ML19296C060
| ML19296C060 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/19/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19296C045 | List: |
| References | |
| NUDOCS 8002250144 | |
| Download: ML19296C060 (3) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACT:R REGULATION RELATED TO AMENDMENT N0. 28 TO FACILITY OPERATING L: CENSE S0. DPR-64 POWER AUTHORITY OF THE STATE OF NEW ORK INDIAN POINT NUCLEAR GENERATING U'4IT NO. 3 DOCKET NO. 50-286 Introduction By letter dated August 24, 1979, Pwer Authority of the State of New York (the licensee), submitted an application to anenc the Technical Specifications appended to Facility Operating License :PR-64 'or Indian Point Unit 3.
One of the requested cranges would dy the -eactor vessel metal reference nil-ductility tenperature '; ;:-) cue :: irradia-tion.
Another requested change wou'd add a re:uirev. to co duct surveillance for reactivity core antralies.
Discussion 10 CFR Part 50, Appendix G " Fracture Toughness Requirenents," requires that pressure-temperature limits be established for reactor ccolant system heatup and cooldown operations, inservice leak and hycrostatic tests, and reactor core operation.
These linits are requirec to ensure that the stresses in the reactor vessel remain within acceptable limits.
They are intended to provide adequate nargins of safety curing any condition of nornal operation, including anticipated operational oc:urrences.
The pressure-temperature linits depene upon the retal';rgical prcrerties of the reactor vessel naterials.
Tre properties cf nerials in :he vessel beltline region vary over the lifetire of the vessel :ecause Of tne effects of neutron irradiation.
One princi, R effect of the neutron irradiation is that it causes the vessel material nil-ductility temperature (RTNDT) to increase with time.
The pressure-temperattre operating linits must be modified periodically to account for this radiation induced increase in RTNOT by increasing the temperature required for a given pressure.
The operating limits for a particular operating period are based on the material properties at the end of the operating period.
By periodically revising the pressure-temperature limits to account for radiation damage, the stresses and stress intensities in the reactor vessel are maintained within acceptable limits.
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. is proportional to the neutron fluence The magnitude of the shift in RTNDT that the materials are subjected to. The shift in RTNDT can be predicted f rom Regulatory Guide 1.99.
To check the validity of the predicted shift NT, a reactor vessel material surveillance program is recuired.
in RT
> Surveil' ance specimens are periodically remoied f rom the vessel and tested.
The results of these tests are compared to t:te predicted shifts in RTNDT, and the pressure-temperature operating limits are revised accordingly.
Although the licensee has been conducting surveillance for core reactivity anomalies, no requirement to do so existed is the Technical Specification.
The omission is corrected by the proposed arendment.
Evaluation The present Technical Specifications contain pressure-temperature operating limits that are effective for two EFPY.
Sirre Indian Point 3 has operated for about two EFPY, Power Authority of the State of New York has submitted revised operating limits.
These limits are proposed for operation through 9.26 EFPY. Radiation damage on vessel materials is predicted # rom the results of tests on material surveillance ca:sule T which was emoved from the reactor vessel at 1.34 EFPY. The liniti ; Nterial is lower shell plate metal having an initial RTNDT of 74*F.
At 9.2f EFPY the RTNDT of the limiting material at the 1/4 T* locatic, is ca'culated to increase to 201 F.
Power Authority of the State of New York transmitted copies of the surveillance report on Capsule T WCAP-9491, with their application for the Technical 18 Spegification change. Specimens ret ived an average fluence of 2.92 x 10 n/m.
This fluence resulted in an 1ncrease in RTNDT for weld metal of 175*F and for plate material of 125*F. We 'have reviewed the test results on Capsule T and consider them to be valid.
We have reviewed the proposed pressure-temperature operating limits and have performed independent calculations to verify their compliance with Appendix G, 10 CFP, Part 50.
We agree that the limiting material is plate material having an RTNDT of 201 F at 9.26 EFPY. We conclude t,at the proposed operating limits are acceptable and are in conformance with Appendix G for operation through 9.26 EFPY.
- l/4 T is one-f ourth the thickness of the vessel wall, measured from the inside.
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' Conformance with Appendix G to 10 CFR Part 50 in establishing safe vperating limitations will ensure adequate safety margins during operation, testing, maintenance, and postulated accident conditions and constitutes an acceptable basis for satisfying the requirements to NRC General Design Criterion 31, Appendix A,10 CFR Part 50.
We find the proposed Technical Specification for conducting surveillance for core activity anomalies to be acceptable.
The added paragraph 3.10.10 is identical to that in the Westinghouse Standard Technical Specifications.
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 determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in cenrection 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 reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed nanner, and (3) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Date: January 19, 1980