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| number = ML061990634 | | number = ML061990634 | ||
| issue date = 07/24/2006 | | issue date = 07/24/2006 | ||
| title = | | title = RAI, Proposed Amendment to Revise the Limiting Condition for Operation 3.10.1 | ||
| author name = Spaulding D | | author name = Spaulding D | ||
| author affiliation = NRC/NRR/ADRO | | author affiliation = NRC/NRR/ADRO | ||
| addressee name = | | addressee name = Vanmiddlesworth G | ||
| addressee affiliation = Nuclear Management Co, LLC | | addressee affiliation = Nuclear Management Co, LLC | ||
| docket = 05000331 | | docket = 05000331 | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:July 24, | {{#Wiki_filter:July 24, 2006 Mr. Gary Van Middlesworth Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785 | ||
==SUBJECT:== | ==SUBJECT:== | ||
DUANE ARNOLD ENERGY CENTER - REQUEST FOR | DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293) | ||
==Dear Mr. Van Middlesworth:== | ==Dear Mr. Van Middlesworth:== | ||
Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting condition for operation 3.10.1, to allow ancillary testing to occur during the evolutions associated with performing 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 the enclosed 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 Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 | |||
==Enclosure:== | |||
RAI cc w/encl: See next page | |||
Mr. Gary Van Middlesworth July 24, 2006 Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785 | |||
==SUBJECT:== | ==SUBJECT:== | ||
DUANE ARNOLD ENERGY CENTER - REQUEST FOR | DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 (TAC NO. MD0293) | ||
==Dear Mr. Van Middlesworth:== | ==Dear Mr. Van Middlesworth:== | ||
Your letter of March 1, 2006, submitted a proposed amendment to revise the limiting condition for operation 3.10.1, to allow ancillary testing to occur during the evolutions associated with performing 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 the enclosed 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 Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331 | |||
==Enclosure:== | |||
RAI cc w/encl: See next page DISTRIBUTION: | |||
PUBLIC LPL3-1 R/F RidsNrrPMDSpaulding RidsNrrLATHarris RidsNrrDorlLple RidsOgcRp RidsAcrsAcnwMailCenter RidsRgn3MailCenter RidsNrrDorlDpr ALewin JGilmer TBoyce ADAMS Accession Number: ML061990634 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC NAME DSpaulding THarris LRaghavan DATE 07/21/06 07/20/06 07/24/06 OFFICIAL RECORD COPY | |||
REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 | |||
: 1. LCO 3.10.1 Rev 3.1a would allow testing in Mode 4 with average reactor coolant temperature 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 technical specification (TS) Bases that average reactor coolant temperature is greater than 200 F as a result 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 is normally 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 temperature greater 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 could result 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 requirements are 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. Stall Senior Nice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. S. Ross Managing Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. R. E. Helfrich Senior Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. W. E. Webster Vice President, Nuclear Operations Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 John Bjorseth Site Director Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 Steven R. Catron Manager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Mr. M. Warner Vice President, Nuclear Operations Support Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. D. A. Curtland Plant Manager Duane Arnold Energy Center 3277 DAEC Rd. | |||
Mr. J. A. | Palo, IA 52324-9785 Mr. R. S. Kundalkar Vice President, Nuclear Engineering Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Daniel McGhee Utilities Division Iowa Department of Commerce Lucas Office Buildings, 5th Floor Des Moines, IA 50319 Chairman, Linn County Board of Supervisors 930 1st Street SW Cedar Rapids, IA 52404}} | ||
Palo, IA | |||
Latest revision as of 08:00, 15 January 2025
| 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, 2006 Mr. Gary Van Middlesworth Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION 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 condition for operation 3.10.1, to allow ancillary testing to occur during the evolutions associated with performing 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 the enclosed 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 Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
RAI cc w/encl: See next page
Mr. Gary Van Middlesworth July 24, 2006 Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION 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 condition for operation 3.10.1, to allow ancillary testing to occur during the evolutions associated with performing 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 the enclosed 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 Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrPMDSpaulding RidsNrrLATHarris RidsNrrDorlLple RidsOgcRp RidsAcrsAcnwMailCenter RidsRgn3MailCenter RidsNrrDorlDpr ALewin JGilmer TBoyce ADAMS Accession Number: ML061990634 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC NAME DSpaulding THarris LRaghavan DATE 07/21/06 07/20/06 07/24/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED AMENDMENT TO REVISE THE LIMITING CONDITION FOR OPERATION (LCO) 3.10.1 DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331
- 1. LCO 3.10.1 Rev 3.1a would allow testing in Mode 4 with average reactor coolant temperature 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 technical specification (TS) Bases that average reactor coolant temperature is greater than 200 F as a result 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 is normally 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 temperature greater 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 could result 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 requirements are 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. Stall Senior Nice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. S. Ross Managing Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. R. E. Helfrich Senior Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. W. E. Webster Vice President, Nuclear Operations Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 John Bjorseth Site Director Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 Steven R. Catron Manager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 U. S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Mr. M. Warner Vice President, Nuclear Operations Support Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. D. A. Curtland Plant Manager Duane Arnold Energy Center 3277 DAEC Rd.
Palo, IA 52324-9785 Mr. R. S. Kundalkar Vice President, Nuclear Engineering Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Daniel McGhee Utilities Division Iowa Department of Commerce Lucas Office Buildings, 5th Floor Des Moines, IA 50319 Chairman, Linn County Board of Supervisors 930 1st Street SW Cedar Rapids, IA 52404