Letter Sequence RAI |
|---|
|
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MONTHYEARML0607605322006-03-0707 March 2006
Technical Specification Change of Interlock for a Reactor Trip on Turbine Trip
Project stage: Other
ML0608306282006-03-31031 March 2006
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML0615202802006-06-0101 June 2006
DC Cook, RAI, Shifting the Reactor Trip on Turbine Trip Interlock from P-7 to P-8
Project stage: RAI
ML0615200982006-06-0101 June 2006
Draft RAI Cook Proposed Amendment, P-7 to P-8
Project stage: Draft RAI
ML0628401622006-10-30030 October 2006
License Amendments 297 and 278 Regarding Reactor Trip System Instrumentation
Project stage: Other
ML0630500862006-10-30030 October 2006
Tech Spec Pages for Amendments 297 and 278 Regarding Reactor Trip System Instrumentation
Project stage: Other
ML0714200712007-05-11011 May 2007
Technical Specification Change of Conditional Surveillance Frequency
Project stage: Other
2006-03-07
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[Table view] |
Text
June 1, 2006MEMORANDUM TO: Richard J. Laufer, Chief Plant Licensing Branch A Division of Operating Reactor LicensingFROM:John A. Nakoski, Chief/RA/PWR Reactor Systems Branch Division of Safety Systems
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: SHIFTING THEREACTOR TRIP ON TURBINE TRIP INTERLOCK FROM P-7 TO P-8 (TAC NOS. MD0496 AND MD0497)Plant Name:D.C. Cook Units 1 and 2Utility:Indiana & Michigan Power CompanyTAC No.:MD0496 and MD0497 Docket Nos.:50-315 and 50-316 Operating License Nos.:DPR-58 and DPR-74 Project Directorate:A Project Manager:Peter Tam Review Branch:DSS/SPWB Review Status:Not completeBy letter dated March 7, 2006, Indiana & Michigan Power Company (I&M), the licensee,proposed certain modifications to the reactor protection systems of the D.C. Cook units, and tothese plants' Technical Specifications, to shift the interlock of reactor trip on turbine trip from the P-7 permissive to the P-8 permissive. The proposed modifications would result in reactor trip, due to turbine trip, when the P-8 permissive is active (at 31% power and above). Currently, the reactor would trip when the turbine trips when the P-7 permissive is active (at 10% power and above). The staff, in order to complete its review of the licensee's proposal, requests the additionalinformation that is identified in the attachment.
Enclosure:
As stated CONTACT: S. Miranda, NRR/DSS/SPWB415-2303 June 1, 2006MEMORANDUM TO: Richard J. Laufer, Chief Plant Licensing Branch A Division of Operating Reactor LicensingFROM:John A. Nakoski, Chief/RA/PWR Reactor Systems Branch Division of Safety Systems
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: SHIFTING THEREACTOR TRIP ON TURBINE TRIP INTERLOCK FROM P-7 TO P-8 (TAC NOS. MD0496 AND MD0497)Plant Name:D.C. Cook Units 1 and 2Utility:Indiana & Michigan Power CompanyTAC No.:MD0496 and MD0497 Docket Nos.:50-315 and 50-316 Operating License Nos.:DPR-58 and DPR-74 Project Directorate:A Project Manager:Peter Tam Review Branch:DSS/SPWB Review Status:Not completeBy letter dated March 7, 2006, Indiana & Michigan Power Company (I&M), the licensee,proposed certain modifications to the reactor protection systems of the D.C. Cook units, and tothese plants' Technical Specifications, to shift the interlock of reactor trip on turbine trip from the P-7 permissive to the P-8 permissive. The proposed modifications would result in reactor trip, due to turbine trip, when the P-8 permissive is active (at 31% power and above). Currently, the reactor would trip when the turbine trips when the P-7 permissive is active (at 10% power and above). The staff, in order to complete its review of the licensee's proposal, requests the additionalinformation that is identified in the attachment.
Enclosure:
As stated CONTACT: S. Miranda, NRR/DSS/SPWB415-2303DISTRIBUTION
- PublicRidsNrrDssSpwb (JNakoski)
DSS/SPWB r/fSMiranda RidsNrrDss (JWermiel) RidsOgcRp RidsAcrsAcnwMailCenterRidsRgn2MailCenterRidsNrrDssDprPTamAccession Number: ML061520280NRR-088OFFICEDSS/SPWB/PMDSS/SPWB/BCNAMESMirandaJNakoskiDATE 6 / 1 /2006 6 / 1 /2006OFFICIAL RECORD COPY Request for Additional Information1.Please provide copies of all Westinghouse Nuclear Safety Advisory Letters (NSALs) thatallude to permissives P-7 and P-8.2.If applicable, describe how these NSALs have been used in preparing the proposal toshift the reactor trip on turbine trip interlock from P-7 to P-8.3.Please provide a safety analysis or evaluation to show that tripping one reactor coolantpump, when the plant is at 31% power, will satisfy all ANS Condition II acceptancecriteria without crediting the low flow reactor trip.4.Please provide a safety analysis or evaluation to show that the seizure of one reactorcoolant pump rotor or the shearing of one reactor coolant pump shaft, when the plant is at 31% power, will satisfy all ANS Condition IV acceptance criteria without crediting thelow flow reactor trip.5.The Cook UFSARs state, "ANS Condition II occurrences are faults that may occur withmoderate frequency during the life of the plant. They are accommodated with, at most, a reactor shutdown with the plant being capable of returning to operation after a corrective action. In addition, no ANS Condition II occurrence shall cause consequential loss of function of fuel cladding and reactor coolant system barriers." Show thatinadvertent actuation of the emergency core cooling system would not cause aconsequential loss of the reactor coolant system barrier (by filling the pressurizer;causing the pressurizer power-operated relief valves to open, to discharge water, and consequently, to fail to reseat properly). See RIS 2005-29 for more information.
