ML052920825
| ML052920825 | |
| Person / Time | |
|---|---|
| Issue date: | 10/20/2005 |
| From: | Tjader T R NRC/NRR/DIPM/IROB |
| To: | Bradley B, Gallagher M P Exelon Nuclear, Nuclear Energy Institute |
| Tjader T., NRC/IROB, 415-1187 | |
| References | |
| Download: ML052920825 (6) | |
Text
October 20, 2005Mr. 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
Dear Mr. Bradley and Mr. Gallagher:
The Nuclear Regulatory Commission (NRC) staff is conducting its review of Risk ManagementTechnical Specifications (RMTS) Initiative 5b, Surveillance Frequency Control Program, which includes the Limerick license amendment request (LAR) 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 me at (301) 415-1187 or e-mail trt@nrc.gov if you have any questions or need furtherinformation on these proposed changes.Sincerely,/RA/T. R. Tjader, Senior Reactor Engineer Technical Specifications Section Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See attached page
ML052920825OFFICESRE:TSS:IROB:DIPMSC:TSS:IROB:DIPMNAMETRTjaderTHBoyce DATE10/20/200510/20/2005 Mr. Bradley and Mr. Gallaghercc via e-mail
- Mr. Michael Gallagher ExelonMr. Tony PietrangeloNuclear Energy InstituteMr. Biff BradleyNuclear Energy InstituteMr. Alan Hackerott, ChairmanOmaha Public Power DistrictMr. Jim KennyPennsylvania Power & Light CompanyMr. James AndrachekWestinghouse Electric CompanyMr. Ray SchneiderWestinghouse Electric CompanyMr. Frank RahnEPRIMr. Wayne HarrisonSTPMr. Gabe SalamonPSEG NuclearMr. Brian WoodsCEOGMr. Rick HillGeneral Electric Nuclear EnergyMr. Michael S. Kitlan, Jr.Duke Energy CorporationMr. Donald HoffmanEXCEL Services CorporationMr. J. E. RhoadsEnergy NorthwestMr. John GaertnerEPRIMr. Gary ChungSCE-SONGSMr. Glen StewartExelonMr. Phil TarpinianExelonMr. David HelherExelonMr. Gene KellyExelonMr. Michael CrouthersBWROGPaul InfangerBWOG Mr. Wes SparkmanWOG DISTRIBUTION
- ADAMS PUBLIC TSS R/F TSS Staff RidsNrrDipm RidsNrrDssa RidsNrrDlpm RidsNrrDssaSpsb RidsNrrDssaSplb RidsNrrDipmlehb RidsOgcRp RidsAcrsAcnwMailCenter NSaltos (NTS)
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REQUEST FOR ADDITIONAL INFORMATION1.The licensee in their application Section 4.2, Key Safety Principles, indicates thatRegulatory Guide 1.174 identifies five key safety principles (a) to be met for all risk-informed applications and (b) to be explicitly addressed in risk-informed plant program change applications. The first of the five key safety principles (required to be explicitly addressed) states: "The proposed change meets the current regulations unless it is explicitly related to a requested exemption or rule change." 10 CFR 50.36(c)(3) states: "Surveillance requirements. Surveillance requirements arerequirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be withinsafety limits, and that the limiting conditions for operation will be met."The licensee in their application indicates that surveillance test intervals (STIs) forsurveillance requirements (SRs) are being relocated to a licensee-controlled program.
SRs will remain as part of the technical specifications (TS). Thus, the proposedrelocation of STIs to a licensee-controlled program meets the first of the five key safety principles. In addition to the provisions of 10 CFR 50.36(c)(3) defined above, SRs (including STIs)are required to meet 10 CFR 50.36(b). 10 CFR 50.36(b) states: "...The technical specifications will be derived from the analyses and evaluation included in the safetyanalysis report...." Analyses and evaluation in safety analysis reports relating to electrical systems includes compliance with the requirements of Criterion 17 of10 CFR Part 50, Appendix A (GDC 17). GDC 17 in part states: "...The onsite electric power supplies, including the batteries, and the onsite electric distribution system, shallhave sufficient independence, redundancy, and testability to perform their safetyfunctions assuming a single failure..." Specifically, GDC 17 requires sufficient testability. Describe how the proposed change meets the sufficient testabilityrequirement of GDC 17.2.A note included as part of Section 1 of Attachment 1 to the application states: NOTE: various TS surveillance requirements, including in some cases theirassociated STIs, were established based on commitments to Regulatory Guides, or based on implementation of NRC-approved Licensing Topical Reports. Withinthe licensee-controlled program, the surveillance requirements themselves willnot be changed and will continue to be performed in accordance with theapplicable Regulatory Guide or Topical Report, as appropriate; however, associated STIs may be modified in accordance with the licensee-controlled program. For cases where the associated STIs were established based on commitments documented inthe plant's safety analysis, clarify the extent these STIs can be changed by the licensee-controlled program without prior NRC approval.Enclosure 3.The 5b process conveys that the licensing commitment for testing will be c hanged todemonstrate the condition of equipment and thus the future operability of electricalequipment. Currently protective devices such as fuses or breakers are tested to demonstrate that they do not trip safety equipment when the safety equipment isfunctionally tested. Describe how each electrical circuit component such as fuses, breakers, and cables will be tested to demonstrate their condition so that futureoperability will be assured. Describe how the current licensing basis for testing ofelectrical equipment will be changed to assure future operability of electrical equipment.The following questions refer to specific Unit 1 technical specification but should also be takenas applicable to the corresponding Unit 2 technical specification.4.Regulatory Guide (RG) 1.118, "Periodic Testing of Electric Power and ProtectionSystems," Rev. 3, endorses, with comments, IEEE 338-1987, "Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems."
IEEE 338-1987, Section 6.5, Test Intervals, requires that changes to test intervals shall conform to the requirements of Subpart 6.5.1. This subpart requires that test intervalsconsider manufacturer's recommendations, historical experience, equipment qualification failure data in addition to plant and system operational goals. Please confirm your conformance to IEEE-338-1987 and RG 1.118 for your proposed Surveillance Frequency Control Program.5.Regulatory Guide 1.9, " Selection, Design, Qualification and Testing of EmergencyDiesel Generator Units Used As Onsite Electric Power Systems for Nuclear Power Plants," Rev. 3, supersedes Regulatory Guide 1.108, "Periodic Testing of Diesel Generator Units Used As Onsite Electric Power Systems for Nuclear Power Plants,"
Rev. 3 of RG 1.9 endorses, with comments, IEEE 387-1984, "IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations". (IEEE 387-1984 has since been superseded by IEEE 387-1995.)
Please confirm your conformance to IEEE 387-1984 and RG 1.9 or identify and explain any exceptions taken. Note, the NRC has not endorsed IEEE 387-1995. 6.Surveillance 4..8.1.1.2.e list the diesel generator refueling outage surveillance testsperformed during a refueling outage. Please confirm that the intervals for these testswill not change in the future if they are moved from the technical specifications.7.Surveillance 4.8.1.1.2.e.8, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Endurance Run. Please confirm that this load test isperformed at a power factor (pf) of < 0.9. If not, please indicate the load pf during thistest and justify how the surveillance test demonstrates the capability of the DG to carrythe post accident loading without overheating. 8.Table 4.8.1.1.2-1, Diesel Generator Test Schedule, provides the test frequency foraccelerated testing of the diesel generators based upon the number of failures in the last 20 valid tests. Generic Letter 94-01, Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators, recommended addressing diesel generator reliability through 10 CFR 50.65, (the maintenance rule.) Pleaseconfirm that the LGS diesel generator reliability is covered by the an appropriateprogrammatic application of the maintenance rule. (10 CFR 50.65)9.Please explain how the licensee-controlled program will meet the reporting requirementsof 10 CFR 50.72.