Letter Sequence RAI |
|---|
|
|
MONTHYEARML0330904002003-11-10010 November 2003
Request for Additional Information, Increase in Main Steam Line Turbine Building High Temperature Trip Setpoint Allowable Value
Project stage: RAI
ML0335000942004-01-0606 January 2004
Request for Additional Information for License Amendment Request, Increase in Main Steam Line Turbine Building High Temperature Trip Setpoint Allowable Value
Project stage: RAI
ML0402006692004-01-16016 January 2004
RAI, Increase in Main Steamline Turbine Building High Temperature Trip Setpoint Allowable Value (Tac. No. MC0342)
Project stage: RAI
ML0403701412004-01-22022 January 2004
Response to RAI Regarding License Amendment Request to Increase Main Steam Line Turbine Building High Temperature Trip Setpoint Allowable Value
Project stage: Response to RAI
ML0408605702004-03-31031 March 2004
Request for Additional Information (Rai), Review of License Amendment Request to Increase the Main Steam Line Turbine Building High Temperature Trip Setpoint Allowable Value
Project stage: RAI
ML0413402602004-05-0606 May 2004
Response to Second Request for Additional Information Regarding License Amendment Request to Increase Main Steam Line Turbine Building High Temperature Trip Setpoint Allowable Value
Project stage: Request
ML0418106862004-07-0909 July 2004
Amendment, Primary Containment and Drywell Isolation Instrumentation
Project stage: Other
ML0419401992004-07-0909 July 2004
Technical Specifications, Issuance of Amendment Regarding Primary Containment and Drywell Isolation Instrumentation to Increase the Analytical Limit for Detected Temperature
Project stage: Approval
ML0423606802004-08-26026 August 2004
Letter, Correction to Safety Evaluation Report in Support of License Amendment 130. TAC No. MC0342
Project stage: Approval
2004-01-06
[Table View] |
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[Table view] |
Text
January 16, 2004 Mr. William R. Kanda, Vice President - Nuclear FirstEnergy Nuclear Operating Company 10 Center Road P.O. Box 97 Perry, OH 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION (RAI) FOR LICENSE AMENDMENT REQUEST (LAR),
INCREASE IN MAIN STEAMLINE TURBINE BUILDING HIGH TEMPERATURE TRIP SETPOINT ALLOWABLE VALUE (AV) (TAC. NO. MC0342)
Dear Mr. Kanda:
By letter dated August 14, 2003, FirstEnergy Nuclear Operating Company (FENOC), requested approval of a license amendment request for the Perry Nuclear Power Plant (PNPP). The proposed LAR increases the analytical limit and the resulting Technical Specification AV related to the setpoint for the main steam line turbine building temperature - high, system isolation function.
During the review, the Nuclear Regulatory Commission staff has identified that additional information is needed in order to complete the review. The specific question is presented in the enclosed request for additional information (RAI).
The enclosed information has already been discussed with your staff. In order to accommodate PNPPs needs, please provide your response for this RAI by February 15, 2004. If you have any questions concerning our review, or additional time is needed to respond to the RAI, please contact me at (301) 415-3154.
Sincerely,
/RA/
Stephen P. Sands, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Request for Additional Information cc w/encl: See next page
January 16, 2004 Mr. William R. Kanda, Vice President - Nuclear FirstEnergy Nuclear Operating Company 10 Center Road P.O. Box 97 Perry, OH 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION (RAI) FOR LICENSE AMENDMENT REQUEST (LAR),
INCREASE IN MAIN STEAMLINE TURBINE BUILDING HIGH TEMPERATURE TRIP SETPOINT ALLOWABLE VALUE (AV) (TAC. NO. MC0342)
Dear Mr. Kanda:
By letter dated August 14, 2003, FirstEnergy Nuclear Operating Company (FENOC), requested approval of a license amendment request for the Perry Nuclear Power Plant (PNPP). The proposed LAR increases the analytical limit and the resulting Technical Specification AV related to the setpoint for the main steam line turbine building temperature - high, system isolation function.
During the review, the Nuclear Regulatory Commission staff has identified that additional information is needed in order to complete the review. The specific question is presented in the enclosed request for additional information (RAI).
The enclosed information has already been discussed with your staff. In order to accommodate PNPPs needs, please provide your response for this RAI by February 15, 2004. If you have any questions concerning our review, or additional time is needed to respond to the RAI, please contact me at (301) 415-3154.
Sincerely,
/RA/
Stephen P. Sands, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440 DISTRIBUTION PUBLIC PD3-2 r/f
Enclosure:
Request for Additional Information AMendiola SSands THarris OGC cc w/encl: See next page ACRS SReynolds, RIII DOCUMENT NAME: ML040200669 OFFICE PM:LPD3-2 LA:LPD3-2 SC:LPD3-2 NAME SSands THarris DPickett for, AMendiola DATE 1/14/04 1/13/04 1/15/04 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION PERRY NUCLEAR POWER PLANT (PNPP)
INCREASE IN MAIN STEAMLINE TURBINE BUILDING HIGH TEMPERATURE TRIP SETPOINT ALLOWABLE VALUE The Nuclear Regulatory Commission staff has reviewed the August 14, 2003, FirstEneregy Nuclear Operatin Company submittal regarding changes to the Perry Nuclear Power Plant license amendment request to increase the main steamline turbine building high temperature -
high, system isolation valve, and has the following additional question concerning the submittal:
The submittal states that with a leak of 280 gallons per minute (gpm), the Main Steam system will isolate in about 17.5 minutes to limit the impact of the leak. The submittal does not discuss leaks of <280 gpm but >25 gpm. The staff is concerned that a lesser, but still substantial leak could go undetected for an extended period of time with unanalyzed consequences. The licensee needs to provide an analysis that addresses the impact of leaks between 25 gpm and 280 gpm.
