mid-cycle inspection was performed when at least 40%
of the Cycle 3 operation was completed. Therefore, our conclusion in the November 20, 1980 letter that the plant can operate for the duration j
of Cycle 3 without additional inspection of the steam generators remains valid.
Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this i
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detemination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR {51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal l
need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reason-able assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date:
January 15, 1981 l
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