ML20206G596

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Amends 108,108,101 & 101 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS Requirements for Spent Fuel Pool Inadvertent Draindown Elevation
ML20206G596
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 05/03/1999
From: Anthony Mendiola
Office of Nuclear Reactor Regulation
To:
Commonwealth Edison Co
Shared Package
ML20206G600 List:
References
NPF-37-A-108, NPF-66-A-108, NPF-72-A-101, NPF-77-A-101 NUDOCS 9905100073
Download: ML20206G596 (11)
v • d • e


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UNITED STATES j-j NUCLEAR REGULATORY COMMISSION o

a WASHINGTON, D.C. 30eeH001 COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. NPF-37 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated October 30,1998, complies with the standards and requirements of the Atomic Ene'rgy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; e

B.

The facility will operate in conformity with the at$lication, the provisions of the Act, and the rules and regulations of the Commiswun; 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:

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r, (2) _ Technical Soecifications The Technical Specifications contained in Appendix A as revised through i

Amendment No.108 and the Environmental Protection Plan contained in

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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.

1 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

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Attachment Changes to the Technical Specifications Date of Issuance: May 3, 1999 i

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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 i

BYRON STATION. UNIT NO. 2 j

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. NPF-66 j

1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated October 30,1998, 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; e

B.

The facility will operate h conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;

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C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the j

public, and (ii) that such activities will be conducted in c.ompliance 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 li, cense is amended by changes to the Technical Specifications as indicated in the aVachment 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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Technical Soecifications j

The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.108 and revised by Attachment 2 to NPF-66,

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and the Environmental Protection Plan contained in Appendix 0, both of whien were attached to License No. NPF-37, dated February 14,1985, are hereby I

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 q

Protection F'lan.

j 3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

FOR THE NUC, LEAR REGULATORY COMMISSION

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,/y/ s L. m y c,s lc nthony Mendicla, Chief, Section 2 3

Project Directorate ill 1

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Division of Licensing Project Management

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Attachment:

Changes to the Technical Specifications j

Date ofissuance:May 3,1999

4 ATTACHMENT TQ LICENSE AMENDMENT NOS.108 AND 108 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-86 QQCKET NOS. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the page identified below and inserting the attached page The revised page is identified by the captioned amendment number and contains marginallines Indicating the area of change.

Remove Paaes Insert Paaes 4.0-2 4.0'2

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m Design Features 4.0 DESIGN FEATURES (continued)

'4.3 Fuel Storage 4.3'1 Criticality The spent fuel stcrape racks are. designed and shall be maintained with:

ac Fuel assemblies-having a maximum U-235 enrichment of 5.0 weight percent; b.

k,y < 1.0 if. fully flooded with unborated water which includes an allowance for uncertainties as described in 1

WCAP-14416-NP-A. " Westinghouse Spent Fuel Rack Criticality Analysis Methodology";

c.

k s 0.95 if fully flooded with water borated to 550 ppm.

wfi$chincludesanallowanceforuncertaintiesasdescribed in WCAP-14416-NP-A. " Westinghouse Spent Fuel Rack Criticality Analysis Methodology":

d.

A nominal 10.32 inch north-south and 10.42 inch east-west c

center to center distance between fuel assemblies placed in Region 1 racks; and e.

A nominal 9.03 inch center to center distance between fuel assemblies placed in Region 2 racks.

4.3.2 Drainaae The spent fuel poni is designed and shall be maintainec' +: revent inadvertent draining of the pool below elevation 410 ft. 0 in,hes.

l 4.3.3 Cacacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 2870 fuel assenblies.

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l BYRON - UNITS 1 L 2 4.0 - 2 Amendment 108 & 108 i

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20086 4001 I

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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 1

BRAIDWOOD STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.101 License No. NPF-72

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l 1.

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

A.

The application for amendment by Commonwealth Edison Company (the j

licensee) dated October 30,1998, complies with the standards and requirements j

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;

)

8.

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

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Commission's regulations; j

D.

The issuance of this amendment will not be inimical to the common defense and 3

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

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Commission's reg:ilations and all applicable requirements have been satisfied, j

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-72 is hereby amended to read as follows:

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Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.101' and the Environmental Fiatection 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 and shall be 1

implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/

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ll nthony Mendiola, Chief, Section 2 I

P oject Directorate 111

/ Division of Licensing Project Management

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Office of Nuclear Reactor Regulation

Attachment:

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Changes to the Technical Specifications Date ofIssuance: May 3,1999 i

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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 License No. NPF-77 1.

The Nuclear Regulatoy Commission (the Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the i

licensee) dated October 30,1998, 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;

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e B.

The facility will operate in conformity with the application, the provisions of the 3

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; j

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 Specifications as i

indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility

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Operating License No. NPF-77 is hereby amended to read as follows:

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Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No.101 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, 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 if its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/

/sv Y AItpony Mendiola, Chief, Section 2

'P 6 ject Directorate 111 e

ivision of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 3, 1999 i

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t ATTACHMENT TO LICENSE AMENDMENT NOS.101 AND 101 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50457 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by amendment number and contains verticallines indicating the area of change.

Remove Paoes Insert Paaes 4.0-2 4.0-2 i

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Design Features I

4.0 DESIGN FEATURES'(continued)-

4.3 Fuel Storage

' 4.3.1 Criticality i

The s with: pent fuel storage racks are designed and shall be maintained a.

Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent:

b.

k,,,ludes an allowance for uncertainties as described in

< 1.0 if fully flooded with unborated water which inc WCAP-14416-NP-A. "Westinghcuse Spent Fuel Rack Criticality l

Analysis Methodology"-

l c.

k s 0.95 if fully flooded with water borated to 550 ppm.

wbch includes an allowance for uncertainties as described in WCAP-1441C-NP-A. " Westinghouse Spent Fuel Rack l

Criticality Analysis Methodology":

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d.

A nominal 10.32 inch north-south and 10.42 inch east-west center to center distance between fuel assemblies placed in #

Region 1 racks: and e.

A nominal 9.03 inch center to center distance between fuel i

assemblies placed in Region 2 racks.

4.3.2 Drainaae The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 410 ft. O inches.

l 4.3.3 Caoacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 2870 fuel assemblies.

1 BRAIDWOOD - UNITS 1 & 2 4.0 - 2 Amendment 101 & 101 i

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