ML081890503

Request for Additional Information for the Review of the Susquehanna Steam Electric Station, Units 1 & 2, License Renewal Application

ML081890503
Person / Time
Site:	Susquehanna
Issue date:	07/09/2008
From:	Gettys E H NRC/NRR/ADRO/DLR
To:	McKinney B T Susquehanna
Gettys Evelyn, NRR/DLR/RLRA 415-4029
References
Download: ML081890503 (8)

Text

July 9, 2008

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 FOR THE REVIEW OF THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION

Dear Mr. McKinney:

By letter dated September 13, 2006, PPL Susquehanna, LLC submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54), to renew the operating licenses for Susquehanna Steam Electric Station, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Duane Filchner, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please

contact me at 301-415-4029 or e-mail evelyn.gettys@nrc.gov. Sincerely,

/RA/

Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosure:

As stated

cc w/encl: See next page

ML081890503 OFFICE LA:DLR PM:RPB1:DLR BC(A): RPB1:DLR NAME IKing EGettys BPham DATE 7/9/08 7/9 /08 7/9 /08 SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION (RAI)

RAI B.2.48-1 In the aging management program (AMP) B.2.48 Preventive Maintenance Activities - reactor core isolation cooling/high pressure cooling injection (RCIC/HPCI) Turbine Casings program, under the "detection of aging effects" program element, the applicant does not provide sufficient detail about this program element. The Standard Review Plan and License Renewal (SRP-LR) Section A.1.2.3.4.1 states, "Detection of aging effects should occur before there is a loss of the structure and component intended function(s). The parameters to be monitored or inspected should be appropriate to ensure that the structure and component intended function(s) will be adequately maintained for license renewal under all current license basis (CLB) design conditions. This includes aspects such as method or technique (e.g., visual, volumetric, surface inspection), frequency, sample size, data collection and timing of new/one-time inspections to ensure timely detection of aging effects. Provide information that links the parameters to be monitored or inspected to the aging effects being managed."

Please provide the following information:

1. Method used to inspect (i.e., type of visual inspection, VT-1 or VT-2)

2. Frequency of inspections

3. Type of data collected RAI B.2.48-2 In the AMP B.2.48 Preventive Maintenance Activities - RCIC/HPCI Turbine Casings program, under the "operating experience" program element, the license renewal application (LRA) states, "The elements that comprise the Preventive Maintenance Activities - RCIC/HPCI Turbine Casings program are consistent with industry practice and have proven effective in maintaining the material condition of the RCIC and HPCI pump turbines, including casings."

What industry practice are you referring to? Also, please provide a justification of how a monitoring program can maintain the material condition of the RCIC and HPCI pump turbines, and whether visual inspections can be used to stop loss of materials.

Preventative Maintenance Activities - HCIC/HPCI Casings RAI 3.0.3.3.48-1 For the "detection of aging effects" program element, the staff reviewed the program in accordance with SRP-LR Section A.1.2.3.4-1 and determined that there was insufficient information in the LRA. What is the method of inspection? What is the frequency of inspections? What kind of data will be taken and how will it be stored?

RAI 3.0.3.3.48-2 In the "operating experience" program element, the applicant states that this monitoring program will ensure that the material condition will be maintained.

Enclosure Please explain how a monitoring program can ensure how monitoring for loss of material will maintain the material condition.

RAI 3.3.2-1 The LRA has indicated Generic Note H for 3.3.2 line Items, 3.3.2-11, 3.3.2-21, 3.3.2-26, and 3.3.2-30 for the emergency service water, the reactor building chilled water, the residual heat removal service water, and the service water system. Generic Note H states, "Aging effect not in the Generic Aging Lessons Learned (GALL) Report (Chapter IV) for this component, material, and environment combination." Plant-specific Note 0347 states, that in order for stress corrosion cracking to occur, the copper alloys would have to have >15% Zinc or >8% Aluminum and there would have to be ammonia or ammonium compounds present. The staff does not know whether the Area-Based non-safety affecting safety (NSAS) Inspection Program is adequate to manage the stress corrosion cracking of copper alloys because there is not enough information provided in the LRA. For instance, what are the specific compositions of the copper alloys, what are possible sources of ammonia or ammonia compounds for these systems, and what is the condition of the copper piping and piping components in terms of residual stresses? Also, has Susquehanna Steam Electric Station ever experienced any stress corrosion cracking of copper piping and piping components in any of these systems?

Aging Management Review Related RAIs RAI 3.3.2.2.7.2-1 In the discussion column of Table 3.3.1, Item 3.3.1-17, the LRA states that flow-accelerated corrosion (FAC) Program is applicable to the reactor water cleanup (RWCU) system valve bodies and that the FAC Program is credited to manage loss of material due to FAC, and Note H is used. This line item addresses loss of material due to general, pitting and crevice corrosion. Please justify why loss of material due to FAC is addressed in this Table 1 line item with Note H, which is not consistent with the GALL Report.

RAI 3.3.2.2.7.2-2 In the discussion column of Table 3.3.1, Item 3.3.1-17, the LRA credits Boiling-Water Reactor Water Chemistry, Chemistry Effectiveness Inspection and the FAC Programs, and references Section 3.3.2.2.7.2 for further evaluation. However, Section 3.3.2.2.7.2 does not address FAC Program. Please clarify why the FAC Program is not addressed in Section 3.3.2.2.7.2.

RAI 3.3.2.3.25-1 In Table 3.3.2-25, RWCU system, the applicant credits FAC Program to manage the aging effect of loss of material due to FAC of carbon steel piping and valve bodies in a treated water environment and has referenced Note H. The definition of Note H implies that these line items are not consistent with the GALL Report. However, the applicant has identified the GALL Report Item VII.E3-18, which is for loss of material due to general, pitting and crevice corrosion.

Please justify why a GALL Report item is identified, if the line item is not consistent with the

GALL Report.

RAI 3.3.2.3.25-2 Note H states that aging effect is not in NUREG-1801 for this component, material and environment combination. Yet in the same table, the LRA has another line item for the same component, material and aging effect combination with an aging effect of loss of material due to FAC where the LRA has referenced Note A and correctly identified the GALL Report Item

VIII.D2-8.

Please justify why Note H is used in one case and Note A for another in the same system.

RAI 3.3.2.1-1 Two lines in Table 3.3.2-13, fire protection system, for heat exchanger tube components, which reference Table 1 Item 3.3.1-83 and Note E, the applicant has credited Fire Water System Program to manage the aging effects of reduction in heat transfer. However, in Table 3.3.1, Item 3.3.1-83, the discussion column does not credit Fire Water System Program. Please resolve this discrepancy.

RAI 3.3.2.2.10.5-1 In the discussion column of Table 3.3.1, Item 3.3.1-27, the applicant states that the System Walkdown Program, the Cooling Units Inspection, and the Supplemental Piping/Tank Inspection are credited to manage loss of material and references Section 3.3.2.2.10.5 for further evaluation. However, Section 3.3.2.2.10.5 does not address the Supplemental Piping/Tank Inspection. Please resolve this discrepancy.

RAI 3.3.1-6 In the discussion column of Table 3.3.1, Item 3.3.1-27, the applicant states that the Cooling Units Inspection will also detect and characterize cracking of aluminum HVAC cooling unit fins, for which Note H is used. However, a review of the Table-2 did not identify a line item where this is identified. Please clarify where in Table-2 the Cooling Units Inspection is credited for managing cracking of aluminum HVAC cooling unit fins.

Letter to B. McKinney from E. Gettys, dated July 9, 2008 DISTRIBUTION

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr RidsNrrDlrRlra

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EGettys FJaxheimer Susquehanna Steam Electric Station, Units 1 and 2

cc:

Cornelius J. Gannon Vice President - Nuclear Operations

PPL Susquehanna, LLC

769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Robert M. Paley General Manager - Plant Support

PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 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

Supervisor - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4

Allentown, PA 18101-1179

Ronald E. Smith General Manager - Site Preparedness and Services PPL Susquehanna, LLC

769 Salem Blvd., NUCSA4

Berwick, PA 18603-0467

Michael H. Rose Manager - Quality Assurance

PPL Susquehanna, LLC

769 Salem Blvd., NUCSB2

Berwick, PA 18603-0467

Joseph J. Scopelliti Community Relations Manager,

Susquehanna

PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467 Bryan A. Snapp, Esq.

Associate General Counsel PPL Services Corporation Two North Ninth Street, GENTW3

Allentown, PA 18101-1179

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, Units 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