ML17332A993
| ML17332A993 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/17/1995 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17332A994 | List: |
| References | |
| NUDOCS 9510270202 | |
| Download: ML17332A993 (18) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY
~E DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 203 License No. DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the
'icensee) dated March 31,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
.and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9510270202 95iOi7 PDR ADQCK 050003i5 P
I 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 8, as revised through Amendment No.
203
, 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 issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 17, 1995 John B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
TTACHMENT TO LICENSE AMENDMENT NO.
203 TO FACILITY 0 ERATING ICENSE NO.
DPR-58 DOCKE 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 vertical lines indicating the area of change.
REMOVE 3/4 1-11 3/4 1-12 3/4 5-5 3/4 6-10 3/4 7-6 INSERT 3/4 1-11 3/4 1-12 3/4 5-5 3/4 6-10 3/4 7-6
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTXVITYCONTROL SYSTEMS
, CHARGING PUMP - SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.1.2.3 One charging pump in the boron injection fiow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
One charging fiowpath associated 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.
~ ~CTION:
a.
With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactiviry changes."
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 or equal to 152'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 ofSpecification 3.0.3 are not applicable.
In addition to the above, when Specification 3.1.2.3.b is applicable and the required flowpath is aot available, retuin the required flowpath to available status within7 days, or provide equivalent shutdown capability in Unit 2 and return the required fiowpath to available status within the next i'ays, or have Unit 2 in HOT STANDBYwithin 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 followmg 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The requirements ofSpecification 3.0.4 are not applicable when Specification 3.1.2.3.b applies.
SURVEILLANCERE UIREMENTS 4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE by verifying that the pump's developed head at the test fiow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.
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 152'F.
'For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the bomn concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.
COOK NUCLEAR PLANT-UNITI Page 3/4 1-11 ALIENE>DMENT9S, 4Ã, 434) 444, ~
203
a 3/4 LIMITINGCONBITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS
~ CHARGING PUMPS - COOPERATING LIMITINGCONDITICk4 FOR OPERATION 3.1.2.4 At least nvo charging pumps shall be OPERABLE.
'MODES 1, 2, 3 and 4.
ACTION:
With only one charging pump OPERABLE, restore at least two charging punips 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 HOT SYANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE status within the next 48lhours or be 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 />.
SURVEILLANCERE CEREMENTS 4.1.2.4 At leasa two charging pumps shall be demonstrated OPERABLE by verifying that the pumps'eveloped head at the test flowpoint is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.
COOK NUCLEAR PLA~x-IiNIT1 Page 3/4 1-12 mIZmMENTIts, 444 203
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
.SURVEILLANCERE UIREMENTS Continued At least once per 18 months by:
1.
Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.
2.
A visual inspection of the containment sump aad verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, ctc.) show no evidence of structural distress or abnormal corrosion.
At least once per 18 months, during shutdown, by:
Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.
2.
Verifying that each of the following pumps stan automatically upon receipt of a safety injection signal:
a)
Ceatrifugal charging pump b)
Safety injection pump c)
Residual heat removal pump By verifying that each of the followiag pumps'eveloped head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.
1.
Centrifugal charging pumps 2.
Safety injection pumps 3.
Residual heat removal pumps g
By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System thronle valves:
1.
Within4 hours following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
COOK NUCLEAR PLANT-UMTI Page 3/4 5-5
'IIENDilIENT4Pf 4jgf 444/ 448$ 444
~ 203
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIRE&IENTS 3/4.6 CONTAINMENTSYSTEMS
'4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENTSPRAY SYSTEM LIMITINGCONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.
'*'CTI ON:
With one containment spray system inoperable, restore the inoperable spray system 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 />; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be 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 />.
SURVEILLANCERE UIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
By verifying that each containment spray pump's developed head at the test fiow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.
C.
At least once per 18 months during shutdown, by:
1.
Verifying that each automatic valve in the low path actuates to its correct position on a Containment Pressure High-High test signal.
2.
Verifying that each spray pump starts automatically on a Containment Pressure High-High test signal.
At least once per 10 years by performing an air or smoke fiow test through each spray header and verifying each spray nozzle is unobstructed.
COOK iNUCLEARPLAiVI'-UNITI Page 3/4 6-10 AilIE; DMENT407, 444, 464'Q 203
3/4 LSIITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCERE UIREMENTS Continued 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE when tested pursuant to Specificatioa 4.0.5 by:
a.
Verifying that each motor driven auxiliary feedwater pump's developed head at the test flow point is greater than or equal to the required developed head.
b.
Verifyinthat the turbine driven auxiliary feedwater pump's developed head at the test fiow point is greater than or equal to the required developed head when the secondary steam supply pressure is greater than 310 psig. The provisions ofSpecification 4.0.4 are aot applicable for entry into MODE 3.
C.
Verifying that each non-automatic valve in the fiow path that is not locked, sealed, or otherwise secured in position is in its correct position.
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 water level.
Verifying at least once per 18 months during shutdown that each automatic valve in the flowpath actuates to its correct position upon receipt ofthe appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
Verifying at least once per 18 months during shutdowa 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.
Verifying at least once per 18 months during shutdowa that the unit cross-tie valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
COOK NUCLEAR PLANT-UNITI Page 3/4 7-6 AilIENDMENT400, ~, 444) 444 203
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 188 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
The application for amendment by Indiana Michigan Power Company (the licensee) dated March 31, 1995, 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 provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
188
, 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 issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 17, 1995 John B.. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear, Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO 188 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 vertical lines indicating the area of change.
REMOVE 3/4 1-11 3/4 1-12 3/4 5-5 3/4 6-10 3/4 7-6 INSERT 3/4 1-11 3/4 1-12 3/4 5-5 3/4 6-10 3/4 7-6
i i
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS
~
CHARGING PUMP - SHUTDOWN LIMITINGCONDITION 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 fiow path associated with support of Unit I shutdown functions shall be available.
'pecification 3.1.2.3.b. - At all times when Unit 1 is in MODES I, 2, 3, or 4.
ACTION:
With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes."
With more than one charging pump OPERABLE or with a safety injection pump(s) OPERABLE when the temperature ofany RCS cold leg is less than or equal to 152'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.
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 fiow path is not available, return the required fiowpath to available status within 7 days, or provide equivalent shutdown capability in Unit I and return the required flow path to available status within the next 60 days, or have Unit I in HOT STANDBYwithin 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 Speciifiication 3.1.2.3.b applies.
SURVEILLANCERE UIREMENTS 4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE by verifying that the pump's developed head at the test flow point is greater than or equal to the requited developed head when tested'pursuant to Specification 4.0.5.
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 152'F.
For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 1-11 mlEiVmiENTgg, uP, 444 188
3/4,.
LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREi>IENTS 3/4.1 REACHVI'IYCONTROL SYSTEMS CHARGI'NG PUMPS - OPERATING LIMITINGCONDITION FOR OPERATION 3.1.2A At least two charging pumps shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one charging pump OPERABLE, restore at least two charging 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 STANDBYand borated to a SHUTDOWiVMARGINequivalent to at least 1% hk/k at 200'F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE status within the next 7 days or. be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCERE UIREMENTS 4.1.2.4 At least two charging pumps shall be demonstrated OPERABLE by verifying that the pumps'developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 1-12 'iWIENDMEiVT B0 188
3/4 LIMITINGCONDITIONS FOR OPERATION ANDSURVEILLANCEREQUHUMENTS 3/4.3 EMERGENCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCERE UIREMENTS Continued d.
At least once per 18 months by:
l.
Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System prcssure is above 600 psig.
2.
A visual inspection of the containment sump and verifying that thc subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of stnictural distress or corrosion.
C.
At least once per 18 months, during shutdown, by:
l.
Verifying that each automatic valve in the fiow path actuates to its correct position on a Safety Injection test signal.
2.
Verifying that each of thc following pumps start automatically upon receipt of a safety injection test signal:
a)
Centrifugal charging pump b)
Safety injection pump c)
Residual heat removal pump By verifyin that, each of the following pumps'eveloped head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.
1.
Centrifugal charging pumps 2.
Safety injection pumps
'.3.
Residual heat removal pumps By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
1.
Within4 hours following completion ofeach valve stroking operation or maintenance on the valve when the ECCS subsystems arc required to be OPERABLE.
COOK NUCLEAR PLANT-UiiT2 Page 3/4 &9 AMEi&SIEÃT434, 434, 4N, 480 188
i i
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIIKMENTS 3/4.6 CONTAINMEiVI'YSTEMS 3/4.'6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENTSPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transfemng suction to the containment sump.
~CTlON:
With one containment spray system inoperable, restore the inoperable spray system 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 />; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be 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 />.
SURVEILLANCERE UIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the fiow path that is not locked, mled, or otherwise secured in position, is in its correct position.
b.
By verifying that each containment spray pump's developed head at the test flow point is greater than or etual to the required developed head when tested pursuant to Specification 4.0.5.
C.
At least once pcr 18 months during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure High-High test signal.
2.
Verifying that each spray pump starts automatically on a Containment Pressure High-High test signal.
At least once per 10 years by performing an air or smoke fiow test through each spray header and verifying each spray nozzle is unobsuucted.
COOK NUCLEAR PLANT-UiiilT2 Page 3/4 6-10 AilfEiVDKIE.iT %, 434, 4$8, 448 188
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIIUMENTS 3/4.7 PLANTSYSTEMS
. SURVEILLANCERE UIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE when tested pursuant to Specification 4.0.5 by:
a.
Verifyingthat each motor driven auxiliary feedwater pump's developed head at the test flowpoint is greater than or equal to the required developed head.
'erifying that the turbine driven auxiliaty feedwater pump's developed head at the test flow point is greater than or equal to the required developed head when the secondary steam supply pressure is greater than 310 psig. The provisions ofSpecification 4.0.4 are not applicable for entry into MODE 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.
d.
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.
e.
Verifying at least once per 18 months during shutdown that each automatic valve in the flowpath actuates to its correct position upon receipt ofthe appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.
Verifying at least once per 18 months during shutdown 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.
g-Verifying at least once per 18 months during shutdown that the unit cross-tie valves can cycle full travel.
Following cycling, the valves will be verified to be in their closed positions.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 74 AjVIENDMENTVV, %, 444, 434, 449~
~,~,
188