ML20195C885
| ML20195C885 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/04/1998 |
| From: | Lyon C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195C890 | List: |
| References | |
| NUDOCS 9811170234 | |
| Download: ML20195C885 (6) | |
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1 UNITED STATES 1
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NUCLEAR REGULATORY COMMISSION
%*****,g WASHINGTON, D.C. 20$654001 NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 License No. DPR-42 j
1.
The Nuclear Regulatory Commission (the Commission) has found that-A.
The application for amendment by Northern States Power Company (the licensee) dated January 29,1997, as supplemented February 11,12, March 7, 10,11,19,20, April 29, June 30, July 10,1997, June 20, June 22, July 24, September 15, and October 1,1998, 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, 1
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 hereby amended to authorize the licensee to change the design basis of the intake canalin its Updated Safety Analysis Report (USAR) as described in its application dated January 29,1997, as supplemented February 11,12, March 7,10,11,19,20, April 29, June 30, July 10,1997, June 20, June 22, July 24, 4
September 15, and October 1,1998, and evaluated in the staff's safety evaluation attached to this amendment. In addition, the license is also amended by changes to Appendix B, " Additional Conditions" as indicated in the attachment to this license i
amendment, and paragraph 2.C.(5) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
9811170234 981104 PDR ADOCK 05000282 P
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l 2-Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No.
140, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Additional Conditions.
3.
This license amendment is effective as of the date of issuance, with implementation within 30 days and implementation of the USAR update no later than June 1,1999, as stated in License Condition 3.
FOR THE NUCLEAR REGULATORY COMMISSION a
l M
i Tae Kim, Senior Project Manager i
Project Directorate 111-1 Division of Reactor Projects - lil/IV i
Office of Nuclear Reactor Regulation i
Attachment:
Appendix B - Additional Conditions Date of Issuance: November 4, 1998 5
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p UNITED STATES s
j NUCLEAR REGULATORY COMMISSION s.,*****j WASHINGTON, D.C. 30eeH001 NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT 2 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.131 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northem States Power Company (the licensee) dated January 29,1997, as supplemented February 11,12, March 7, 10,11,19,20, April 29, June 30, July 10,1997, June 20, June 22, July 24, September 15, and October 1,1998, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; t
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 1
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 hereby amended to authorize the licensee to change the design basis of the intake cand in its Updated Safety Analysis Report (USAR) as described in its application dated January 29,1997, as supplemented February 11,12, March 7,10,11,19,20, April 29, June 30, July 10,1997, June 20, June 22, July 24, September 15, and October 1,1998, and evaluated in the staffs safety evaluation attached to this amendment. In addition, the license is also amended by changes to Appendix B, " Additional Conditions' as indicated in the attachment to this license amendment, and paragraph 2.C.(5) of Facility Operating License No. DPR 60 is hereby amended to read as follows:
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. l Additional Conditions l
The Additional Conditions contained in Appendix B, as revised through L
Amendment No. 131
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Additional Conditions.
3.
This license amendment is effective as of the date of issuance, with lmplementation within 30 days and implementation of the USAR update no later than June 1,1999, as t
stated in License Condition 3.
FOR THE NUCLEAR REGULATORY COMMISSION dA l
Tae Kim, Senior Project Manager Project Directorate lil-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
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Specifications s
Date of issuance: November 4, 1998 l
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APPENDIX B l
ADDITIONAL CONDITIONS l
FACILITY OPERATING LICENSE NO. DPR-42 Northern States Power Company shall comply with the following conditions on the schedules noted below:
1 i
1 Amendment implementation Number Additional Condition Date
(
128
- 1. NSP will provide a licensed operator in the control room Prior to Unit 2 entering j
on an interim basis for the dedicated purpose of identifying Mode 2.
i an earthquake which results in a decreasing safeguards t
cooling water bay level. This operator will be in addition to Completed - See i
the normal NSP administrative control room staffing Amendment No.140 requirements and will be provided until License Condition 2 is satisfied.
l 128
- 2. NSP will submit dynamic finite element analyses of the July 1,1997, and intake canal banks by July 1,1997 for NRC review. By December 31,1998, as December 31,1998, NSP will complete, as required, stated in Condition 2.
l additional analyses or physical modifications which provide the basis for extending the time for operator post-seismic Completed - See cooling water load management and eliminating the Amendment No. 140 dedicated operator specified in License Condition 1.
128
- 3. Based on the results of License Condition 2, NSP will At the next USAR revise the Updated Safety Analysis Report to incorporate update following the changes into the plant design bases. These changes completion of will be included in the next scheduled revision of the Condition 2, but no Updated Safety Analysis Report following completion of later than June 1, License Condition 2 activities.
- 1999, 130
- 4. Prairie Island will assure that heavy loads do not present This is effective a potential for damaging irradiated fuel through use of 1) a immediately upon single-failure-proof crane with rigging and procedures which issuance of the implement Prairie Island commitments to NUREG-0612; or amendment.
- 2) spent fuel pool covers with their implementing plant procedures for installation and use.
133
- 5. NSP will assure that during the implementation of steam This is effective generator repairs utilizing the voltage-based repair criteria, immediately upon the total calculated primary to secondary side leakage from issuance of the the faulted steam generator, under main steamline break amendment.
conditions (outside containment and upstream of the main l
steam isolation valves), will not exceed 1.42 gallons per r
i minute (based on a reactor coolant system temperature of j
578 'F).
i l
Amendment No.140 l
l l
l-I APPENDIX B l
ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-60 Northern States Power Company shall comply with the following conditions on the schedules noted below:
l Amendment implementation Number Additional Condition Date 120
- 1. NSP will provide a licensed operator in the control room Prior to Unit 2 entenng on an interim basis for the dedicated purpose of identifying Mode 2.
an earthquake which results in a decreasing safeguards cooling water bay level. This operator will be in addition to Completed - See the normal NSP administrative control room staffing Amendment No.131 requirements and will be provided until License Condition 2 is satisfied.
l-120
- 2. NSP will submit dynamic finite element analyses of the July 1,1997, and i
intake canal banks by July 1,1997 for NRC review. By December 31,1998, as December 31,1998, NSP will complete, as required, stated in Condition 2.
additional analyses or physical modifications which provide the basis for extending the time for operator post-seismic Completed - See i
cooling water load management and eliminating the Amendment No.131 dedicated operator specified in License Condition 1.
120
- 3. Based on the results of License Condition 2, NSP will At the next USAR revise the Updated Safety Analysis Report to incorporate update following the changes into the plant design bases. These changes completion of f
will be included in the next scheduled revision of the Condition 2, but no Updated Safety Analysis Report following completion of later than June 1, License Condition 2 activities.
1999.
122
- 4. Prairie Island will assure that heavy loads do not present This is effective a potential for damaging irradiated fuel through use of 1) a immediately upon l
single-failure-proof crane with rigging and procedures which issuance of the implement Prairie Island commitments to NUREG-0612, or amendment.
- 2) spent fuel pool covers with their implementing plant
(
procedures for installation and use.
125
- 5. NSP will assure that during the implementation of steam This is effective generator repairs utilizing the voltage-based repair criteria, immediately upon the total calculated primary to secondary side leakage from issuance of the the faulted steam generator, under main steamline break amendment.
conditions (outside containment and upstream of the main steam isolation valves), will not exceed 1.42 gallons per i
minute (based on a reactor coolant system temperature of I
578 *F).
Amendment No.131
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