ML20138H885

Amend 173 to License DPR-30,modifying Section 5.3.A, Design Features of TS to Reflect ATRIUM-9B Design & Would Include Various Siemens Power Corp Topical Repts in Section 6.9.A.6 to Reflect Mechanical Design Criteria for Fuel & Repts

ML20138H885
Person / Time
Site:	Quad Cities
Issue date:	05/02/1997
From:	Capra R NRC (Affiliation Not Assigned)
To:
Shared Package
ML20138H887	List: ML20138H885 ML20138H892
References
NUDOCS 9705070314
Download: ML20138H885 (5)

Text

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UNITED STATES g

.j NUCLEAR REGULATORY COMMISSION i

WASHINGTON, D.C. 2066t@0N l

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COMMONWEALTH EDISON COMPANY l

AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 l

OUAD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 173 License No. DPR-30 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated April 29, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the i

Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; t

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 l

E.

The issuance of this amendment is in accordance with 10 CFR i

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 l

Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby l

amended to read as follows:

9705070314 97o502 PDR ADOCK 05000265 PDR

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B.

Technical Soecifications The Technical Specifications contained in Appendices A and B, as l

revised through Amendment No. 173, are hereby incorporated in the l

license. The licensee shall operate the facility in accordance t

l with the Technical Specifications.

i 3.

This license amendment is effective as of the date of its issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION I

v nRober A. Capra, Di ector Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

i Changes to the Technical Specifications

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1 Date of Issuance:

May 2, 1997

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l ATTACHMENT TO LICENSE AMENDMENT NO. 173 l

l FACILITY OPERATING LICENSE N0. DPR-30 I

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DOCKET NO. 50-265 f

Revise the Unit 2 Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised Unit 2 pages l

are identified by the captioned amendment number and contain marginal lines l

indicating the area of change.

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REMOVE INSERT 5-5a

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6-16a i

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l REACTOR CORE 5.3 5.0 DESIGN FEATURES 5.2 REACTOR CORE Fuel Assemblies i*

5.3.A The reactor core shall contain 724 fuel assemblies'. Each assembly consists of a l

matrix of Zircoloy clad fuel rods with an initial composition of natural er slightly enriched uranium dioxide as fuel material. The assemblies may contain water rods or water boxes. Limited substitutions of Zircaloy or ZlRLO,in accordance with NRC-approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel j

safety design bases'. A limited number of lead test assemblies that have not i

l completed representative testing may be placed in non-limiting core regions.

Control Rod Assemblies l

5.3.B The reactor core shall contain 177 cruciform shaped control rod assemblies. The 1

control material shall be boron carbide powder (8 C) and/or hafnium metal. The 4

control rod assembly rhall have a nominal axial absorber length of 143 inches.

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• All changes for Amendment No.173 apply to Unit 2 only.

1 ATRIUM-9B fuel is only allowed in the reactor core in Operational Modes 3,4 and 5, and with no more than one control rod withdrawn.

2 The design bases applicable to ATP. LUM-9B fuel are those which are applicable to Operational Modes 3,4, and 5.

QUAD CITIES - UNIT 2 5 Sa Amendment No.173

R: porting R:quir:m:nts 6.9 i

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i ADMINISTRATIVE CONTROLS y

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(3)

Commonwealth Edison Topical Report NFSR-0085, Supplement 1, l

• Benchmark of BWR Nuclear Design Methods - Quad Cities Gamma Scan l

Comparisons," (latest approved revision).

l (4)

Commonwealth Edison Topical Report NFSR 0085, Supplement 2, j

• 8enchmark of BWR Nuclear Design Methods - Neutronic Licensing Analyses,"

1 (latest approved revision).

(5)

Advanced Nuclear Fuels Methodology for Boiling Water Reactors, XN-NF l 19(PHA), Volume 1 Supplement 3, Supplement 3 Appendix F, and j

Supplement 4, Advanced Nuclear Fuels Corporation, November 1990.

(6)

Commonwealth Edison Topical Report NFSR-0091, " Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods", Revision 0, Supplements 1 and 2, December 1991, March 1992, and May 1992, l

i respectively; SER letter dated March 22,1993.

(7)

Generic Mechanical Design Criteria for BWR Fuel Designs, ANF-89-98(P)(A) i Revision 1, and Revision 1 Supplement 1, Advanced Nuclear Fuels l

Corporation, May 1995.

4 (8)

Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced i

Nuclear Fuels 9X9 IX and 9X9 9X BWR Reload Fuel, ANF-89-014(P)(A),

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Revision 1 and Supplements 1 and 2, Advanced Nuclear Fuels Corporation, October 1991.

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c.

The core operating limits shall be determined so that all applicable limits (e.g., fuel 3

thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional j

Administrator and Resident inspector.

f 6.9.B Special Reports i

1 Special reports shall be submitted to the Regional Administrator of the NRC Regional l

Office within the time period specified for each report.

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• All chan9es for Amendment No.173 apply to Unit 2 only.

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OUAD CITIES - UNIT 2 6-16 a.

Amendment No.173 i

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