ML20246F518

Amends 124 & 127 to Licenses DPR-24 & DPR-27,respectively, Clarifying Reporting Requirements for Operation of Overpressure Mitigating Sys & Deleting Two Schedular Commitments Already Implemented

ML20246F518
Person / Time
Site:	Point Beach   (DPR-24-A-124, DPR-27-A-127)
Issue date:	08/24/1989
From:	Hannon J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246F522	List: ML20246F518 ML20246F525
References
NUDOCS 8908310032
Download: ML20246F518 (8)

Text

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UNITED STATES -

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5 NUCLEAR REGULATORY COMMISSION p c. : 4 ;, f; WASHINGTON, D. C. 20555

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WISCONSIN ELECTRIC POWER COMPANY' DOCKET NO. 50-266 POINT BEACH NUCLEAR' PLANT, UNIT NO.'1 I

AMENDMENT TO FACILITY OPERATING LICENSE.

Amendment' Ho. 124 License-No'. DPR-24.

.lt The' Nuclear Regulatory Comission (the Comission) h'as found that:

A.

The application for amendment by Wisconsin Electric Power Company

.(the: licensee)'datedApril'26,-1989 complies with the standards-and requirements of the Atomic Energy Act of 195a, as amendec (the.

Act), and the Comission's rules and regulations ' set forth iti 10

.CFR Chapter I; B.

The facility will operate in conformity with the anoli;2 tion, the provisions of the Act, and the rules.and regulations sr *,he Comission;

)

C.-

There is reasonable assurance (i) that the activitier authorized <

H 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 issuarce of this coendment will not be inimical to.the comon defense and security or to the-health and safety of the public; and 4

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 l

of the Comission's regulations and all applicable requirements have-been satisfied.

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1 890B310032 090824 PDR ADDCK 05000266' P

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Accordingly, the license is anended 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 Specifications contained in Appendices A and B, as revised through Amendment No.124, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license anendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 20 days from the date of issuance.

FOR THE NULLEAR REGULATORY COMMISSION b.

John H. Hannon, Director b Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 24, 1989

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UNITED STATES j

NUCLEAR REGULATORY COMMISSION g-l Ta j,

WASHINGTON, D. C. 20555

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1 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 l

l POINT BEACH NUCLEAR PLANT, UNIT NO. 2 1

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.127 License No. DPR-27 1.

The Nuclear Regulatory Comission (the Comissien) has found that:

A. -

The application for amendment by Wisconsin Electric Power Company (the licensee) dated April 26, 1989 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 Conraission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the hecith 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 rot be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

~.

2.

Accordingly, the license is amended by changes to the Technical i

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:

l l

B.

Technical Specifications The Technical Specifications contained in Appendices A and S, as revised through Amendment No.127, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 20 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION John N. Hannon, Director b Project Directorate 111-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 24, 1989 l

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ATTACHMENT TO LICENSE AfiENDMENT N05.124 AND 127

.TO FACILITY OPERATING LICENSE NOS. DPR-24 AND.DPR-27 i

DOCKET NOS. 50-266 AND 50-301 P,evise 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 marginal lines indicating the area of change.

REMOVE INSERT Page 15.6.9-4 Page 15.6.9 Table 15.3.5-1(Page2of2)

Teble15.3.5-1(Page2of2)

Table 15.7.4-2 (Continued)

Table 15.7.4-2(Continued)

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L; 15.6.9.2 : 0nique Reporti.1g Requirements The following written reports shall be submitted to the Director,.

L0ffice of Nuclear Reactor Regulation, USNRC:

- A.

Integrated Leak Rate Test Each integrated leak test shall be the subject of.a summary technical report, including results of'the local leak rate.

tests'and isolation valve leak rate tests since the last report. The report'shall include' analysis and interpretations-j of the results which demonstrate compliance with specified leak rate limits.

B.

Poison Assembly Removal From Spent Fuel Storage Racks Plans for removal of any poison assemblies from the spent

-fuel storage racks shall be reported and described at least' 14 days prior to the planned activity. Such report shall describe neutron attenuation testing for any replacement poison ~ assemblies, if applicable, to confirm the presence of boron material.

C.

Overpressure Mitigating System Operation In the event the overpressure mitigating system (power operated relief valves in the low temperature overpressure protection mode) or residual heat removal system relief valves are operated to relieve a pressure transient which, by licensee's evaluation, could have resulted ir. an overpressurization incident-had the system not been operable, a special report shall be prepared and submitted to the Commission within 30 days.

The report shall describe the circumstances initiating the transient, the effect of the system on the transient and any corrective action necessary to prevent recurrence.

15.6.9-4 Unit 1 - Amendment No.19,EE.97,702,124 Unit 2 - Amendment No. 63,29,JDJ,705.127

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