Letter Sequence RAI |
|---|
|
|
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
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Project stage: Draft RAI
ML0628401622006-10-30030 October 2006
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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, 2006 MEMORANDUM TO: Richard J. Laufer, Chief Plant Licensing Branch A Division of Operating Reactor Licensing FROM: John A. Nakoski, Chief /RA/
PWR Reactor Systems Branch Division of Safety Systems
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: SHIFTING THE REACTOR TRIP ON TURBINE TRIP INTERLOCK FROM P-7 TO P-8 (TAC NOS. MD0496 AND MD0497)
Plant Name: D.C. Cook Units 1 and 2 Utility: Indiana & Michigan Power Company TAC 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 complete By 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 to these 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 licensees proposal, requests the additional information that is identified in the attachment.
Enclosure:
As stated CONTACT: S. Miranda, NRR/DSS/SPWB 415-2303
June 1, 2006 MEMORANDUM TO: Richard J. Laufer, Chief Plant Licensing Branch A Division of Operating Reactor Licensing FROM: John A. Nakoski, Chief /RA/
PWR Reactor Systems Branch Division of Safety Systems
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: SHIFTING THE REACTOR TRIP ON TURBINE TRIP INTERLOCK FROM P-7 TO P-8 (TAC NOS. MD0496 AND MD0497)
Plant Name: D.C. Cook Units 1 and 2 Utility: Indiana & Michigan Power Company TAC 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 complete By 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 to these 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 licensees proposal, requests the additional information that is identified in the attachment.
Enclosure:
As stated CONTACT: S. Miranda, NRR/DSS/SPWB 415-2303 DISTRIBUTION:
Public RidsNrrDssSpwb (JNakoski)
DSS/SPWB r/f SMiranda RidsNrrDss (JWermiel) RidsOgcRp RidsAcrsAcnwMailCenter RidsRgn2MailCenter RidsNrrDssDpr PTam Accession Number: ML061520280 NRR-088 OFFICE DSS/SPWB/PM DSS/SPWB/BC NAME SMiranda JNakoski DATE 6 / 1 /2006 6 / 1 /2006 OFFICIAL RECORD COPY
Request for Additional Information
- 1. Please provide copies of all Westinghouse Nuclear Safety Advisory Letters (NSALs) that allude to permissives P-7 and P-8.
- 2. If applicable, describe how these NSALs have been used in preparing the proposal to shift 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 coolant pump, when the plant is at 31% power, will satisfy all ANS Condition II acceptance criteria without crediting the low flow reactor trip.
- 4. Please provide a safety analysis or evaluation to show that the seizure of one reactor coolant 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 the low flow reactor trip.
- 5. The Cook UFSARs state, ANS Condition II occurrences are faults that may occur with moderate 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 that inadvertent actuation of the emergency core cooling system would not cause a consequential 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.
