ML17326B290
| ML17326B290 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/10/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17326B291 | List: |
| References | |
| NUDOCS 8704160213 | |
| Download: ML17326B290 (15) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No.106 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated October 11, 1985, 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 (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.
DPR-58 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.j.06, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The Technical Specifications are effective within 45 days of issuance.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 10, 1987 Dave L. Wiggi on, Project Manager PWR Project Directorate ¹4 Division of PWR Licensing-A PWR¹4/
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TABLE 3.3-11 r'OST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE
.1.
Containment Pressure 2 ~
3.
5.
Reactor Coolant Outlet Temperature - T (Wide Range)
Reactor Coolant Inlet Temperature - T (Wide Range)
COLD Reactor Coolant Pressure - Wide Range Pressurizer Water Level 6.
Steam Line Pressure 7.
Steam Generator Water Level - Narrow Range 8.
Refueling Water Storage Tank Water Level 9.
Boric Acid Tank Solution Level 10.
Auxiliary Feedwater Flow Rate 11.
Reactor Coolant System Subcooling Margin Monitor 12.
PORV Position Indicator - Limit Switches***
13.
PORV Block:Valve Position Indicator - Limit Switches 14.
Safety Valve Position Indicator - Acoustic Monitor 15.
Incore Thermocouples (Core Exit Thermocouples) 16.
Reactor Coolant Inventory Tracking 'System (Reactor Vessel Level Indication)
I 2/Steam Generator 1/Steam Generator 1/Steam Generator*
1*1 1/Valve 1/Valve 1/Valve 2/Core Quadrant One Train (3 channels/Train)
I Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.
PRODAC 250 subcooling margin readout can be used as a substitute for the subcooling monitor instrument.
~** Acoustic monitoring of PORV position (1 channel per three valves - headered discharge) can be used as a substitute for the PORV Indicator >> Limit Switches instruments.
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TABLE 4'-7,i
'OST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION 1.
Containment Pressure M
2.
3 ~
Reactor Coolant Outlet Temperature - T (Wide Range)
React'or Coolant Inlet Temperature - T (Wide Range)
Reactor Coolant Pressure - Wide Range 5.
Pressurizer Water Level 6.
Steam Line Pressure 7.
Steam Generator Water Level - Narrow Range 8.
RWST Water Level 9.
Boric Acid Tank Solution Level 10.
Auxiliary Feedwater Flow Rate 11.
Reactor Coolant System Subcooling Margin Monitor 12.
PORV Position Indicator - Iimit Switches 13.
PORV Block Valve Position Indicator - Limit Switches R
R R
14.
15.
16.
Safety Valve Position Indicator - Acoustic Monitor Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant Inventory Tracking System:
(Reactor Vessel Level Indication)
M(2)
R(1)
R(3)
I (1) Partial range channel calibration for sensor to be performed below P-12 in MODE 3.
(2) With one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK toiverify the remaining Reactor Vessel Indication train OPERABLE.
(3) Completion of channel calibration for sensozs to be performed below P-12 in MODE 3.
I The provisions of Specification 4.0.6 are applicable.
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated October 11, 1985, 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'orth 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 (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.
DPR-74 is hereby amended to read as follows:
, (2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
92 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The Technical Specifications are effective following the refueling outage currently scheduled for 1988.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications
,Date of Issuance:
APril 10, 1987 Dave L. Wigginton, Project'Manager PWR Project Directorate ¹4 Division of PWR Licensing-A PWR¹4/
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TABLE 3'-10
'OST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE 1.
Containment Pressure 2 ~
3.
4 ~
Reactor Coolant Outlet Temperature - T (Wide Range)
Reactor Coolant Inlet Temperature - T (Wide Range)
COLD Reactor Coolant Pressure - Wide Range 5.
Pressurizer Water Level 6.
7 ~
Steam Line Pressure Steam Generator Water Level - Narrow Range 2/Steam Generator 1/Steam Generator 8.
Refueling Water Storage Tank Water Level 9.
Boric Acid Tank Solution Level 10.
Auxiliary Feedwater Flow Rate 11.
Reactor Coolant System Subcooling Margin Monitor 12.
PORV Position Indicator - Limit Switches***
13.
PORV Block Valve Position Indicator Iimit Switches 14.
Safety Valve Position Indicator - Acoustic'Monitor 1/Steam Generator*
1/Valve 1/Valve 1/Valve 15.
16.
Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication) 2/Core Quadrant One Train (3 channels/Train)
Steam Generator Water Level Channels can be used as a substitute for the co'rresponding auxiliary feedwater flow rate channel instrument.
PRODAC 250 subcooling margin readout can be used as a substitute for the subcooling monitor instrument.
Acoustic monitoring of PORV position (1 channel per three valves - headered discharge) can be used as a substitute for the PORV Indicator.- Limit Switches instruments.
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TABLE 4.3-10
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POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS O
o INSTRUMENT I
g 1.
Containment Pressure M
2.
3 ~
Reactor Coolant Outlet Temperature - T (Wide Range)
Reactor Coolant Inlet Temperature - T (Wide Range)
Reactor Coolant Pressure Wide Range 4 ~
5.
Pressurizer Water Level 6.
Steam Line Pressure 7.
Steam Generator Water Level - Narrow Range 8.
RWST Water Level 9.
Boric Acid Tank Solution Level 10.
Auxiliary Feedwater Flow Rate 11.
Reactor Coolant System Subcooling Margin Monitor 12.
PORV Position Indicator Limit Switches 13.
PORV Block Valve Position Indicator - Limit Switches
- CHANNEL CHECK CHANNEL CALIBRATION
.14 ~
15.
16.
Safety Valve Position Indicator - Acoustic Monitor Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant Inventory Tracking System
'Reactor Vessel Level Indication)
M (2)
R(1)
R(3)
O ft 0
I (1) Partial range channel calibration for sensor to be performed below P-12 in MODE 3.
(2) With one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perfoxm a CHANNEL CHECK toiverify the remaining Reactor Vessel Indication train OPERABLE.
(3) Completion of channel calibration for sensors to be performed below P-12 in MODE 3.
I)* - The provisions of Specification 4.0.6 are applicable.
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.>o6 FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NOS. 50-315 AND 50-316 Revise Appendix A as follows:
Remove Pa es Un1t 1
3/4 3-55 3/4 3-56 Unit 2 3/4 3-46 3/4 3-47 Insert Paqes 3/4 3-55 3/4 3-56 3/4 3-46 3/4 3-47