ML17328A592
| ML17328A592 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/09/1990 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17328A593 | List: |
| References | |
| NUDOCS 9003020153 | |
| Download: ML17328A592 (66) | |
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/y/p 4***4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA YICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT, UNIT NO.
1 At)ENDVIENT TO FACILITY OPERATING LICENSE Amendment No. 131 License No.
DPR-58 1.
The Nuclear Reculatory Corm ission (the Commission) has found that:
A.
The application for amendment by Indiana V;ichigan Power Company (the licensee) dated Nay 30,
- 1986, as further clarified and revised in submittals dated June 23, 1986, February c5, March 2, and Jure 16,
- 1988, and
)anuary c3, 1989, ccrrplies viith the stardards and require-ments oi the Atomic Erergy Act of 1954, as amended (the Act), and the Commissior,'s rules and regulatiors set forth in 1G CFR Chapter I; B.
The facility will operate in corformity with the application, the provisions of the Act, and the rules and regulations of the CorTIission; C.
There is reasonable assurance (i) that the activities authorized by this aI-endment can be conducted without endareering the health and safety of the public, and (ii) that such activities will be conducted in compliance with.he Commission's regulations; C.
The issuance of this aIIIendIIIent wi','. rct be 'inimicalI tc the ccrrror Crfense and security or to thE, health ard safety of the publIic; and E.
The issuance of.his amendment is ir. accordance with 1C CFR Part 51 of the COIrIIission's regulations arC all applicable requiremer ts have been satisfied.
9003020153 900209 PDR ADOCK- 0500031!5 P
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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. 131', 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 COh>MISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 9,
1990 Jo n 0. Thoma, Acting Director Project Directorate III-I Division of Reactor Projects - III, IV, V 5 Special Projects Office of Nuclear Reactor Regulation
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA YIICHIGAII PO'li'ER COHPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLAIIT UNIT NO.
2 AIIENDHENT TO FACILITY OPERATING LICENSE Amendment lio. 116 License No. DPR-74 1.
The Nuclear REAL':atory Coiir,ission
( thc Gorvriissicn) has found A.
The app 1 ication for ameridmert by Iridia ra I'ichi gan Power Company (the licensee) dated Vay 30, 1986, as further clarified and revised in submittals dated
.lurie P3,
- 1986, Februarv 25, I~arch 2, and June 16,
- 198S, and Jaruary 23,
- 1909, complies with the stanoards and require-ilierts of the Atomic Energv Act of 1954, as amended '(the Act),
are'. the Corx.issior,'s rules and re'culations set forth in 10 CFR Chapter I; B.
The facility will operate in conforliity with the applicatior, the provisions of the Act, and the rules and regulations of the Commissicr:;
C.
There is reasonable assurarice (i) that the activities authorized by tIiis arendment can be conducted without eridangeiiiig the health and safety of the public, and (ii) that such activities will be ccrducted in compliarce TTtith the Cowrission's reci;laticns; D.
The issuance of this amerdment wi" rct be'inimical to the coiiir:.or defense arid security or to the health arid safety of the puhlic; c nd E.
The issuarice of this aIIieIldIIieni is ir: accoraance with 10 CFR Par'.
51 of the CorIiiission's reculatiors ard all applicable reouiieiients have beeri sati..fied.
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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-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
1<6, 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 J
hr, O. Thoma, Acting Director Project Directorate III-I Division of Reactor Projects - III, IV, V E Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 9, i990
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0 ATTACHMENT TO LICENSE AMENDMENT NO.
131 FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO. 50-315 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 1-11 3/4 3-48 3/4 7-5 3/4 7-6 3/4 7-15 3/4 7-17 B 3/4 1-3 B 3/4 1-4 B 3/4 3-2 B 3/4 7-2 B 3/4 7 B 3/4 7-8 INSERT 3/4 i-ii 3/4 1-lla 3/4 3-48 3/4 3-48a 3/4 3-48b 3/4 3-48c 3/4 3-48d 3/4 7-5 3/4 '7-6 3/ 7-i5 3/4 7-17 B 3/4 1-3 B 3/4 1-4 B 3/4 3-2 B 3/4 7-2 B 3/4 7-4 B 3/4 7-8 0 3/4 7-9
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REACTIVITY CONTROL SYSTEMS CHARGING PUMP -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 a.
One charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
b.
One charging flowpath associaged with support of Unit 2 shutdown functions shall be available.
APPLICABILITY: Specification 3.1.2.3.a.
- MODES 5 and 6
Specification 3.1.2.3.b.
- At all times when Unit 2 is in MODES 1, 2,
3, or 4.
ACTION:
a.
With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
b.
With more than one charging pump OPERABLE or with a safety injection pump(s)
OPERABLE when the temperature of any RCS cold leg is less than 0
or equal to 170 F, unless the reactor vessel head is removed, remove the additional charging pump(s) and the safety injection pump(s) motor circuit breakers from the electrical power circuit within one hour.
c.
The provisions of Specification 3.0.3 are not applicable.
In addition to the above, when Specification 3.1.2.3.b is applicable and the required flow path is not available, return the required flow path to available status within 7 days, or provide equivalent shutdown capability in Unit, 2 and return the required flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN 'within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e.
The requirements of Specification 3.0.4 are not applicable when Specification 3.1.2.3.b applies.
SURVEILLANCE RE UIREMENTS 4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of
> 2390 psig when tested pursuant to Specification 4.0.5 at least once per 31 days.
4.1.2.3.2 All charging pumps and safety injection pumps, excluding the above required OPERABLE charging pump, shall be demonstrated inoperable by verifying that the motor circuit breakers have been removed from their electrical power supply circuits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, except when:
+A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 170 F.
0 D.
C.
COOYi - UNIT 1 3/4 1-11 Amendment No. 98,120,131
SURVEILLANCE RE UIREMENTS a.
The reactor vessel head is removed, or 0
b.
The temperature of all RCS cold legs is greater than 170 F 4.1.2.3.3 Charging line cross-tie valves to Unit 2 will be cycled full travel at least once per 18 months.
Following cycling, the valves will be verified to be in their closed positons.
D.
C.
COOK - UNIT 1 3/4 1-lla Amendment No. 13i
O00 TABLE 4.3-6 MMlZE SHUZIXNN MDNZI'C6GNG IN SURVEIIZANCE Reactor Trip Hxealcer Indication 2.
Pressurizer Pressure 3.
Pressurizer level Hot Shutdown panel in Unit No.
2 Control Roam Hot Shutdown panel in Unit No.
2 Control Roam Hot Shutdown Pane1 in Unit No.
2 Control Roam N.A.
N.A.
R+
4.
Steam Generator level 5.
Steam Generator Pressure Hot Shutdawn Panel in Unit No.
2 Control Roam Hot Shutdown Panel in Unit No.
2 Control Roam R
R+
0 C)
C) 40
+ The provisions of Specification 4.0.6 are applicable.
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INSTRUMENTATION APPENDIX R REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5.1 The Appendix R remote shutdown instrumentation channels shown in Table 3.3-9A be OPERABLE with an opposite unit power supply available and with read out capability at the LSI-panels.
APPLICABILITY MODES 1, 2, and 3
ACTION a.
With the number of OPERABLE Appendix R remote shutdown monitoring channels less than required by Table 3.3-9A, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b, With the opposite unit power supply not available, restore the power supply to available status within 7 days, or provide fire watches in the affected areas and restore the inoperable channel to OPERABLE status within the next 60 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.3.5.1 Each Appendix R remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the 'frequencies shown in Table 4.3-6A.
D.
C.
COOK - UNIT 1 3/4 3-48a Amendment No. i31
TABLE 3.3-9A APPENDIX R REMOTE SHUTDOWN MONITORING INSTRUMENTATION INSTRUMENT READOUT LOCATION MEASUREMENT RANGE MINIMUM CHANNELS OPERABLE l.
and 4 Level LSI Cabinet 1 and LSI Cabinet 4
0-100% wide range instrument span one on each LSI cabinet for each steam generator 2.
and 3 Level LSI Cabinet 2 and LSI Cabinet 4
0-100't wide range instrument span one on each LSI cabinet for each steam generator 3.
and 4 Pressure FALSI Cabinet 4 and LSI Cabinet 5
0-1500 psig one on each LSI cabinet for each steam generator 4.
and 3 Pressure LSI Cabinet 4 and LSI Cabinet 6
0-1500 psig one on each LSI cabinet for each steam generator 5.
Reactor Coolant Loop 4 Temperature (Cold)
LSI Cabinet 4 and LSI Cabinet 5
0-700 F
one on each LSI cabinet 6.
Reactor Coolant Loop 4 Temperature (Hot)
LSI Cabinet 4 and-LSI Cabinet 5
0-700 F
one on each LSI cabinet 7.
Reactor Coolant Loop 2 Temperature (Cold)
LSI Cabinet 4 and LSI Cabinet 6'-700 F
one on each LSI cabinet 8.
Reactor Coolant Loop 2 Temperature (Hot)
LSI Cabinet 4 and LSI Cabinet 6
0-700 F
one on each LSI cabinet
TABLE 3.3-9A cont.
APENDIX R REMOTE SHUTDOWN MONITORING INSTRUMENTATION INSTRUMENT 9.
Presurizer Level READOUT LOCATION LSI Cabinet 3
MEASUREMENT RANGE 0-100% of instrument span MINIMUM CHANNELS OPERABLE 10.
Reactor Coolant System Pressure 11.
Charging Cross-Flow Between Units 12.
Source Range Neutron Detector (N-23)
LSI Cabinet 3
Corridor Elev.
587'SI Cabinet 4 0-3000 psig 0-150 gpm 1-1 X 10 cps 6
TABLE 4.3-6A APPENDIX R REMOTE SHUTDOMN MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT LOCATION CMNNEL CHECK CHANNEL CALIBRAT ION 1.
and 4 Level 2.
and 3 Level LSI Cabinet 1 and LSI Cabinet 4
LSI Cabinet 2 and LSI Cabinet 4
3.
and 4 Pressure LSI Cabinet 4 and LSI Cabinet 5
4.
.and 3 Pressure LSI Cabinet 4 and LSI Cabinet 6
5.
Reactor Coolant Loop 4 Temperature (Cold)
LSI Cabinet 4 and LSI'Cabinet 5
R 6.
Reactor Coolant Loop 4 Temperature (Hot)
LSI Cabinet 4 and LSI Cabinet 5
7.
Reactor Coolant Loop 2 Temperature (Cold)
LSI Cabinet 4 and LSI Cabinet 6
8.
Reactor Coolant Loop 2 Temperature (Hot)
LSI Cabinet 4 and LSI Cabinet 6
M 9.
Pressurizer Level 10.
Reactor Coolant System Pressure LSI Cabinet 3.
LSI Cabinet 3
ll.
Charging Cross-Flow Between Units Corridor Elev.587'/a 12.
Source Range Neutron Detector (N-23)
LSI Cabinet 4
nba Charging Cross-Flow between Units is an instrument common to both Unit 1 and 2.
This surveillance will only be conducted on an interval consistent with Unit 1 refueling.
PLANT SYSTEMS AUXILIARYFEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 a.
At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
1.
Two feedwater
- pumps, each capable of being powered from separate emergency
- busses, and 2.
One feedwater pump capable of being powered from an OPERABLE steam supply system.
b.
At least one auxiliary feedwater flowpath in support of Unit 2 shutdown functions shall be available.
APPLICABILITY: Specification 3.7.1.2.a
- MODES 1, 2, 3.
Specification 3.7.1.2.b
- At all times when Unit 2 is in MODES 1,- 2, or 3.
ACTIONS:
When Specification 3.7.1.2.a is applicable:
a.
With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With three-auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
When Specification 3.7.1.2.b is applicable:
With no flow path to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or'ave Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The requirements of Specification 3.0.4 are not applicable.
D.
C.
COO}'
UNIT 1 3/4 7-5 Amendment No. 92,120,126, 131
PLANT SYSTEMS SURVEILLANCE RE UlREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a ~
At least once per 31 days by:
1.
Verifying that each motor driven pump develops an equivalent discharge pressure of > 1375 psig at 60'F on recirculation flow.
2.
Verifying that the steam turbine driven pump develops a discharge pressure of > 1285 psig at 60 F and at a flow of > 700 gpm when 0
the secondary steam supply pressure is greater than 310 psig.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
3.
Verifying that each non-'automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.
,4.
Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10%,
RATED THERMAL POWER.
This requirement is not applicable for those portions of the Auxiliary Feedwater System being used intermittently to maintain steam generator level..
b.
At least once per 18 months during shutdown by:
- 1.
Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4. 3. 2.
2.
Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate'ngineered
'safety features actuation test signal required by Specification 3/4.3.2.
3.
Verifying that the unit cross-tie valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
- The provisions of Specification 4.0.6 are applicable.
D. C.
COOK UNIT 1 3/4 7-6 Amendment No. 100,131
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PLANT SYSTEMS 3 4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 a.
At least two independent component cooling water-loops shall be OPERABLE.
b.
At least one component cooling ~ater flowpath in support of Unit 2 shutdown functions shall be available.
APPLICABILITY: Specification 3.7.3.1.a.
MODES 1, 2, 3, 4.
Specification 3.7.3.1.b.
- At all times when Unit 2 is in MODES 1, 2, 3, or 4.
ACTION:
When Specification 3.7.3.1.a is applicable:
With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
When Specification 3.7.3.1.b is applicable:
With no flowpath to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The requirements of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4'.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related'equipment that is not
- locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.*
'L c.
At least 'once per 31 days on a STAGGERED TEST BASIS, by verifying that each pump develops at least 93% of the discharge pressure for the applicable flow rate as determined from the manufacturer's Pump Performance Curve.
Amendment No. 107,131 d.
At least once per 18 months during shutdown, by verifying that the cross-tie valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
~ The provisions of Specification 4.0.6 are applicable.
D.
C.
COOK - UNIT 1 3/4 7-15
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PLANT SYSTEMS 3 4.7.4 ESSENTIAL SERVICE WATER SYS'EM LIMITING CONDITION FOR OPERATION 3 '.4.1 a.
At least two independent essential service water loops shall be OPERABLE.
b.
At least one essential service water flowpath associated with support of Unit 2 shutdown functions shall be available.
APPLICABILITY: Specification 3.7.4.l.a.
- MODES 1, 2, 3, and 4.
Specification 3.7.4.1.b.
- At all times when Unit 2 is in MODES 1, 2, 3 or 4.
ACTION:
When Specification 3.7.4.l.a is applicable:
With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
When Specification 3.7.4.1.b is applicable:
With no essential service water flow path available in support of Unit'2 shutdown functions, return at least one flow path available status within 7 days or provide equivalent shutdown capability in Unit 2.and return the equipment to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24'ours'he requirements of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not
- locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct positon on a Safety Injection test signal.*
C.
At least once per 31 days on a STAGGERED TEST BASIS, by,verifying 'that each pump. develops at least 93% of the discharge pressure for the applicable flow rate as determined from the manufacturer's Pump Performance Curve.
- The provisions of Specification 4.0.6 are applicable.
D.
C.
COOK - UNIT 1 3/4 7-17 Amendment No. 107,131
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REACTIVITY CONTROL SYSTEMS BASES BORATION.SYSTEMS Continued With the RCS average temperature above 200 F, one injection system is acceptable 0
without single failure consideration on t'e basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and safety injection pumps,.
0 except the required OPERABLE charging pump, to be inoperable below 170 F, unless the reactor vessel head is removed, provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
The boration capability required below 200 F is sufficient to provide a SHUTDOWN MARGIN of 1% Q k/k after xenon decay and cooldown from 200 F to 140 F.
This condition 0
0 requires either 835 gallons of 20,000 ppm borated water from the boric acid storage tanks or 9690 gallons of 1950 ppm borated water from the refueling water storage tank.
The charging flowpath of Unit 1 required for Unit 2 shutdown support ensures that flow is available to Unit 2 and addresses the requirements of 10 CFR 50 Appendix R.
The flowpath consists of a charging pump powered from an electrical bus and associated water supplies and delivery system.
Fire watches posted in the affected opposite unit areas (i.e., Unit 2 areas requiring use of the Unit 1 charging system in the event of a fire) may serve as the equivalent shutdown c'apability specified in the action statements of Specification 3.1.2.3.
In the affected areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per Specification 4.3.3.7 and establish hourly fire watch patrols.
The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfillingits intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure.
An additional plant procedure details how the above noted fire watches will be implemented.
3 4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod ejection accident.
OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
The ACTION statements which permit limited variations from the basic requirements are accompanied by 'additional restrictions which ensure that the original criteria are met.
Misalignment of a rod requires measurement of peaking factors or a restriction in THERMAL POWER; either of these restrictions provide assurance of fuel rod integrity during continued operation.
The reactivity worth of a misaligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumptions used in the accident a'nalysis for a rod ejection accident.
D.
C.
COOK - UNIT 1 B 3/4 1-3 Amendment No. 88,120,131
REACTIVITY CONTROL SYSTEMS BASES MOVABLE CONTROL ASSEMBLIES (Continued)
The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses.
Measurement with T 5541 F and with all reactor coolant pumps operating ensures that the measured'rop times will be representative of insertion times experienced during a reactor trip at operating conditions.
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required. if an automatic monitoiing channel is inoperable.
These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.
D. C.
COOK - UNIT 1 B 3/4 1-4 Amendmen=
No. 53,131
INSTRUMENTATION BASES 3 4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
3 4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility.
3 4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological dat.- is available for estimating potential radiation doses to the public as a resul: of routine or accidental release of radioactive materials to the atmosphere.
Tnis capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
3 4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3 4.3.3.5.1 APPENDIX R REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the Appendix R remote shutdown instrumentation ensures that sufficient instrumentation is available to permit shutdown of the facility to COLD SHUTDOWN conditions at the local shutdown indication (LSI) panel.
In the event of a fire, normal power to the LSI panels may be lose.
As a result, capability to repower the LSI panels from Unit 2 has been provided. If the alternate power supply is not available, fire watches will be established in those fire areas where loss of normal power to the LSI panels could occur in the event of fire.
This will consist of either establishing continuous fire watches or verifying OPERABILITY of fire detectors per Specification 4.3.3.7 and
'stablishing hourly fire watches.
The details of how these fire watches are to be implemented are included in a plant procedure.
D.
C.
COOK - UNIT 1 B 3/4 3-2 Amendment No. 94,127,131
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PLANT SYSTEMS BASES U
Maximum number of inoperable safety valves per operating steam line - 1, 2, or 3.
(109) - Power Range Neutron Flux-High Trip Setpoint for 4 loop operation.
(76) - Maximum percent of RATED THERMAL POWER permissible by P-8 Setpoint for 3 loop operation.
X - Total relieving capacity of all safety valves per steam line
- 4,288,450 lbs/hour.
Y - Maximum relieving capacity of any one safety valve-857,690 lbs/hour.
3 4.7.1.2 AUXILIARYFEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant system can be cooled down to less then 350 F from normal operating conditions in the 0
event of a total loss of off-site power.'ach electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pressure of 1065 psig to the entrance of the steam generators.
The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant system temperature to less than 350 F when the Residual Heat Removal system may be placed into operation.
0 The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60 F.
Water density corrections are permitted to allow comparison of test results which vary depending on ambient conditions.
In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation).
During this time, the system design allows for automatic initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.
B 3/4 7-2 The auxiliary feedwater flowpath, with a pump and associated water supplies and piping, will support shutdown cooling requirements of Unit 2.
This capacity addresses the 10 CFR 50 Appendix R safe shutdown requirements.
Fire watches posted in the affected opposite unit areas (i.e., Unit 2 areas requiring use of the Unit 1 auxiliary feedwater system in the event of a fire) may serve as the equivalent shutdown capability specified in the action statements of Specification 3.7.1.2.
In the affected areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per Specification 4.3.3.7 and-establish hourly fire watch patrols.
The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfillingits intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure.
An additional plant procedure details how the above noted fire watches will be implemented.
D.
C.
COOK - UNIT 1 Amendment No. 92,131
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 0
steam generator impact values taken at +10 F and are sufficient to prevent brittle 0
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
signal failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
3 4.7.3 AND 3 4.7.4 The OPERABILITY of the Unit 1 flowpaths which support Unit 2 shutdown functions ensures the availability of cooling functions on Unit 2 and addresses the requirements of 10 CFR 50 Appendix R.
The required flowpath consists of a pump and associated water supplies and delivery systems.
Fire watches posted in the affected opposite unit areas (i.e., Unit 2 areas requiring use of the Unit 1 component cooling water system or essential service water system in the event of a fire) may serve as the equivalent shutdown capability specified in the action statements of Specifications 3.7.3.1 and 3.7.4.1.
In the affected areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per Specification 4.3.3.7 and establish hourly fire watch patrols.
The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfillingits intended Appendix R alternate safe shutdown functions have been established and are included in a plant procedure.
An additional plant procedure details how the above noted fire watches will be implemented.
D.
C.
COOK
- UNIT 1 B 3/4 7-4 Amendment No. i31
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BASES 3/4.7.9 Cont.
The purpose of the charcoal filter fire suppression T/S is to account for detection and suppression of fires in the charcoal filters.
Manual operation Gf these systems is al lowed because two-,point heat detection. with control room and local annunciation of trouble conditions is provided for the charcoal filters.
The OPERABILITY of the fire suppression system protecting the charcoal filters is only required when there charcoal in the filters.
Actuation of spray water onto the charcoal filters requires both the manual opening of the system isolation valve and reaching the high temperature alarm setpoint for the automatic opening of the system deluge valve.
Because of the inaccessibility of. the lower containment to personnel during operation Cue to ALARA radiation exposure
- concerns, the use of one or more CCTVs in the lower containment, to monitor for fire and smoke, is an acceptable substitute to an hourly fire watch, if.the fire suppression system becomes inoperable.
All hourly fire. watch patrols are performed at intervals of sixty minutes with a margin of fifteen minutes..
A continuous fire watch requires that a trained indiv.idual be in the specified area at all times and that each fire zone within the specified area be patrolled at least once every fifteen minutes with a margin of five minutes.
A control valve is defined as a valve that when closed does not leave an alternate open flow path to a system.
A sectionalizing=-valve is defined as a
valve that when closed does not prevent an alternate open flow path to a
system and hence does not make the fire suppression water system inoperable Under certain situations, the closure of a sectionalizing valve followed by the closure of a second valve will not leave an open flow path to one of the specified systems.
In this instance, Action Statement b of Specification 3.7.9.1 is applicable.
Manual actuation of CO fire supporession systems provides adequate fire protection for the protected areas based on operable fire detection in the
- area, low combustible
- loadings, and prompt fire brigade response to alarms.
Many of the action statements take credit for operable fire detection in lieu of a fire watch when a fire protection system is inoperable.
Operable fire detection provides sufficient early warning capability of a fire to the appropriate Control Room.
During Surveillance Testing of a Low Pressure CO System with the system inoperable, the requirement for a continuous fir(.watch may be suspended during portions of the test which result or may result in a discharge into the CO protected area.
Similarly, if a CO actuation occurs which results in the need to have the Low Pressure CO System made inoperable, the requirement for a continuous fire watch may be suspended.
In either case, the area affected shall be restored to habitability as soon as practicable, after which the continuous fire watch is to be re-established if the system is still inoperable.
D.
C.
COOK - UNIT I B 3/4 7-8 Amendment No.
130,131 July 15, 1986 Bases Clarification
0 I
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3/4.7. IO FIRE RATED ASSEMBLIES The OPERABILITY of the fire barriers and barrier penetrations ensure that fire damage will be limited.
These design features minimize the possibility of a single fire involving more than one fire area prior to detection and extinguish-ment.
The fire barriers and fire barrier penetration sealing devices are periodically inspected to verify their OPERABILITY.
The functional testing of the fire dampers is provided to ensure that the dampers remain functional.
The ventilation seals area seals around ventilation duct work penetrating fire barriers.
It is not our intent to rely on backup systems or other compensatory measures for an extended period of time and action will be taken to restore the inoperable portions of the fire rated assembly to OPERABLE status within a reasonable period.
For the purpose of determining OPERABILITY, an OPERABLE fire rated assembly and/or sealing device is one, that is capable of performing its intended safety function.
D. C.
COOK - UNIT 1 B 3/4 7-9 Amendment No.
131
ATTACHMENT TO LICENSE AMENDMENT NO. 116 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 1-11 3/4 3-43*
3/4 3-44 3/4 7-5 3/4 7-6 3/4 7-12 3/4 7-13 8 3/4 1-3 8 3/4 1-4 8 3/4 3=2 8 3/4 3-2a 8 3/4 7-2 8 3/4 7-4 8 3/4 7-7 8 3/4 7-8 INSERT.
3/4 1-11 3/4 1-lla 3/4 3"43*
3/4 3-44 3/4 3-44a 3/4 3-44b 3/4 3-44c 3/4 3-44d 3/4 7"5 3/4 7-6 3/4 7-12 3/4 7-13 8 3/4 1-3 8 3/4 1-4 8 3/4 3-2 8 3/4 3-2a 8 3/4 7-2 8 3/4 7-4 8 3/4 7-7 8 3/4 7-8
- Overleaf page provided to maintain document completeness.
No changes contained on this page.
E I
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< 2390 psig when tested pursuant to Specification 4.0.5.
- A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature 0
of one or more of the RCS cold legs is less than or equal to 152 F.
D.
C.
COOK - UNIT 2 3/4 1-11 Amendment No. 85,107,ii6
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SURVEILLANCE RE UIREMENTS 4.1.2.3.2, All charging pumps and safety injection pumps, excluding the above-required OPERABLE charging pump, shall be demonstrated inoperable by verifying that the motor circuit breakers have been removed from their electrical power supply circuits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, except when:
a.
The reactor vessel head is removed, or t
0 b.
The temperature of all RCS cold legs is greater than 152 F.
- 4. 1.2.3.3
~ Charging line cross-tie valves to Unit 1 'will be cycled full travel at least once per 18 months.
Following cycling, the valves will be verified to be in their closed positions.
D. C.
COOK UNIT 2 3/4 1-lla Amendment No. 1i16
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TABLE 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION INSTRUMENT 1.
Reactor Trip Breaker Indication 2.
Pressurizer Pressure 3.
Pressurizer Level 4.
Steam Generator Pressure 5.
Steam Generator Level READOUT LOCATION MEASUREMENT RANGE Hot Shutdown Panel in OPEN-CLOSE Unit No.
1 Control Room Hot Shutdown Panel in 1700-2500 psig Unit No.
1 Control Room Hot Shutdown Panel in 0-lOOX of Unit No.
1 Control Room instrument span Hot Shutdown Panel in 0-1200 psig Unit No.
1 Control Room Hot Shutdown Panel in 0-1005 wide range Unit No.
1 Control Room instrument span MINIMUM CHANNELS OPERABLE 1/trip breaker I/stean generator 1/steam generator
TABIZ 4.3-6 O00 RM3IR SHVZIXNMMNZIORING IN SURVEILLANCE INSTfKMERP 1.
Reactor Trip Breaker Indication 2.
Pressurizer Pressure 3.
Pressurizer level 4.
Steam Generator Zavel 5.
Steam Generator Pressure Hot Shutdown Panel in Unit No. 1 Oontrol Roan Hot Shutdown ~ in Unit No. 1 Contxol Roan Hot Shutdown~ in Unit No. 1 Oontxol Roan Hot Shutdown Panel in Unit No. 1 Oontxol Roan Hot Shutdown Panel in Unit No. 1 Contxol Roan N.A.
N.A.
INSTRUMENTATION APPENDIX R REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5.1 The Appendix R remote shutdown instrumentation channels shown in Table 3.3-9A shall be OPERABLE with an opposite unit power supply available and with read out capability at the LSI panels.
APPLICABILITY MODES 1, 2, and 3
ACTION N
a.
With the number of OPERABLE Appendix R remote shutdown monitoring channels less than required by Table 3.3-9A, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the opposite unit power supply not available, restore the power supply to available status within 7 days, or provide fire watches in the affected areas and restore the inoperable channel. to OPERABLE status within the next 60 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
The provisions of Specification 3.0,4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.3.5.1 Each Appendix R remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6A.
D.
C.
COOK - UNIT 2 3/4 3-44a Amendment No.
116
TABLE 3.3-9A APPENDIX R REMOTE SHUTDOWN MONITORING INSTRUMENTATION INSTRUMENT 1.
and 4 Level READOUT LOCATION LSI Cabinet 1 and LSI Cabinet 4
MEASUREMENT RANGE 0-100't wide range instrument span MINIMUM CHANNELS OPERABLE one on each LSI cabinet for eac) steam generator 2.
and 3 Level LSI Cabinet.2 and LSI Cabinet 4
0-100% wide range instrument span one on each LSI cabinet for each steam generator 3.
and 4 Pressure J
4.
and 3 Pressure 5.
Reactor Coolant Loop 4 Temperature (Cold)
LSI Cabinet 4 and LSI Cabinet 5
LSI Cabinet 4 and LSI Cabinet 6
LSI Cabinet 4 and LSI Cabinet 5
0-1500 psig 0-1500 psig 0-700 F
one on each LSI cabinet for each steam generato'r one on each LSI cabinet for each steam generator one on each LSI cabinet 6.
Reactor Coolant Loop 4 Temperature (Hot) 7.
Reactor Coolant Loop 2 Temperature (Cold)
D 5
8.
Reactor Coolant Loop 2 Temperature (Hot)
LSI Cabinet 4 and LSI Cabinet 5
LSI Cabinet 4 and LSI Cabinet 6
LSI Cabinet 4 and LSI Cabinet 6
0-700 F
0-700 F
0-700 F
one on each LSI cabinet one on each LSI cabinet one on each LSI cabinet.
TABLE 3.3-9A cont.
APENDIX R REMOTE SHUTDOWN MONITORING INSTRUMENTATION I
c INSTRUMENT
'9.
Presurizer Level 10.
Reactor Coolant System Pressure 11.
Charging Cross-Flow Between Units 12.
Source Range Neutron Detector (N-23)
READOUT LOCATION LSI Cabinet 3
LSI Cabinet 3
Corridor Elev.
587'SI Cabinet 4
MEASUREMENT RANGE
'-100%
of instrument span 0-3000 psig 0-150 gpm 1-1 X 10 cps 6
MINIMUM CHANNELS OPERABLE 0
n A
OO I
C INSTRUMENT
. 1.
and 4 Level LOCATION CHANNEL CHECK LSI Cabinet 1 and LSI Cabinet 4
TABLF. 4.3-6A APPFNDIX R REMOTE SHUTDOWN MONITORING INSTRUMFNTATION SURVEILLANCE RE UIREMENTS CHANNEL CALIBRATION 2.
and 3 Level LSI Cabinet 2 and LSI Cabinet 4
3.
and 4 Pressure LSI Cabinet 4 and LSI Cab inet 5
4.
and 3 Pressure LSI Cabinet 4 and LSI Cabinet 6
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0 5.
Reactor Coolant Loop 4 Temperature (Cold) 6.
Reactor Coolant Loop 4 Temperature (Hot)
LSI Cabinet 4 and LSI Cabinet 5
LSI Cabinet 4 and LSI Cabinet 5
7.
Reactor Coolant Loop 2 Temperature (Cold)
LSI Cabinet 4 and LSI Cabinet 6
8.
Reactor Coolant Loop 2 Temperature (Hot)
LSI Cabinet 4 and LSI Cabinet 6
9.
Pressurizer Level g
10.
Reactor'Coolant System Pressure 11.
Charging Cross-Flow Between Units 12.
Source Range Neutron Detector (N-23)
LSI Cabinet 3
LSI Cabinet 3
Corridor Elev.
587'SI Cabinet 4
"M M
n/a n/a Charging Cross-Flow between Units is an instrument common to both Unit 1 and 2.
This surveillance will only be conducted on an interval consistent with Unit 1 refueling.
PLANT SYSTEMS AUXILIARYFEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3,7.1.2 H
a.
At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
1.
Two feedwater
- pumps, each capable of being powered from separate emergency
- busses, and 2.
One feedwater pump capable of being powered from an OPERABLE steam supply system.
b.
At least one auxiliary feedwater flow path in support of Unit 1 shutdown functions shall be available.
APPLICABILITY: Specification 3.7.1.2.a
- MODES 1, 2, 3.
Specification 3.7.1.2.b
- At all times when Unit 1 is in MODES 1, 2, or 3.
I ACTIONS:
I When Specification 3.7.1.2.a is applicable:
a.
With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
When -Specification 3.7.1.2.b is applicable:
With no flow path to Unit 1 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 1 and return at least one flow path to available status within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The requirements of Specification 3.0.4 are not applicable.
D.
C.
COOK - UNIT '2 3/4 7-5 Amendment No. 82 '>116
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PLANT SYSTEMS AUXILIARYFEEDWATER SYSTEM SURVEILLANCE RE UIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying that each motor driven pump develops an equivalent discharge pressure of ) 1240 psig at 60 F on recirculation flow.
2.
Verifying that the steam turbine driven pump develops an equivalent 0
discharge pressure of ) 1180 psig at 60 F and at a flow of )700 gpm when the secondary steam supply pressure is greater than 310 psig.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
3.
Verifying that each non-automatic valve in the flow path that is not
- locked, sealed, or otherwise secured in position is in its correct position.
4.
Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10%
RATED THERMAL POWER.
This requirement is not applicable for those portions of the Auxiliary Feedwater System being used intermittently to maintain steam generator level.
b.
At least once per 18 months during shutdown by:*
1.
Verifying that e'ach automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
2.
Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
3.
Verifying that the unit cross-tie valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
- The provisions of Specification 4.0.7 are applicable.
D.
C.
COOK - UNIT 2 3/4 7-6 Amendment No 77 97,116
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PLANT SYSTEMS 3 4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 a.
b.
At least two independent component cooling water loops shall At least one component cooling water flow path in support of functions shall be available.
be OPERABLE.
Unit 1 shutdown APPLICABILITY: Specification 3.7.3.l.a.
- MODES 1, 2, 3, 4.
Specification 3.7.3.l.b.
- At all times when Unit 1 is in MODES 1, 2, 3, or 4.
ACTION:
When Specification 3.7.3.1.a is applicable:
With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
When Specification 3.7.3.l.b is applicable:
With no flowpath in Unit 1 available, return at least one flowpath to available status within 7 days, or provide equivalent shutdown capability in Unit 1 and return at least one flow path to available status within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The requirements of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked,
- sealed, or otherwise secured 'in position, is in its correct position.
b.
At least once per 18 months during shutdown, by verifying that each automatic.
valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.*
4.7.3.2 At least once per 18 months during shutdown, verify that the unit cross-tie
. valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
- The provisions of Specification 4.0.7 are applicable.
D.
C.
COOK - UNIT 2 3/4 7-12, Amendment No. 97,116
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PLANT SYSTEMS 3 4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 a.
At least two independent essential service water loops shall be OPERABLE.
b.
At least one essential service ~ater flowpath associated with support of Unit 1 shutdown functions shall be available.
APPLICABILITY: Specification 3.7.4.l.a.
- MODES 1, 2, 3, and 4.
specification 3.7.4.1.b.
- At all times when Unit 1 is in MODES 1, 2, 3
or 4.
ACTION When Specification 3.7.4.1.a is applicable:
With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72"hours or be in at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
When specification 3.7.4.l.b is applicable:
With no essential service water flow path available in support of Unit 1 shutdown functions, return at least one flow path to available status within 7 days or provide equivalent shutdown capability in Unit 1 and return the equipment to service within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HOT SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The requirements of Specifications 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked,
- sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety. Injection test signal.*
- The provisions of Specification 4.0.7 are applicable.
C.
D.
COOK - UNIT 2 3/4 7-13 Amendment No. 97, f)(j
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4.1 REACTIVITY CONTROL SYSTEMS BASES With the RCS average temperature above 200 F, a minimum of two separate and redundant 0
boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoperable.
Allowable out
-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and safety injection pumps, except the required OPERABLE charging pump, to be inoperable below 152 F, unless the reactor vessel head is removed, provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
The boration capability of either system is sufficient to provide the required SHUTDOWN MARGIN from expected operating conditions after xenon decay and cooldown to 200 F.
The maximum expected boration capability usable volume requirement is 3700 gallons of-20,000 ppm borated water from the boric acid storage tanks or 118,000 gallons of 2000 ppm borated water from,the refueling water storage tank.
The numbers included in the Technical Specifications (BAST: 5470 gallons / RWST: 350,000 gallons) conservatively bound these and other applicable accident analysis requirements.
With the RCS average temperature below 200 F, one injection system is acceptable 0
without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
The boron capability required below 200 F is sufficient to provide the required MODE 5 SHUTDOWN MARGIN after xenon decay and cooldown from 200 F to 140 F.
This condition 0
0 requires usable volumes of either 4300 gallons of 20,0000 ppm borated water from the boric acid storage tanks or 90,000 gallons of 2000 ppm borated water from the refueling water storage tank.
The charging flowpath of Unit 2 required for Unit 1 shutdown support ensures that flow.is available to Unit 1 and addresses the requirements of 10 CFR 50 Appendix R.
The flowpath consists of a charging pump powered from an electrical bus and associated water supplies and delivery system.
Fire watches posted in the affected opposite unit areas (i.e., Unit 1 areas requiring use of the Unit 2 charging system in the event of a fire) may serve as the equivalent shutdown capability specified in the action statements of Specification 3.1.2'.
In the affected areas, either establish continuous fire watches or verify the OPERABILITY'of fire detectors per Specification 4.3.3.7 and establish hourly fire watch patrols.
The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfillingits intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure.
An additional plant procedure details how the above noted fire watches will be implemented.
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COOK - UNIT 2 B 3/4 1-3 Amendment No. 82, 107,116
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REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS Continued The limits on contained water volume and boron concentration of the RWST also ensure a
pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
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The OPERABILITY of boron in]ection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.-
3 4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod misalignment on associated accident analyses.
OPERABILITY of the control rod position indicators is required to determine control rod positions and.
thereby ensure compliance with tne control rod alignment and insertion limits.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.
Misalignment of a rod requires measurement of peaking factors or a restriction in THERMAL POWER; either of these restrictions provide assurance of fuel rod integrity during continued operation.
In addition, those accident analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.
The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses.
Measurement with T 541 F and with all reactor 0
ave coolant pumps operating ensures that the measured Sr5p times will be representative of insertion times experienced during a reactor trip at operating conditions.
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.
These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.
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COOK - UNIT 2 B 3/4 1-4 Amendment No. 39,116
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3 4.3 INSTRUMENTATION BASES 3 4.3.3 MONITORING INSTRUMENTATION 3 4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3 4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstr'ated by irradiating each detector used and normalizing its respective output.
3 4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capa-bility is required to permit comparison of the measured response to that used in the design basis for the facility.
3 4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological, instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
3 4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability if required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3 4.3.3.5.1 APPENDIX R REMOTE SHUTDOWN INSTRUMENTATION The OPER'ABILITY of the Appendix R remote shutdown instrumentation ensures that sufficient instrumentation is available to permit shutdown of the facility to COLD SHUTDOWN conditions at the local shutdown indication (LSI) panel.
In the event of a fire, normal power to the LSI panels may be lost.
As a result,.
capability to repower the LSI panels from Unit 1 has been provided. If the alternate power supply is not available, fire watches will be, established in D.
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COOK - UNIT 2 B 3/4 3-2 Amendment No. 82,95, 113,116
3 4.3 INSTRUMENTATION BASES cont.
these fire areas where loss of normal power to the LSI power could occur in the event of fire.
This will consist of either establishing continuous fire watches or verifying OPERABILITY of fire detectors per Specification 4.3.3.7 and establishing hourly fire watches.
The details of how these fire watches are to be implemented are included in a plant procedure.
3 4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident, The containment"water level and containment sump level transmitters will be modified or replaced and OPERABLE by the end of the outage currently scheduled to begin in May 1988.
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COOK - UNIT 2 B 3/4 3-2a Amendment No. 113,116 Amendment 95 (Effective before start up following refueling outage current scheduled in early 1988)
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PLANT SYSTEMS BASES 3 4.7.1.2 AUXILIARYFEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350 F from normal operating conditions in the 0
event of a total loss of off-site power.
Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pr'essure of 1065 psig to the entrance of the steam generators.
The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant system temperature to less than 350 F when the Residual Heat Removal System may be placed into operation.
The acceptance discharge pressures for the auxiliary feedwater pumps are.based on a fluid,,temperature of 60 F.
Wager density corrections are permitted to allow comparison 0
of test results, which vary depending on ambient conditions.
In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation).
During this time, the system design allows for automati.c initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.
The auxiliary feedwater flowpath, with a pump and associated water supplies and piping, will support shutdown cooling requirements of Unit 1.
This capacity addresses the 10 CFR 50 Appendix R safe shutdown requirements.
Fire watches posed in the affected opposite unit areas (i.e., Unit 1 areas requiring use of the Unit 2 auxiliary feedwater system in the event of a fire) may serve as the equivalent shutdown capability specified in the action statements of Specifications 3.7.1.2.
In the affected. areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per specification 4.3.3.7 and establish hourly fire watch patrols.
The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfillingits intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure.,
An additional plant procedure details how the above noted fire watches will be implemented.
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COOYi - UNIT 2 B 3/4 7-2 Amendment No. 82,~'16
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e 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 0
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 0
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
signal failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
3 4.7.3 AND 3 4.7.4 The OPERABILITY of the Unit 2 flowpaths which support Unit 1 shutdown functions ensures the availability of cooling functions on Unit 1 and addresses the requirements of 10 CFR 50 Appendix R.
The required flowpath consists of a pump and associated water supplies and delivery systems.
Fire watches posted in the affected opposite unit areas (i.e., Unit 1 areas requiring use of the Unit 2 component cooling water system or essential service water system in the event of a fire) may serve as the equivalent shutdown capability specified in the action statements of Specifications 3.7.3.1 and 3.7.4.1.
In the affected areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per Specification 4.3.3.7 and establish hourly fire watch patrols.
The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfillingits intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure.
An additional plant procedure details how the above noted fire watches will be implemented.
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 instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room 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 requirements of General Design Criteria 19 of Appendix "A",
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COOK - UNIT 2 B 3/4 7-4 Amendment No. 116
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(A PLANT SYSTEMS BASES other tasks (e.g.,
an operator on tour) provided that such personnel fulfilled the above stated requirements.
As a minimum, each area affected by an isolated low pressure CO system mu'st be visited every twenty-five (25) to thirty-five (35) minutes by the Roving Fire Watch Patrol.
Such measures will provide the necessary level of fire.protection while affordin'g necessary provisions for personnel safety.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is -required to be made avai lable in the affected areas until the inoperable equipment is restored to service.
When the inoperable fire-fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
Backup fire protection, equipment will normally take the form of permanently mounted fire extinguishers and/or fire hose stations in or near the
- area, or fire hoses routed to the affected areas.
However, it is not our intent to rely. on backup systems or other compensatory measures for an extended period of time and action will be taken to restore the inoperable portions of the fire suppression system to OPERABLE status within a reasonable period.
h The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met.
An allowance's made for ensuring a sufficient volume of Halon and CO in the storage tanks by verifying either the weight, level or pressure o$ the tanks.
In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capabi lity of the plant.
The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression, capability for continued protection of the nuclear plant.
The purpose of the charcoal filter fire suppression T/S is to account for detection and suppression of fires in the charcoal filters.
Yanual operation of these systems is allowed be'cause two-point heat detection with control room and local annunciation of trouble conditions is'rovided for the charcoal filters.
The OPERABILITY of the fire suppression system protecting the charcoal filters is only required when there is charcoal in the filters.
Actuation of spray.water onto the charcoal filters requires both the manual opening of the system'solation valve and reaching the high temperature alarm setpoint for the automatic opening of the system deluge valve.
Because of the inaccessibi lity of the lower containment to personnel during operation due to ALARA radiation exposure
- concerns, the use of, one or more CCTVS in the lower containment to monitor for fire and smoke, is an acceptable substitute to a continuous fire watch, if the fire suppression system becomes inoperable.
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COOK - UNIT 2 B 3/4 7-7 Amendment No. 115,i<6 July 15, 1986 Bases Clarification
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PLANT SYSTEMS BASES All hourly fire watch patrols are performed at intervals of sixty minutes with a margin of fifteen minutes.
A continuous fire watch requires that a trained individual be in the specified area at all times and that each fire zone within the specified area is patrolled at least once every fifteen minutes with a margin of five minutes.
A control valve is defined as a valve that when closed does not leave an alternate open flow path to a system.
A sectionalizing valve is defined as a
valve that when closed does not prevent an alternate open flow path to a system and hence does not make the fire suppression water system inoperable.
Under certain situations, the closure of a sectionalizing valve followed by the closure of a second valve will not leave an open flow path to one of the specified systems.
In this instance, Action Statement b of Specification 3.7.9. 1 i s app 1 icab 1 e.
Manual actuation of CO fire suppression systems provides adequate fire protection for the protected areas based on operable fire detection in the
- area, low combustible
- loadings, and prompt fire brigade response to alarms.
Many of the action statements take credit for operable fire detection in lieu of a fire watch when a fire protection system in inoperable.
Operable fire detection provides sufficient early warning capability of a fire to the appropriate Control Room.
During Surveillance Testing of a Low Pressure CO System with the system inoperable, t:he requirement for a continuous fir( watch may be suspended during portions of the test which result or may result in a discharge into the CO protected area.
Similarly, if a CO actuation occurs which results in the need to have the Low Pressure CO S)stem made inoperable, the requirement for a continuous fire watch may be suspended.
In either case, the area affected shall be restored to habitabi lity as soon as practicable, after which the continuous fire watch is to be re-established if the system is still inoperable.
~34.7.10 FIRE RATED ASSEIIBLIES The OPERABILITY of the fire barriers and barrier penetrations ensures that fire damage will be limited.
These design features minimize the possibility of a single fire involving more than one fire area prior to detection and extinguishment.
The fire barriers and fire barrier penetration sealing devices are periodically inspected to verify their OPERABILITY.
The functional testing of the fire dampers is provided to ensure that the dampers remain functional.
The ventilation seals are seals around ventilation duct work penetrating fire barriers.
It is not our intent to rely on backup systems or other compensatory measures for an extended period of time and action will be taken to restore the inoperable portions of the fire rated assembly to OPERABLE status within a reasonable period.
For the purpose of determining OPERABILITY, an OPERABLE fire rated assembly/
sealing device is one that is capable of performing its intended safety function.
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COOK - UNIT 2 B 3/4 7-8 Amendment No. 115,)i6 July 15, 1986 Bases Clarification
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