ML17328A339

Amends 140 & 127 to Licenses DPR-58 & DPR-74,respectively, Modifying Reactor Protection Sys to Change Logic for Reactor Coolant Pump Breaker Position

ML17328A339
Person / Time
Site:	Cook
Issue date:	06/28/1990
From:	Pierson R Office of Nuclear Reactor Regulation
To:
Shared Package
ML17328A340	List: ML17328A339 ML17328A341
References
NUDOCS 9007260114
Download: ML17328A339 (17)

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 14O License No.

DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated January 27, 1986 and supplemented on December 21,

1988, 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.

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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:

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 140

, 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 its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION c.(

Robert C. Pierson, Acting Director Project Directorate III-I Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 28, 3.990

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Pevise 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 marginal lines indicating the area of change.

RENOVE 3/4 3-5 3/4 3-8 B 2-7 INSERT 3/4 3-5 3/4 3-8 B 2-7

OOO I

TABLE 3-Co ti ued EACTO RIP SYS E

NSTRUMENTATION TOTAL NOi OF CHANNE 4-1/bus 4-1/bus MINIMUM CHANNELS CHANNELS gODTR P

~OPERABI, NCTIONA UN

16. Undervoltage-Reactor Coolant-Pumps

17. Underfrequency-Reactor Coolant Pumps

18. Turbine Trip A. Low Fluid Oil Pressure B.. Turbine Stop Valve Closure

19. Safety In)ection Input from ESF

20. Reactor Coolant Pump Breaker Position Trip APPLICABLE MODES

~CTION 1

1 1

0'bove P-7

21. Reactor Trip Breakers

22. Automatic Trip Logic 1/breaker 1/breaker per oper-ating loop ip 2

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3* 4* 5*

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14

USES ndervolta e and Unde re ue cv -

eacto Coo ant um The Undervoltage and Underfrequency Reactor Coolant Pump bus trips provide reactor core protection against DNB as a result of loss of voltage or underfrequency to more than one reactor coolant pump.

The specified'e points assure a reactor trip signal is generated before the low flow trip set point is reached.

A 0.1 second time delay is incorporated in each of these trips to prevent spurious reactor trips from momentary electrical power transients.

ubne A Turbine Trip causes a d1rect reactor trip when opera(kg above P-7.

Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient.

No credit was taken in the accident analyses for operation of these trips.

Their functional capability at the specified trip settings is required to enhance the overall reliability of the Reactor Protection System.

Safet In ection In t from ESF If a reactor trip has not already been generated by the reactor protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety in5ection.

This trip is provided to protect the core in the event of a LOCA.

The ESF instrumentation channels which initiate a safety injection signal are shown, in Table 3.3-3.

Reactor Coolant ourn Breaker Position Tri

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This trip is blocked below P-7.

The open/close position trip assures a reactor trip signal is generated before the low flow trip setpoint is reached.

No credit was taken in the accident analyses for operation of this trip.

The functional capability at the open/close position settings is required to enhance the overall reliability of the Reactor Protection System.

D..C.

COOK - VNIT 1 B 2-7 NcEHDNEHT NO. PgP,140

TABLE 3.3-1 Continued ACTION 8

ACTION 9

ACTION 10 ACTION 11 (Deleted.)

(Deleted.)

(Deleted.)

With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 12 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

ACTION 13 With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and apply ACTION 1.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 14 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.

REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range Neutryy Flux Channels less than 6X10 amps.

P-6 prevents or defeats the manual block of source range reactor trip.

D.

C.

COOK - UNIT 1 3/4 3-8 AMENDMENT Np, PP,ggg, 140

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

127 License No.

DPR-74 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated January 27, 1986 and supplemented on December 21,

1988, 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 wi 11 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:

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 127, 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 its issuance.

FOR THE NUCLEAR REGULATORY COYiYiISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 28, 1990

~c.P Robert C. Pierson, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 5 Special Projects Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

127 FACILITY OPERATING LICENSE NO.

DPR"74 DOCKET NO. 50-316 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 marginal lines indicating the area of change.

REMOVE 3/4 3-4 3/4 3-7 B 2-8 INSERT 3/4 3-4 3/4 3-7 B 2-8

TABLE 3.3-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 16.

Undervoltage-Reactor Coolant Pumps 17.

Underfrequency-Reactor Coolant Pumps TOTAL NO.

OF CHANNELS 4-1/bus 4-1/bus CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE 3

APPLICABLE MODES ACTION t6.

Turbine Trip A.

LoM Fluid Oil Pressure B. Turbine Stop Yalve Closure 6 ¹ 19.

Safety Injection Input from ESF 1,

2 20.

Reactor Coolant Pump Breaker Position Trip Above P-7 21.

Reactor Trip Breakers 1/breaker 1/breaker per operat-ing loop 1, 2, 3* 4*, 5*

1, 13, 14 22.

Automatic Trip Logic 1,2, 3*, 4*, 5*

1, 14 4

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TABLE 3. 3-1 Continued ACTION ll - With less than the Minimum Number of Channels

OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 12

- With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

ACTION 13

- With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and apply ACTION 1.

The breaker shall not be bypassed while. one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 14

- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.

DESIGNATION REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT FUNCTION p-6 With 2 of 2 Intermediate Range Neutron Flux Channels ( 6 X 10 amps.

P-6 prevents or defeats the manual block of source range reactor trip.

D.

C.

COOK

- UNIT 2 3/4 3-7 Amendment No. pg,A/7

2.2 LIMITING SAFETY SYSTEM SETTINGS BASES Safet In ection In ut from ESF If a reactor trip has not already been generated by the reactor protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety injection.

This trip is provided to protect the core in the event of a LOCA.

The ESF instrumentation channels which initiate a safety injection signal are shown in Table 3.3-3.

Reactor Coolant Pum Breaker Position Tri The Reactor Coolant Pump Breaker Position Trip is an anticipatory trip which provides reactor core protection against DNB resulting from the opening of two or more pump breakers above P-7.

This trip is blocked below P-7.

The open/close position trip assures a reactor trip signal is generated before the low flow trip setpoint is reached.

No credit was taken in the accident analyses for operation of this trip.

The functional capability at the open/close position settings is required to enhance the overall reliability of the Reactor Protection System.

D. C.

COOK - UNIT 2 B 2-8 Amendment No,/$ 7