ML17321A793
| ML17321A793 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/05/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17321A794 | List: |
| References | |
| NUDOCS 8508150461 | |
| Download: ML17321A793 (9) | |
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UNITEDSTATES 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 Amendment No.
85 License No.
DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated March 29,
- 1982, as supplemented, by letters dated April 18,
- 1983, November 29,
- 1983, and February 12, 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 i 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 Comission'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:
8508150461 850805 PDR ADOCK 05000315 P
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I (2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLE EGULATORY COMMISSION
- rga, Operating Reactors ra ch ¹1 Division of Licensin 4
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Attachment:
Changes to the Technical Specifications Date of Issuance August 5, 1985
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UNITEDSTATES 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. 71 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 March 29,
- 1982, as supplemented by letters dated April 18,
- 1983, November 29, 1983, and February 12, 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 coIImon 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. 71
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The change in Technical Specifications is to become effective within 30 days of issuance of the amendment.
4.
This license amendment is effective as of the 'date of its issuance.
FOR THE NUCLEAR R ULATORY COMMISSION ven
- rga, Ch e Operating Reactors ra ch Pl Division of Licensi
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 5, 1985
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.
85 FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT NO.
7l FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NOS.
50-315 AND 50-316 Revise Appendix A as follows:
Remove Pa es Unit 1
3/4 3-9 3/4 3-10*
Unit 2 3/4 3-8 Insert Pa es 3/4 3-9 3/4 3-10*
3/4 3-8
- No changes - Page provided for convenience.
TABLE 3:3-1 Continued DESIGNATION CONDITION AND SETPOINT FUNCTION P-7 P-8 P-10 With 2 of 4 Power Range Neutron Flux Channels
> illof RATED THERMAL POWER or 1 of 2 Turbine First Stage Pressure
. channels
>37 pslg ~
With 2 of 4 Power Range Neutron Flux channels 51% of RATED THERMAL POWER.
With 3 of 4 Power range neutron flux channels
< 9X of RATED THERMAL POWER.
P-7 prevents or defeats the automatic block of reactor trip on:
Low flow in more than one primary coolant loop, reactor coolant pump under-voltage and under-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.
P-8 prevents or defeats the automatic block of reactor trip on low coolant flow in a single loop.
P-10 prevents or defeats the manual block of:
Power range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod stops.
Provides input to P-7.
D. C.
COOK-UNIT 1 3/4 3-9 Amendment No. 85
TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT l.
Power Range, Neutron Flux 3.
Power Range, Neutron Flux, High Positive Rate 4.
Power Range, Neutron Flux, High Negative Rate 5.
Intermediate
- Range, Neutron Flux 6.
Source
- Range, Neutron Flux
, 7.
Overtemperature aT 8.
Overpower aT 9.
Pressurizer Pressure Low 10.
Pressurizer Pressure High
RESPONSE
TIME NOT APPLICABLE
< 0.5 seconds*
NOT APPLICABLE
< 0.5 seconds*
NOT APPLICABLE NOT APPLICABLE
< 6.0 seconds*
NOT APPLICABLE
< 1.0 seconds
< 1.0 seconds 11.
Pressurizer Water Level--High NOT APPLICABLE Neutron detectors are exempt from response time testing.
Response
time shall be measured from detector output or input of first electronic component in channel.
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DESIGNATION TABLE 3.3-1 Continued CONDITION AND SETPOINT FUNCTION P-7 With 2'of 4 Power Range Neutron Flux Channels
> 11K of RATED THERMAL POWER or 1 of 2 'Pressure Before the First Stage channels
> 66 psia.
P-7 prevents or defeats the automatic block of reactor trip on:
Low flow in more than one primary coolant loop, reactor coolant pump under-voltage and under-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.
P-8 With 2 of 4 Power Range Neutron Flux channels
> 31K of RATED THERMAL POWER.
P-8 prevents or defeats.
the automatic block of reactor trip on low coolant flow in a single loop.
0-10 With 3 of 4 Power range neutron-.
flux channels
< 9X of RATED THERMAL POWER.
P-10 pr events or defeats the manual block of:
Power range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod stops.
Provides input to P-7.
D.
C.
COOK - UNIT 2 3/4 3-8 Amendment No. 71