ML17331A638
| ML17331A638 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/28/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17326A839 | List: |
| References | |
| NUDOCS 8102190167 | |
| Download: ML17331A638 (15) | |
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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 INDIANA AND NICMIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment,No.
43 License No.
DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated February 22, 1980, 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 provision's 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:
(2)
Technical S'ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43
, are hereby incorporated in the license.
The licensee shall operate the faci1ity in, accordance with the Technical Specifications.
"2" 3.
Thss 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:
January 28, 1981
, Chi teven A.
arg Operating Reactors B
Division of Licensi nch 81
ATTACHMENT TO LICENSE AMENDMENT AMENOf)ENT*NO, 43 TO FACILITY OPERATINh LICENSE NO. DPR-58 DOCKET'O. 5O-3l5 Revise Appendix A as follows:
Remove Pa es 2"5 2"6 3/4 3-26a Insert Pa e
2-5 2-6 3/4 3-26a
TASLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS C)
CD CD FUNCTIONAL UNIT
- l. Manual Reactor Trip 2.
Power
- Range, Neutron Flux 3.
Power Range, Neutron Flux, High Positive Rate J
4.
Power Range, Neutron Flux, High Negative Rate TRIP SETPOINT Not Applicable Low Setpoint - < 25K of RATED THERMAL POWER High Setpoint - <109$ of RATED THERMAL POWER
< 5~ of RATED THERMAL POWER with a time constant
> 2 seconds 5%%u of RATED THERMAL POWER with a time constant
> 2 seconds ALLOWABLE VALUES Not Applicable
~l Low Setpoint -
< 26$ of RATED THERMAL PQWER High Setpoint 110%%u of RATED THERMAL POWER
< 5.5% of RATED THERMAL POWER with a time constant 2 seconds
< 5.5X, of RATED THERMAL POWER with a time constant
> 2.seconds
- 7. Overtemperature AT 8; Overpower aT See Note 1
See Note 2
- 9. Pressurizer Pressure--Low
> 1865 psig
- 10. Pressurizer Pressure--High
< 2385 psig ll. Pressurizer Water Level--High 92%%u of instrument span
- 5. Intermediate
- Range, Neutron 25%%u of RATED THERMAL POWER Flux 6..Source
- Range, Neutron Flux
< 10 counts per second 5
30%%u of RATED THERMAL POWER
< 1.3 x 10 counts per second See Note 3
See Note 3
> 1855 psig
< 2395 psig
-< 93K of instrument span 12.
Loss of Flow
> 90Ã of design flow per loop*
89%%u of design flow per 'loop*
- Design flow is 88,500 qpm per loop.
TABLE 2.2-1 Continued FUNCTIONAL UNIT REACTOR TRIt SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP SETPOINT ALLOWABLE VALUES 13.
Steam Generator Mater Level - Low-Lo>>
- 14. Steam/Feedwater Flow Mismatch and Low Steam Generator Mater Level
- 15. Undervoltaqe - Reactor Coolant Pumps
- 16. Underfrequency - Reactor Coolant Pumps
- 17. Turbine Trip A.
Low Trip System Pressure B.
Turbine Stop Valve Closure
> 17K of narrow range instrument spah - each steam generator
< 0.71 x 10 lb/hr of steam flow 6
at RATED THERMAL POWER coincident with steam generator water level
> 25K of narrow range instru-ment span - each steam generator
> 2750 volts - each bus
> 57.5 Hz - each bus
> 800 pslg
> lX open 16% of narrow range instrument span - each steam generator
< 0.73 x 10 1bs/hr of steam flow at RATED THERMAL POWER coincident with steam generator water level 24K, of narrow range instru-ment span - each steam generator
> 2725 volts - each bus
> 57.4 Hz - each bus
> 750 psig 1% open
- 18. Safety Injection Input from ESF Not Applicable Not Applicable
- 19. Reactor Coolant Pump Breaker Position Trip Not Applicable Not Applicable
TABLE 3. 3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT 6.
MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.
Steam Generator Water Level -- Low-Low b.
4 kv Bus Loss of Voltage TRIP SETPOINT 17% of narrow range instrument span each steam generator 3196 volts with a 2-second delay ALLOWABLE VALUES 16% of narrow range instrument span each steam generator 3196+18 volts with a 2+.2 second delay 7.
TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.
Steam Generator Hater Level -- Low-Low 8.
LOSS OF POWER a.=
4 kv Bus Loss of Voltage 17K of narrow range instrument span each steam generator 3196 volts with a 2-second delay
> 16K or narrow range instrument span each steam generator 3196+18 volts with a 2+.2 second delay b.
4 kv Bus Degraded Voltage 3596 volts with a 2.0 min. time delay 3596+18 volts with a 2.0 minute + 6 second time delay
gal WROTE~'O 0+*44 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON,D. C. 20555 INDIANA AND MICH!GAN ELECTRIC COMPANY I
I DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No., 25 License No; DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
B.
C.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated February 22, 1980, 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; The facility will operate in conformity with the application, th' 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 will be conducted in compliance with the Commission's regulations; P.
,The issuance ot 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:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through. Amendment No. 25
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
-2" 3.
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:
January 28) 1981 even
. Varg Ch>
Operating Reactor's 8
Division of Licensi f
h 01'
ATTACHMENT TO LICENSE'AtlENDl1ENT At1ENDt'lENT NO. 25 TO FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise Appendix A as follows:
Remove Pa es 2-6 3/4 3-25a 3/4 3-26 Insert Pa es 2-5 2-6 3/5 3-25a 3/5, 3-/26
TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT
- 1. Manual Reactor Trip 2;
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 TRIP SETPOINT Not Applicable Low Setpoint - < 25K of RATED THERMA POWER High-Setpoint -
< 109Ã of RATED THERMAL POWER
< 5X. of RATED THERMAL POWER with a.time constant 2 seconds
< 5X of RATED THERMAL POWER with a time constant
> 2 seconds
< 25K of RATED THERMAL POWER ALLOWABLE VALUES Not Applicable Low Setpoint - < 26% of RATED THERMAL POWER High Setpoin't -
< 110K of RATED THERMAL POWER
< 5.5X of RATED THERMAL POWER with a time constant
> 2 seconds
< 5.5'X of RATED THERMAL POWER with a time constant
> 2 seconds 30'X of RATED THERMAL POWER 5
- 6. Source
- Range, Neutron Flux
< 10 counts per second
< 1.: x 10 counts per second 5
?. Overtemperature hT
- 8. Overpower hT See Note 1
See Note 2
See Note 3
See Note 3
- 9. Pressurizer Pressure--Low
>.1950 psig
- 10. Pressurizer Pressure--High
< 2385 psig ll. Pressurizer Mater Level--High
< 92K of instrument span
> 1940 psig
< 2395 psig
< 93Ã of instrument span
- 12. Loss:of Flow
> 901 of design flow per loop*
> 89K of design flow per loop*.
- Design flow is 93,750 gpm per. loop.
TABLE 2.2-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 13.
Steam Generator Water Level Low-Low
- 14. Steam/Feedwater Flow Mismatch and Low Steam Generator Water Level
- 15. Undervoltage - Reactor Coolant Pumps i6. Underfrequency - Reactor Coolant Pumps-
- 17. Turbine Trip A.
Low Trip System Pressure B.
Turbine Stop Valve Closure
> 21/ of narrow range=instrument span - each steam generator 6
< 1.47 x 10 lb/hr of steam flow at RATED THERMAL POWER coincident with steam generator water level
> 25K of narrow range instru-ment span - each steam generator
> 2750 volts - each bus
> 58.2 Hz - each bus
> 58 psig
> 1X open
> 20$ of narrow range instrument span - each steam generator 6
< 1. 56 x 10 1bs/hr of steam flow~
at RATED THERMAL POWER coincident ~
with steam generator water level
> 24K of narrow range instru-ment span - each steam generator
> 2725 volts - each bus
> 58.1 Hz - each bus
> 57 psig
> ll open
- 18. Safety Injection Input from ESF
- 19. Reactor Coolant Pump Breaker Position Trip Not Applicable Not Applicable Not Applicable Not Applicable
TABLE 3. 3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPQINT ALLOWABLE VALUES 6.
MOTOR DRIVEN AUXILIARY FEEDMATER PUMPS a.
Steam Generator Water Level -- Low-Low b.
4 kv Bus Loss of Voltage 7.
TURBINE DRIVEN AUXILIARYFEEDWATER PUMPS a.
- Water, Level -- Low-Low 8.
LOSS OF POWER a.
4 kv Bus Loss of Voltage b.
4 kv Bus Degraded Voltage
> 21K-of narrow range instrument span each steam generator 3196 volts with a 2 second delay
> 21/ of narrow range instrument span each steam generator 3196 volts with a 2 second delay 3596 volts with a 2.0 minute time delay
> 20g of narrow range Tnstrument span each steam generator 3196
+ 18 volts with a 2 + 0.2 second delay
> 20K of narrow range instrument span each steam generator 3196 + 18 volts with a 2 + 0.2 second delay 3596 + 18 volts with a 2.0 minute + 6 second time delay
4 r
~I E
TABLE 3.3-5 ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS Manual a.
Safety Injection (ECCS)
Feedwater Isolation Reactor Trip (SI)
Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System Containment Air Recirculation Fqn b.
Containment Spray Containment Isolation-Phase "B"
Containment Purge and Exhaust Isolati on c.
Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation d.
Steam Line Isolation Not Appl icable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable No) Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable 2.
Containment Pressure-Hi h
a ~
b.
C.
g, Safety Injection (ECCS)
Reactor Trip (from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isol a tion Auxiliary Feedwater Pumps
-Essential Service Water System..
Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicably Not Applicable D. C.
COOK - UNIT 2 3/4 3-26
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