ML20078L938
| ML20078L938 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/17/1983 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078L942 | List: |
| References | |
| TAC-48929, TAC-48930, NUDOCS 8310240122 | |
| Download: ML20078L938 (7) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g'
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACli NUCLEAR PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. DPR-24 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 30, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.
There is reasonable assurance (1) that the activ'ities 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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1 8310240122 831005 PDR ADOCK 05000266 P
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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:
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B.
Tech'nical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
77, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This 1.icense amendment is effective 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ames R. Miller, Chief.
j Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 17, 1983 t
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UNITED STATES 3
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WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. OPR-27 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 30, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.
DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Apoendices A and B, as revised through Amendment No. 81
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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ames R. Miller, Chief perating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 17, 1983
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 77 TO FACILITY OPERATING LICENSE N0. DPR-24 AMENDMENT N0. 81 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NO. 50-266 AND 50-301 Revise Appendix A as follows:
Remove Pages Insert Paaes 15.3.1-3 15.3.1-3 15.5.4-1 15.5.4-1 e
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5.
Pressurizer Power Operated Relief Valves (PORV) and FORV 31ock Valves a.
Two PORVs and their associated block valves shall be operable.
(1) If a PORV is inoperable due to leakage in excess of that allowed
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in Specification 15.3.1.D, the PORV shall be restored to an
. operable condition within one hour or the associated block valve shall be closed.
(2) If a PORV is inoperable due to a channel functional test failure, l,
the associated PORV control switch shall be placed and maintained in the closed position or the associated block valve shall be closed within one hour.
(3) If a PORV block valve is inoperable, the block valve shall be
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restored to an operable condition within one hour or the block valve shall be closed with power removed from the block valve; otherwise the unit shall be in hot shutdown within the next six hours.
6.
The pressurizer shall be operable with at least 100 KW of pressurizer heaters available and a water level greater than 10% and less than 95%
during steady-state power operation. At least one bank of pressurizer heaters shall be supplied by an amergency bus power supply.
Basis When the boron concentration of the reactor coolant systen is to be reduced, the process must be uniform to prevent sudden reactivity changes in the reactor. Mix-ing of the reactor coolant will be sufficient to maintain a uniform boron concen-tration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place. The residual heat removal pump will circulate the primary system volume in approximately one-half hour.
The pressur-izer is of little concern because of the lower pressurizer volume and because pressurizer boron concentration normally will be higher than that of the rest of the reactor coolant.
Specification 15.3.1.A.1 requires that a sufficient number of reactor coolant pumps be operable to provide core cooling in the event a loss of power occurs. The flow provided in each case will keep DNBR well above 1.30 as discussed in FFDSAR, Section 14.1.9.
Therefore, cladding damage and release of fission products to the re'accor Heat transfer analyses ( } show that reactor heat equivalent coolant will not occur.
to 10% of rated power can be removed with natural circulation only; hence the specified upper limit of 1% rated power without operating pamps provides a subctan-tial safety factor.
Item 14.3.1.A.l.c. (2) permits an orderly reduction in power if a reactor cools.nt pump is lost during operation between 10% and 50% of rated power.
15.3.1-3 Unit 1 _ Amendment No. 55, 56,, 77
15.5.4 FUEL STORAGE j
Applicability Applies to the capacity and storage arrays of new and spent fuel, 0
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'o define those aspects of fuel storage relating to prevention of criticality in fuel storage areas.
Specification 1.
The new fuel storage and spent fuel poc1 structures are designed to withstand the anticipated earthquake loadings as Class I structures.
The spent fuel pool has a stainless steel liner to ensure against loss of water.
2.
The new and spent fuel storage racks are designed so that it is impossible to store assemblies in other than the prescribed storage locations.
The fuel is stored vertically in an array with sufficient center-to-center. distance between assemblies to assure K,gf < 0.95 with the storage pool filled with unborated water and with the fuel loading in the assemblies limited to 44.8 grams of U-235 per axial centimeter of fuel assembly. An insp2ction area shall allow rotation of fuel assemblies for visual inspection, but shall not be used for storage.
3.
The spent fuel storage pool shall be filled with borated water'at a concentration of at least 1800 ppa boron whenever there are spent fuel assemblies in the storage pool.
4.
Except for the two storage locations adjacent to the designated slot for the spent fuel storage rack neutron absorbing material surveillance specimen irradiation, spent fuel assembly storage locations immediately adjacent to the spent fuel pool perimeter or divider wa'Is shall not be occupied by fuel assemblies which have been suberitical for less than one year.
References:
FSAR Section 9.3 15.5.4-1 Unit 1 - Amendment No. 35, 77 Unit 2 - Amendment No. 41, 81 m