ML17335A400
| ML17335A400 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/18/1998 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17335A401 | List: |
| References | |
| NUDOCS 9812180146 | |
| Download: ML17335A400 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 D
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GNP 0 PNY DON LD DOC 0
0-LE R LAN UN D
E TT ILI RA N
ICEN Amendment No. 225 License No. DPR-58 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Indiana Michigan Power Company (the licensee) dated August 1, 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 facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot 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.
98i2i80i46 98i2iQ PDR ADOCX OSOaasiS P
PDR 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-58 is hereby amended to read as follows:
echic S eifi i
The Technical Specifications 'contained in Appendices A and B, as revised through Amendment No. 225, 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'fullimplementation within 45 days.
FOR THE NUCLEAR REGULATORYCOMMISSION C
hn F. Stang,
- r. Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Change to the Technical Specifications Date of Issuance:
December 10, 1998
ENSE AMEND E
0 F I
0 ERATI G ENSE DPR-5 DO 0-3 Revise Appendix ATechnical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by amendment number and contains a vertical line indicating the area of change.
QQIV~OVE-;
~E~R Page 3/4 7-6 Page 3/4 7-6
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCERE UIREMENTS Continued V
4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE when tested pursuant to Specification 4.0.5 by:
a.
Verifying that each motor driven auxiliary feedwater pump's developed head at the test flow point is greater than or equal to the required developed head.
b.
Verifying that the turbine driven auxiliary feedwater pump's developed head at the test flow point is greater than or equal to the required developed head.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.
Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is'placed in automatic control or when above 10% RATED THERMAL POWER.
This requirement is not applicable for those portions of the auxiliary feedwater system being used intermittently to maintain steam generator water level.
Verifying at least once per 18 months during shutdown that each automatic valve in the flowpath actuates to its correct position upon receipt ofthe appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
f.
Verifying at least once per 18 months during shutdown that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
Verifying at least once per 18 months during shutdown that the unit cross-tie valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 7W AMENDMENT400, 48k, 444, 444, 225
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055!M001 NDIANAM Hl AN PO P NY 0-31 DON LD OOK CLE P
NT NIT 2 DMENTTO FACILI 0
E LI Amendment No. 209 License No. DPR-74 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Indiana Michigan Power Company (the licensee) dated August 1, 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. 'he facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 willbe 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-74 is hereby amended to read as follows:
c i al iic i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 209, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORYCOMMISSION hn F. Stang,
- r. Project Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Change to the Technical Specifications Date of Issuance:
December 10, 1998
H EN 0
EN E
ME NT C
0 RA IN I
ENO D
-4 D CKETNO 5 -
1 Revise Appendix ATechnical Specifications by removing the pages identified below and inserting the attached page.
The revised page is identified by amendment number and contains a vertical line indicating the area of change.
EMOV
~SE~T Page 3/4 7-6 Page 3/4 7-6
I
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCERE UIREMENTS 4.7.1.2 Each auxiliary fecdwater pump shall be demonstrated OPERABLE when tested pursuant to Specification 4.0.5 by:
Verifying that each motor driven auxiliary feed pump's developed head at the test flow point is greater than or equal to the required developed head.
b.
Verifying that the turbine driven auxiliary feedwater pump's developed head at the test flow point is greater than or equal to the required developed head.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
Verifying'that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.
Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary. feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER.
This requirement is not applicable for those portions of the auxiliary feedwater system being used intermittently to maintain steam generator level.
Verifying at least once per 18 months during shutdown that each automatic valve in the flow path actuates to its correct position upon receipt ofthe appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
Verifying at least once per 18 months during shutdown that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
g Verifying at least once per 18 months during shutdown that the unit cross-tie valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
COOK NUCLEARPLANT-UNIT2
.Page 3/4 7A AMENDMENTW, 97, 444, @at, 449,
~,~,ae, 209
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