ML103270580
| ML103270580 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 11/23/2010 |
| From: | Price J Dominion Energy Kewaunee |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 10-707 | |
| Download: ML103270580 (10) | |
Text
Dominion Energy Kewaunee, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 November 23, 2010 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 DOlllinion Serial No.:
10-707 LR/MWH RO Docket No.:
50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION SUPPLEMENTAL INFORMATION FOR THE REVIEW OF THE KEWAUNEE POWER STATION LICENSE RENEWAL APPLICATION During a telephone conference held on Wednesday, November 17, 2010, members of the NRC and Dominion Energy Kewaunee, Inc. (DEK) staffs discussed four requests for additional information (RAls) related to the review of the Kewaunee Power Station (KPS) License Renewal Application (LRA) (reference 1). to this letter provides the DEK responses to the RAls discussed in the telephone conference.
Should you have any questions regarding this submittal, please contact Mr. Paul C.
Aitken at (804) 273-2818.
Very truly yours, rice sident - Nuclear Engineering COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO VICKI L.HULL Notary Public commonw.1ItII ofVIrginia 140s.t2 MyColllmlliion Explr.1 May 31.~014
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The foregoing document was acknowledged before me, in and for the County and State aforesaid, today by J. Alan Price, who is Vice President - Nuclear Engineering of Dominion Energy Kewaunee, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me thiscJ3tf day O't/(ghmk I 2010.
My Commission Expires:~ 3/,.;)01 Mia: t. jf j,< Ill.
Notary Public
Serial No.10-707 Docket No. 50-305 Page 2 of 3
Attachment:
- 1. Responses to RAls 82.1.31-7,82.1.31-8,82.1.31-9, and 82.1.29-2
References:
- 1. Letter from D. A. Christian (DEK) to NRC, "Kewaunee Power Station Application for Renewed Operating License," dated August 12, 2008. [ADAMS Accession No. ML082341020]
Commitments made in this letter:
- 1. License Renewal Commitment 54 will be added to LRA Table A6.0-1, consistent with the response to RAI 82.1.31-9.
The commitment is proposed to support approval of the renewed operating license, and may change during the NRC review period.
cc:
U.S. Nuclear Regulatory Commission Regional Administrator, Region III 2443 Warrenville Road Suite 210 Lisle, IL 60532-4532 Mr. K. D. Feintuch, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Daniel Doyle Environmental Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0-11 F1 Washington, DC 20555-0001 Mr. John Daily License Renewal Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0-11 F1 Washington, DC 20555-0001 NRC Senior Resident Inspector Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216 Public Service Commission of Wisconsin Electric Division P.O. Box 7854 Madison, WI 53707 David Hardtke Chairman - Town of Carlton E2334 Lakeshore Road Kewaunee, WI 54216 Serial No.10-707 Docket No. 50-305 Page 3 of 3
Serial No.10-707 Docket No. 50-305 ATTACHMENT 1 Responses to RAls 82.1.31-7, 82.1.31-8, 82.1.31-9, and 82.1.29-2 KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
Serial No.10-707 Docket No. 50-305 /Page 1 of 6 RAI 82.1.31-7. XI.S5-2: Masonry Walls Inspection Interval
Background:
NRC staff review has determined that masonry walls in the scope of license renewal should be visually examined at least every five years, with provisions for more frequent inspections in areas where significant loss ofmaterial or cracking is observed.
Issue:
The LRA did not discuss the inspection interval for in scope masonry walls.
Request:
Provide the inspection interval for in scope masonry walls.
If the interval exceeds five years clearly explain why, and how the interval will ensure there is no loss of intended function between inspections.
DEK Response Masonry walls within the scope of license renewal are inspected on a five year interval.
Serial No.10-707 Docket No. 50-305 /Page 2 of 6 RAI 82.1.31-8, XI.S6-4: Structures Monitoring Program Inspection Interval
Background:
NRC staff review has determined that structures in the scope of the Structures Monitoring Program should be monitored at an interval not to exceed five years. Some structures of lower safety significance, and subjected to benign environmental conditions, may be monitored at an interval exceeding five years; however, these structures should be listed along with the environment they are exposed to and a summary ofpast degradation..
Issue:
The LRA did not clearly identify an inspection interval for structures in the scope of the Structures Monitoring Program.
Request:
Identify the inspection interval for the Structures Monitoring Program.
If the interval is greater than five years, provide justification for the longer interval.
Adequate justification for a longer interval should include, at a minimum, a list of structures subject to the extended interval, their environments, and a summary ofpast degradation.
DEK Response Accessible portions of structures within the scope of license renewal are inspected on a five year interval in accordance with the Structures Monitoring Program.
Inaccessible portions of the structures will only be inspected if excavated or otherwise exposed for other reasons as described in LRA Section 82.1.31, Structures Monitoring Program.
Serial No.10-707 Docket No. 50-305 /Page 3 of 6 RAI 82.1.31-9, XI.S6-6: Structures Monitoring Program Acceptance Criteria
Background:
NRC staff review has determined that adequate acceptance criteria for the Structures Monitoring Program should include quantitative limits for characterizing degradation.
Chapter 5 of ACI 349.3R provides acceptable criteria for concrete structures.
If the acceptance criteria in ACI 349.3R are not used, the plant-specific criteria should be described and a technical basis for deviation from AC1349.3R should be provided.
Issue:
In response to RAI B2.1.31-2, the applicant included ACI 349.3R in the Structures Monitoring Program as a reference for program elements 3 and 6.
However, the applicant has not committed to the ACI 349.3R acceptance criteria, or identified equivalent quantitative acceptance criteria for Structures Monitoring Program inspections.
Request:
a) Confirm that quantitative acceptance criteria of ACI 349.3R are used for the Structures Monitoring Program.
If the criteria deviate from those discussed in ACI 349.3R, provide technical justification for the differences.
b) If quantitative acceptance criteria will be added to the program as an enhancement, provide plans and a schedule to conduct a baseline inspection with the quantitative acceptance criteria prior to the period oiexiended operation.
DEK Response a) The Structures Monitoring Program will be revised to include the evaluation criteria of ACI 349.3R-96, Chapter 5, as the criteria to be used when evaluating conditions or findings identified during concrete structure inspections.
b) The inspection interval for the Structures Monitoring Program is as stated in the response to RAI 82.1.31-8.
The next inspection is scheduled to be performed prior to the period of extended operation. The Structures Monitoring Program will be revised to include the evaluation criteria of ACI 349.3R-96, Chapter 5 as described in the answer to part 'a' of this RAI prior to the performance of the next inspection.
Serial No.10-707 Docket No. 50-305 /Page 4 of 6 Commitment 54 will be added to LRA Appendix A, USAR Supplement, Table A6.0-1 as follows:
Item Commitment Source Schedule 54 The Structures Monitoring Program will be Letter 10-707; Prior to the revised to include the evaluation criteria of Response to period of ACI 349.3R-96, Chapter 5, as the criteria RAI82.1.31-9 extended to be used when evaluating conditions or operation.
findings identified during concrete structure inspections. This will be done prior to the performance of the next scheduled inspection which will occur prior to the period of extended operation.
Serial No.10-707 Docket No. 50-305 /Page 5 of 6 RAI 82.1.31-9, XI.M33: Selective Leaching of Materials
Background
GALL AMP XI.M33, "Selective Leaching of Materials" states in element 1, "scope of program" that the program includes a one-time visual inspection and hardness measurement of a selected set of sample components to determine whether loss of material due to selective leaching is not occurring for the period of extended operation.
LRA Section B2.1.29, Selective Leaching of Materials, states that the program will inspect a representative sample of selected components that may be susceptible to selective leaching.
Issue Due to the uncertainty in determining the most susceptible locations and the potential for aging to occur in other locations, the staff noted that large sample sizes (at least 20%) may be required in order to adequately confirm an aging effect is not occurring.
The applicant's Selective Leaching Program did not include specific information regarding how the selected set of components are to be sampled or how the sample size will be determined.
Request Provide specific information regarding how the selected set of components to be sampled will be determined and the size of the sample of components that will be inspected.
DEK Response The sample size and inspection locations for the inspections associated with the Selective Leaching Program will be developed to ensure that a representative sample of material/environment combinations is selected with a focus on inspecting leading indicator components.
This approach provides assurance that the aging of the components is being adequately managed.
The representative sample size and inspection locations will be determined based on the materials of fabrication; that is, gray cast iron and copper alloys (containing greater than 15% zinc or greater than 8% aluminum). A sample size of 20% of the population (up to a maximum of 25 inspections) will be established for each of the two material groups consistent with the methodology discussed in Section 4, "Sampling Program Description" of EPRI TR-107514, Age-Related Degradation Inspection Method and Demonstration In Behalf of Calvert Cliffs Nuclear Power Plant License Renewal Application.
Serial No.10-707 Docket No. 50-305 /Page 6 of 6 Inspections will include each material/environment combination of in-scope equipment for each material-based sample set. The specific inspection locations will be identified considering the bounding or leading components most susceptible to selective leaching based on time in service, severity of operating conditions/environment (e.g., stagnant or low flow areas), and lowest design margins.