ML17326A593
| ML17326A593 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/29/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17326A594 | List: |
| References | |
| NUDOCS 8003310220 | |
| Download: ML17326A593 (22) | |
Text
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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. 36 License No.
DPR-5B 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated October 25, 1979, 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, the pro-visions 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 tPe Comission's regulations and all applicable requirenents have been satis-fied.
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-5B 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.
36
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Speci-fications.
80088X0~*2CO
3.
In addition, the license is hereby amended to include the following para-graph:
"2.C.(3)(m)
Secondar Water Chemistr Monitorin Pro ram The licensee shall implement a secondary water chemistry monitoring pro-gram to inhibit steam generator tube degradation.
This program shall be described in the station chemistry manual and shall include:
l.
Identification of a sampling schedule for the critical paramaters and control points for these parameters; 2.
Identification of the procedues used to measure the values of the critical parameters; 3.
Identification of process sampling points; 4.
Procedure for the recording and management of data; 5.
Procedures defining, corrective actions for off control point chemistry conditions; and 6.
A procedure identifying (a) the authorit~ responsible for the interpretation of the data.
and (b) the sequence and timing of administrative events required to initiate corrective actions.'-'.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COlOISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 29, 1980 A. Schwencer, Chief Operating Reactors Branch 81 Division of Operating Reactors
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATI' LICENSE NO.
DPR-58 DOCKET NO. 50-315 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided for document completeness.
~Pa es VII 3/4 7-11 3/4 7-12 3/4 7-13 8 3/4 7-3 D. C.
Cook - Unit 1
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 4.7 PLANT SYSTEMS 3/4,7.1 TURBINE CYCLE Safety Valves.............
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Auxi1iary Feedwater System.
Condensate Storage Tank....
A tctlv 1 tyo
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Steam Generator Stop Valves 3/4 7-1 3/4 7-5 3/4 7-7 3/4 7-8 3/4 7-10
/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION........
3/4 7-14
/4.7.3 COMPONENT COOLING WATER SYSTEM.;.......................
3/4 7-15
/4.7.4 ESSENTIAL'ERVICE WATER SYSTEM....................,....
3/4 7-17
/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM..............
3/4 7-19
/4.7.6 ESF VENTILATIONSYSTEM.................................
3/4 7-23
/4.7.7 SEALED SOURCE CONTAMINATION............................
3/4 7-26
/4.7.8 HYDRAULIC SNUBBERS.....................................
3/4 7-27
/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System.
Spray and/or Sprinkler Systems Low Pressure C02 Systems......
Halon Systemo
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Fire Hose Stations............
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3/4 7-41 3/4 7-44 3/4 7-47 3/4 7-49 3/4 7-50
/4.7.10 PENETRATION FIRE BARRIERS..............................
3/4 7-51
. C.
COOK - UNIT 1 VII Amendment No. gg, 36
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS 3 4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.
SOURCES 0peratsng..........'............................-.......
hutdownt ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 00 ~ ~ ~ ~ ~
~ ~
S 3/4 8-1 3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating...................-.......
A.C. Distribution - Shutdown...........................
D.C. Distribution - Operating......................
D.C; Distribution - Shutdown.............-....--...
D.C. Distribution - Operating - Train N Battery...
3/4. 9 REFUELING OPERATIONS 3/4 8-6 3/4 8-7 3/4 8-8 3/4 8-12 3/4 8-13 3/4.9.1 3/4.9.2 3/4.9.3 BORON CONCENTRATION....................... -.. -......
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INSTRUMENTATION................................-.......
ECAY TIME................:..................---.......
D 3/4 9-1 3/4 9-2 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS............----......
3/4 9-4 3/4.9.5 3/4.9.6 3/4.9.7 3/4.9.8 COMMUNICATIONSo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ e ~ ~ e ~ ~ ~ o ~ ~ ~ e e e o ~ ~ ~ ~
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MANIPULATOR CRANE OPERABILITY........". ~..
~.. - -. ~ ~
CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING--~ ~
COOLANT CIRCULATION.................... -.... - - - -".
3/4 9-5 3/4 9-6 3/4 9-8 3/4 9-9 3/4.9.9 CONTAINMENT PURGE AND'XHAUST ISOLATION SYSTEM. -.......,
3/4 9-10 D. C.
COOK - UNIT 1 VIII Amendment No. 35
his page intentionally left blank.
D. C.. COOK-VNIT 1 3/4 7-12 Amendment No.
36
his page intentionally left blank.
C.
COOK-UNIT 1 3/4 7-11 Amendment No.
PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2.1 The temperatures of both the primary and secondary coolants in the steam generators shall be
> 70'F when the pressure of either coolant in the steam generator is
> 200 psig.
APPLICABILITY: At all times.
ACTION:
With the -requirements of the above specification not satisfied:
a.
Reduce the steam generator pressure of the applicable side to
< 200. psig within 30 minutes, and b.
Perform an analysis to determine the effect of the overpres-surization on the structural integrity of the steam generator.
Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200'F SURVEILLANCE RE UIREMENTS 4.7.2.1 The pressure in each side of the steam generator shall be determined to be
< 200 psig at least once per hour when the temperature of either the primary or secondary coolant in the steam generator is <
70'F.
D.
C.
COOK-UNIT 1 3/4 7-14
This page intentionally left blank, D. C.
COOK-UNIT 1
3/4 7-13 Amendment No. 36
PLANT SYSTEMS BASES 3/4.7.2 STEAM GENERATOR PRESSURE TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.
The limitations of 70'F and 200 psig are based on average steam generator impact values taken at +10'F and are sufficient to prevent brittle fracture.
3 4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM The OPERABILITY of the essential service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
D. C.
COOK-UNIT 1
B 3/4 7-4
PLANT SYSTEMS BASES 3 4.7.1.4 ACTIVITY Continued 10 CFR Part 100 limits in the event of a steam line rupture.
This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line.
These values are consistent with the assumptions used in the accident analyses.
3 4.7.1.5
. STEAM GENERATOR STOP VALVES The OPERABILITY of the steam generator stop valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.
This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the steam generator stop valves within. the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses...
D. C.
COOK-UNIT 1
B 3/4 7-3 Amendment No. 36
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. 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. 18 License No. DPR-74 1.
The Nuclear Regulatory Comission (the ComIission) has found that:.
A.
The applications for amendment by Indiana and Michigan Electric Company (the licensee) dated October 25, 1979 and November 30, 1979, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR ChapterI; B.
The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i} that the ac'tivities 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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. 18, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
aooosxog+0
3.
In addition, the license is hereby amended to include the following para-graph:
"2.C. (7)
Secondar Mater Chemistr Honitorin Pro ram The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
This program shall be des-cribed in the station chemistry manual and shall include:
l.
Identification of a sampling schedule for the critica1 parameters and control points for these parameters; 2.
Identification of the procedures used to measure the values of the critical parameters; 3.
Identification of process sampling points; 4.
Procedure for the recording and management of data; 5.
Procedures defining corrective actions for off control point chemistry conditions; and 6.
A procedure identifying (a) the authority responsible for the interpretation of the data, and [b) the sequence and timing of administrative events required to initiate corrective actions."
4.
This license amendment is effective as of the date of its issuance.
FOR THE NU LEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specif ications Date of Issuance:
February 29, 1980 A. Schwencer, Chief Operating Reactors Branch 81 Division of Operating Reactors
ATTACHMENT TO LICENSE AMENDMENT NO, 18 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
Revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided for document completeness.
~Pe es VII 3/4 7-10a (delete page) 3/4 7-10b (delete page) 3/4 7-10c (delete page B 3/4 7-3 D.
C.
COOK - Uk!IT 2
INOEX IMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS ECTION PAGE
/4.7 PLANT SYSTEMS
/4.7.1 TURBINE CYCLE afety Valves..........................................
S Auxiliary Feedwater System...........,.................
Condensate Storage Tank..............................,.
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Steam Generator Stop Valves............................
3/4 7-1 3/4 7-5 3/4 7-7 3/4 7-8 3/4 7-10
/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION........
3/4 7-11
/4.7.3 COMPONENT COOLING ldATER SYSTEM.........................
3/4 7-12
/4.7.4 ESSENTIAL SERVICE MATER SYSTEM.....
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/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM..............
3/4 7-14 C
/4.7.6 ESF VENTILATIONSYSTEM........................'....
3/4 7-17
/4.7.7 HYDRAULIC SNUBBERS...
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3/4 7-20
/4.7.8 SEALED SOURCE CONTAMINATION............................
3/4 7-34
/4.7.9 FIRE SUPPRESSION Fire Suppression Mater System...
Spray and/or Sprinkler Systems..
Low Pressure CO Systems........
Halon Systemt
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Fire Hose Stations.............,
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3/4 7-36 3/4 7-39 3/4 7-42 3/4 7-44 3/4 7-45
/4.7.10 PENETRATION FIRE BARRIERS..............................
3/4 7-46 D. C.
COOK - UNIT 2 VII Amendment No. 18
0'NDEZ LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS 3 4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.
SOURCES 0peratlng..............................................
hutdown...............................................
S 3/4 8-1 3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating..........................
A.C. Distribution - Shutdown...........................
D.C. Distribution - Operating..........................
D.C. Distribution - Shutdown...........................
D.C. Distribution - Operating - Train N Battery...
3 4.9 REFUELING OPERATIONS 3/4 8-6 3/4 8-7 3/4 8-8 3/4 8-11
~
r 3/4.9.1 U
3/4.9.2 3/4.9.3 BORON CONCENTRATION....................................
INSTRUMENTATION........................................
ECAY TIME.............................,,....,...,,....
0 3/4 9-1 3/4 9>>2 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................
3/4 9-4 3/4.9.5 COMMUNICATIONS..........;..............................
3/4 9-5 3/4.9.6 MANIPULATOR CRANE OPERABILITY..........................
3/4 9-6 3/4.9.7 3/4.9.8 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING.;......
COOLANT CIRCULATION...........................;........
j 3/4 9-7 3/4 9-8 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.........
3/4 9-9 D. C..COOK - UNIT 2 VIII Amendment NG.
16
PLANT SYSTEMS BASES 3/4.7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.
The limitations of 70'F and 200 psig are based on average steam generator impact values taken at +10'F and are sufficient to prevent brittle fracture.
3 4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related eq'uipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM The OPERABILITY of the essential service water system ensures that sufficient cooling capacity is available for continued operation of'safety related equipment during normal and accident conditions.
The redundant
cooling capacity of this, system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room EMERGENCY ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumenta-tion co'oled by this system and 2) the control room will remain habitable for operations personnel during and followjng all credible accident condi-tions.
The OPERABILITY of this system in conjunction with control rootn design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the r equirements of General Design Criteria 19 of Appendix "A", 10 CFR 50.
D.
C.
COOK - UNIT 2 B 3/4 7-4
PLANT SYSTEMS BASES 3 4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.
This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line.
These values are consistent with the assumptions used in the accident analyses.
3 4.7.1.5 STEAM GENERATOR STOP VALVES The OPERABILITY of the steam generator stop valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.
This restriction is required to 1) minimize the positive reacti-vity effects of the Reactor Coolant System cooldown associated with the blowdown, and
- 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the steam generator stop valves within the closure times of the, surveillance requirements are consistent with the assumptions used in the accident analyses.
0.
C.
COOK - UNIT 2 B 3/4 7-3 Amendment No. 18