ML041270558
| ML041270558 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/04/2004 |
| From: | Michelle Honcharik NRC/NRR/DLPM/LPD4 |
| To: | Edington R Nebraska Public Power District (NPPD) |
| Honcharik M, NRR/DLPM, 301-415-1774 | |
| References | |
| TAC MC1572 | |
| Download: ML041270558 (5) | |
Text
May 4, 2004 Mr. Randall K. Edington Vice President-Nuclear and CNO Nebraska Public Power District P. O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LOSS-OF-COOLANT ACCIDENT (LOCA) DOSE CALCULATION METHODOLOGY AND RESOLUTION OF REMAINING LICENSE CONDITION 2.C.(6) ISSUES (TAC NO. MC1572)
Dear Mr. Edington:
By letter dated December 9, 2003, Nebraska Public Power District (NPPD or the licensee) requested the Nuclear Regulatory Commission (NRC) staff to approve its proposed license amendment request for LOCA dose calculation methodology and resolution of remaining License Condition 2.C.(6) issues. The subject amendment request also included responses to a request for additional information (RAI) issued on October 2, 2003.
On April 28, 2004, the NRC staff held a telephone call with the licensee to pose several questions regarding the RAI response. The NRC staff has reviewed the information provided during the April 28, 2004, telephone call and determined that the enclosed RAI is required in order to complete the review and approval of the changes. As agreed upon in a telephone call between Michelle Honcharik and Edward McCutchen on May 3, 2004, the licensee will respond to the RAI within 30 days.
Sincerely,
/RA/
Michelle C. Honcharik, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
RAI cc w/encl: See next page
May 4, 2004 Mr. Randall K. Edington Vice President-Nuclear and CNO Nebraska Public Power District P. O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LOSS-OF-COOLANT ACCIDENT (LOCA) DOSE CALCULATION METHODOLOGY AND RESOLUTION OF REMAINING LICENSE CONDITION 2.C.(6) ISSUES (TAC NO. MC1572)
Dear Mr. Edington:
By letter dated December 9, 2003, Nebraska Public Power District (NPPD or the licensee) requested the Nuclear Regulatory Commission (NRC) staff to approve its proposed license amendment request for LOCA dose calculation methodology and resolution of remaining License Condition 2.C.(6) issues. The subject amendment request also included responses to a request for additional information (RAI) issued on October 2, 2003.
On April 28, 2004, the NRC staff held a telephone call with the licensee to pose several questions regarding the RAI response. The NRC staff has reviewed the information provided during the April 28, 2004, telephone call and determined that the enclosed RAI is required in order to complete the review and approval of the changes. As agreed upon in a telephone call between Michelle Honcharik and Edward McCutchen on May 3, 2004, the licensee will respond to the RAI within 30 days.
Sincerely,
/RA/
Michelle C. Honcharik, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC PDIV-1 r/f RidsNrrDlpmLpdiv (HBerkow)
RidsNrrPMMHoncharik RidsNrrLADBaxley RidsNrrDlpmLpdiv1 (RGramm)
RidsAcrsAcnwMailCenter RidsOgcRp RidsNrrDlpmDpr JBongarra RidsNrrDipmDpr RidsRgn4MailCenter (KKennedy)
ACCESSION NO: ML041270558 OFFICE PDIV-1/PM PDIV-1/LA PDIV-1/SC NAME MHoncharik DBaxley RGramm DATE 5/4/04 5/4/04 5/04/04 OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML041270558.wpd
Enclosure REQUEST FOR ADDITIONAL INFORMATION ISSUES RELATED TO LOSS-OF-COOLANT ACCIDENT (LOCA)
DOSE CALCULATION METHODOLOGY AND RESOLUTION OF REMAINING LICENSE CONDITION 2.C.(6) ISSUES COOPER NUCLEAR STATION (CNS)
All page references are to Attachment 1 of the December 9, 2003, submittal.
- 1.
Page 7 - Please describe how the operator will be able to access both Turbine Stop Valves that are located approximately 8.5 ft. off the floor.
- 2.
Page 8 - Please describe how the walk down was performed. For example, how many individuals/crews participated in the walk down? What actions were actually demonstrated to be performed within the "estimated 30 minutes" to accomplish the task...e.g., did the time include ingress/egress to the valve locations, access to the tools that are 25-30 feet away from the valves, etc? The illustration provided in the December 9, 2003, submittal shows an operator at the valve location dressed in "anti-Cs", it appears. Did the 30 minute time estimate include time to dress-out?
- 3.
Page 8 - "With the MSIV [main steam isolation valve] leakage assumed in the LOCA analysis and conservative assumptions, this evolution would be performed well before any radiological release to the Turbine Building could occur from Turbine Valve shaft clearance area leakage. The implementing emergency procedure directs completion within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />." Please explain how the 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> time frame to take the required manual actions was derived. What is the minimum amount of time that an operator will have to perform the required actions before encountering a hostile environment?
- 4.
Page 9 - Please explain what modifications were made after refueling outage 21 to improve the capability of the emergency lighting system. "Directly after a LOCA induced shutdown, the area surrounding the Turbine Stop Valves would be hot from residual heat in the piping and valves..." Though the "majority of equipment in the area is insulated," how hot is the area expected to become? Is there need for special personnel protection/equipment?
- 5.
Page 15 (Table 1) - Please explain/clarify: Are all the manual actions in the table required to "configure the MSIV Leakage Pathway," as the table title (and Page 3) indicate? If so, please explain how the manual actions (other than the Turbine Stop Valve adjustments) are accomplished. For example, where are the locations of the other valves in relation to the Turbine Stop Valves? Does the same person who is manually adjusting the Turbine Stop Valves carry out the remaining valve closures?
What steps are required to perform the remaining valve manipulations? How much time is required to complete the remaining valve manipulations? How has it been determined that the other valve manipulations can be successfully performed in the time allowable?
December 2003 Cooper Nuclear Station cc:
Mr. William J. Fehrman President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. Clay C. Warren Vice President - Nuclear Nebraska Public Power District P. O. Box 98 Brownville, NE 68321 Mr. John R. McPhail, General Counsel Nebraska Public Power District P. O. Box 499 Columbus, NE 68602-0499 Mr. Paul V. Fleming, Licensing and Regulatory Affairs Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 Mr. Michael J. Linder, Director Nebraska Department of Environmental Quality P. O. Box 98922 Lincoln, NE 68509-8922 Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305 Ms. Cheryl K. Rogers, Program Manager Nebraska Health & Human Services System Division of Public Health Assurance Consumer Services Section 301 Centennial Mall, South P. O. Box 95007 Lincoln, NE 68509-5007 Mr. Ronald A. Kucera, Director of Intergovernmental Cooperation Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 218 Brownville, NE 68321 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Jerry Uhlmann, Director State Emergency Management Agency P. O. Box 116 Jefferson City, MO 65101 Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson Suite 310 Topeka, KS 66612-1366 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health 401 SW 7th Street Suite D Des Moines, IA 50309 Mr. Scott Clardy, Director Section for Environmental Public Health P.O. Box 570 Jefferson City, MO 65102-0570