ML20247M012
| ML20247M012 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/20/1989 |
| From: | Shemanski P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247M017 | List: |
| References | |
| NUDOCS 8908010410 | |
| Download: ML20247M012 (10) | |
Text
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COMMONWEALTH EDISON COMPANY I
' DOCKET NO. 504456 BPAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. NPF-72 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the itcensee) dated January 3,1989,-supplemented January 24 and February 10, 1989, complies with the standards and requirements of theAtomicEnergyActof1954,asamended(theAct)andthe 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 tne Comission's regulations; D.
The issuance of this avendment will not be inimical to the comon defense and security r,r to the health and safety of the public; and E.
The issuance of thi: amendment is in accordance with 10 CFR Part 51 6
of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicted in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
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(2). Technical Specifications The Technical Specifications contained in Appendix A as revised through 1.aendment No. 20 and the Environmental' Protection Plan con-tained in Appendix B, 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.
FOR THE HUCLEAR REGULATORY COMMISSION
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Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects Attechment:
Changes to the Technical Specifications
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i ATTACHMENT TO LICENSE AMENDMENTS N05. 20 AND 20 FACILITY OPERATING LICENSE NOS. NPF-72-AND NPF-77 l. "J DOCKET NO. 50-456 AND 50-457 Revise Appendix A as follows:
Remove Pages Insert Pages 5-5 5-5' 5-Sa
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5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Akgff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a co.servative allowance for
. uncertainties as described in Section 9.1 of the FSAR.
This is based on spent fuel storage in Region 2 with enrichments'and burnup in accordance with Figure 5.6-1, or in a checkerboard pattern; and b.
A ncminal 10.32 inch' north-south and 10.42 inch east-west center to center distance between fuel assemblies placed in Region I spent fuel racks and a nominal 9.03 inch center to center distance between fuel assemblies placed in Region 2 spent fuel storage racks.
5.6.1.2 The k,ff 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 0 inches.
CAPACITY 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.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 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.
BRAIDWOOD - UNITS 1 & 2 5-5 Amendment No. 20
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. NPF-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 3,1989, supplemented January 24 and February 10, 1989, 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 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 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 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. NPF-77 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 20 and the Environmental Protection Plan contained in Appendix B, 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.
FOR THE NUCLEAR REGULATORY COMMISSION C?
Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications l
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ATTACHMENT TO LICENSE AMENDMENT NOS. 20 AND 20
.;F FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 j
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DOCKET NOS. 50-456 AND 50-457-
- Revise Appendix A as follows:
Reseve Pages -
Insert Pages 5-5 5-5 5-Sa' L
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DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Ak equivalent to less than or equal to 0.95 when flooded with eff unborated water, which includes a conservative allowance for uncertainties as described in Section 9.1 of the FSAR.
This is based on spent fuel storage in Region 2 with enrichments and burnup in accordance with Ficure 5.6-1, or in a checkerboard pattern; anc b.
A nominal 10.32 inch north-south and 10.42 inch east-west center to center distance between fuel assemblies placed in Region 1 spent fuel racks and a nominal 9.03 inch center to center distance between fuel assemblies placed in Region 2 spent fuel storage racks.
5.6.1.2 The k,ff for new fuel for the first core loading stored dry in Sie 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 0 inches.
CAPACITY 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.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 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.
BRAIDWOOD - UNITS 1 & 2 5-5 Amendment No. 20
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