RNP-RA/16-0065, Supplement to Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test.: Difference between revisions

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{{Adams
#REDIRECT [[RNP-RA/16-0065, H. B. Robinson, Unit 2, Supplement to Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrat]]
| number = ML16235A187
| issue date = 08/18/2016
| title = Supplement to Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test.
| author name = Glover R M
| author affiliation = Duke Energy Corp
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000261
| license number = DPR-023
| contact person =
| case reference number = RNP-RA/16-0065
| document type = Letter type:RNP
| page count = 5
}}
 
=Text=
{{#Wiki_filter:AUG 1 *s: 201& Serial: RNP-RA/16-0065 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 I RENEWED LICENSE NO. DPR-23 R. Michael Glover H. B. Robinson Steam Electric Plant Unit 2 Site Vice President Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0: 843 857 1704 F: 843 857 1319 Mike. G/o1*er@d11ke-energy
.com 10 CFR 50.90 SUPPLEMENT TO PROPOSED AMENDMENT TO TECHNICAL SPECIFICATION 5.5.16 FOR THE ADOPTION OF OPTION B OF 10 CFR 50, APPENDIX J FOR TYPE B AND TYPE C TESTING AND THE PERMANENT CHANGE IN 10 CFR 50, APPENDIX J, INTEGRATED LEAK RATE TEST INTERVAL AND TYPE C LEAK RATE TESTING FREQUENCY
 
==References:==
: 1. Letter from R. Michael Glover (Duke Energy Progress , Inc.) to the U.S. Nuclear Regulatory Commission (Serial: RNP-RA/15-0090), Proposed Amendment to Technical Specification  
: 5. 5. 16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 1 O CFR 50, Appendix J, Integrated Leak Rate Test Interval and Type C Leak Rate Testing Frequency, dated November 19, 2015, ADAMS Accession Number ML 15323A085.
 
==Dear Sir/Madam:==
 
By letter dated November 19, 2015 (Reference 1 ), Duke Energy Progress, Inc. submitted a request for an amendment to the Technical Specifications (TS) for H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2).
The proposed change requests to revise TS 5.5.16, Containment Leakage Rate Testing Program, TS 3.6.1, Containment, and TS 3.6.2, Containment Air Lock, for HBRSEP2, to allow the following:
Increase in the existing integrated leak rate test (ILRT) program test interval from 10 to 15 years, Adopt 1 O CFR 50, Appendix J, Option B, as modified by approved exemptions, for the performance-based testing of Types B and C tested components in accordance with the guidance of Technical Specification Task Force (TSTF)-52, Implement 10 CFR 50, Appendix J , Option B (Reference 11 of the Enclosure),
U.S. Nuclear Regulatory Commission Serial: RNP-RA/16-0065 Page2 Allow an extension to the 120-month frequency currently permitted by Option B for Type B leakage rate testing, Allow an extension from the 60-month frequency currently permitted by Option B to a 75-month frequency for Type C leakage rate testing, The proposed change would also adopt a more conservative grace interval of 9 months, for Type B and Type C tests in accordance with Nuclear Energy Institute (NEI) Topical Report NEI 94-01, revision 3-A. Duke Energy Progress, Inc. is submitting this supplement to Reference 1 as discussed with the NRC Project Manager via teleconference held on August 10, 2016. Updated markup and retyped TS pages are provided in the enclosure to this letter. Please address any comments or questions regarding this matter to Mr. Tony Pilo, Acting Manager-Nuclear Regulatory Affairs at (843) 857-1409.
I declare under penalty of perjury that the foregoing is true and correct. Executed on
\ 5 I 2016. Sincerely, R. Michael Glover Site Vice President RMG/jmw Enclosure cc: Region Administrator, NRC, Region II Dennis Galvin, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP2 Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)
U.S. Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/16-0065 3 Pages (including this cover page) Supplemental Technical Specifications Markup and Retyped Page The markup and retyped Technical Specifications Page has been revised as discussed per teleconference.
The revised pages are provided by means of this Enclosure and supersedes those pages conveyed via the original submittal.
Please replace the pages of the original submittal as indicated below. Original Page Revised Page TS Markup: 5. 0-22 TS Markup: 5.0-22 TS Retyped: 5.0-22 TS Retyped: 5.0-22 Insert 1: NEI 94-01 , "Industry Guideline for Implementing Based Option of 10 CFR Part 50, Appendix J ," Revision 3-A , dated July 2012 , and the conditions and limitations specified in NEI 94-01 , Revision 2-A. dated October 2008. Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 The containment design pressure is 42 psig. Containment Leakage Rate Testing Program The peak containment pressure.
Pa, is specified as the containment design pressure of 42 psig, whieh exeeeas the peak calculated eoAtainment iAternal pressure for the design basis loss of coolant accident.
The maximum allowable containment leakage rate. La, at Pa, shall be O." U of the containment air weight per day. Leakage rate acceptance criteria are: LJ---7 v. Containment leakage rate acceptance criteria is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are< 0.60 La.for the Type Band Type C tests, and !Insert 2 1-7 < 0. 75 La for Type A tests. The provisions of SR 3.0.3 applicable to the Containment Leakage Rate Testing Program.
* 5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be implemented to ensure that, with an OPERABLE Control Room Emergency Filtration System. CRE occupants can control the nuclear power unit safely following a radiological event, hazardous chemical release, or a smoke challenge.
The program shall include the followino elements:
Insert 2: 2. Air lock testing acceptance criteria are: a. Overall air lock leakage rate 0.05 La when tested Pa. (continued)
: b. For each door , leakage rate 0.01 La when pressurized 42 psig. Insert 3: Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50 , Appendix J. HBRSEP Unit No. 2 5.0-22 Amendment No.-fi9-Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 5.5.17 Containment Leakage Rate Testing Program A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in NEI 94-01, "Industry Guideline for Implementing Based Option of 10 CFR Part 50, Appendix J," Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008. The peak containment pressure, Pa. is specified as the containment design pressure of 42 psig. The containment design pressure is 42 psig. The maximum allowable containment leakage rate, La. at Pa. shall be 0.1 % of the containment air weight per day. Leakage rate acceptance criteria are: 1. Containment leakage rate acceptance criterion 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria 0.60 La for the Type B and Type C tests, and 0. 75 La for Type A tests. 2. Air lock testing acceptance criteria are: a. Overall air lock leakage rate is s 0.05 La when tested Pa. b. For each door, leakage rate is s 0.01 La when pressurized to 42 psig. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J. Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be implemented to ensure that, with an OPERABLE Control Room Emergency Filtration System, CRE occupants can control the nuclear power unit safely following a radiological event, hazardous chemical release, or a smoke challenge.
The program shall include the following elements: (continued)
HBRSEP Unit No. 2 5.0-22 Amendment No.}}

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