ML15029A496
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| ML15029A496 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/14/2015 |
| From: | Jensen J Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2015-015, TAC MF4694, TAC MF4695 | |
| Download: ML15029A496 (10) | |
Text
January 14, 2015FPLL-2015-01510 CFR 50.90U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555-0001Re: St. Lucie Units 1 and 2Dockets Nos. 50-335 and 50-389Response to Request for Additional Information (RAI) Regarding LicenseAmendment Request to Permanently Extend the IntegratedLeak Rate Test (ILRT) Frequency to 15 Years (MF4694 AND MF4695)
References:
- 1. FPL letter L-2014-230 dated August 26, 2014: St. Lucie Plant -Application forTechnical Specifications Change to Permanently Extend the Integrated Leak RateTest (ILRT) Frequency to 15 Years (ADAMS Accession No. ML14241A496)2. NRC letter dated December 18, 2014: Request for Additional Information RAIRegarding to LAR for a Permanent Extension to the Containment Type A Leak RateTesting License Amendment Request for a Permanent Extension to the ContainmentType A Leak Rate Testing (MF4694 AND MF4695) (ADAMS Accession No.ML14356A147)Per Reference 1 above, Florida Power & Light Company (FPL) requested anamendment to the Renewed Facility Operating Licenses for St. Lucie Unit 1 and Unit 2.The license amendment request (LAR) would modify the St. Lucie Units 1 and 2Technical Specifications to permanently extend the frequency of the containmentintegrated leak rate test (ILRT) from once per 10 years to once per 15 years.By letter dated December 18, 2014 (Reference 2), NRC staff requested additionalinformation regarding the LAR. The enclosure and attachments to this letter provide adetailed response to a request for additional information (RAI) from the Containment andVentilation Branch (SCVB).The information provided in this submittal does not impact the 10 CFR 50.92 evaluationof "No Significant Hazards Consideration" previously provided in FPL letter L-2014-230.This submittal makes no new commitments or changes to existing commitments.Should you have any questions regarding this submittal, please contact Mr. EricKatzman, Licensing Manager, at (772) 467-7734.Florida Power & Light Company6501 S. Ocean Drive, Jensen Beach, FL 34957 Page 2L-2015-015I declare under penalty of perjury that the foregoing is true and correct.Executed on January .14, 2015.Respectfully submitted,St. Lucie Nuclear Plant
Enclosure:
- 1. St. Lucie Units 1 and 2 ILRT LAR RAI ResponseAttachments:1. Unit 1 Technical Specifications Markup2. Unit 2 Technical Specifications Markupcc: USNRC Regional Administrator, Region IIUSNRC Senior Resident Inspector, St. Lucie Units 1 and 2USNRC Project Manager, St. Lucie Units 1 and 2Ms. Cindy Becker, Florida Department of Health to L-2015-015Page 1 of 2Enclosure ISt. Lucie Units I and 2 ILRT LAR RAI ResponseResponse to Request for Additional Information (RAI) Regarding License AmendmentRequest to Permanently Extend the Integrated Leak Rate Test (ILRT)Frequency to 15 Years (MF4694 AND MF4695)SCVB RAI 1 to L-2015-015Page 2 of 2SCVB RAI 110 CFR 50 Appendix J, Option B Implementation item #3 states that:The regulatory guide or other implementation document used by a licensee orapplicant for an operating license under this part or a combined license underpart 52 of this chapter to develop a performance-based leakage-testingprogram must be included, by general reference, in the plant technicalspecifications.In addition, in the August 20, 2013 letter from NRC to Nuclear Energy Institute (NEI) (ADAMSAccession no. ML13192A394) (Reference 2), the staff indicated that:Due to the omission of the limitations and conditions from NEI 94-01, Revision 2SE into NEI 94-01, Revision 3-A, the NRC will not be able to reference NEI 94-01, Revision 3-A in the update to RG 1.163. Any licensee submissionsreferencing the TR [Technical Report] will require requests for additionalinformation from the NRC to address the limitations and conditions from the NRCSE for NEI 94-01, Revision 2.In the enclosure to the submittal dated August 26, 2014, Section 2.0, "Detailed Description,"changes to the proposed TS 6.8.4.h for Units 1 and 2, included a reference to Nuclear EnergyInstitute, NEI 94-01, Revision 3-A. However, the conditions and limitations contained in NEI 94-01, Revision 2-A, were not incorporated in NEI 94-01, Revision 3-A.Explain how the 10 CFR 50 Appendix J, Option B Implementation item #3 and NRC concernsstated in the August 20, 2013 letter from NRC to NEI will be addressed.REFERENCES1. Florida Power & Light Company letter to NRC dated August 26, 2014 "St Lucie NuclearPlant Docket Nos. 50-335 and 50-389 LAR Application for TSs Change to PermanentlyExtend the ILRT Frequency to 15 Years" (ADAMS Accession Number ML14241A496).2. NRC letter to Biff Bradley (Director, Nuclear Energy Institute), dated August 20, 2013,"REQUEST REVISION TO TOPICAL REPORT NEI 94-01, REVISION 3-A, "IndustryGuideline for Implementing Performance-Based Option of 10 CFR PART 50, AppendixJ", (ADAMS Accession Number ML13192A394).RESPONSEFlorida Power & Light Company proposes to change the reference in Unit 1 and Unit 2Technical Specification (TS) 6.8.4.h from NEI 94-01, Revision 3-A to NEI 94-01, Revision 2-A asshown in Attachments 1 and 2 for Unit 1 and Unit 2, respectively. (The markup for Unit 2 TS6.8.4.h contains an editorial correction that was proposed in the application.) The limitationsand conditions contained in NEI 94-01, Revision 2 (i.e., Revision 2-A) are addressed in theapplication. to L-2015-015Page 1 of 3Attachment 1Unit I Technical Specifications Markup to L-2015-015Page 2 of 3Unit 1 Technical Specifications InsertInsert ANEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of10 CFR Part 50, Appendix J," except that the next Type A test performed after the December 8,2005 Type A test shall be performed no later than December 8, 2020. to L-2015-015Page 3 of 3ADMINISTRATIVE CONTROLS(2) conform to the guidance of Appendix I to 10 CFR Part 50, and(3) include the following:1) Monitoring, sampling, analysis, and reporting of radiation andradionuclides in the environment in accordance with the methodologyand parameters in the ODCM.2) A Land Use Census to ensure that changes in the use of areas at andbeyond the SITE BOUNDARY are identified and that modifications tothe monitoring program are made if required by the results of thiscensus, and3) Participation in a Interlaboratory Comparison Program to ensure thatindependent checks on the precision and accuracy of the measurementsof radioactive materials in environmental sample matrices are performedas part of the quality assurance program for environmental monitoring.h. Containment Leakage Rate Testing ProgramA program to implement the leakage rate testing of the containment asrequired by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, asmodified by approved exemptions. This program is in accordance with theINu Lguidelnes containe .R .. 1.163, "P.. form.anc. Based;-MtLeak1 et Pregram,' as moedified by the follow-ming exccptien(s}-.a-) Be-htet-T-epiea-Rep ,$ -e eby.R-G.- .-1&)-w ll-lbe-used-for-type-A4esMiRAgb) .,-T-h,-fir-t-Type-A-test-peFfeormed-after-4he4e-My 1993-Type-A4est--,ha4-be-Re-feter-han-Meay-2.00e8&The peak calculated containment internal pressure for the design basis lossof coolant accident Pa, is 42.8 psig. The containment design pressure is 44 psig.The maximum allowed containment leakage rate, La, at Pa, shall be 0.50% ofcontainment air weight per day.Leakage rate acceptance criteria are:a. Containment leakage rate acceptance criterion is < 1.0 La. During thefirst unit startup following testing in accordance with this program, theleakage rate acceptance criteria are < 0.60 La for the Type B and C tests,< 0.75 La for Type A tests, and < 0.096 La for secondary containmentbypass leakage paths.b. Air lock testing acceptance criteria are:1) Overall air lock leakage rate is < 0.05 La when tested at > Pa.2) For the personnel air lock door seal, leakage rate is < 0.01 Lawhen pressurized to > 1.0 Pa.3) For the emergency air lock door seal, leakage rate is < 0.01 Lawhen pressurized to > 10 psig.ST LUCIE -UNIT 1 6-15b Amendment No. 6.9, -1 4 , 44-9447-, 4W, 2-N,-24 to L-2015-015Page 1 of 3Attachment 2Unit 2 Technical Specifications Markup to L-2015-015Page 2 of 3Unit 2 Technical Specifications InsertInsert BNEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of10 CFR Part 50, Appendix J," except that the next Type A test performed after the December 18,2007 Type A test shall be performed no later than December 18, 2022. to L-2015-015ADMINISTRATIVE CONTROLS Page 3 of 3than 8 days in gaseous effluents released from each unit to areas beyond theSITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,10) Limitations on the annual dose or dose commitment to any MEMBEROF THE PUBLIC, beyond the site boundary, due to releases of radioactivityand to radiation from uranium fuel cycle sources conforming to 40 CFRPart 190.The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the RadioactiveEffluent Controls Program surveillance frequency.g. Radiological Environmental Monitoring Pro qramA program shall be provided to monitor the radiation and radionuclides in theenvirons of the plant. The program shall provide (1) representative measurementsof radioactivity in the highest potential exposure pathways, and (2) verification ofthe accuracy of the effluent monitoring program and modeling of the environmentalexposure pathways. The program shall (1) be contained in the ODCM,(2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include thefollowing:1) Monitoring, sampling, analysis, and reporting of radiation and radionuclidesin the environment in accordance with the methodology and parameters inthe ODCM.2) A Land Use Census to ensure that changes in the use of areas at andbeyond the SITE BOUNDARY are identified and that modifications to themonitoring program are made if required by the results of this census, and3) Participation in a Interlaboratory Comparison Program to ensure thatindependent checks on the precision and accuracy of the measurements ofradioactive materials in environmental sample matrices are performed aspart of the quality assurance program for environmental monitoring.h. Containment Leakage Rate Testing ProgramA program to implement the leakage rate testing of the containment as required by10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, as modified by approvedINSERT B --exemptions. This program is in accordance with the guidelines contained inRegulater'y Guide 1.163, "Performnancc Based Containment Lealk Test Program,"onediied by-Beehtel 1epie-a[Repe~fl N TOP 1 )F-ANS-56-.84994-(asFeeefnmnded- y-RG-A463 whieh.wil ,-be-used-fe pe A testngThe peak calculated containment internal pressure for the design basis loss ofcoolant accident Pa, is 43.48 psig. The containment design pressure is 44 psig.allowed]The maximum containment leakage rate, La, at Pa, shall be 0.50% ofcontainment air weight per day.ST. LUCIE -UNIT 2 6-15b Amendment No. 64 88, 4-0, 44.,446,163