ML20030D812
| ML20030D812 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/28/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20030D813 | List: |
| References | |
| TAC-43744, TAC-43745, NUDOCS 8109160304 | |
| Download: ML20030D812 (10) | |
Text
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- atrugh UNITED STATES g,'*
NUCLEAR REGULATORY COMMISSION 3
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wAsHiNorou. c. c. 20sss WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POIN'i BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE l
. Amendment No. 53 License No. DPR-24 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 witn the standards l
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; i
l 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 1
I 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 tu the common defense and security or to the health and safety of the public; i
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirem'ents have been satisfied.
l 0109160304 81 8
PDR ADOCK 050 66 P
_OR l
2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specification!. contained in Appendices A and B, as revised through Amendment No. 53, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
>FOR THE NUCLEAR REGULATORY COMMISSION be.
4
(
bert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications i
Date of 1ssuance: August 23, 1981
(
L.
' ATTACHMENT TO LICENSE AMEN 0MENTS AMEN 0 MENT NO. 53 TO FACILITY OPERATING LICENSE NO. OPR-24 DOCKET NO. 50-266 Revise Appendix A as follows:
Remove Pages Insert _Pages 15.3.1-7 15.3.1-7 Figure 15.3.1-1 Figure 15.3.1-1 Figure 15.3.1-2
. Figure 15.3.1-2 O
19
-2 neutron exposure of the vessel is computed to be 3.9 x 10 neutrons /cm for 40 years of operation at 1518 MWt and 80 percent load factor.(2)
This is the exposure expected at the inner reactor vessel wall. However, the neutron fluence 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 the location of interest when the heatup and cooldown curves are to be revised.
Once the fluence is determined, the temperature shift used in revising the heatup anc cooldown curves is obtained from the temperature versus fluence (the 0.25% Copper Base, 0.20% Weld line for Unit 1 and the 0.30% Copper curves base 0.25% Weld line for Unit 2) also contained in References 3 and 4.
These curves are used because 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 prcsented 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 G, " 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) to the required temperature and the pressure correction is uade by subtracting the pressure error (64 psi)'from the required pressure. These,rrections adjust the curves in the conservative direction.
Unit No.1 - Amendment No. 24, 53 Unic No. 2 - Amendment No. 57, gg 15.3.1-7
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j UNITED STATES y,
- NUCLEAR REGULATORY COMMISSION o
,I waswiwoTow. o. c.20s4,
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4,.....s WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. ?
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.59 License No. DPR-27 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 Commissicn'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.
1
c
~
, 2.
Accordingly,_ the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the. Technical Specifications. -
3.
This license amendment is effective as of the date of its issuance.
FOR THE HUCLEAR REGULATORY COMMISSION F
H skRobert A. Clark, Chief
/
Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 28, 1981 4
r-ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NO. 50-301 Revise Appendix A as follows:
Remove Page Insert Page 15.3.1-7 15.3.1-7 W
c.
9
i s
1 neutronexposureofthevesseliscomputedtobe3.9x10kneutrons/cm for 40 years of operation at 1518 MWt and 80 percent load factor.( ) This'is the exposure expected at the inner reactor vessel wall. However, the neutron fluence used to predict the ART shif t is the one-quarter shell thickn2ss 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 the location of interest when the heatup and cooldown curves tre to be revised.
Once the fluence is determined, the teaperature shift used in revising the heatup ano cooldown curves is obtained from the temperature versus fluence curves (the 0.25% Copper Base, 0.20% Weld line for Unir 1 and the 0.30% Copper base, 0.25% Weld line for Unit 2) also cor.tained in References 3 and 4.
These curves are used because they are based upon a substantial amount of experimental data and represent the results of the chem *ical analysis of the j
weld metal in the reactor vessels.
The heatup and cooldown curves presented 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 te=perature error (24*F) to the required temperature and the pressure correction is made by subtracting the pressure error (64' psi) from the required pressure. These corrections adjust the curves in the conservative direction.
Unit No. l. - Amendment No. '24, 53 Unit No. 2 - Amendment No. 57, gg 15.3.1-7
_..