ML20082M556
| ML20082M556 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/18/1995 |
| From: | Carpenter C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20082M559 | List: |
| References | |
| NUDOCS 9504240266 | |
| Download: ML20082M556 (8) | |
Text
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man y)t UNITED STATES pe
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,j NUCLEAR REGULATORY COMMISSION
'f WASHINGTON, D.C. 20666 4 001 o
NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated February 23 and March 3, 1995, 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 (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 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. DPR-42 is hereby amended to read as follows:
9504240266 950418 PDR ADOCK 05000282-P PDR
a Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 117, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, with full implementation within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION d
Cyn.hia Carpenter, Acting Director Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1995
f ATTACHMENT TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-42 DOCKET NO.' 50-282 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change, t
REMOVE INSERT TS 4.4-2 TS 4.4-2 i
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Initial and periodic type B.(except airlocks) and type C tests of penetrations shall be performed at a pressure of 46 psig (P.) in accordance with the provisions of Appendix J,Section III.B and Section III.C, and Specification 4.4.A.5.
.The airlocks shall be tested initially and at six-month intervals at 46 psig by pressurizing the inner volume.
In addition, when CONTAINMENT INTEGRITY is required, each airlock shall be tested every 3 days if.-
it is in use by pressurizing the intergasket space to 10 psig.
3.
Type A tests will be considered to be satisfactory if the acceptance criteria delineated in Appendix J Section III.A are met.
4.
Type B and C tests will be considered to be satisfactory if the i
combined leakage rate of all components ' subjected to Type B and C tests does not exceed 60% of the L. and if the following conditions are met.
I a.
For pipes connected to systems that are in the auxiliary building special ventilation zone, the total. leakage past isolation valves shall be less than 0.1 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure P..
j b.
For pipes connected to systems that are exterior to both the shield building and the auxiliary building special ventilation zone, the total leakage past isolation valves shall be less than 0.01 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure P..
f c.
For airlocks, the leakage shall be less than 14 of the L. at 10 psig for door intergasket tests and 56 of the L. at 46 psig for overall airlock tests.
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5.
The retest schedules for Type A,
B, and C tests will be in.
accordance with Section III.D of Appendix J and all approved i
exemptions. Each shield building shall be ratested in accordance with the Type A test schedule for its containment. The auxiliary building special ventilation zone shall be ratested in accordance with the Type A test schedule for Unit 1 containment.
I 6.
Type A, E and C tests will be in accordance with Section V of Appendix J.
Inspection and reporting requirements of each shield building test shall be the same for Type A tests.
The auxiliary
- building special ventilation zone shall have the same inspection and reporting requirements as for the Type A tests of Unit 1.
1 Prairie Island Unit 1 Amendment No. 62, 107, 117 Prairie Island Unit 2 Amendment No. 56, 100, 110 l
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g UNITED STATES E
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 205W201
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-30.1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 110 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated February 23 and March 3,1995, 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 (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 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. DPR-60 is hereby amended to read as follows:
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. : cs Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.110, are hereby incorporated in the license.
.The licensee shall operate the facility in accordance with the Technical Specifications.
' 3.
This license amendment is effective as of the date of issuance, with full implementation within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION h
Cynthia Carpenter, Acting Director i
Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1995 e
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I ATTACHMENT TO LICENSE AMENDMENT NO. 110
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FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 Revise Appendix A Technical Specifications by removing the pages identified 1
below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT TS 4.4-2 TS 4,4-2 b
6
~.
TS.4.4 2 i
1 2.
Initial and periodic type B (except airlocks) and type C tests of penetrations'shall be performed at a pressure of 46 psig (P.) in accordance with the provisions of Appendix J.
Section III.B and Section III.C, and Specification 4.4.A.5.
The airlocks shall be tested initially and at six-month intervals at 46 psig by pressurizing the inner volume.
In addition, when CONTAlbHENT INTEGRITY is required, each airlock shall be tested every 3 days if it is in use by pressurizing the intergasket space to 10 psig.
3.
Type A tests will be considered to be satisfactory if the acceptance criteria delineated in Appendix J,Section III.A are met.
4.
Type B and C tests will be considered to be satisfactory if the combined leakage rate of all components subjected to Type B and C tests does not exceed 60% of the L, and if thn following conditions are met.
a.
For pipes conne.: ted to systems that are in the auxiliary building special ventilation zone, the total leakage past isolation valves shall be less than 0.1 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure P..
b.
For pipes connected to systems that are exterior to both the shield building and the auxiliary building special ventilation zone, the total leakage past isolation valves shall be less t
than 0.01 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure P..
c.
For airlocks, the leakage shall be less than it of the L. at 10 psig for door intergasket tests and 5% of the L at 46 psig for overall airlock tests.
5.
The retest schedules for Type A,
B, and C tests will be in accordance with Section III.D of Appendix J and all approved exemptions. Each shield building shall be retested in accordance with the Type A test schedule for its containment. The auxiliary buildin8 special ventilation zone shall be retested in accordance with the Type A test schedule for Unit 1 containment.
6.
Type A, B and C tests will be in accordance with Section V of Appendix J.
Inspection and reporting requirements of each shield building test shall be the same for Type A tests.
The auxiliary building special ventilation zone shall have the same inspection and reporting requirements as for the Type A tests of Unit 1.
Prairie Island Unit 1 Amendment No. 52, 107, 117 Prairie Island Unit 2 Amendment No. M, 100, 110