ML20137L920

Amends 92 & 82 to Licenses DPR-39 & DPR-48 Respectively, Changing Specimen Capsule Withdrawal Schedule to Reflect Low Leakage Loading Patterns & 10CFR50,App H Requirements

ML20137L920
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	01/16/1986
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20137L889	List: ML20137L885 ML20137L920 ML20137M725
References
NUDOCS 8601280137
Download: ML20137L920 (7)

Text

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p ueg g jog UNITED STATES NUCLEAR REGULATORY COMMISSION n a wasmNotoN. o. c. 20sss

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COMMONWEALTH EDIS0N COMPANY -

DOCKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 -

AMENDMENT TO FACILITY OPERATING LICENSE Amendment NoS2 License No. DPR-39

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Comonwealth Edison Company (the licensee) dated August 19, 1985, 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 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.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:

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(2) Technical Specifications The Technical Specifications contained in Appendices -

A and B, as revised through Amendment No. 92 , 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 NU EA EGULATORY COMMISSION dQLjo Steven A. Varga, frector

, j PWR Project Directorate #3 Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuance: January 16,1986 i

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~ o NUCLEAR REGULATORY COMMISSION g wAsHWGTON, D. C. 20655 g, . . . . . ,e; ,

COMMONWEALTH EDISON COMPANY DOCKET N0. 50-304

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ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-48

1. The. Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Commonwealth Edison Company (the licensee) dated August 19, 1985, 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 reason %ble 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.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:

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(2) Technical Specifications The Technical Specifications contained in Appendices.

A and B, as revised through Amendment No. 82, 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 NUCLEAR REGULATORY COMMISSION f

Steven A(.

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/arga, Director PWR Project Directorate #3 Division of PWR Licensing-A

Attachment:

Charges to the Technical Specifications Date of Issuance: January 16., 1986

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 92- FACILITY OPERATING LICENSE NO. OPR-39 .

AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 ,

Revise Appendix A as follows:

Remove Pages Insert Pages

, 105 105 119 119 i

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l LIMITING CGriDITION FOR OPERAil0N SURVEILLANCE REQUIREMENT 3.3.4 4.3.4 D. Materials Irradiation Surveillance Specimen Inspection. (per unit)

Specimen capsules to be used in the reactor vessel material surveillance program shall be withdrawn during the refueling period either immediately preceeding or following the Effective

! full Power Years.(EIPY) of unit life as follows:

3 CAPSULE WITHDRAWAL SCHEDULE 1

, UNIT 1 j CAPSULE CAPSULE DESIGNATION REMOVAL TIME (EFPY) i REMOVED (1.16)

U REMOVED (3.52)

X REMOVED ( 5.17)

Y 8.5 W,5,V,Z STAND BY U_ WIT 2 CAPSULE CAPSULE DESIGNATION RIMOVAL TIME [EFPY)

U REMOVED (1.27)

T REMOVED (3.56)

Y 8.5 K STAND BY W.S.V,Z STAND BY i

105 Amendment No. 92 and 82 09f;30

Basis 4.3.4 The surveillance inspection program has ,

been developed to comply with Section Al of the ASME Boller and Pressure Vessel Code and applicable addenda as required i by 10 CFR 50, Section 50.55a(g), except where specific written reitef has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(1). The design of the plant, state of non-destructive testing technology, and access to areas ,

to be inspected require such relief.

The Reactor Vessel Material Surveillance Program 15 designed to evaluate the effects of radiation on the fracture

• toughness of reactor vessel steel based

on the transition temperature approach and the fracture mechanics approach.

10 CFR 50 Appendix H, paragraph II B.1 requires that the reactor vessel unterial surveillance program shall meet the requirements of ASTM E185-82 such that the surveillance capsules represent end-of-life fluences at the reactor vessel 1/4 and wall thicknesses.

Previous capsules were removed under Amendment Nos. 62 and 59. ,

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ng Amendment Nos. 92 and 82 09030 l

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