ML061990634

RAI, Proposed Amendment to Revise the Limiting Condition for Operation 3.10.1

ML061990634
Person / Time
Site:	Duane Arnold
Issue date:	07/24/2006
From:	Spaulding D NRC/NRR/ADRO
To:	Vanmiddlesworth G Nuclear Management Co
D. Spaulding LPL3-1 X2928
References
TAC MD0293
Download: ML061990634 (6)

Text

July 24, 2006Mr. Gary Van MiddlesworthVice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785

SUBJECT:

DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONALINFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293)

Dear Mr. Van Middlesworth:

Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting conditionfor operation 3.10.1, to allow ancillary testing to occur during the evolutions associated withperforming the American Society of Mechanical Engineers Code Class I leak test of the reactor pressure vessel, at the Duane Arnold Energy Center. We are reviewing this information, and find that we need additional information as shown in theenclosed request for additional information (RAI). I discussed this RAI with Tony Browning of your organization on July 18, 2006, and he agreed to respond within 30 days of receipt of this RAI. Please contact me at (301) 415-2928 if you have questions.Sincerely,/RA/Deirdre W. Spaulding, Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-331

Enclosure:

RAIcc w/encl: See next page Mr. Gary Van MiddlesworthJuly 24, 2006Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785

SUBJECT:

DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONALINFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293)

Dear Mr. Van Middlesworth:

Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting conditionfor operation 3.10.1, to allow ancillary testing to occur during the evolutions associated withperforming the American Society of Mechanical Engineers Code Class I leak test of the reactor pressure vessel, at the Duane Arnold Energy Center. We are reviewing this information, and find that we need additional information as shown in theenclosed request for additional information (RAI). I discussed this RAI with Tony Browing of your organization on July 18, 2006, and he agreed to respond within 30 days of receipt of this RAI. Please contact me at (301) 415-2928 if you have questions.Sincerely,/RA/Deirdre W. Spaulding, Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-331

Enclosure:

RAIcc w/encl: See next page DISTRIBUTION

PUBLICLPL3-1 R/FRidsNrrPMDSpauldingRidsNrrLATHarris RidsNrrDorlLpleRidsOgcRpRidsAcrsAcnwMailCenterRidsRgn3MailCenterRidsNrrDorlDprALewinJGilmerTBoyceADAMS Accession Number: ML061990634OFFICENRR/LPL3-1/PMNRR/LPL3-1/LANRR/LPL3-1/BCNAMEDSpauldingTHarrisLRaghavan DATE07/21/0607/20/0607/24/06OFFICIAL RECORD COPY REQUEST FOR ADDITIONAL INFORMATIONRELATED TO THE PROPOSED AMENDMENT TOREVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1DUANE ARNOLD ENERGY CENTERDOCKET NO. 50-3311. LCO 3.10.1 Rev 3.1a would allow testing in Mode 4 with average reactor coolanttemperature drifting greater than 200 F as a result of decay heat. Primary containment requirements are relaxed in LCO 3.10.1 Rev 3.0 with the reasoning in the technicalspecification (TS) Bases that average reactor coolant temperature is greater than 200 F as aresult of testing and not due to significant decay heat. Please explain why it is acceptable to be in Mode 4 (with average reactor coolant temperature greater than 200 F) vice Mode 3 with the presence of decay heat contributing to an increase in the average reactor coolant temperature.2. LCO 3.4.7 "RCS Specific Activity," is normally not required in Mode 4 because the reactor isnormally not pressurized. Please provide justification for not including LCO 3.4.7 under LCO 3.10.1 Rev 3.1a requirements when in Mode 4 with average reactor coolant temperaturegreater than 200 F.3. The Bases for TS 3.10.1 Rev 3.1a discusses conducting other unnamed testing while the TS 3.10.1 Rev 3.1a specifically mentions conducting only inservice leak or hydrostatic tests and control rod scram time tests. Please elaborate on the intent of the TS and Bases as written with regards to "other testing."4. The use of the verbiage "as a consequence of" in the LCO under TS 3.10.1 Rev 3.1a couldresult in steady state Mode 4 with reactor coolant temperature > 200 F even though testing is over and no longer being conducted. This seems to be the reasoning for eliminating the statement in the Bases for TS 3.10.1 Rev 3.0 which states that normal Mode 4 requirementsare in effect immediately prior to and immediately after LCO 3.10.1 operations. Please elaborate on what would require returning to normal Mode 4 requirements after testing is completed.

ENCLOSURE Duane Arnold Energy Center cc:

Mr. J. A. StallSenior Nice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. S. RossManaging Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. R. E. HelfrichSenior Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. W. E. WebsterVice President, Nuclear Operations Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420John BjorsethSite Director Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324Steven R. CatronManager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324U. S. Nuclear Regulatory CommissionResident Inspector's Office Rural Route #1 Palo, IA 52324Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville RoadLisle, IL 60532-4351Mr. M. WarnerVice President, Nuclear Operations Support Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. D. A. CurtlandPlant Manager Duane Arnold Energy Center 3277 DAEC Rd.

Palo, IA 52324-9785Mr. R. S. KundalkarVice President, Nuclear Engineering Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Daniel McGheeUtilities Division Iowa Department of Commerce Lucas Office Buildings, 5th Floor Des Moines, IA 50319Chairman, Linn CountyBoard of Supervisors 930 1st Street SW Cedar Rapids, IA 52404