ML071020315

(SSES 1 and 2), Request for Additional Information (Rai), - Extended Power Uprate Application Balance-of-Plant Physics Technical Review

ML071020315
Person / Time
Site:	Susquehanna
Issue date:	04/16/2007
From:	Richard Guzman NRC/NRR/ADRO/DORL/LPLI-1
To:	Mckinney B Susquehanna
Guzman R, NRR/DORL, 415-1030
References
TAC MD3309, TAC MD3310
Download: ML071020315 (5)

Text

April 16, 2007 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, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: BALANCE-OF-PLANT SAFETY SYSTEMS REVIEW (TAC NOS. MD3309 AND MD3310)

Dear Mr. McKinney:

In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission 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 April 11, 2007. As agreed to by your staff, we request you respond by May 16, 2007.

If you have any questions, please contact me at 301-415-1030.

Sincerely,

/RA/

Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosure:

RAI cc w/encl: See next page

April 16, 2007 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, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: BALANCE-OF-PLANT SAFETY SYSTEMS REVIEW (TAC NOS. MD3309 AND MD3310)

Dear Mr. McKinney:

In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission 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 April 11, 2007. As agreed to by your staff, we request you respond by May 16, 2007.

If you have any questions, please contact me at 301-415-1030.

Sincerely,

/RA/

Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosure:

RAI cc w/encl: See next page DISTRIBUTION:

Public RidsOgcMailCenter RidsNrrPmRGuzman RidsNrrSpbpBC AStubbs LPLI-1 R/F RidsNrrDorlLpl1-1 RidsAcrsAcnwMailCenter RidsNrrLaSLittle Accession Number: ML071020315

• RAI provided by memo. No substantive changes made.

OFFICE NRR/LPLI-1/PM NRR/LPLI-1/LA NRR/SBPB/BC NRR/LPLI-1/BC NAME RGuzman SLittle JSegala*

MKowal DATE 4/16/07 4/16/07 3/20/07 4/16/07 OFFICIAL RECORD COPY

Enclosure Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE APPLICATION FOR EXTENDED POWER UPRATE (EPU)

BALANCE-OF-PLANT SAFETY SYSTEMS SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2)

PPL SUSQUEHANNA, LLC DOCKET NOS. 50-387 AND 50-388 The Nuclear Regulatory Commission (NRC) staff is reviewing the request from PPL Susquehanna, LLC (PPL, the licensee) to support the application of the EPU for SSES 1 and 2.

The NRC staff has determined that additional information requested below will be needed to complete its review.

1.

Section 6.3 of the Susquehanna Power Uprate Safety Analysis Report (PUSAR) states that during refueling conditions, the three Fuel Pool Cooling and Cleanup System (FPCCS) heat exchangers in the outage unit are typically supplied with river water with an assumed maximum river temperature limit of 75 EF. Table 6-4 and 6-5 of the report indicate that 75 EF cooling water temperatures were used for these heat exchangers in analyses in which the maximum spent fuel pool (SFP) cooling bulk water temperature and time to boil were calculated. The results presented are only bounding provided (1) river water is used as the supply, and (2) the river water temperature does not exceed the 75 EF temperature limit.

a) In Section 9.1.3.2 of the Susquehanna Final Safety Analysis Report (FSAR), the potential to use river water to cool SFP cooling heat exchangers for the refueling unit or temporary cooling tower chillers are discussed. However, the use of river water at 75 EF, does not appear to be credited for maintaining the pool below its design temperature of 125 EF. For the current licensing basis, please provide the inputs, assumptions, and results used in the fuel pool cooling analysis. Your response should include the information contained in Tables 6-4 and 6-5 of the PUSAR.

b) Provide the basis for use of the 75 EF temperature used in your EPU SFP cooling analysis.

c) Provide a discussion of administrative and/or procedural controls that will ensure that the assumed conditions (river water at or below 75 EF will supply the three FPCCS heat exchangers of the outage unit) are met prior to the start of refueling, or that a cycle specific evaluation is performed to confirm that pool temperature limits will not be exceeded.

2.

In evaluating the impact of postulated failures, typically the failure of active equipment is postulated. In Table 6.4 and 6.5 of the PUSAR, postulated failure of heat exchanges (passive equipment) are shown. Please discuss what effect the failure of active equipment such as the failure of a FPCCS pump would have on the heat removal capacity and the resultant pool temperature.

3.

Section 6.4.1 of the PUSAR addresses the impact of EPU on the service water system, however, it fails to address any effects of Generic Letter (GL) 96-06. Please describe any impacts that the proposed EPU will have on the issues discussed in GL 96-06, Assurance of Equipment Operability and Containment Integrity during Design-Basis Accident Conditions, and GL 96-06, Supplement 1 including the basis for your determination. In particular, confirm that water hammer and two-phase flow analyses that were completed in accordance with GL 96-06 continue to be valid.

4.

In Section 6.4.5 of the Susquehanna PUSAR, it is stated that, The average nozzle flow rate, in turn, will allow confirmation that the analytical assumptions for nozzle pressure and spray height are conservative based on known correlations between flow and spray. Please explain how modification testing will be used to verify that the actual height of spray from the most limiting (lowest pressure) nozzle is consistent with the analytically modeled spray height results.

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 Terry L. Harpster General Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Rocco R. Sgarro Manager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Supervisor -

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 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