ML072360232

Summary of Telephone Conference Call Held on August 23, 2007, Between the U.S. Nuclear Regulatory Commission and PPL Susquehanna, LLC, Concerning Draft Requests for Additional Information Pertaining to the Susquehanna Steam Electric Station

ML072360232
Person / Time
Site:	Susquehanna
Issue date:	09/07/2007
From:	Gettys E NRC/NRR/ADRO/DLR/RLRA
To:	Susquehanna
Gettys Evelyn, NRR/DLR/RLRA 415-4029
References
Download: ML072360232 (10)

Text

September 7, 2007LICENSEE:PPL Susquehanna, LLCFACILITY:Susquehanna Steam Electric Station, Units 1 and 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 23, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY

COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT

REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE

RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on August 23, 2007, to discuss and clarify

the staff's draft requests for additional information (D-RAIs) concerning the Susquehanna Steam

Electric Station, Units 1 and 2, license renewal application. The telephone conference call was

useful in clarifying the intent of the staff's D-RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/Evelyn Gettys, Project Manager License Renewal Branch A

Division of License Renewal

Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

As stated cc w/encls: See next page

ML072360232OFFICEPM:RLRA:DLRLA:DLRBC:RLRA:DLRNAMEEGettysSFigueroaLLundDATE09/4/0709/06/0709/07/07

TELEPHONE CONFERENCE CALL SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS AUGUST 23, 2007 PARTICIPANTS AFFILIATIONSEvelyn GettysU.S. Nuclear Regulatory Commission (NRC)Simon ShengNRC Duane FilchnerPPL Susquehanna, LLC (PPL)

Jeff WeikPPL Mike DetamorePPL DRAFT REQUESTS FOR ADDITIONAL INFORMATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION August 23, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on August 23, 2007, to discuss and clarify

the following draft requests for additional information (D-RAIs) concerning the Susquehanna

Steam Electric Station (SSES), Units 1 and 2, license renewal application (LRA).

D-RAI 4.2.1-1 Section 4.2.1 of the Susquehanna LRA, "Neutron Fluence," provides the calculated reactor pressure vessel (RPV) beltline fluence values at 54 effective full power years (EFPY) for both

units. Please confirm that this fluence calculation is consistent with that associated with the

current pressure-temperature (P-T) limits, valid for 35.7 EFPY for Unit 1 and 30.2 EFPY for

Unit 2. Provide the fluence values and approximate expiration dates corresponding to these

EFPYs for the current P-T limits.

Discussion

The discussion between the staff and the applicant eliminated this D-RAI .

Therefore, this question is withdrawn and will not be sent as a formal RAI.

D-RAI 4.2.5-1 In the July 28, 1998, SER on BWRVIP-05, the NRC staff concluded that examination of the RPV circumferential shell welds would need to be performed if the corresponding volumetric

examinations of the RPV axial shell welds revealed the presence of an age-related degradation

mechanism. Confirm whether or not previous vo lumetric examinations of the RPV axial shell welds have shown any indication of cracking or other age-related degradation mechanisms in

the welds. Please also confirm whether there are any flaw evaluations performed to date on

RPV flaws as a result of previous volumetric ex aminations of the RPVs, and, if flaw evaluations exist, why they are not considered as TLAAs.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 4.7.3-1 LRA Section 4.7.3 states that, based on BWRVIP-25, "BWR Core Plate Inspection and Flaw Evaluation Guidelines," the core plate hold-down bolts will have at least 81-percent preload

remaining at 54 EFPY and, based on the GE extended power uprate (EPU) analyses of the core

plate hold-down bolts, the preload at the end of 60 years would be adequate to prevent lateral

motion of the core plate for the period of extended operation. This conclusion is not supported

by any Susquehanna plant-specific evaluation. Please provide the following additional

information: (1) Demonstrate the applicability of the BWRVIP-25 loss of preload analysis to the Susquehanna units. Identify the temperature of the bolts during the normal

operation and the projected bolt neutron fluence at the end of the period of

extended operation for the Susquehanna units. Provide a plant-specific evaluation

demonstrating that the loss of preload due to stress relaxation for the

Susquehanna RPV core plate hold-down bolts is bounded by the value of 19

percent from Appendix B of BWRVIP-25.

(2)Perform a plant-specific core plate hold-down bolt analysis using the BWRVIP-25 Appendix A methodology, demonstrating that the axial and bending stresses for

the mean and highest loaded hold-down bolts will not exceed the American Society

of Mechanical Engineers Boiler and Pressure Vessel Code Section III allowable

stresses for P m (primary membrane) and P m + P b (primary membrane plus bending) as a result of a plant-specific reduction in the bolt preload at the end of the

extended period of operation. State clearly the assumptions on which the plant-

specific analysis was based. (3)Provide sufficient information regarding the "GE EPU analyses" on the core plate hold-down bolts so that the staff can determine whether the Susquehanna

hold-down bolts are adequate to prevent lateral motion of the core plate for the

period of extended operation.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 4.7.3-2 LRA Appendix C discussed the applicant's response to BWRVIP report application action items.

The majority of these BWRVIP reports are related to degradation of the structural integrity of

austenitic stainless steel RPV internals due to irradiation assisted stress corrosion cracking, and

the associated BWRVIP application action items require evaluation of TLAA for these RPV

internals for the period of extended operation. Except for a couple of cases, the LRA

plant-specific responses to these BWRVIP reports do not address TLAA. Please address the

TLAA for RPV internals discussed in the Appendix C and demonstrate that the Susquehanna

RPV internals are bounded by these BWRVIP reports. For the Susquehanna RPV internals

which are not bounded by these BWRVIP reports, discuss any additional programs and

activities to be implemented in the extended period of operation so that their TLAAs will be

acceptable. Further, perform a similar evaluation for Susquehanna RPV core shrouds, referencing BWRVIP-76, "Boiling Water Reactor Core Shroud Inspection and Flaw Evaluation

Guidelines."

Discussion

Based on the discussion with the applicant, the staff agreed to revise this question as follows. The revised question will be sent as a formal RAI. RAI 4.7.3-2 LRA Appendix C discussed the applicant's response to BWRVIP report application action items.

The BWRVIP reports addressing the TLAA regarding irradiation assisted stress corrosion

cracking (IASCC) in austenitic stainless steel RPV internals are BWRVIP-25, BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines," BWRVIP-76, "BWR Core Shroud

Inspection and Flaw Evaluation Guidelines," and BWRVIP-47-A, "BWR Lower Plenum

Inspection and Flaw Evaluation Guidelines." Although managing TLAA using aging

management programs or other measures is stat ed in Appendix C in your response to BWRVIP report application action items, IASCC in austenitic stainless steel RPV internals should be

discussed in the TLAA section to build the connection between LRA Section 4.0 and Appendix

C. Further, the fact that BWRVIP-47 is under the NRC staff review doesn't imply that you don't

need to address it. In addition to your plant-specific evaluation using BWRVIP-76, you need to

make a commitment to follow all BWRVIP-76 requirements and limitations, as adjusted by the

NRC staff's safety evaluation on the BWRVIP-76 report.

Letter to PPL Susquehanna, from E. Gettys dated September 7, 2007

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 23, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY

COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT

REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE

RENEWAL APPLICATION DISTRIBUTION

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YDiaz RGuzman BRogers EGettys Susquehanna Steam Electric Station, Units 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 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.

Associate 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 Susquehanna Steam Electric Station, Units 1 and 2 cc:-2-Ms. Julie Keys Nuclear Energy Institute

1776 I Street, NW, Suite 400

Washington, DC 20006-3708