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| issue date = 09/03/2015
| issue date = 09/03/2015
| title = Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years
| title = Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years
| author name = Orenak M D
| author name = Orenak M
| author affiliation = NRC/NRR/DORL
| author affiliation = NRC/NRR/DORL
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:Vice President, Operations Entergy Operations, Inc. UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Semptember 3, 2015 Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Semptember 3, 2015 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093


==SUBJECT:==
==SUBJECT:==
WATERFORD STEAM ELECTRIC STATION, UNIT 3 -CORRECTION TO ISSUANCE OF AMENDMENT NO. 244 REGARDING EXTENSION OF THE INTEGRATED LEAK RATE TESTING TO 15 YEARS (TAC NO. MF4727)  
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO ISSUANCE OF AMENDMENT NO. 244 REGARDING EXTENSION OF THE INTEGRATED LEAK RATE TESTING TO 15 YEARS (TAC NO. MF4727)


==Dear Sir or Madam:==
==Dear Sir or Madam:==
By letter dated August 24, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15217A143), the U.S. Nuclear Regulatory Commission (NRC) approved a license amendment request (LAR) to revise the Waterford Steam Electric Station, Unit 3 (WF3) Technical Specification (TS) 6.15, "Containment Leakage Rate Testing Program," by replacing the reference to Regulatory Guide 1.163, "Performance-Based Containment Leak Test Program," with a reference to Nuclear Energy Institute (NEI) 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," as the implementation document used by Entergy Operations, Inc. (Entergy) to develop the WF3 performance-based leakage testing program in accordance with Option B, "Performance Based Requirements," of Title 10 of the Code of Federal Regulations Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." The approval was in response to the Entergy LAR dated August 28, 2014 (ADAMS Accession No. ML 14241A305), as supplemented by letters dated April 15, May 4, and June 18, 2015 (ADAMS Accession Nos. ML 15105A615, ML 15124A946, and ML 15169A180, respectively).
 
Subsequent to issuing the amendment, the NRC staff identified an error in the approved TS 6.15 on page 6-24. On page 7 of 23 in Attachment 1 to the May 4, 2015, supplement, editorial changes were made to TS 6.15 for clarification purposes, but a revised page 6-24 was not included in the supplement, and the amendment was issued without the editorial changes. The safety evaluation (SE) for the LAR did incorporate the editorial changes as a partial basis for its conclusion.
By letter dated August 24, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15217A143), the U.S. Nuclear Regulatory Commission (NRC) approved a license amendment request (LAR) to revise the Waterford Steam Electric Station, Unit 3 (WF3) Technical Specification (TS) 6.15, "Containment Leakage Rate Testing Program,"
This letter corrects TS 6.15 on page 6-24 to account for the editorial changes. The errors contained in the issued TS 6.15 on page 6-24 have no impact on the SE or the SE conclusion that the licensee has adequately implemented its Containment Leakage Rate Testing Program. The WF3 Containment Leakage Rate Testing Program continues to demonstrate acceptable performance of the containment and that the structural and leak-tight integrity of the containment structure is adequately managed and will continue to be periodically monitored and managed. The NRC staff continues to find that the licensee has addressed the NRC conditions to demonstrate acceptability of adopting NEI 94-01, Revision 2-A, without undue risk to public health and safety.
by replacing the reference to Regulatory Guide 1.163, "Performance-Based Containment Leak Test Program," with a reference to Nuclear Energy Institute (NEI) 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," as the implementation document used by Entergy Operations, Inc. (Entergy) to develop the WF3 performance-based leakage testing program in accordance with Option B, "Performance Based Requirements," of Title 10 of the Code of Federal Regulations Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." The approval was in response to the Entergy LAR dated August 28, 2014 (ADAMS Accession No. ML14241A305),
Vice President, Operations If you have any questions, please contact me at 301-415-3229 or Michael.Orenak@nrc.gov.
as supplemented by letters dated April 15, May 4, and June 18, 2015 (ADAMS Accession Nos. ML15105A615, ML15124A946, and ML15169A180, respectively).
Docket No. 50-382  
Subsequent to issuing the amendment, the NRC staff identified an error in the approved TS 6.15 on page 6-24. On page 7 of 23 in Attachment 1 to the May 4, 2015, supplement, editorial changes were made to TS 6.15 for clarification purposes, but a revised page 6-24 was not included in the supplement, and the amendment was issued without the editorial changes.
The safety evaluation (SE) for the LAR did incorporate the editorial changes as a partial basis for its conclusion. This letter corrects TS 6.15 on page 6-24 to account for the editorial changes.
The errors contained in the issued TS 6.15 on page 6-24 have no impact on the SE or the SE conclusion that the licensee has adequately implemented its Containment Leakage Rate Testing Program. The WF3 Containment Leakage Rate Testing Program continues to demonstrate acceptable performance of the containment and that the structural and leak-tight integrity of the containment structure is adequately managed and will continue to be periodically monitored and managed. The NRC staff continues to find that the licensee has addressed the NRC conditions to demonstrate acceptability of adopting NEI 94-01, Revision 2-A, without undue risk to public health and safety.
 
Vice President, Operations               If you have any questions, please contact me at 301-415-3229 or Michael.Orenak@nrc.gov.
Sincerely,
                                            ~~
Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382


==Enclosure:==
==Enclosure:==


Correction to Technical Specifications cc w/enclosure:
Correction to Technical Specifications cc w/enclosure: Distribution via Listserv
Distribution via Listserv Sincerely, Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CORRECTION TO TECHNICAL SPECIFICATIONS FOR WATERFORD STEAM ELECTRIC STATION. UNIT 3 FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Revise the Technical Specifications as follows: Remove page Insert page 6-24 6-24 Enclosure ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)  
 
: 1. Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change(s) and 2. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.  
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CORRECTION TO TECHNICAL SPECIFICATIONS FOR WATERFORD STEAM ELECTRIC STATION. UNIT 3 FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Revise the Technical Specifications as follows:
Remove page           Insert page 6-24                   6-24 Enclosure
 
ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)
: 1. Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change(s) and
: 2. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
: b. Shall become effective after the approval of the General Manager Plant Operations.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1    The ODCM shall be approved by the Commission prior to implementation.
6.14.2    Licensee-initiated changes to the ODCM:
: a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Manual. This document shall contain:
: 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
: 2. A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
: b. Shall become effective after the approval of the General Manager Plant Operations.
: b. Shall become effective after the approval of the General Manager Plant Operations.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM: a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Manual. This document shall contain: 1 . Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2. A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
: b. Shall become effective after the approval of the General Manager Plant Operations.
: c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
: c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement 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.
6.15   CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement 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, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J," dated October, 2008. The next Type A test performed after the May 21, 2005 Type A test shall be performed no later than May 20, 2020.
This program shall be in accordance with the guidelines contained in NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J," dated October, 2008. The next Type A test performed after the May 21, 2005 Type A test shall be performed no later than May 20, 2020. WATERFORD-UNIT 3 6-24 AMENDMENT NO. 68, 84, 116, 124, 146, 4-§2, -+e+, 78, 244 Vice President, Operations  If you have any questions, please contact me at 301-415-3229 or Michael.Orenak@nrc.gov.
WATERFORD- UNIT 3                               6-24   AMENDMENT NO. 68, 84, 116, 124, 146, 4-§2, -+e+, 78, 244
Docket No. 50-382
 
==Enclosure:==


Correction to Technical Specifications cc w/enclosure:
ML152448386 OFFICE NRR/DORULPL4-2/PM NRR/DORULPL4-2/LA             NRR/DORULPL4-2/BC NRR/DORULPL4-2/PM NAME   MOrenak             PBlechman (LRonewicz for) MKhanna           MOrenak DATE   9/2/15             9/2/15                     9/3/15             9/3/15}}
Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4-2 R/F RidsACRS_MailCTR Resource RidsNrrDorllpl4-2 Resource RidsNrrPMWaterford Resource RidsNrrLAPBlechman Resource RidsRgn4MailCenter Resource FFarzam, NRR SPeng, NRR RidsN rrDssStsb RecordsAmend ADAMS Accession No.: ML 152448386 Sincerely, IRA/ Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE NRR/DORULPL4-2/PM NRR/DORULPL4-2/LA NRR/DORULPL4-2/BC NRR/DORULPL4-2/PM NAME MOrenak PBlechman (LRonewicz for) MKhanna MOrenak DATE 9/2/15 9/2/15 9/3/15 9/3/15 OFFICIAL RECORD COPY}}

Latest revision as of 07:04, 31 October 2019

Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years
ML15244B386
Person / Time
Site: Waterford Entergy icon.png
Issue date: 09/03/2015
From: Michael Orenak
Division of Operating Reactor Licensing
To:
Entergy Operations
Michael Orenak, 415-3229
References
TAC MF4727
Download: ML15244B386 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Semptember 3, 2015 Vice President, Operations Entergy Operations, Inc.

Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO ISSUANCE OF AMENDMENT NO. 244 REGARDING EXTENSION OF THE INTEGRATED LEAK RATE TESTING TO 15 YEARS (TAC NO. MF4727)

Dear Sir or Madam:

By letter dated August 24, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15217A143), the U.S. Nuclear Regulatory Commission (NRC) approved a license amendment request (LAR) to revise the Waterford Steam Electric Station, Unit 3 (WF3) Technical Specification (TS) 6.15, "Containment Leakage Rate Testing Program,"

by replacing the reference to Regulatory Guide 1.163, "Performance-Based Containment Leak Test Program," with a reference to Nuclear Energy Institute (NEI) 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," as the implementation document used by Entergy Operations, Inc. (Entergy) to develop the WF3 performance-based leakage testing program in accordance with Option B, "Performance Based Requirements," of Title 10 of the Code of Federal Regulations Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." The approval was in response to the Entergy LAR dated August 28, 2014 (ADAMS Accession No. ML14241A305),

as supplemented by letters dated April 15, May 4, and June 18, 2015 (ADAMS Accession Nos. ML15105A615, ML15124A946, and ML15169A180, respectively).

Subsequent to issuing the amendment, the NRC staff identified an error in the approved TS 6.15 on page 6-24. On page 7 of 23 in Attachment 1 to the May 4, 2015, supplement, editorial changes were made to TS 6.15 for clarification purposes, but a revised page 6-24 was not included in the supplement, and the amendment was issued without the editorial changes.

The safety evaluation (SE) for the LAR did incorporate the editorial changes as a partial basis for its conclusion. This letter corrects TS 6.15 on page 6-24 to account for the editorial changes.

The errors contained in the issued TS 6.15 on page 6-24 have no impact on the SE or the SE conclusion that the licensee has adequately implemented its Containment Leakage Rate Testing Program. The WF3 Containment Leakage Rate Testing Program continues to demonstrate acceptable performance of the containment and that the structural and leak-tight integrity of the containment structure is adequately managed and will continue to be periodically monitored and managed. The NRC staff continues to find that the licensee has addressed the NRC conditions to demonstrate acceptability of adopting NEI 94-01, Revision 2-A, without undue risk to public health and safety.

Vice President, Operations If you have any questions, please contact me at 301-415-3229 or Michael.Orenak@nrc.gov.

Sincerely,

~~

Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosure:

Correction to Technical Specifications cc w/enclosure: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CORRECTION TO TECHNICAL SPECIFICATIONS FOR WATERFORD STEAM ELECTRIC STATION. UNIT 3 FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Revise the Technical Specifications as follows:

Remove page Insert page 6-24 6-24 Enclosure

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

1. Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change(s) and
2. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b. Shall become effective after the approval of the General Manager Plant Operations.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Manual. This document shall contain:
1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
2. A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
b. Shall become effective after the approval of the General Manager Plant Operations.
c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement 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, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J," dated October, 2008. The next Type A test performed after the May 21, 2005 Type A test shall be performed no later than May 20, 2020.

WATERFORD- UNIT 3 6-24 AMENDMENT NO. 68, 84, 116, 124, 146, 4-§2, -+e+, 78, 244

ML152448386 OFFICE NRR/DORULPL4-2/PM NRR/DORULPL4-2/LA NRR/DORULPL4-2/BC NRR/DORULPL4-2/PM NAME MOrenak PBlechman (LRonewicz for) MKhanna MOrenak DATE 9/2/15 9/2/15 9/3/15 9/3/15

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