ML20216G551
| ML20216G551 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/03/1997 |
| From: | Grundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216G556 | List: |
| References | |
| NUDOCS 9709150225 | |
| Download: ML20216G551 (7) | |
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t UNITED STATES j
j-NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30046 0001 4 %...
WISCONS.LN ELECTRIC POWER COMPANY POCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO.1 AMENDMENT,,TO FACILIT/ OPERATING LICENSE Amendment No.178 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 April 14,1997, 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 atSvities 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 issum.1ce 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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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 Specificatione contained in Appendices A and B, as revised through Amendment No.178, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the dat; of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION va[w MLu1W Linda L. Gundrum, Project Manager Project Directorate lll 1 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation Adachment: Changes to the Technical Specifications Date of issuance:
September 3, 1997 L
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g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. seseHeM WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 6MBDMENT TO FACILITY OPERATING LICENSE Amendment No.182 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 April 14,1997, 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 endani;ering the hea'.h and safety of the public, and (ii) that such activities will be conduct 6d 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 satisfed, i
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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-27 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.182, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
5.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION sukk k LCbLuw Linda L. Gundrum, Project Manager Project Directorate lil 1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Attachtnent: Changes to the Technical Specifications Date of issuance:
September 3, 1997 j
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-e ATTACHMENT TO L) CENSE AMENDMENT NOS.178 AND 182 TO FACILITY OPERATING LICENSE NOS. DPR 24 AND DPR 27 DOCKET NOS. 50 266 AND 50 301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain verticallines indicating the area of change.
REMOVE INSERT 15.3.1-1 15.3.1-1 15.3.1 3c 15.3.1-3c 9
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.o 15.3-LIMITING CONDITIONS FOR OPERATION 15.3.1-. _ REACTOR COOLANT SYSTEM.
Acolicabihty Applies to the operating status of the Reactor Coolant System Obiective To specify those limiting conditions for operation of the Reactor Coolant System which must be met to ensure safe reactor operation.
Soecification A.
OPERATIONAL COMPONENTS
- 1.. - Coolant Pumps
- a.
When the reactor is critical, both reactor coolant pumps shall be in operationi
'(1) If one or both reactor coolant pumps cease operating, the reactor shall be
- placed in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
When the reactor is subcritical and the average reactor coolant temperature is greater than 350 Y, except for tests, at least one reactor coolant pump shall be in operation.
(1) Both reactor coolant pumps may be doenergized provided:
a.
No operations are permitted that would cause dilution of the reactor coolant system boron concentration,
- b. - Core outlet temperature is maintained at least 10 7 below saturation temperature,- and c.
The reactor trip breakers are open.
c.
At least one reactor coolant pump or residual heat removal system shall be in operation when a reduction is made in the boron concentration of the reactor coolant.
2.
- si One steam generator shall be operable whenever the average reactor coolant temperature is above 350 T.
3.
Components Required for Redundant Decay Heat Removal Capability *-
s.- _ Reactor coolant temperature less than 350 Y and greater than 140 T.
]
' (1). At least two of the decay heat removal methods listed shall be operable.
(a) Reactor Coolant Loop A, its associated steam generator and either reactor coolant pump.
(b)' Reactor. Coolant Loop B, its associated steam generator and either reactor -
coolant pump
- Applicable only when one or more fuel assemblies are in the reactor vessel.
. Unit 11 Amendment 403,~ 178 Unit 2 - Amendment 406,- 182 15.3.1-1 l
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-items 15.3.1.A.1.s permits an orderly reducSon in power if a reactor coolant pump is lost during operation at less than ur equal to C0% of rated power, Above 50% power, an automatic reactor trip will occur if either pump is lost. The power to-flow ratio will be maintained equal to or less than 1.0, which ensures that the minimum DNB ratio increases at lower flow since the maximum enthalpy rise does not increase above its normal full-flow maximum value.*
Specification 15.3.1.A.3 provides limiting conditions for operation to ensure that redundsney in decay heat removal methods is provided. A single reactor coolant loop with its associated steam generator and a reactor coolant pump or a single residual heat removal loop provides sufficient heat removal capacity for removing the reactor core decay heat; however, single failure considerations require that at least two decay heat removal methods be available.
Operability of a steam generator for decay _ heat removal includes two sources of water, water levelindication in the steam generator, a vent path to atmosphere, and the Reactor Coolant System filled and vented so thermal convection cooling of the core is possible, if the steam generators are not available for decay heat removal, this Specification requires both residual heat removal loops to be operable unless the reactor system is in the refueling shutdown condition with the refueling cavity flooded and no operations in progress which could cause an increase in reactor decay heat load or a decrease in boron concentration. In this condition, the reactor vessel is essentially a fuel storage pool and removing a RHR loop from service provides conservative conditions should operability problems develop in the other RHR loop. Also, one residual heat removal loop may be temporarily out of service due to surveillance testing, calibration, or inspection requirements. The surveillance procedures follow administrative controls which allow for timely restoration of the residual heat removal loop to service if required.
Additionally, with reactor coolant temperature between 350 'F and 140 'F, all operating decay heat removal pumps (either reactor coolant pumps or residual heat removal pumps) are allo.wed to be deenergized for a short time (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) with the stipulation that boron dilution activities are not allowed and that core outlet temperature remain 10 'F below saturation.
' Unit 1 - Amendment No. 46,178 Unit 2 - Amendment No. 40,182 15.3.1-3c