ML20009B888
| ML20009B888 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/10/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009B889 | List: |
| References | |
| TAC-43744, TAC-43745, NUDOCS 8107170316 | |
| Download: ML20009B888 (15) | |
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[ ' ;., g j NUCLE,",R REGULATCRY COT. ifs $10N
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WISCONSIN ELECTRIC POWER CCMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDfENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. OPR-?.4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated March 31, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements
-have been satisfied.
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N 12..-; Accordingly,ithe license.f s amended by. changes to the Technical' Specifications as indicated in the attachnant to this license amendment,;and paragraphL3.B of Facility Operating License
- No ' 0PR-24 'is hereby-_ amended to -read as follows:
B.-1 Technical Specifications-The Technical Specifications contained in Appendices A and B, as1 revised through Amendment No. 5_
,.are l
hereby incorporated in the _ license. The licenses shall operate.the facility in accordance with the Technical
- Speci fications.
-This'1f cense anendment is effective as.of the date of its f ssuance.
3.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Clark, Chief.
Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to-the Technical Specifications-Date of Issuance: July 10, 1981 9
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- ATTACHMENTTOLICENSE-AsEhDMENT-
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AMENDMENT NO.251 TO FACILITY OPERATING LICENSE-NO. OPR-24 c' '
DOCKET N0; 50-266"
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[ Revise Appendixi AT 3 followsi-
' Remove Pages Insert Pages
- 15. 3.'l -8 a 15.3.1-8a
- 15.3.1-17...
15.3.1 ! Table 15.3.1-1 Table 15.3.1-1 e
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. scheduled re= oval dat'esivill provide materials data represen:ative of about-10%,'[20%,'h0%,i 70%,f and 90% of the actual reactor ' vessel exposure anticipated -
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'during the' vessel =11fe.
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References s
(1). FSAR, Sectionf4.1.5
~
~ (2); a'estinghouse Electric. corporation,1WCAP-8739 '
y (3)l 'a'estinghouse Electric Corporation,.'a' CAP 8743
'(4); Westinghouse-Electric Corporation, WCAP-8738 2
i Unit 1 '- Amendment No.. 51 s
. Unit: 2 Amend =ent-No. 157 15.3.1-8a
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-MIN EM CONDI!!CNS FOR CRITICALITY Siecification:-
1.
. Except. during low 1 power physics tests, the reactor shall not'be =ade
~
critical"unless.the moderator te=perature coefficient is negative.
2.
'In no case shall the'teactor be =ade critical (other than for the' a
purpese of low level physics tests)'~to theLleft of the reactor core criticality curve ' presented in. Figures 15.3.1-1 for Unit 1 and
~
- 15.3.1-3 for Udit 2.
7
- hen-the reactor coolant te:perature is in a range where the =oderator-3.(
temperature coef ficient is positive, the recctor shall be suberitical by an amount equal.o or greater than the potential reactivity insar-tion-due to depressurization.
'4.
The reactor shall be maintained subcritical by at least 1% akg until nor:al water-level is established in the pressuricer.
Basis:
'During-the early part of the initial fuel cycle, the moderator temperature-coefficient is calculated to be slightly positive at coolant temperatures below the power operating range.(1)(2)
Ths moderator coefficient at low te=peratures will be most positive at the beginning of life of the initial
' fuel-cycle, when the boron concentration in the coolant is the greatest.
Later.in the life of she fuel cycle, the boron concentrations in the coolant
. ill'be lower' and the moderator coef ficients will be either less positive or-w will be negative. At all times, the =oderator coefficient is negative in the power operating range. '1)(2)
Suitable physics =easurements of moderator
/
coefficient of-reactivity will be =ade as part of the startup program to verify analytic predictions.
Unic l - Amendment No. 51 l
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1 Uni ( 2 A=endbeng.o.
57-15.3.1-17 A.
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- O.e actual removal J.ates will be adjusted to coincide with the 01:sest scheduled plant refueling cutage or majer reaca plant shutd:vn.
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Unit 1 --Amendnent No. 51
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'WISCCNSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301_
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POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57.
License No. OPP-27
~
1.
The. Nuclear Regulatory Ccomission.(the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Pcwer Company (the licensee) dated March 31,1981, ' complies with the standards and requirements of.the Atomic Energy Act of 1954, as amended (the Act).and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate ~ in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance -(i) that' the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and-(ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and-security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the 'lic'ense' is amended b) changes to the Technical l Specifications as. indicated in the attachment to this license
. amendment,.and ' paragraph 3.8 of Facility Operating License
.No. OPR-27 is hereby amended to read as, follows:
B.. Technictl ' Specifications
>The Technical Specifications ' contained in Appendices L A and.B, as revised through Anendmant No. g7, are
~hereby' incorporated in the license.
The licensee shall LoperateL the facility in accordance with the Technical Specifications.
~
!3. ^This license anend ent is effective.as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION D
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Robert A..' Clark, Chief
~0perating Reactors Branch #3 -
Oivision of Licensing Attschment:
Changes to the Technical Specifications
-Date of Issuance:
July 10,-1981 3
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-ATTACHMENT T0-Li ENSE AMEN 3 MENT v 7.c
.c-l A!!EN0f TENT NO.- 57 TO FACILITY OPERATING LICENSE NO.~ 0PR-27
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. DOCKET NO. 50-301 sg, 5.-
- levise Appendix' Af as.fo11cws:
A Insert Pages_
Remove Pages 15.3.1-7 15.3.1 7 15.3.1-8a
~ 15. 3.1 -8 a -
15.3.1 15.3.1-17 Table'15.3.1-2.
Table 15.3.1-2,
' Figure 15.3.1-3 Figure 15.3.1-3 Figure 15.3.1-4 Figure 15.3.1-4 e
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neutron exposure of the' vessel is computed to be 3.9-x 10 ' neutrins/em 1
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for pf This is'the 40 years of operation at 1518 MWe and 80 percent. load factor.
exposure exp.,;ted at'the-inner reactor. vessel wall.
Hovaver, the neutron flhence used-to predict _the' ART shif t = is the one-quarter shell ' thickness NDT neutron' exposure. The relationship between fluence'at the vessel ID wall.and the fluence at the;one-quarter;and three-quarter shell thickness locations has been calculated and is presented in. References 3 and 4 as a function of Effective Full Power Years. These curves are used to determine. the fluence at be revised.
ithe location' of ' interest when the heatup and cooldown curves are to Once the fluence 'is determined, the temperature shif t used in revising the heatup ane cooldown curves.is obtained from the temperature versus fluence curves (the 0.25% copper Base, 0.20% k* eld line for Unit 1 and the 0.30% Copper base, 0.25% Weld line for Unit 2) also contained in References 3 and 4.
These curves are used bc cause they are based upon a substantial amount of experimental data and represent the results of the chemical analysis' of 'the weld metal in the reactor vessels.
The heatup and cooldown curves prew nted in Figures 15.3.1-1 and 15.3.1-2 (Unit 1) and 15.3.1-3 and 15.3.1-4 (Unit 2) were calculated based on the above information and the methods of ASME Code Section III (1974 Edition)
Appendix C, " Protection Against Nonductile Failure", and are : applicable up to
. the_ operational exposure indicated on the figures. Corrections for possible instrumentation inaccuracies have been incorporated into these curves. The temperature correction is made by adding the temperature error (24'F, Unit 2) l
. to the' required ' temperature and the pressure correction is made by subtracting l
the pressure error (64 psi, Unit 2) from the required pressure. These correc-tions ad',ust the curves in the conservative direction.
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9 scheduled removal dates will provide esterials data representative of abou.
10%, 207., 50%, 70%, and 90% of the actual reactor vessel exposure anticipated l
during the vessel life.
References (1)
FSAR, Section 4.1.5 (2) Westinghouse Electric Corporation, WCAP-8739 (3) Westinghouse Electric Corporation, WCAP-8/43 (4) Westinghouse Electric Ccrporation, WCAP-8738 Unit 1 - Amendment No. 51 Unit 2 - Amendment No. 57 15.3.1-Sa n
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li 7-FE MINDit'4 CONDITf 0NS FOR' CRITICALITY -
.jpecification:
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t he made
-1.
' Except during low power physics' tests,. the reactor shall not critical unless the moderator temperature coefficient is negative.
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In:no case shall. the reactor.be made critical (other' than for the spurpose of low level physics tests).co the lef t of the; reactor core criticality' curve presented in. Figures 15.3.1-1 for Un'it-1 and 15.3.1-5 for Unit 2.
'3.
.When che' reactor coolkat temperature is in a range where the moderator temperature coefficient is positive,~.the reactor'shall be suberitical.
by an amount equal to or greater than the potential reactivity inser-tion due t'o depressurization.
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The reactor shall be maintained subcritical by at least normal water level is established in the pressurizer.
Basis:
During the early part of the initial fuel cycle, the noderator temperature coef ficient is calculated to be-slightly positive at coolant temperatures below the power operating range.( }( )
The moderator coefficient at low temperatures will be most positive at the beginning of life of the initial fuel cycle, when the boron concentration in the coolant is the greatest.
Later in the life of the fuel cycle, the boron concentrations in the coolant will be lower and the moderator coefficients will be either less positive or
.will be-negative. At all times, the modcrator coef ficient is negative in the power operating range.(1)( ) - Suitable ph / sics =easurements of moderator coefficient of reactivity will be made as part of the startup program to verify analytic predictions.
~
Unit l - Amendment No. 51 Unit 2
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.t:endment No. 57 L.
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