ML20079K499
| ML20079K499 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/15/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079K487 | List: |
| References | |
| NUDOCS 9110220306 | |
| Download: ML20079K499 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.161 TO FACILITY OPERATING LICENSE NO. DPR-66 AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO. NPF-73 DUQUESNE LIGHT COMPANY
~~DhlD'lbEbrtDh)1hr PENitSYLVANI A PTMllf~tDh)ANY THE CLEVIDhD'llitTMtllIElilTTRG COMPANY Tli,E,Tp,L,EDD7hEDh"tDh)ANY BE AVER V ALL_E,f, POWER, S,T ATION_,_ UN_IT_!iOS,,1, A,ND,2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By letter dated May 6,1991, the Dtuluesne Light Company (DLC/the licensee) submitted a request for changes to the Beaver Valley Power Station, Unit Nos. I and 2 Technical Specifications (TS). The requested change would add a surveil-lance requirement to Technical Specification 3/4.4.9, Pressure / Temperature Limits -Reactor Coolant System. The new surveillance requirement, 4.4.9.1.c, will provide for the removal and examination of the reactor vessel material irradiation surveillance specimens in accordance with 10 CFR Part 50, Appendix H.
Guidance on the TS change was provided by Generic Letter 91-01, dated January 4, 1991, to all holders of operating licenses or construction permits for nuclear power reactors.
2.0 BACKGROUND
On January 4,1991, the NFC issued Generic Letter 91-01, " Removal of the Schedule for the Withdrawal of Reactor Vessel Material Specimens from Technical Specifications." This Generic Letter provided for the removal of the schedule, Table 4.5-5, from the TSs since it duplicated the controls on changes to this schedule that have been established by 10 CFR Part 50, Appendix H.
Amendments 142 and 18, issued July 12,19f,9, deleted Table 4.5-5, Reactor Vessel Material Irradiation Surveillance Schedule, and the associated Surveillance Requirement 4.4.9.1.c.
The proposed amendments would reinstate the requirement that the results of the material examination shall be used to update Figures 3.4-2 and 3.4-3 (Reactor Coolant System heatup and cooldown curves) and add a reference to 10 CFR Part 50, Appendix H.
This would, in effect, restore a part of the previously deleted surveillance requirement 4.4.9.1.c.
9110220306 911015 PDR ADOCK 05000334 P
2-3.0 EVALUATION TS 3/4.4.9, Pressure / Temperature Limits, contains a limiting condition for operation for the. Reactor Coolant System (RCS) that limits the rate of change in temperature and pressure to values consistent with the-fracture toughness requirements of the American Society of Mechanical Engineers (ASME) Code-and 10 CFR Part 50, Appendix G.
Changes in the values of these limits are necessary because the fracture toughness properties of ferritic materials in tie reactor vessel change as a function of reactor operating time (neutron f'.d e n ce ).
The proposed amendments woult ing TS 3/4.4.9.1 into agreement with Generic Letter 91-01. Specifically, it would add a requirement for the removal and
-examination of the reactor vessel specimens in accordance with 10 CFR Part 50, Appendix H, to determine changes in material properties.
It-would also-ensure that figures 3.4-2 and 3.4-3 are updated following reactor vessel sample examination. Currently the requirement for updating the heatup and cooldown curves is found only in.the Updated Final Safety Analysis Report.
The staff has~ determined that the new surveillance requirement is administrative in nature and will not reduce the safety of the plant. Adding the additional surveillance requirement-will further ensure that figures 3.4-2 and 3.4-3 are updated following vessel irradiated sample examination, Also, this change will not affect the reactor vessel surveillance program, alter any plant configuration, or_ affect any mode of operation. Therefore, the NRC staff finds
~the addition of the new surveillance requirenient acceptable.
4.0 STATE CONSUL,T_A,TJON In accordance with the Commission's regulations, a good faith attempt was made to contact the Pennsylvania State official regarding the proposed issuance of the amendments.
5.0 E N,VJ,R,0pp,Ep,T,A,L,,C,0 N S I D E R AT I O N
,The amendments change a surveillance requirement. The NRC staff has determined that the amendments involve nn 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 radiation exposure. The Comeission has previously issued a proposed finding that the amendments involve no significant. hazards consideration and there has been no public comment on such finding (56~FR 41581). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 151.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental. assessment need be prepared in connection with the issuance of the amendments.
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6.0 CONCLUSION
The Commission has 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, (2) such activities will be conducted in compliance with the Coomission's regulations, and (3) the issuance of the amendments will not be inimical to the common -
defense and security or to_the health and safety of the public.
Principal Contributor: James W. Andersen Date: October 15,_1991
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