ML17325B653
| ML17325B653 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/08/1999 |
| From: | Craig C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17325B654 | List: |
| References | |
| NUDOCS 9906150127 | |
| Download: ML17325B653 (14) | |
Text
gp,S AEgi UNITED STATES NUCLEAR REGULATORY COMMlSSlON WASHlNGTON, D.C. 2055&0001 INDIANAMICHIGANPOWER COMPANY DOCKET NO. 50-315 DONALDC. COOK NUCLEAR PLANT UNIT 1 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 228 License No. DPR-58 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated April 19, 1999, 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 facilitywilloperate in conformity with the application, the provisions ofthe 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 willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot 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 ofthe Commission's regulations and all applicable requirements have been satisfied.
(
9'PObi50i27 990b08 l
PDR ADQCK 050003i5 PDR Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-58 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 228, are hereby incorporated in the license. The licensee shaH operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as ofthe date of issuance, with fullimplementation within 45 days.
FOR THE NUCLEAR REGULATORYCOMMISSION
<0 Claudia M. Craig, Chief, Section 1
Project Directorate III Division of Licensing Project, Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 8, 1999
ATTACHMENTTO LICENSE AMENDMENTNO.228 TO FACILITYOPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE 3/4 8-9 B 3/4 8-1 INSERT 3/4 8-9 B 3/4 8-1
~
3/4 LIMI'IINGCONDITIONS FOR OPERATION ANDSURVEILLANCEREQUIREMEN'IS 3/4.8 ELECTRICALPOQXR SYSTEMS SHUTDOWN L'IMITINGCONDITION FOR OPERATION 3.8.'1.2 As a minimum, the followingA.C. electrical power sources shall be OPERABLE:
a.
One circuit between the offsite transmission network and the onsite Class 1E distribution system, and One diesel generator with:
1.
A day fuel tank containing a minimum of70 gallons of fuel, 2.
A fuel storage system containing a milium indicated volume of.46,000 gallons of fuel, and 3.
A fuel transfer pump.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONSor positive reactivity changes until the minimum required A.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCERE UIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2.a.5.
Commencing in l999 during the extended shutdown initiated in 1997, the 18-month surveillance requirements 4.8.1.12.e.4.a) and b); 4.8.1.12.e.6.a),
b) and c); 4.8.1.1.2.e.8; 4.8.1.1.2.e.9.a),
b) and c); 4.8.1.12.e.10.a) and b); and 4.8.1.12.e.l I, may bc delayed one time untiljust prior to the
~ first entry into MODE4 followingthe shutdown.
'For purposes ofthis specification, addition ofwater 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.b2.
COOK NUCLEARPLANT-UNITI Page 3/4 8-9 AMENDMENT &5, 44S 228
3/4 BASES 3/4.8 ELEC'DUCALPOWER. SYSTEMS The OPERABIUTYof the A.C. and D.C power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for I) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility.
The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix "A"to 10 CFR 50.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation, The OPERABIUTY of the power sources are consistent with the initial condition assumptions of the accident aitalyses and are based upon maintaining at least.
one of each of the onsite A.C. and D.C. power sources and associated disn.bution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and.single faHure of the other onsite A.C.
sollfce.
The OPERABILITYof the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the facility status.
Specific surveillance requirements (SRs) ofSR 4.8.1.2 may be delayed one time untiljust prior to the first entry into MODE 4 following the extended outage that commenced. in 1997.
The delay is permitted to recognize the significant ongoing maintenance to safety systems and components that would be required to be OPERABLE solely to support the referenced surveillances.
The delay recognizes the reduced decay heat load and fission product activities resulting from the extended shutdown and consequently the small benefit &om performing the surveillances prior to the next entry into MODE 4. It is the intent that these SRs must still be capable ofbeing met.
but actual performance is not required until the required safety systems are ready to support entry into MODE 4.
The AB and CD station banery systems provide a reliable source of continuous power for supply and control of plant loads such as switchgear and annunciator control circuits, static inverters, valve control centers, emergency lighting and motor control centers.
The design duty cycles of these batteries are composite load profiles resulting from the c'ombination of the three hour Loss Of Coolant Accident/Loss Of Offsite Power battery load profiles and the four hour Station Blackout battery load profiles.
The train N station battery system provides an independent 250 volt DC power supply for power and control of the turbine driven auxiliary feedwater pump train.
'Ihe limiting conditions of operation for the train N battery are consistent with the requirements of the auxiliary feedwater system.
The surveillance requirements for the train N battery system are consistent'with the requirements ofthe AB and CD station batteries.
The train N battery loads are derived from equipment in the turbine driven auxBiary feedwater pump train and battery sizing is consistent with the functional requirements of these components.
Simulated loads for battery tests are loads equivalent to measured actual loads.
COOK NUCLEARPLANT-UNITI Page B 3/4 8-1 AMENDMENT86, 498 228.
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~O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHlNGTON, D.C. 2055&0001 INDIANAMICHIGANPOWER COMPANY DOCKET NO. 50-316 DONALDC. COOK NUCLEAR PLANT UNIT2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No.'11 License No. DPR-74 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated April 19, 1999, 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 facilitywilloperate 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 willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot 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 ofthe Commission's regulations and all applicable requirements have been satisfied.
2.
3.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-74 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 211, are hereby incorporated in the license. The licensee shall operate the facilityin accordance with the Technical Specifications.
This license amendment is effective as of the date of issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORYCOMMISSION Claudia M. Craig, Chief, Section 1
Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 8, 1999
ATTACHMENTTO LICENSE AMENDMENTNO. 211 FACILITYOPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE 3/4 8-9 B 3/4 8-1 INSERT 3/4 8-9 B 3/4 8-1
3/4 LIMI'HNGCONDITIONS FOR OPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.8.1.2 As a minimum, the folio+kgA.C. electrical power sources shall be OPERABLE:
a.
One circuit between the offsite transmission network and the onsite Class 1E distribution system, and One diesel generator with:
1.
A day fuel tank containing a minimum of70 gallons of fuel, 2.
A fuel storage system containing a minimum indicated volume of 46,000 gallons offuel, and
/
g APPLICABILITY:
3.
A fuel transfer pump.
MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONSor positive reactivity changes until the minimum required A.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCERE UIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2.a5.
Commencing in 1999 during the extended shutdown initiated in 1997, the 18-month surveillance requirements 4.8.1.12.e.4.a) and b); 4.8.1.12.e.6.a),
b) and c); 4.8.1.12.e.8; 4.8.1.12.e.9.a),
b) and c); 4.8.1.12.e.l0.a) and b); and 4.8.1.12.e.i I, may be delayed one time untiljust prior to the first entry into MODE4 followingthe shutdown.
For purposes ofthis specification, addition ofwater 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 NUCLEARPLANT-UNIT2 Page 3/4 $-9 AMENDMENT442, 482, 459 211
3/4 BASES 3/4.8 ELECTRICALPOWER SYSTIMS The OPERABILITYofthe A.C. and D.C power sources and associated distribution systems during operation ensures that efficient'power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility.
The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requiremems of General Design Criteria 17 ofAppendix "A"to 10 CFR 50.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon contini=~ facBity operation commensurate with the level of degradation.
The OPERABILITYof the power sources are consistent with the initial condition assumptions of the accident analyses and are based upon maintaining at least one of each of the onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsit'e A.C.
source.
The OPERABILITYof the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that I) the facBity can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the facBity status.
Specific surveillance requirements (SRs) ofSR 4.8.12 may be delayed one time untiljust prior to the first entry into MODE 4 following the extended outage that commenced in 1997.
The delay is permitted to recognize the significant ongoing maintenance to safety systems and components that would be required to be OPERABLE solely to support the referenced surveillances.
The delay recognizes the reduced 'decay heat load and reduced fission product activities resulting from the extended shutdown and consequently the small benefit from performing the surveillances prior to the next entry into MODE 4. It is the intern that these SRs must still be capable ofbeing met, but actual performance is not required until the required safety systems are ready to support entry into MODE 4.
The AB and CD station battery systems provide a reliable source ofcontinuous power for'supply and control ofplant
'oads such as switchgear and annunciator control circuits, static inverters, valve control centers, emergency lighting and motor control centers.
The design duty cycles of these batteries are composite load profiles.resultmg from the combination of the three hour Loss Of Coolant Accident/Loss Of Offsite Power battery load profiles and the four hour Station Blackout battery load profiles.
The train N station battery system provides an independent 250 volt DC power supply for power and control of the turbine driven auxiliary feedwater pump train.
The limiting conditions of operation for the train N battety are consistent with the requirements of the auxiliaty feedwater system.
'IIte surveillance requirements for the train N battery system are consistent with the requirements of the AB and CD station batteries.
The train N battety loads are derive'd from equipment in the turbine driven auxiiiaty feedwater pump train and battery sizing is consistent with the functional requirements of these components.
Simulated loads for battery tests are loads equivalent to measured actual loads.
COOK NUCLEARPLANT-UNIT2 Page B 3/4 8-1 AMIM)MENTVB, 483 211