ML091250254

Summary of Tele Conf Call Held on April 14th, 2009, Between the USNRC and PPL Susquehanna, LLC, Concerning Draft Requests for Additional Information Pertaining to the SSES, Units 1 and 2, License Renewal Application

ML091250254
Person / Time
Site:	Susquehanna
Issue date:	05/07/2009
From:	Gettys E License Renewal Projects Branch 1
To:	Office of Nuclear Reactor Regulation
Gettys Evelyn, NRR/DLR/RLRA 415-4029
References
TAC MD3019, TAC MD3020
Download: ML091250254 (8)

Text

May 7, 2009 LICENSEE: PPL Susquehanna, LLC FACILITY: Susquehanna Steam Electric Station, Units 1 and 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON APRIL 14, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUEST 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 April 14, 2009, to discuss and clarify the staffs draft request for additional information (D-RAI) 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 staffs D-RAIs.

The Enclosure provides a listing of the participants.

The applicant had an opportunity to comment on this summary.

\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/encls: See next page

ML091250254 OFFICE LA:DLR PM:RPB1:DLR BC: RPB1:DLR NAME SFigueroa EGettys DPelton DATE 5/6/09 5/7/09 5/7/09

TELEPHONE CONFERENCE CALL SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS April 14, 2009 PARTICIPANTS AFFILIATIONS Evelyn Gettys U.S. Nuclear Regulatory Commission (NRC)

Allen Hiser NRC Chuang-Yeh Yang NRC Duane Filchner PPL Susquehanna, LLC (PPL)

Dave Flyte PPL Jeff Weik PPL Gary Stevens Structural Integrity ENCLOSURE 1

DRAFT REQUEST FOR ADDITIONAL INFORMATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION April 14, 2009 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on April 14, 2009, to discuss and clarify the following draft request for additional information (D-RAI) concerning the Susquehanna Steam Electric Station (SSES), Units 1 and 2 license renewal application (LRA).

D-RAI 4.3.1-1 The Susquehanna Steam Electric Station (SSES) Fatigue Monitoring Program (FMP) relies on transient cycle monitoring to evaluate the fatigue usage described in the license renewal application. It is essential that all thermal and pressure activities are bounded by the design specifications and cycles of all significant thermal events are captured and logged. In the response to RAI B.3.1-1, dated August 01, 2008, it states that SSES FMP cycle counting assumes every event has a severity equal to that assumed in the design basis.

To ensure effectiveness and validity of the fatigue monitoring program, the staff requests additional information, as described below:

a) Confirm that all monitored transient events were bounded by the design specifications.

b) Specify the time (years) over which actual transient monitoring and cycle tracking activities took place. If there have been periods in which transients data are not recorded since the plant startup, for any types of transients, specify the affected time frame. For the time periods for which transients were not monitored, provide justification to demonstrate that the projected cycles for this unmonitored period are conservative.

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

D-RAI 4.3.1-2 LRA Section 4.3.1 states that Normal, upset, and test conditions used in the fatigue analyses of the Reactor Pressure Vessel (RPV) assembly are summarized in Table 4.3-1.

Design cumulative usage factors (CUFs) for the limiting RPV assembly locations are obtained from applicable design reports and are summarized in Table 4.3-2... LRA Tables 4.3-1 and 4.3-2 include 60-year cycle projections and 60-year CUF projections, respectively, for Units 1 and 2.

ENCLOSURE 2

a) LRA Table 4.3-1 shows that the 60-year projected cycles for a majority of transients are lower than the respective design cycles, approximately by a factor between 2 and 3 for both units. For startup and shutdown transients, the 60-year projected cycles are higher than the design cycles, by approximately 30%. LRA Table 4.3-2 shows that for some of the limiting RCPB locations, the 60-year projected CUF values are much lower than the 40-year design CUF values, up to a factor of 10 and even greater.

Describe the basis for the large reductions in CUF values with relatively minor reduction in cycle projections, in spite of some cases having projected higher cycles higher than the design cycles.

b) LRA Table 4.3-1 indicates that the ratios of the design cycles to the 60-year projected cycles are distinct for each transient. Describe how 60-year CUF projections were made.

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

D-RAI 4.3-9R In letter dated November 26, 2008, the applicant responded to RAI 4.3-9 by stating the following:

The dissolved oxygen levels in the SSES Unit 1 and Unit 2 feedwater systems, before and after the implementation of hydrogen water chemistry, are maintained at less than 50 parts per billion (ppb).

In addition, footnotes to the tables on page 4 and 5 of Enclosure 1 to PLA-6464 state that the environmental CUF values were determined assuming the following dissolved oxygen levels for the Feedwater system: 47 ppb with Normal Water Chemistry, 40 ppb with Hydrogen Water Chemistry for Unit 1; 40 ppb with Normal Water Chemistry and 39 ppb with Hydrogen Water Chemistry for Unit 2.

To facilitate its review and evaluation, the staff is requesting that the applicant:

a) Describe how the SSES reactor/turbine/condensate system is designed to maintain the oxygen level in the feedwater system less than 50 ppb.

b) Provide justification of why the data in Enclosure 1 to PLA-6464, entitled Dissolved Oxygen Data to Support Response to RAI 4.3-9, from 1994 to 1998 (before implementation of hydrogen water chemistry) is applicable for the entire operating period from startup through 1994 for the feedwater system.

c) Provide dissolved oxygen (DO) data for the SSES at full power for the three summer months of each of the following years: 1985, 1988 and 1991, for both Units 1 and 2. If the unit was not at full power during these periods, provide data from the next 3 month period that the unit was at full power.

d) Identify any periods where DO content in the feedwater system was greater than 50 ppb.

How were these periods consistently handled in the CUF calculations?

e) Provide the basis of sampling method, including the location(s) where water samples were taken, and confirm that the DO data in the feedwater system shown in PLA-6464 are bounding and applicable to all NUREG/CR-6260 locations for Fen calculations.

Discussion: The applicant indicated that the question is clear, however section b and d are pre decisional for PPL. The applicant stated, that at this time, SSES will not have answers to the question asked in b and d. This D-RAI will be sent as a formal RAI with the elimination of questions b and d.

Letter to PPL Susquehanna, LLC from E. Gettys, dated May 7, 2009 DISTRIBUTION:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON APRIL 14, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC., CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION HARD COPY:

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EGettys FJaxheimer

Susquehanna Steam Electric Station, Units 1 and 2 cc:

Cornelius J. Gannon Document Control Services Vice President - Nuclear Operations PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENPL4 769 Salem Blvd., NUCSB3 Allentown, PA 18101-1179 Berwick, PA 18603-0467 Richard W. Osborne Robert M. Paley Allegheny Electric Cooperative, Inc.

General Manager - Plant Support 212 Locust Street PPL Susquehanna, LLC P.O. Box 1266 769 Salem Blvd., NUCSB2 Harrisburg, PA 17108-1266 Berwick, PA 18603-0467 Director, Bureau of Radiation Protection Michael H. Crowthers Pennsylvania Department of Manager - Nuclear Regulatory Affairs Environmental Protection PPL Susquehanna, LLC Rachel Carson State Office Building Two North Ninth Street, GENPL4 P.O. Box 8469 Allentown, PA 18101-1179 Harrisburg, PA 17105-8469 Ronald E. Smith Senior Resident Inspector General Manager - Site Preparedness U.S. Nuclear Regulatory Commission and Services P.O. Box 35, NUCSA4 PPL Susquehanna, LLC Berwick, PA 18603-0035 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Michael H. Rose 475 Allendale Road Manager - Quality Assurance King of Prussia, PA 19406 PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Dr. Judith Johnsrud Berwick, PA 18603-0467 National Energy Committee Sierra Club Joseph J. Scopelliti 443 Orlando Avenue Community Relations Manager, State College, PA 16803 Susquehanna PPL Susquehanna, LLC Dayne R. Brophy 634 Salem Blvd., SSO Nuclear Regulatory Affairs Berwick, PA 18603-0467 PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Board of Supervisors Berwick, PA 18603-0467 Salem Township P.O. Box 405 Berwick, PA 18603-0035 Bryan A. Snapp, Esq.

Associate General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179