ML053050276
| ML053050276 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/01/2005 |
| From: | Richard Guzman NRC/NRR/DORL/LPLA |
| To: | Mckinney B Susquehanna |
| Guzman R, NRR/DLPM 415-1030 | |
| References | |
| TAC MC8626 | |
| Download: ML053050276 (5) | |
Text
November 1, 2005 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 (SSES 1) - REVISED MINIMUM CRITICAL POWER RATIO SAFETY LIMIT (TAC NO. MC8626)
Dear Mr. McKinney:
In reviewing your submittal of October 14, 2005, concerning a request to revise Technical Specification 2.1.1.2 for SSES 1, the Nuclear Regulatory Commission (NRC) staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on October 25, 2005. As agreed to by your staff, we request you respond within 30 days of the date of this letter. In addition, we request that you meet with the NRC staff following the SSES 1 startup to discuss your post-outage testing results and root-cause analysis with respect to the fuel channel/control cell interference issues at SSES 1.
If you have any questions, please contact me at 301-415-1030.
Sincerely,
/RA/
Richard V. Guzman, Project Manager Plant Licensing Branch A Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-387
Enclosure:
RAI cc w/encl: See next page
November 1, 2005 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 (SSES 1) - REVISED MINIMUM CRITICAL POWER RATIO SAFETY LIMIT (TAC NO. MC8626)
Dear Mr. McKinney:
In reviewing your submittal of October 14, 2005, concerning a request to revise Technical Specification 2.1.1.2 for SSES 1, the Nuclear Regulatory Commission (NRC) staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on October 25, 2005. As agreed to by your staff, we request you respond within 30 days of the date of this letter. In addition, we request that you meet with the NRC staff following the SSES 1 startup to discuss your post-outage testing results and root-cause analysis with respect to the fuel channel/control cell interference issues at SSES 1.
If you have any questions, please contact me at 301-415-1030.
Sincerely,
/RA/
Richard V. Guzman, Project Manager Plant Licensing Branch A Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-387
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
Public OGC RGuzman DLPM DPR FAkstulewicz PDI-1 R/F RLaufer MO'Brien THuang ACRS PClifford SWu Accession Number: ML053050276 OFFICE NRR/LPLA/PM NRR/LPLA/LA NRR/SNPB/BC NRR/LPLA/BC NAME RGuzman SLittle FAkstulewicz RLaufer DATE 11/1/05 10/31/05 11/1/05 11/1/05 OFFICIAL RECORD COPY
Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATING TO MINIMUM CRITICAL POWER RATIO SAFETY LIMIT FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 (SSES 1)
DOCKET NO. 50-387 The Nuclear Regulatory Commission (NRC) staff is reviewing the proposed license amendment to Facility Operating License No. NPF-14 requesting to revise the SSES 1 Cycle 14 (U1C14A) mnimum critical power ratio safety limit (MCPRSL). The NRC staff has determined that the information requested below will be needed to complete its review.
1.
Please describe how the U1C14A core loading pattern is established and what criteria should be met to reinsert twice burned fuel bundles. Identify which design documentation file was used for this core design.
2.
Please justify that assumed bow twice the Advanced Nuclear Fuels (ANF) database is conservative for the redesign U1C14A core. Also, provide clarification that channel bow required for MCPRSL calculation specified in ANF-524(P)(A), Revision 2, ANF Critical Power Methodology for Boiling Water Reactors, and Supplement 1, Revision 2, is still applicable to the MCPRSL calculation.
3.
Please describe the PPL channel management action plan with respect to the General Electric (GE) guidance provided by GE report SC05-06, Updated Surveillance Program for Fuel Channel-Control Blade Interference Monitoring, dated July 14, 2005, and justify the difference if any.
4.
Please describe the fuel assembly inspection program planned for the mid-cycle outage as well as follow-on pool-side inspection programs prior to Cycle 15. Include in this program description the following:
a)
Description of the measurement device and the accuracy of its channel deflection measurements.
b)
Threshold used to determine when to re-channel and/or re-insert a fuel assembly.
c)
Degree of fuel pin inspections.
d)
List of channel bow measurements on channels being used to re-channel assemblies.
e)
Qualify the relationship between cold, unstressed pool-side measurements and hot, stressed (delta-pressure across channel wall during operation) in-reactor channel deflection.
Susquehanna Steam Electric Station, Unit Nos. 1 and 2
cc:
Robert A. Saccone Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Aloysius J. Wrape, III General Manager - Performance Improvement and Oversight PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Terry L. Harpster General Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Richard D. Pagodin General Manager - Nuclear Engineering PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Rocco R. Sgarro Manager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Walter E. Morrissey Supervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Michael H. Crowthers Supervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Steven M. Cook Manager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Luis A. Ramos Community Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467 Bryan A. Snapp, Esq Assoc. General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179 Supervisor - Document Control Services PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Richard W. Osborne Allegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266 Director, Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035 Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803