ML063410108

Request for Additional Information Related to Relief Request NDE-R005 and NDE-R007 (TAC Nos. MD2521 and MD2523)

ML063410108
Person / Time
Site:	Duane Arnold
Issue date:	12/08/2006
From:	Richard Ennis NRC/NRR/ADRO/DORL/LPLIII-1
To:	Vanmiddlesworth G Duane Arnold
Feintuch K, NRR/DORL/LPL3-1, 415-3079
References
NDE-R007, NEDE-R005, TAC MD2521, TAC MD2523
Download: ML063410108 (5)

Text

December 8, 2006 Mr. Gary Van Middlesworth Site Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785

SUBJECT:

DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST NDE-R005 AND NDE-R007 (TAC NOS. MD2521 AND MD2523)

Dear Mr. Van Middlesworth:

By letter dated June 30, 2006, FPL Energy Duane Arnold, LLC requested approval of several relief requests for the fourth 10-year inservice inspection interval at the Duane Arnold Energy Center. In relief request NDE-R005, you requested relief from certain requirements for inservice inspection specified in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). In relief request NDE-R007, you requested relief from certain requirements for visual examination in Section XI of the ASME Code.

The Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on December 5, 2006, Mr. Tom Byrne and members of your technical staff agreed to provide a response for NDE-R005 within one week and a response for NDE-R007 within two weeks of receipt of this RAI. If circumstances result in the need to revise your response dates, or if you have any questions, please contact Karl Feintuch at (301) 415-3079.

Sincerely,

/RA/

Richard B. Ennis, Senior 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

ML063410108 OFFICE LPL3-1/PM LPL3-1/PM LPL3-1/LA APLB/BC CFEB/BC LPL3-1/BC NAME KFeintuch REnnis THarris LMrowca KGruss LRaghavan DATE 12/7/06 12/7/06 12/7/06 12/7/06 12/8/06 12/8/06 Duane Arnold Energy Center cc:

Mr. J. A. Stall Mr. M. Warner Senior Vice President, Nuclear and Chief Vice President, Nuclear Operations Nuclear Officer Support Florida Power & Light Company Florida Power & Light Company P. O. Box 14000 P. O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Mr. M. S. Ross Mr. D. A. Curtland Managing Attorney Plant Manager Florida Power & Light Company Duane Arnold Energy Center P. O. Box 14000 3277 DAEC Rd.

Juno Beach, FL 33408-0420 Palo, IA 52324-9785 Mr. R. E. Helfrich Mr. R. S. Kundalkar Senior Attorney Vice President, Nuclear Engineering Florida Power & Light Company Florida Power & Light Company P. O. Box 14000 P. O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Mr. W. E. Webster Daniel K. McGhee Vice President, Nuclear Operations Iowa Department of Public Health Florida Power & Light Company Bureau of Radiological Health P. O. Box 14000 321 East 12th Street Juno Beach, FL 33408-0420 Lucas State Office Building, 5th Floor Des Moines, IA 50319-0075 John Bjorseth Site Director Chairman, Linn County Duane Arnold Energy Center Board of Supervisors 3277 DAEC Road 930 1st Street SW Palo, IA 52324 Cedar Rapids, IA 52404 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 October 12, 2006 Lisle, IL 60532-4351

REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUESTS NDE-R005 AND NDE-R007 DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 By letter dated June 30, 2006, FPL Energy Duane Arnold, LLC (FPL Energy or the licensee) requested approval of several relief requests for the fourth 10-year inservice inspection (ISI) interval at the Duane Arnold Energy Center (DAEC). The Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that the following information will be needed for the staff to complete its review.

Relief Request NDE-R005

1. Page 29 of 45 of the DAEC Fourth Ten Year ISI Plan - Relief Request NDE-R005 states that This Table shows the final consequence ranking has not changed for individual line segments, and therefore the change in risk assessment for the new inspection interval as compared to the original RI-ISI [risk-informed ISI] submittal meets the acceptance criteria of the original RI-ISI submittal. However we identified some inconsistencies below:

1a. Note (16) of this table says that The risk rank was increased from low to medium as an effect from the Updated PSA [probabilistic safety assessment].

1b. The number of welds selected for the nondestructive examination for the fourth interval are reduced, especially for control rod drive system. Please provide an explanation for this inconsistency and the rationale for the reduction.

1c. In Table 1, the risk ranking of the reactor core isolation cooling system is increased from low to medium as an effect from the updated PSA, but none of the welds were selected for the inspection, please explain.

2. Where your explanations in response to items 1a, 1b, and 1c warrant, please provide results from the cumulative risk impacts analysis demonstrating that the change in risk associated with implementation of the probabilistic risk assessment (PRA) Revision 5B model is consistent with the change in the Electric Power Research Institute TR-112657 Revision B-A risk guidelines.

3. The RI-ISI consequence results should also be ranked based on the impact on containment performance. Please provide the DAEC large early release frequency (LERF) and PRA model version/date used in support of the RI-ISI relief.

Enclosure

4. There is no specific mention of the Boiling Water Reactors Owners Group PRA certification associated with the LERF calculation. Please confirm if this certification has or has not been performed. If the certification has been performed, have the Level A and B Facts and Observations (F&Os) that the peer review team identified regarding LERF been resolved and/or incorporated into the models? If the F&Os have not been incorporated, please state why the unincorporated F&Os are not expected to have an impact on the RI-ISI consequence evaluation.

Relief Request NDE-R007

1. The system pressure test for nonisolable buried components in the Essential Sevice Water (ESW) piping requires a test to confirm that flow during operation is not impaired.

Relief Request NDE-R007 proposes an alternative to use the results of quarterly pump testing under the inservice test (IST) program for pumps, along with a visual examination of the ground surface, to verify that the flow is not impaired in the buried portion of ESW piping. The NRC staff requests the licensee to clarify how the results of the pump test will be used to confirm adequate flow from a qualitative determination of flow impairment in the buried ESW piping.