ML20137L476
| ML20137L476 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/02/1997 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137L479 | List: |
| References | |
| NPF-37-A-086, NPF-66-A-086 NUDOCS 9704070241 | |
| Download: ML20137L476 (8) | |
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'4 UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30eeMo01
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COPMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 86 License No. NPF-37
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1.
The Nuclear Regulatory Consiission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 5,1996, as supplemented February 27 and March 30, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the C maission'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, i
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There is reasonable assurance (i) that the activities authorized C.
by this amendeant 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; 4
and E.
The issuance of this amendment is in accordance with 10 CFR l
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 2.C.(2) of Facility Operating License No. NFF-37 is hereby amended to read as follows:
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I 9704070241 970402 PDR ADOCK 05000454 P
PDR l
(2)
Technical Snecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 86 and the Environmental Protection Plan 1
contained in Appendix 8, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COPMISSION h George F. Dick, Jr., 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:
April 2, 1997 i
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION I C WASHINGTON. D.C. 2006dHmot 4,.....,o COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. NPF-66 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 5, 1996, as supplemented February 27 and March 30, 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 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 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 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
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(2)
Technical Snecifications The Technical Specifications contained in Appendix A (NUREG-lll3),
as revised through Amendment No. 86 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 45 days.
L FOR THE NUCLEAR REGULATORY COMMISSION Wf George F. Dick, Jr., Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
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Specifications Date of Issuance: April 2, 1997 1
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ATTACHMENT TO LICENSE AMENDMENT NOS. 86 AND 86 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Panes Insert Paaes 3/4 9-13 3/4 9-13 5-5 5-5 5-Sa i
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t REFUELING OPERATIONS 3/4.9.11 WATER LEVEL /B0RON CONCENTRATION - STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.11 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks. The dissolved baron concentration of the water,in the storage pool shall be maintained at greater than or equal to 2000 ppm.
APPLICABILITY: Whene<er irradiated fuel assemblies are in the storage pool.
ACTION:
a.
With the water level requirements of the above specification not l
satisfied, suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas ard restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
With the boron concentration requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane i
operations with loads in the fuel storage areas and immediately take action to restore the dissolved boron concentration to within its limit as soon as possible.*
c.
The provisions of Specification 3.0.3 are not applicable.
l SURVEILLANCE RE0VIREMENTS 4.9.11 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool.
4.9.ll.a Boron concentration in the storage pool shall be determined to be greater than or equal to 2000 ppm at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
These requirements shall be in effect until December 31, 1997.
BYRON - UNITS 1 & 2 3/4 9-13 AMENDMENT N0. 86
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DESIGN FEATURES 5.6 FUEL STORAGE t
CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with I
r less than or equal to 0.95 when flooded with unborated water, which I
a k ' des a conservative allowance for uncertainties as-described in Section inclu of the UFSAR. This is ensured by controlling fuel assembly placement in each region as follows:
a.
REGION 1 1.
A nominal 10.32 inch north-south and 10.42 inch east-west, center-to-center distance is maintained between fuel assemblies placed.in the spent fuel storage racks.
1 2.
Fuel assemblies may be stored in this region with a) a maximum nominal initial U-235 enrichment of less than or equal to 4.2 weight percent, or b) a maximum nominal initial U-235 enrichment of 5.0 weight percent with sufficient Integral Fuel Burnable Absorbers present in each fuel assembly such that the maximum reference fuel assembly km is less than or equal to 1.470 at 68'F.
b.
REGION 2 1.
A nominal 9.03 inch center-to-center distance is maintained between fuel assemblies placed in the spent fuel storage racks.
2.
a)
Fuel assemblies may be stored in this region with a maximum nominal initial U-235 enrichment.of 1.6 weight percent with no burnup and up to 5.0 weight percent U-235 with a minimum discharge burnup as specified in Figure 5.6-1, or b)
Fuel assemblies with a maximum nominal initial U-235 enrichment of greater than 1.6 and less than or equal to 4.2 weight percent that do not meet the minimum burnup specified in Figure 5.6-1, shall be loaded in a checkerboard pattern for storage in this region.
5.6.1.2 The k,,, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 423 feet 2 inches.
Until December 31, 1997, the spent fuel storage racks shall be maintained of less than or equal to 0.95 when flooded with water containing with a K,,,
f 2000 ppm soluble boron.
a minimum o BYRON - UNITS 1 & 2 5-5 Amendment No. 86
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DESIGN FEATURES 5.6 ' FUEL STORAGE (continued)
CAPACITY-l 5.6.3 The spent fuel. storage pool is designed and shall be maintained with a storage capacity limited to no more than 2870 fuel. assemblies.
i 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT g
5.7.1. The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
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BYRON - UNITS 1 & 2 5-5a Amendment No. 86
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