ML20141E161
| ML20141E161 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/16/1997 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141E164 | List: |
| References | |
| NUDOCS 9705200348 | |
| Download: ML20141E161 (8) | |
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p a ciouqk UNITED STATES y
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NUCLEAR RESULATORY COMMISSION ff WASHINGTON, D.C. 20066 4001
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 159 License No. OPR-19 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated June 20, 1996, as supplemented December 30, 1996, and March 5, 1997, 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 Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:
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(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.159, are hereby incorporated in the license. The licensee shall operate the facility in accordance l
with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION n F. Stang enior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 16, 1997 1
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i UNITED STATES NUCLEAR RE2ULATORY COMMISSION WASHINGTON, D.C. 20066 4 001 y.....)
COMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated June 20, 1996, as supplemented December 30, 1996, and March 5, 1997, 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:.
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B.
Technical Soecifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 154, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its issuance and I
shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
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6 onF.Stang,(eniorProjectManager Project Directorate III-2 i
Division of Reactor Projects - III/IV l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 16, 1997 i
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ATTACHMENT TO LICENSE AMENDMENT NOS. 159 AND 154 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 Revise the Appendix A Technical Specifications by renoving the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment numbers and contain marginal lines indicating the area of change.
REMOVE INSERT 5-5 5-5 6-15 6-15 6-16 6-16 f
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REACTOR CORE 5.3 i /
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DESIGN FEATURES 5J REACTOR CORE Fuel Assemblies -
5.3.A The reactor core shall contain 724 fuel assemblies'. Each assembly consists of a l
matrix of Zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material. The assemblies may contain water rods or a water box. Limited substitutions of Zircaloy or ZlRLO or stainless steel filler rods for fuel rods, 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 3
analyzed with applicable NRC staff-approved codes and methods, and shown by tests 2
or analyses to comply with all fuel safety design bases. A limited number of lead l
test assemblies that have not completed representative testing may be placed in non-limiting core regions.
i Control Rod Assemblies 5.3.B The reector core shall contain 177 cruciform shaped control rod assemblies. The control material shall be boron carbide powder (B C) and/or hafnium metal. The control rod assembly shall have a nominal axial absorber length of 143 inches.
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ATRIUM-98 fuel with exception of lead test assemblies is only ellowed in the reactor core in operational Modes 3,4 and 5, and with no more then one control rod withdrawn.
j The design bases applicable to ATRIUM-98 fuel are those which are applicable to operationel Modes 3,4, and 5.
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DRESDEN - UNITS 2 & 3 55 Amendment Nos. 159 & 154
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Riporting R3quircments 6.9 I
p' 9 ADMINISTRATIVE CONTROLS j
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The analytical methods used to determine the operating limits shall be those previously reviewed and approved by the NRC in the latest approved revision or supplement of topical reports:
(1) ANF-1125(P)(A), " Critical Power Correlation - ANFB."
(2) ANF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors."
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(3) XN-NF-79-71(P)(A), " Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors."
(4) XN-NF-80-19(P)(A), " Exxon Nuclear Methodology for Boiling Water Reactors."
l (5) XN-NF-85-67(P)(A), " Generic Mechanical Design for Exxon Nuclear Jet Pump Boiling Water Reactors Reload Fuel."
(6) XN-NF 8122(P)(A), " Generic Statisitical Uncertainty Analysis Methodology."
l (7) ANF-913(P)(A), "CONTRANSA2: A Computer Program for Boiling Water Reactor Transient Analysis."
(8) Commonwealth Edison Company Topical Report NFSR-0091, " Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods", and associated Supplements on Neutronics Licensing Analyses (Supplement 1) and La Salle County Unit 2 Benchmarking (Supplement 2).
l (9) ANF-8914(P)(A), Advanced Nuclear Fuels Corporation Generic Mechanical j
Design for Advance Nuclear Fuels Corporation 9x9-IX and 9x9-9X BWR Reload Fuel, Revision 1 and Supplements 1 and 2, Advanced Nuclear Fuels
- Corporation, October 1991.
(10) ANF-89 98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs, Revision 1 and Revision 1 Supplement 1, Advanced Nuclear Fuels Corporation, May 1995.
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l i-DRESDEN - UNITS 2 & 3 6-15
. Amendment Nos. 159 & 154
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v Rsporting Requirements 6.9 l l
. ADMINISTRATIVE CONTROLS The core operating limits shall be determined so that all applicable limits (e.g., fuel c.
thermal-mechanical limits, core thermal-hydraulic lirsits, ECCS limits, nuclear limits such as shutdown margin, and transient and acciderd analysis '.imits) of the safety analysis are met. The CORE OPERATING LIMITS REFORT, ine:udirra any mid-cycle l.
revisions or supplements thereto, shall be provided upon isr;ance, for each reload -
cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident inspector.
6.9.8 Special Reports f
Special reports shall be submitted to the Regional' Administrator of the NRC Regional Office l
within the time period specified for each report.
l 6.10 IINTENTIONALLY LEFT BLANK 1 1
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J DRESDEN - UNITS 2 & 3 6-16 Amendment Nos.159.& 154)
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