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{{#Wiki_filter:June 6, 2006Mr. Biff BradleyMr. Michael P. GallagherNuclear Energy InstituteDirector, Licensing & Regulatory Affairs Suite 400Exelon Nuclear 1776 I Street, NW200 Exelon Way Washington, DC 20006-3708Kennett Square, PA 19348
{{#Wiki_filter:June 6, 2006 Mr. Biff Bradley                                      Mr. Michael P. Gallagher Nuclear Energy Institute                              Director, Licensing & Regulatory Affairs Suite 400                                            Exelon Nuclear 1776 I Street, NW                                    200 Exelon Way Washington, DC 20006-3708                            Kennett Square, PA 19348


==Dear Mr. Bradley and Mr. Gallagher:==
==Dear Mr. Bradley and Mr. Gallagher:==


The Nuclear Regulatory Commission staff is conducting its review of Risk ManagementTechnical Specifications Initiative 5b, Surveillance Frequency Control Program, which includes the Limerick license amendment request of June 11, 2004, and the Nuclear Energy Institute(NEI) proposed process methodology document NEI 04-10. Enclosed are the final set of staff comments and requests for additional information (RAIs) (see Enclosure) resulting from its review of the initial submittals. We are prepared to meet with you to further discuss these comments and RAIs. Pleasecontact Bob Tjader at (301) 415-1187 or e-mail trt@nrc.gov if you have any questions or needfurther information on these proposed changes.Sincerely,/RA/Timothy J. Kobetz, ChiefTechnical Specifications Branch Division of Inspection & Regional Support Office of Nuclear Reactor Regulation
The Nuclear Regulatory Commission staff is conducting its review of Risk Management Technical Specifications Initiative 5b, Surveillance Frequency Control Program, which includes the Limerick license amendment request of June 11, 2004, and the Nuclear Energy Institute (NEI) proposed process methodology document NEI 04-10. Enclosed are the final set of staff comments and requests for additional information (RAIs) (see Enclosure) resulting from its review of the initial submittals.
We are prepared to meet with you to further discuss these comments and RAIs. Please contact Bob Tjader at (301) 415-1187 or e-mail trt@nrc.gov if you have any questions or need further information on these proposed changes.
Sincerely,
                                              /RA/
Timothy J. Kobetz, Chief Technical Specifications Branch Division of Inspection & Regional Support Office of Nuclear Reactor Regulation


==Enclosure:==
==Enclosure:==
As statedcc:  See attached page


ML061520205OFFICEITSB/DIRSEEEB/DEITSB/DIRSNAMETRTjaderGAWilsonTJKobetz DATE6/2/066/6/066/6/06 Letter to Mr. Biff Bradley and M. Gallagher from T.J. Kobetz dated:  cc via e-mail
As stated cc: See attached page
:Mr. Tony PietrangeloNuclear Energy Institute arp@nei.orgMr. Biff Bradley Nuclear Energy Institute reb@nei.orgMr. Mike Schoppman Nuclear Energy Institute mas@nei.orgMr. Alan Hackerott, Chairman Omaha Public Power District hhackerott@oppd.comMr. Ray Schneider Westinghouse Electric Company raymond.e.schneider@us.westinghouse.comMr. Jim Kenny Pennsylvania Power & Light Company jimkenny@pploweb.comMr. James Andrachek Westinghouse Electric Company Andracjd@westinghouse.comMr. John Gaertner EPRI jgaertner@erpi.com Mr. Frank RahnEPRI frahn@epri.com Mr. Gabe SalamonNMC gabor.salamon@nmcco.com Mr. Glenn StewartExelon glenn.stewart@exeloncorp.com Mr. Michael S. Kitlan, Jr.Duke Energy Corporation mskitlan@duke-energy.com Mr. Donald HoffmanEXCEL Services Corporation donaldh@excelservices.comMr. Wayne Harrison STP awharrison@stpegs.comMr. Jerry Andre Westinghouse Electric Company Adykes@absconsulting.com Mr. Eugene KellyExelon eugene.kelly@exeloncorp.com Mr. Andrew Dykes ABSC Adykes@absconsulting.com


Mr. Courtney Smyth PSEG Nuclear LLC courtneysmyth@pseg.com Mr. Gary ChungSCE-SONGS gary.chung@songs.sce.com
ML061520205 OFFICE ITSB/DIRS                    EEEB/DE                  ITSB/DIRS NAME TRTjader                      GAWilson                TJKobetz DATE      6/2/06                  6/6/06                  6/6/06


Letter to: Mr. Bradley and Mr. Gallager, by T.J. Kobetz Dated: DISTRIBUTION:ADAMS PUBLIC TSS R/F TSS Staff RidsNrrDIRS RidsNrrAdro RidsNrrDss RidsNrrDssSbpb RidsNrrDssSbwb RidsNrrDra RidsNrrDrp RidsNrrDnrl RidsNrrDorl RidsNrrDlr RidsNrrDe RidsOgcRp RidsAcrsAcnwMailCenter NSaltos (NTS)
Letter to Mr. Biff Bradley and M. Gallagher from T.J. Kobetz dated:
cc via e-mail:
Mr. Tony Pietrangelo                                Mr. Gabe Salamon Nuclear Energy Institute                            NMC arp@nei.org                                        gabor.salamon@nmcco.com Mr. Biff Bradley                                    Mr. Glenn Stewart Nuclear Energy Institute                            Exelon reb@nei.org                                        glenn.stewart@exeloncorp.com Mr. Mike Schoppman                                  Mr. Michael S. Kitlan, Jr.
Nuclear Energy Institute                            Duke Energy Corporation mas@nei.org                                        mskitlan@duke-energy.com Mr. Alan Hackerott, Chairman                        Mr. Donald Hoffman Omaha Public Power District                        EXCEL Services Corporation hhackerott@oppd.com                                donaldh@excelservices.com Mr. Ray Schneider                                  Mr. Wayne Harrison Westinghouse Electric Company                      STP raymond.e.schneider@us.westinghouse.com            awharrison@stpegs.com Mr. Jim Kenny                                      Mr. Jerry Andre Pennsylvania Power & Light Company                  Westinghouse Electric Company jimkenny@pploweb.com                                Adykes@absconsulting.com Mr. James Andrachek                                Mr. Eugene Kelly Westinghouse Electric Company                      Exelon Andracjd@westinghouse.com                          eugene.kelly@exeloncorp.com Mr. John Gaertner                                  Mr. Andrew Dykes EPRI                                                ABSC jgaertner@erpi.com                                  Adykes@absconsulting.com Mr. Frank Rahn                                      Mr. Courtney Smyth EPRI                                                PSEG Nuclear LLC frahn@epri.com                                      courtneysmyth@pseg.com Mr. Gary Chung SCE-SONGS gary.chung@songs.sce.com
 
Letter to: Mr. Bradley and Mr. Gallager, by T.J. Kobetz Dated:
DISTRIBUTION:
ADAMS PUBLIC TSS R/F TSS Staff RidsNrrDIRS RidsNrrAdro RidsNrrDss RidsNrrDssSbpb RidsNrrDssSbwb RidsNrrDra RidsNrrDrp RidsNrrDnrl RidsNrrDorl RidsNrrDlr RidsNrrDe RidsOgcRp RidsAcrsAcnwMailCenter NSaltos (NTS)
MLWohl (MLW1)
MLWohl (MLW1)
GSShukla (GSS)
GSShukla (GSS)
Line 56: Line 65:
GAWilson (GAW1)
GAWilson (GAW1)
METonacci (MET)
METonacci (MET)
EnclosureREQUEST FOR ADDITIONAL INFORMATIONRELOCATE SURVEILLANCE TEST FREQUENCIES FROM THE BODY OF THE TECHNICAL SPECIFICATIONS AND PLACE THEM INTO A RISK BASED OWNER CONTROLLED PROGRAM RAI 1Integrated Decision Making Panel (Expert Panel) Review of SurveillanceFrequencies Based on Codes and StandardsProvide deterministic criteria in the basis document that would be used to approve revisions tosurveillance frequencies that are based upon approved Codes and Standards.A critical attribute for any calibration or surveillance test is the interval between calibrations ortests. Many of the present surveillances, surveillance test intervals, and acceptance criteria were established over a 40 year history of industry consensus standards and regulatory endorsement through the regulatory guide processes. The guidance in RG 1.174 states thatsufficient safety margins are maintained when codes and standards (e.g., American Society of Mechanical Engineers (ASME), Institute of Electrical and Electronic Engineers (IEEE) or alternatives approved for use by the Nuclear Regulatory Commission (NRC) are met. The current draft of the methodology document recognizes that Codes and Standards helpmaintain safety margins but does not contain criteria for revising surveillance frequencies. The importance of recognizing requirements based on codes and standards is demonstrated by an example evaluation included with the Limerick pilot plant request (STI#4). The example indicated the Expert Panel determined there were no codes or standards associated with the Limerick emergency diesel generator (EDG) surveillance test frequencies. However the EDGsurveillances are directly mentioned in IEEE Std.- 387, "Standard Criteria for Diesel-GeneratorUnits Applied as Standby Power Supplies for Nuclear Power Generating Stations.Refer to attached Table 1.RAI 2Technical Specification Surveillance Frequencies vs Acceptance Criteria Provide deterministic criteria in the basis document to address whether more conservativeacceptance criteria will be necessary for an extended surveillance frequency. Specifically,discuss when a surveillance frequency extension would require a change in the acceptancecriteria, such as the as-found and as-left allowable values. RAI 3Monitoring for Conditioning/Exercising Provide deterministic criteria in the basis document that evaluates the degree that asurveillance provides a conditioning exercise to maintain equipment operability, prior tochanging the surveillance frequency.Many surveillances exercise safety-related components and supporting systems on a periodicbasis. This periodic exercise of the components provide a measure of conditioning, such as lubrication of bearings and electro-pneumatic relays, or electrical contact wiping (cleaning) of built-up oxidation. RAI 4Controls on the Time of Permitted Surveillance Frequency ExtensionsProvide deterministic criteria in the basis document of a minimum number of surveillanceintervals that would be required to establish a database to further extend a previously extendedsurveillance frequency. RAI 5 Monitoring Criteria For Returning to the Original Surveillance Frequency Provide deterministic criteria in the basis document that describes how monitoring andfeedback of a surveillance with an extended frequency would result in a return to the originalfrequency when the number of surveillance test failures are determined to be too many.
 
AttachmentTABLE 1A Comparison of Selected Limerick Technical Specifications for the Emergency Diesel Generators to IEEE Standards and NRC Regulatory GuidesEmergency Diesel Generator SurveillancesLimerick Tech Spec4.8.1.1.x.x.x.IEEE-387-1995Section 7.5.xReg Guide 1.9Endorses 387-1984Monthly Interval Availability Tests Start2.a.47.5.12.2.1 Load Run2.a.57.5.22.2.2 Six Month Availability Tests Fast Start and Load2.h7.5.32.2.3 Shutdown/Refueling Outage Interval System Operation Tests LOOP2.e.47.5.42.2.4 ECCS Actuation2.e.57.5.52.2.5 Combined ECCS and LOOP2.e.67.5.62.2.6Largest Load Reject2.e.27.5.72.2.7Design Load Reject2.e.37.5.82.2.8 Endurance and Load2.e.8.a7.5.92.2.9 Hot Restart2.e.8.b7.5.102.2.10 Synchronizing2.e.107.5.112.2.11 Protective TripBypass2.e.77.5.122.2.12Test Mode Override2.e.117.5.132.2.1310 Year Interval Division Independence Independence2.f7.5.142.2.14}}
REQUEST FOR ADDITIONAL INFORMATION RELOCATE SURVEILLANCE TEST FREQUENCIES FROM THE BODY OF THE TECHNICAL SPECIFICATIONS AND PLACE THEM INTO A RISK BASED OWNER CONTROLLED PROGRAM RAI 1          Integrated Decision Making Panel (Expert Panel) Review of Surveillance Frequencies Based on Codes and Standards Provide deterministic criteria in the basis document that would be used to approve revisions to surveillance frequencies that are based upon approved Codes and Standards.
A critical attribute for any calibration or surveillance test is the interval between calibrations or tests. Many of the present surveillances, surveillance test intervals, and acceptance criteria were established over a 40 year history of industry consensus standards and regulatory endorsement through the regulatory guide processes. The guidance in RG 1.174 states that sufficient safety margins are maintained when codes and standards (e.g., American Society of Mechanical Engineers (ASME), Institute of Electrical and Electronic Engineers (IEEE) or alternatives approved for use by the Nuclear Regulatory Commission (NRC) are met.
The current draft of the methodology document recognizes that Codes and Standards help maintain safety margins but does not contain criteria for revising surveillance frequencies.
The importance of recognizing requirements based on codes and standards is demonstrated by an example evaluation included with the Limerick pilot plant request (STI#4). The example indicated the Expert Panel determined there were no codes or standards associated with the Limerick emergency diesel generator (EDG) surveillance test frequencies. However the EDG surveillances are directly mentioned in IEEE Std.- 387, Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations. Refer to attached Table 1.
RAI 2          Technical Specification Surveillance Frequencies vs Acceptance Criteria Provide deterministic criteria in the basis document to address whether more conservative acceptance criteria will be necessary for an extended surveillance frequency. Specifically, discuss when a surveillance frequency extension would require a change in the acceptance criteria, such as the as-found and as-left allowable values.
RAI 3          Monitoring for Conditioning/Exercising Provide deterministic criteria in the basis document that evaluates the degree that a surveillance provides a conditioning exercise to maintain equipment operability, prior to changing the surveillance frequency.
Many surveillances exercise safety-related components and supporting systems on a periodic basis. This periodic exercise of the components provide a measure of conditioning, such as lubrication of bearings and electro-pneumatic relays, or electrical contact wiping (cleaning) of built-up oxidation.
Enclosure
 
RAI 4        Controls on the Time of Permitted Surveillance Frequency Extensions Provide deterministic criteria in the basis document of a minimum number of surveillance intervals that would be required to establish a database to further extend a previously extended surveillance frequency.
RAI 5       Monitoring Criteria For Returning to the Original Surveillance Frequency Provide deterministic criteria in the basis document that describes how monitoring and feedback of a surveillance with an extended frequency would result in a return to the original frequency when the number of surveillance test failures are determined to be too many.
 
TABLE 1 A Comparison of Selected Limerick Technical Specifications for the Emergency Diesel Generators to IEEE Standards and NRC Regulatory Guides Emergency Diesel Generator Surveillances Limerick Tech Spec IEEE-387-1995          Reg Guide 1.9 4.8.1.1.x.x.x. Section 7.5.x        Endorses 387-1984 Monthly Interval Availability Tests Start                    2.a.4              7.5.1                2.2.1 Load Run                2.a.5              7.5.2                2.2.2 Six Month Availability Tests Fast Start and Load    2.h                7.5.3                2.2.3 Shutdown/Refueling Outage Interval System Operation Tests LOOP                    2.e.4              7.5.4                2.2.4 ECCS Actuation          2.e.5              7.5.5                2.2.5 Combined ECCS           2.e.6              7.5.6                2.2.6 and LOOP Largest Load Reject    2.e.2              7.5.7                2.2.7 Design Load Reject      2.e.3              7.5.8                2.2.8 Endurance and Load      2.e.8.a            7.5.9                2.2.9 Hot Restart              2.e.8.b            7.5.10              2.2.10 Synchronizing            2.e.10            7.5.11              2.2.11 Protective Trip          2.e.7              7.5.12              2.2.12 Bypass Test Mode Override      2.e.11            7.5.13              2.2.13 10 Year Interval Division Independence Independence            2.f                7.5.14              2.2.14 Attachment}}

Revision as of 17:57, 23 November 2019

Request for Additional Information on Relocating Surveillance Test Frequencies from Body of the Technical Specifications and Place Them Into a Risk Based Owner Controlled Program
ML061520205
Person / Time
Issue date: 06/06/2006
From: Kobetz T
NRC/NRR/ADRO/DIRS/ITSB
To: Bradley B, Gallagher M
Exelon Nuclear, Nuclear Energy Institute
Tjader T NRR/DIRS/ITSB 415-1187
References
Download: ML061520205 (7)


Text

June 6, 2006 Mr. Biff Bradley Mr. Michael P. Gallagher Nuclear Energy Institute Director, Licensing & Regulatory Affairs Suite 400 Exelon Nuclear 1776 I Street, NW 200 Exelon Way Washington, DC 20006-3708 Kennett Square, PA 19348

Dear Mr. Bradley and Mr. Gallagher:

The Nuclear Regulatory Commission staff is conducting its review of Risk Management Technical Specifications Initiative 5b, Surveillance Frequency Control Program, which includes the Limerick license amendment request of June 11, 2004, and the Nuclear Energy Institute (NEI) proposed process methodology document NEI 04-10. Enclosed are the final set of staff comments and requests for additional information (RAIs) (see Enclosure) resulting from its review of the initial submittals.

We are prepared to meet with you to further discuss these comments and RAIs. Please contact Bob Tjader at (301) 415-1187 or e-mail trt@nrc.gov if you have any questions or need further information on these proposed changes.

Sincerely,

/RA/

Timothy J. Kobetz, Chief Technical Specifications Branch Division of Inspection & Regional Support Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See attached page

ML061520205 OFFICE ITSB/DIRS EEEB/DE ITSB/DIRS NAME TRTjader GAWilson TJKobetz DATE 6/2/06 6/6/06 6/6/06

Letter to Mr. Biff Bradley and M. Gallagher from T.J. Kobetz dated:

cc via e-mail:

Mr. Tony Pietrangelo Mr. Gabe Salamon Nuclear Energy Institute NMC arp@nei.org gabor.salamon@nmcco.com Mr. Biff Bradley Mr. Glenn Stewart Nuclear Energy Institute Exelon reb@nei.org glenn.stewart@exeloncorp.com Mr. Mike Schoppman Mr. Michael S. Kitlan, Jr.

Nuclear Energy Institute Duke Energy Corporation mas@nei.org mskitlan@duke-energy.com Mr. Alan Hackerott, Chairman Mr. Donald Hoffman Omaha Public Power District EXCEL Services Corporation hhackerott@oppd.com donaldh@excelservices.com Mr. Ray Schneider Mr. Wayne Harrison Westinghouse Electric Company STP raymond.e.schneider@us.westinghouse.com awharrison@stpegs.com Mr. Jim Kenny Mr. Jerry Andre Pennsylvania Power & Light Company Westinghouse Electric Company jimkenny@pploweb.com Adykes@absconsulting.com Mr. James Andrachek Mr. Eugene Kelly Westinghouse Electric Company Exelon Andracjd@westinghouse.com eugene.kelly@exeloncorp.com Mr. John Gaertner Mr. Andrew Dykes EPRI ABSC jgaertner@erpi.com Adykes@absconsulting.com Mr. Frank Rahn Mr. Courtney Smyth EPRI PSEG Nuclear LLC frahn@epri.com courtneysmyth@pseg.com Mr. Gary Chung SCE-SONGS gary.chung@songs.sce.com

Letter to: Mr. Bradley and Mr. Gallager, by T.J. Kobetz Dated:

DISTRIBUTION:

ADAMS PUBLIC TSS R/F TSS Staff RidsNrrDIRS RidsNrrAdro RidsNrrDss RidsNrrDssSbpb RidsNrrDssSbwb RidsNrrDra RidsNrrDrp RidsNrrDnrl RidsNrrDorl RidsNrrDlr RidsNrrDe RidsOgcRp RidsAcrsAcnwMailCenter NSaltos (NTS)

MLWohl (MLW1)

GSShukla (GSS)

FMReinhart (FMR)

DGHarrison (DGH)

CKDoutt (CKD)]

DFThatcher (DFT)

PFPrescott (PFP)

KCoyne (KXC)

MDrouin (MXD)

MCThadani (MCT)

GWMorris (GWM2)

YGHsii (YGH)

DHShum (DHS)

GWParry (GWP)

ABWang (ABW)

BMPham (BMP)

AJHowe (AJH1)

TWAlexion (TWA)

MAStutzkie (MAS7)

DHJaffe (DHJ)

LAMrowca (LXM4)

JSKim (JSK)

GAWilson (GAW1)

METonacci (MET)

REQUEST FOR ADDITIONAL INFORMATION RELOCATE SURVEILLANCE TEST FREQUENCIES FROM THE BODY OF THE TECHNICAL SPECIFICATIONS AND PLACE THEM INTO A RISK BASED OWNER CONTROLLED PROGRAM RAI 1 Integrated Decision Making Panel (Expert Panel) Review of Surveillance Frequencies Based on Codes and Standards Provide deterministic criteria in the basis document that would be used to approve revisions to surveillance frequencies that are based upon approved Codes and Standards.

A critical attribute for any calibration or surveillance test is the interval between calibrations or tests. Many of the present surveillances, surveillance test intervals, and acceptance criteria were established over a 40 year history of industry consensus standards and regulatory endorsement through the regulatory guide processes. The guidance in RG 1.174 states that sufficient safety margins are maintained when codes and standards (e.g., American Society of Mechanical Engineers (ASME), Institute of Electrical and Electronic Engineers (IEEE) or alternatives approved for use by the Nuclear Regulatory Commission (NRC) are met.

The current draft of the methodology document recognizes that Codes and Standards help maintain safety margins but does not contain criteria for revising surveillance frequencies.

The importance of recognizing requirements based on codes and standards is demonstrated by an example evaluation included with the Limerick pilot plant request (STI#4). The example indicated the Expert Panel determined there were no codes or standards associated with the Limerick emergency diesel generator (EDG) surveillance test frequencies. However the EDG surveillances are directly mentioned in IEEE Std.- 387, Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations. Refer to attached Table 1.

RAI 2 Technical Specification Surveillance Frequencies vs Acceptance Criteria Provide deterministic criteria in the basis document to address whether more conservative acceptance criteria will be necessary for an extended surveillance frequency. Specifically, discuss when a surveillance frequency extension would require a change in the acceptance criteria, such as the as-found and as-left allowable values.

RAI 3 Monitoring for Conditioning/Exercising Provide deterministic criteria in the basis document that evaluates the degree that a surveillance provides a conditioning exercise to maintain equipment operability, prior to changing the surveillance frequency.

Many surveillances exercise safety-related components and supporting systems on a periodic basis. This periodic exercise of the components provide a measure of conditioning, such as lubrication of bearings and electro-pneumatic relays, or electrical contact wiping (cleaning) of built-up oxidation.

Enclosure

RAI 4 Controls on the Time of Permitted Surveillance Frequency Extensions Provide deterministic criteria in the basis document of a minimum number of surveillance intervals that would be required to establish a database to further extend a previously extended surveillance frequency.

RAI 5 Monitoring Criteria For Returning to the Original Surveillance Frequency Provide deterministic criteria in the basis document that describes how monitoring and feedback of a surveillance with an extended frequency would result in a return to the original frequency when the number of surveillance test failures are determined to be too many.

TABLE 1 A Comparison of Selected Limerick Technical Specifications for the Emergency Diesel Generators to IEEE Standards and NRC Regulatory Guides Emergency Diesel Generator Surveillances Limerick Tech Spec IEEE-387-1995 Reg Guide 1.9 4.8.1.1.x.x.x. Section 7.5.x Endorses 387-1984 Monthly Interval Availability Tests Start 2.a.4 7.5.1 2.2.1 Load Run 2.a.5 7.5.2 2.2.2 Six Month Availability Tests Fast Start and Load 2.h 7.5.3 2.2.3 Shutdown/Refueling Outage Interval System Operation Tests LOOP 2.e.4 7.5.4 2.2.4 ECCS Actuation 2.e.5 7.5.5 2.2.5 Combined ECCS 2.e.6 7.5.6 2.2.6 and LOOP Largest Load Reject 2.e.2 7.5.7 2.2.7 Design Load Reject 2.e.3 7.5.8 2.2.8 Endurance and Load 2.e.8.a 7.5.9 2.2.9 Hot Restart 2.e.8.b 7.5.10 2.2.10 Synchronizing 2.e.10 7.5.11 2.2.11 Protective Trip 2.e.7 7.5.12 2.2.12 Bypass Test Mode Override 2.e.11 7.5.13 2.2.13 10 Year Interval Division Independence Independence 2.f 7.5.14 2.2.14 Attachment