ML043650004
| ML043650004 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/23/2004 |
| From: | Rowley J NRC/NRR/DRIP/RLEP |
| To: | Division of Regulatory Improvement Programs |
| Rowley J, NRR/DRIP/RLEP, 415-4053 | |
| References | |
| Download: ML043650004 (8) | |
Text
December 23, 2004 LICENSEE:
Indiana Michigan Power Company FACILITY:
Donald C. Cook Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 10, 2004, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND INDIANA MICHIGAN POWER COMPANY, PERTAINING TO THE DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (the NRC or the staff) and representatives of Indiana Michigan Power Company (I&M) held a telephone conference call on November 10, 2004, to discuss and clarify requests for additional information (RAIs) concerning the Donald C. Cook Nuclear Plant, Units 1 and 2, license renewal application (LRA). The conference call was useful in clarifying the intent of the staffs RAIs. provides a listing of the telephone conference call participants. Enclosure 2 contains the items discussed with the applicant, including a brief description on the status of the items.
The applicant has had an opportunity to comment on this summary.
/RA/
Jonathan G. Rowley, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos.: 50-315 and 50-316
Enclosures:
As stated cc w/encls: See next page
ML043650004 DOCUMENT NAME: E:\\Filenet\\ML043650004.wpd OFFICE PM:RLEP LA:RLEP SC:RLEP NAME JRowley MJenkins SLee DATE 12/22/04 12/22/04 12/23/04
DISTRIBUTION: Licensee: Indiana Michigan Power Co., Re: Donald C.Cook Plant, Units 1 and 2, Dated: December 23, 2004 Accession No: ML043650004 HARD COPY RLEP RF J. Rowley (PM)
E-MAIL:
RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski J. Fair RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis C. Li M. Itzkowitz (RidsOgcMailCenter)
R. Weisman M. Mayfield A. Murphy S. Smith (srs3)
S. Duraiswamy Y. L. (Renee) Li RLEP Staff K. Coyne L. Lund S. Coffin T. Chan J. Minns R. Gramm A. Howell M. Shuaibi J. Strasma, RIV M. Kotzalas OPA NRR/ADPT Secretary (RidsNrrAdpt)
LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALL TO DISCUSS THE DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION NOVEMBER 10, 2004 Attendees Affiliations Jonathan Rowley U.S. Nuclear Regulatory Commission (NRC)
James Strnisha NRC Thomas Cheng NRC Rich McNally NRC Charlie Hoffmeyer Brookhaven National Laboratories (BNL)*
Richard Morante BNL Robert Kalinowski Indiana Michigan Power Company (I&M)
Neil Haggerty I&M Rich Grumbir I&M Doug Badgero I&M Allen Cox Entergy
- NRC Contractor
- I&M Contractor REQUESTS FOR ADDITIONAL INFORMATION DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION NOVEMBER 10, 2004 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Indiana Michigan Power Company (I&M) held a telephone conference call on November 10, 2004, to discuss and clarify requests for additional information (RAIs) concerning the Donald C. Cook Nuclear Plant, Units 1 and 2 (CNP), license renewal application (LRA). The following RAIs were discussed during the telephone conference call.
- 1. RAI 3.3.2.1.11-1 The applicant submitted the supplemental response to RAI 3.3.2.1.11-1 in a letter to the NRC (AEP:NRC:4034-17) dated October 18, 2004. The staff had an additional question for the applicant following the review of the response.
Additional Information Requested In the I&M Supplemental Response to RAI 3.3.2.1.11-1, the applicant states, The remaining systems (CONT, DRAIN, RMS, RWD, and SD) have copper alloy, carbon steel, stainless steel, or glass components that may be pressurized and contain raw water or untreated water. As discussed above, glass exposed to a raw or treated water environment has no aging effect requiring management. I&M will include components containing raw or untreated water subject to aging management review that were included for 10 CFR 54.4(a)(2) in these systems in the Chemistry One-Time Inspection Program. For components in a raw or untreated water environment where an aging effect is likely to occur, the GALL report recommends use of a mitigative program with a One-Time Inspection Program to verify the program effectiveness or the use of periodic inspections. For components in these system, it is not clear to the staff if the applicant is crediting a mitigative program in conjunction with the One-Time Inspection Program or if a one-time inspection alone is credited to manage these aging effects.
Status The applicant clarified that several A(2) systems contain treated water from the main steam and main feed system and that the water in these system is managed by water chemistry and one-time inspections. One-time inspections will be performed on these systems or will be bounded by other one-time inspections. The applicant maintains that the response to this question has followed previous NRC accepted positions for aging management of A(2) components that are in scope for spray and leakage interaction. The applicant has agreed to provide a written response to further clarify their position regarding the systems that are addressed by this question.
- 2. RAI 3.4-4 The applicant provided the staff a draft of its supplemental response to RAI 3.4-4 for the staffs review and comment. The staff had an additional question for the applicant following the review of the response.
Additional Information Requested The response does not address our comment that the management of loss of preload in bolting is limited to bolts subject to long term exposure to elevated temperatures or significant vibration and not all safety related bolting identified in GALL AMP XI.M18 and NUREG-1339. The applicant is requested to clarify the basis for not managing loss of preload for all safety related bolting and other bolting within scope.
Status The applicant stated that the response to this question has followed operating experience and previously NRC accepted positions on loss of preload related to bolting and torquing. The staff has requested confirmation of maintenance activities including bolting and torquing. The applicant will provide a written response stating their maintenance activities.
- 3. RAI 2.4-2(a)
The applicant submitted the supplemental response to RAI 2.4-2(a) in a letter to the NRC (AEP:NRC:4034-11) dated August 11, 2004. The staff had an additional question for the applicant following the review of the response.
Additional Information Requested The staff indicated that the thermal insulation scoping issue needs to be more specific. The staff requested clarification as to what intended function for license renewal the thermal insulation has and what does the aging management review (AMR) of the insulation include.
Status The applicant stated that thermal insulation for penetrations does not meet the 10 CFR 54.4 (a)(1), (a)(2), or (a)(3) criteria. The applicant will determine if insulation should be conservatively considered in scope and subject to aging management and will provide this determination in a written response. The staff had no further questions at the time of the call.
- 4. RAI 2.4-2(b)
The applicant submitted the supplemental response to RAI 2.4-2(b) in a letter to the NRC (AEP:NRC:4034-11) dated August 11, 2004. The staff had an additional question for the applicant following the review of the response.
Additional Information Requested The staff indicated that the divider barrier seals and the divider barrier hatch seals need to be included in the scope of the Divider Barrier Seal Inspection Program.
Status The applicant stated that the divider barrier seals and the divider barrier hatch seals will be included in program scope. The applicant will submit a formal response.
- 5. RAI 2.4-3 The applicant submitted the supplemental response to RAI 2.4-3 in a letter to the NRC (AEP:NRC:4034-11) dated August 11, 2004. The staff had an additional question for the applicant following the review of the response.
Additional Information Requested The applicant is requested to clarify the details regarding discharge jets and trash baskets and collection equipment Additionally, the staff requested the applicant to identify the components that are relied on for de-icing to ensure an adequate supply of cooling water for safe shutdown, and to verify these components are included in the license renewal scope.
Status The applicant stated the request is clear. The applicant will submit a formal response.
- 6. RAI 2.4-5 The applicant submitted the supplemental response to RAI 2.4-5 in a letter to the NRC (AEP:NRC:4034-11) dated August 11, 2004. The staff had an additional question for the applicant following the review of the response.
Additional Information Requested The staff requested that the applicant clarify which aging management program (AMP) is credited to ensure structural performance of cable feed-through assemblies.
Status The staff position is that the assemblies perform a pressure boundary intended function, thus requiring an AMP. The staff believes this is consistent with 10 CFR 50, Appendix J. The applicant will reevaluate and respond in a formal letter.
Donald C. Cook Nuclear Plant, Units 1 and 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4351 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, MI 49127 David W. Jenkins, Esquire Indiana Michigan Power Company One Cook Place Bridgman, MI 49106 Mayor, City of Bridgman P.O. Box 366 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI 48909 Mr. John A. Zwolinski Director, Design Engineering and Regulatory Affairs Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107 Patricia Lougheed 2443 Warrenville Rd.
Lisle, IL 60532 Michigan Department of Environmental Quality Waste and Hazardous Materials Div.
Hazardous Waste & Radiological Protection Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 Michael J. Finissi, Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Mr. Joseph N. Jensen, Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Mr. Fred Emerson Nuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, DC 20006-3708 Richard J. Grumbir Project Manager, License Renewal Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107 Mr. Mano K. Nazar Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107