ML101480726

Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2 License Renewal Application Regarding Section B.3.1.1 (TAC Nos. ME1834 and ME1836)

ML101480726
Person / Time
Site:	Salem
Issue date:	06/30/2010
From:	Bennett Brady License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group
CUADRADO S
References
TAC ME1834, TAC ME1836
Download: ML101480726 (10)

Text

June 30, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REGARDING SECTION B.3.1.1 (TAC NOS. ME1834 AND ME1836)

Dear Mr. Joyce:

By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station, Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs request for additional information is included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were provided to John Hufnagel and other members of your staff, 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 by telephone at 301-415-2981 or by e-mail at bennett.brady@nrc.gov.

Sincerely,

/RA/

Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-272 and 50-311

Enclosure:

As stated cc w/encl: See next page

ML101480726 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME B. Brady I. King B. Pham B. Brady DATE 06/09/10 06/09/10 06/30/10 06/30/10

Letter to T. Joyce from B. Brady dated June 30, 2010

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REGARDING SECTION B.3.1.1 (TAC NOS. ME1834 AND ME1836)

DISTRIBUTION:

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Salem Nuclear Generating Station, Units 1 and 2 cc:

Mr. Robert Braun Mr. Ali Fakhar Senior Vice President Nuclear Manager, License Renewal PSEG Nuclear LLC PSEG Nuclear LLC One Alloway Creek Neck Road One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Carl Fricker Mr. William Mattingly Station Vice President - Salem Manager - Salem Regulatory Assurance PSEG Nuclear LLC PSEG Nuclear LLC One Alloway Creek Neck Road One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Michael Gallagher Township Clerk Vice President - License Renewal Projects Lower Alloways Creek Township Exelon Nuclear LLC Municipal Building, P.O. Box 157 200 Exelon Way Hancocks Bridge, NJ 08038 Kennett Square, PA 19348 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Ed Eilola Radiation Protection Programs Plant Manager - Salem NJ Department of Environmental PSEG Nuclear LLC Protection and Energy, CN 415 One Alloway Creek Neck Road Trenton, NJ 08625-0415 Hancocks Bridge, NJ 08038 Mr. Brian Beam Mr. Brian Booth Board of Public Utilities Director Nuclear Oversight 2 Gateway Center, Tenth Floor PSEG Nuclear Newark, NJ 07102 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Jeffrie J. Keenan, Esquire 475 Allendale Road Manager - Licensing King of Prussia, PA 19406 PSEG Nuclear LLC One Alloway Creek Neck Road Mr. Gregory Sosson Hancocks Bridge, NJ 08038 Director Corporate Engineering PSEG Nuclear LLC Senior Resident Inspector One Alloway Creek Neck Road Salem Nuclear Generating Station Hancocks Bridge, NJ 08038 U.S. Nuclear Regulatory Commission Drawer 0509 Mr. Paul Davison Hancocks Bridge, NJ 08038 Vice President, Operations Support PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038

Salem Nuclear Generating Station, 2 Units 1 and 2 cc:

Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REGARDING SECTION B.3.1.1 RAI B.3.1.1-01

Background:

Enhancement 1 of license renewal application (LRA) aging management program (AMP)

B.3.1.1, Metal Fatigue of Reactor Coolant Pressure Boundary Program, states that the parameters monitored or inspected program element of the AMP will be enhanced to include additional transients beyond those defined in the Technical Specifications (TS) and the updated final safety analysis report (UFSAR), and expanding the fatigue monitoring program to encompass other components identified to have fatigue as an analyzed aging effect, which require monitoring.

The U.S. Nuclear Regulatory Commissions (NRCs or the staffs) recommended program elements for these types of AMPs are given in Section X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary, of NUREG-1801, Revision 1, Volume 2 (Generic Aging Lessons Learned [GALL] AMP X.M1). Section 3.0 of NUREG-1800, Revision 1, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR), defines such enhancements.

Issue 1:

It is not evident whether the stated enhancement is being made to make the parameters monitored or inspected program element of AMP B.3.1.1 consistent with the corresponding program element in GALL AMP X.M1. It is also not apparent to the staff what is being enhanced relative to the information that has been provided for LRA AMP B.3.1.1, and specifically whether the enhancement will be of the basis document or procedure for this AMP or the implementing procedure for this AMP, or both.

Request 1:

Confirm that the stated enhancement is being proposed to make the parameter monitored or inspected program element of LRA AMP B.3.1.1 consistent with that in GALL AMP X.M1. Also, clarify what documents or procedures will be enhanced (e.g., basis document, implementing procedure, etc.) relative to enhancement 1 of LRA AMP B3.1.1.

Issue 2:

The current licensing basis transients for Salem Nuclear Generating Station (SNGS) are those specified in TS Table 5.7.1-1, which are required to be tracked pursuant to the requirements in TS 5.7.1. The design basis transients for SNGS are identified in UFSAR Sections 3.9.1.1.1 through 3.9.1.1.11 and in UFSAR Tables 3.9-1 and 3.9-1a. The UFSAR sections and tables include transients that are listed in TS Table 5.7.1-1. SNGS would require tracking design basis ENCLOSURE

transients that are listed in one of the stated UFSAR sections or tables but are not within the scope of the stated TS requirements.

Request 2:

Clarify the process, procedure, or protocol that will be used at SNGS to track the occurrences of those design basis transients that are listed in UFSAR but are not within the scope of TS 5.7.1.

Issue 3:

The enhancement states that the program will be enhanced to track additional transients that are not within the scope of either the applicable TS requirements or UFSAR design basis sections or tables. The staff needs to know which transients are being referred to here, and if it is necessary to track them for possible inclusion in updated cumulative usage factor (CUF) analyses, and whether the applicant will be updating the design basis in UFSAR Section 3.9.1.1 to include them.

Request 3:

Identify the additional transients that are being referred to in Enhancement 1 of the AMP, and clarify which American Society of Mechanical Engineers (ASME) Code Class 1 components these additional transients are related to. Clarify whether an update of the design basis will be performed to include these transients. If the design basis will be updated, identify which of the Sections or Tables in UFSAR Section 3.9.1.1 will be updated to include these transients and clarify whether this will be covered within the scope of an applicable LRA commitment. Justify your basis for omitting these transients from the design basis (as given in applicable sections or tables in UFSAR Section 3.9.1.1) if the design basis will not be updated to include these transients.

Issue 4:

The enhancement states, in part, that the program will be enhanced to expand the fatigue monitoring program to encompass other components identified to have fatigue as an analyzed aging effect, which require monitoring. However, it appears that a similar enhancement is given in Enhancement 4 of the AMP, which was placed appropriately on thecorrective actions program element in GALL AMP X.M1. The corrective action program element recommendation in GALL AMP X.M1 states, in part, that for programs that monitor a sample of high fatigue usage locations, corrective actions include a review of additional affected reactor coolant pressure boundary locations, and appears to be the only program element in GALL AMP X.M1 that specifically mentions expansion of program to additional reactor coolant pressure boundary components. Thus, it is not apparent to the staff whether the expansion criteria in Enhancement 1 should be applied to scope of program, monitoring and trending, or corrective actions program elements for the program (or to some combination of these elements), or whether it is redundant with the enhancement discussed in Enhancement 4 of the AMP.

Request 4:

Clarify whether the expansion criterion in Enhancement 1 is being applied as an enhancement of the monitoring and trending program element or corrective actions program element of the AMP, or whether it is redundant with the enhancement discussed in Enhancement 4 of the AMP. Justify why the expansion aspect of Enhancement 1 has also not been placed on the scope of program or monitoring and trending program elements of the AMP, if the expansion aspect of the enhancement does not relate to a corrective action activity.

RAI B.3.1.1-02

Background:

Enhancement 2 of LRA AMP B.3.1.1 states that the Metal Fatigue of Reactor Coolant Pressure Boundary Program will be enhanced to use a software program to automatically count transients and calculate cumulative usage on select components. The applicant identifies that this enhancement is applicable to the following program elements of the AMP: (1) scope of program; (2) preventative actions; (3) parameters monitored or inspected; (4) monitoring and trending; and (5) acceptance criteria.

The GALL and SRP-LR criteria stated as background information for request for additional information (RAI) B.3.1.1-1 apply to this RAI as well.

Issue:

It is not evident whether the stated enhancement is being made to the scope of program; preventative actions; parameters monitored or inspected; monitoring and trending; and acceptance criteria program elements of AMP B.3.1.1 in order to make them consistent with the corresponding program elements in GALL AMP X.M1. It is also not apparent to the staff exactly what is being enhanced and specifically whether the enhancement will involve an enhancement of the computer programming for WESTEMS monitoring software, the stated program elements in the basis document or procedure for this AMP, the implementing procedure for this AMP, or some combination of these software/document bases. It is also not evident to the staff how this enhancement will be tied to the stated program elements of this AMP and to the implementing procedure for the software package if the enhancement only pertains to an anticipated update of WESTEMS software programming to cover the scope of the scope of program; preventative actions; parameters monitored or inspected; monitoring and trending; and acceptance criteria program elements in GALL AMP X.M1.

Request:

Confirm that the stated enhancement is being proposed to make the scope of program; preventative actions; parameters monitored or inspected; monitoring and trending; and acceptance criteria program elements of AMP B3.1.1 consistent with those in GALL AMP X.M1. Clarify exactly what will be enhanced (e.g., WESTEMS software programming, program elements in the basis document, implementing procedure, etc.) relative to Enhancement 1 of LRA AMP B.3.1.1. Justify why the associated program elements in AMP B.3.1.1 and the associated implementing procedure would not have to be updated as well

to account for this enhancement if the implementation of the enhancement will be limited only to an anticipated update of WESTEMS software programming (i.e., only for the purpose of adjusting the scope of the software programming to include and bound the scope of the scope of program; preventative actions; parameters monitored or inspected; monitoring and trending; and acceptance criteria program element recommendations in GALL AMP X.M1).

RAI B.3.1.1-03

Background:

Enhancement 3 of LRA AMP B.3.1.1 states that the Metal Fatigue of Reactor Coolant Pressure Boundary Program will be enhanced to address the effects of the reactor coolant environment on component fatigue life by assessing the impact of the reactor coolant environment on a sample of critical components for the plant identified in NUREG/CR-6260. The applicant identifies that this enhancement is applicable to the following program elements of the AMP:

(1) preventative actions; (2) parameters monitored or inspected; (3) monitoring and trending; and (4) acceptance criteria.

The GALL and SRP-LR criteria stated as background information for RAI B.3.1.1-1 apply to this RAI as well. The monitoring and trending and acceptance criteria program elements in GALL AMP X.M1 are the only program elements that deal with the adequacy of environmental fatigue calculations. The monitoring and trending program element recommendation relates the need to the AMP to monitor and trend the impact of environmental fatigue on the CUF values of the Class 1 reactor coolant pressure boundary components that correspond to those listed and analyzed in NUREG/CR-6260 or that are considered to be bounding for the component locations listed in the NUREG. The acceptance criteria program element recommendation relates the need to the AMP to establish acceptance criteria for CUF calculations based on the ASME Section III design limit for CUF calculations, and for the need to adjust this criterion (in either the calculations themselves or on a reduction of the acceptance limit) if the component being analyzed is one of the components for the environmental fatigue calculations in the AMP.

Issue:

The relationship of Enhancement 3 to the monitoring and trending program element recommendation in GALL AMP X.M1 appears to be self evident. However, it is not apparent to the staff whether this enhancement is being used to make the preventative actions, parameters monitored or inspected, and acceptance criteria program elements for AMP B.3.1.1 consistent with those in GALL AMP X.M1. If this is the purpose, the staff seeks clarification on how this enhancement relates to the acceptance criterion recommendation for environmental fatigue calculations in the acceptance criteria program element of GALL AMP X.M1. It is also not evident to the staff how this enhancement relates to the preventative actions and parameters monitored or trended program elements in GALL AMP X.M1 (which do not mention criteria for environmental calculations or assessments).

Request:

Confirm that the stated enhancement is being proposed to make the preventative actions; parameters monitored or inspected; monitoring and trending; and acceptance criteria program elements of AMP B.3.1.1 consistent with that in GALL AMP X.M1. Clarify how this enhancement relates to conforming with the acceptance criterion recommendation for environmental fatigue calculations in the acceptance criteria program element of GALL AMP X.M1 and with the aging management recommendations in the preventative actions and parameters monitored or trended program elements in GALL AMP X.M1 (which are silent relative to criteria for environmental fatigue calculations).

RAI B.3.1.1-04

Background:

Enhancement 4 of LRA AMP B.3.1.1 states that the Metal Fatigue of Reactor Coolant Pressure Boundary Program will be enhanced to require a review of additional reactor coolant pressure boundary locations if the usage factor for one of the environmental fatigue sample locations approaches its design limit. The applicant identifies that this enhancement is applicable to the corrective action program element of the AMP.

The GALL and SRP-LR criteria stated as background information for RAI B.3.1.1-1 apply to this RAI as well.

Issue:

It is not evident whether the stated enhancement is being made to make the corrective actions program element of AMP B.3.1.1 consistent with the corresponding program element in GALL AMP X.M1. It is also not apparent to the staff about what is being enhanced relative to the information that has been docketed for LRA AMP B.3.1.1, and specifically whether the enhancement will involve an enhancement of the basis document or procedure for this AMP, the implementing procedure for this AMP, or both.

Request:

Confirm that the stated enhancement is being proposed to make the corrective actions program element of LRA AMP B.3.1.1 consistent with that in GALL AMP X.M1. Clarify what will be enhanced (e.g., basis document, implementing procedure, etc.) relative to Enhancement 4 of LRA AMP B.3.1.1.