ONS-2018-029, Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 3

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Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 3
ML18096A685
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 04/04/2018
From: Burchfield J
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ONS-2018-029 LAR 2015-03, Supp 3
Download: ML18096A685 (12)
v • d • e


Text

J. Ed Burchfield, Jr.

( ., DUKE Vice President ENERGY Oconee Nuclear Station Duke Energy ON01 VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873. 3478

f. 864.873. 4208 Ed.Burchfield@duke-energy.com ONS-20 18-029 10 CFR 50.90 April 4, 2018 ATTN : Document Control Desk U. S. Nuclear Regulatory Commission

. 11555 Rockville Pike Rockville, Maryland 20852 Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1, 2 and 3 Docket Numbers: 50-269, 50-270, and 50-287 Renewed Operating Licenses: DPR-38, DPR-47, and DPR-55

Subject:

Technical Specifications Task Force (TSTF) - 448, Revision 3, "Control Room Habitability," License Amendment Request No. 2015-03, Supplement 3 On March 22, 2018, during a NRC status call associated with the TSTF-448 R3 License Amendment Request (LAR), the NRC identified two areas within the LAR which would require adjustment before the Staff could complete their review. One involved a wording change to the LAR's proposed license condition for clarity purposes, and the other was to provide an updated Technical Specifications Table of Contents (TS TOC) page to show a page number change. In a follow-up call on March 22, 2018, Duke Energy provided the NRC with its proposed resolutions to these issues. The NRC indicated that the changes proposed were acceptable but needed to be docketed. As such, the enclosure to this letter provides the description of the proposed changes and the associated attachment provides the revised/retyped license condition pages for all three units as well as the TS TOC page.

Inquiries on this proposed license amendment request should be directed to Stephen C. Newman, ONS Regulatory Affairs Group, at (864) 873-4388.

I declare under penalty of perjury that the foregoing is true and correct. Executed on April 4, 2018.

Sincerely,

<lf'Jwµf J. Ed Burchfield , Jr.

Vice President Oconee Nuclear Station Enclosure/Attachment cc w/enclosure/attachment:

License Amendment Request No. 2015-08 Page 2 Supplement 3 April 4, 2018 Ms. Catherine Haney, Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave. , NE, Suite 1200 Atlanta , GA 30303-1257 Ms. Audrey L. Klett, Project Manager (by electronic mail only)

U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-08B1A Rockville , MD 20852-2738 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station Ms. Susan E. Jenkins, Manager, (by electronic mail only: jenkinse@dhec.sc.gov)

Infectious and Radioactive Waste Management, Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia , SC 29201

ENCLOSURE Proposed Changes to LAR No. 2015-03

Enclosure - Proposed Changes to LAR No. 2015-03 Page 1 April 4, 2018 Proposed Change 1:

Section 2.3 (Page 4) of the original LAR Enclosure, contains a sentence in license condition subsections (a) and (b), which has no defined meaning outside the context of the LAR; Consequently, for the license condition final wording , it is proposed to strike both highlighted sentences as shown below:

2.3 License Condition Regarding Initial Performance of New Surveillance and Assessment Requirements Duke Energy proposes the following as a license condition to support implementation of the proposed TS changes:

Upon implementation of the Amendment adopting TSTF-448, Revision 3, the determination of CRE unfiltered air in-leakage as required by TS SR 3.7.9.4, in accordance with TS 5.5.23.c.(i); the assessment of CRE habitability as required by TS 5.5.23.c.(ii); and the measurement of pressure as required by TS 5.5.23.d, shall be considered met. Following implementation :

(a ) The first performance of SR 3.7.9.4 in accordance with Specification 5.5.23.c.(i), shall be within the specified Frequency of 6 years , plus the 18 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years . The most recent successful test as of the date of this submittal is June, 2007.

(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.23.c.(ii), shall be within 3 years, plus the 9 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years . The most recent successful test as of the date of this submittal is June, 2007.

(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.23.d shall be within 24 months plus the 6 months allowed by SR 3.0.2, as measured from the most recent successful pressure measurement test, or within 6 months if not performed previously.

The revised/retyped license condition pages for all three (3) units are provided in the Attachment.

Proposed Change 2:

When [new] Technical Specification 5.5.23, "Control Room Envelope Habitability Program," was proposed , the subsequent starting page of Technical Specification Section 5.6, "Reporting Requirements," moved from page 5.0-24 to 5.0-25. The revised/retyped page is provided in the Attachment.

ATTACHMENT Retyped License Condition and Table of Contents Pages

(b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets
2. Communications
3. Minimizing fire spread
4. Procedures for implementing integrated fire response strategy
5. Identification of readily-available pre-staged equipment
6. Training on integrated fire response strategy
7. SFP mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders I. Protected Service Water System Seismic Assessment License Condition Duke Energy Carolinas, LLC (Duke Energy) shall perform a seismic probabilistic risk assessment (SPRA) which includes the Protected Service Water (PSW) system , in accordance with the Electric Power Research Institute (EPRI) Report No. 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, " (i.e., the SPID report, November 2012) for the Oconee Nuclear Station (ONS). Duke Energy shall expand the Seismic Equipment List (SEL) to include the PSW system.

J. Upon implementation of the Amendment adopting TSTF-448, Revision 3, the determination of CRE unfiltered air in-leakage as required by TS SR 3.7.9.4, in accordance with TS 5.5.23.c.(i); the assessment of CRE habitability as required by TS 5.5.23.c.(ii); and the measurement of pressure as required by TS 5.5.23.d, shall be considered met. Following implementation:

(a ) The first performance of SR 3.7.9.4 in accordance with Specification 5.5.23.c.(i), shall be within the specified Frequency of 6 years, plus the 18 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.23.c.(ii), shall be within 3 years, plus the 9 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.23.d shall be within 24 months plus the 6 months allowed by SR 3.0.2, as measured from the most recent successful pressure measurement test, or within 6 months if not performed previously.

Renewed License No. DPR-38 Amendment No.

4. This renewed license is effective as of the date of issuance and shall expire at midnight on February 6, 2033.

FOR THE NUCLEAR REGULA TORY COMMISSION Original signed by Roy P. Zimmerman Roy Zimmerman, Acting Director Office of Nuclear Reactor Regulation

Attachment:

1) Appendix A- Technical Specifications Renewed License No. DPR-38 Date of Issuance: May 23, 2000 Renewed License No. DPR-38 Amendment No.

(b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets
2. Communications
3. Minimizing fire spread
4. Procedures for implementing integrated fire response strategy
5. Identification of read ily-available pre-staged equipment
6. Training on integrated fire response strategy
7. SFP mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders I. Protected Service Water System Seismic Assessment License Condition Duke Energy Carolinas, LLC (Duke Energy) shall perform a seismic probabilistic risk assessment (SPRA) which includes the Protected Service Water (PSW) system , in accordance with the Electric Power Research Institute (EPRI) Report No. 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, " (i.e., the SPID report, November 2012) for the Oconee Nuclear Station (ONS). Duke Energy shall expand the Seismic Equipment List (SEL) to include the PSW system .

J. Upon implementation of the Amendment adopting TSTF-448, Revision 3, the determination of CRE unfiltered air in-leakage as required by TS SR 3.7.9.4, in accordance with TS 5.5.23.c.(i); the assessment of CRE habitability as required by TS 5.5.23.c.(ii); and the measurement of pressure as required by TS 5.5.23.d , shall be considered met. Following implementation:

(a) The first performance of SR 3.7.9.4 in accordance with Specification

5. 5.23.c.(i), shall be within the specified Frequency of 6 years , plus the 18 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years .

(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.23.c.(ii), shall be within 3 years , plus the 9 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years .

(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.23.d shall be within 24 months plus the 6 months allowed by SR 3.0.2, as measured from the most recent successful pressure measurement test, or within 6 months if not performed previously.

Renewed License No. DPR-47 Amendment No.

4. This renewed license is effective as of the date of issuance and shall expire at midnight on October 6, 2033.

FOR THE NUCLEAR REGULA TORY COMMISSION Original signed by Roy P. Zimmerman Roy Zimmerman, Acting Director Office of Nuclear Reactor Regulation

Attachment:

1) Appendix A- Technical Specifications Renewed License No. DPR-47 Date of Issuance: May 23, 2000 Renewed License No. DPR-47 Amendment No.

(b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets
2. Communications
3. Minimizing fire spread
4. Procedures for implementing integrated fire response strategy
5. Identification of readily-available pre-staged equipment
6. Training on integrated fire response strategy
7. SFP mitigation measures (c) Actions to minimize release to include consideration of:
1. Water spray scrubbing
2. Dose to onsite responders I. Protected Service Water System Seismic Assessment License Condition Duke Energy Carolinas, LLC (Duke Energy) shall perform a seism ic probabilistic risk assessment (SPRA) which includes the Protected Service Water (PSW) system , in accordance with the Electric Power Research Institute (EPRI) Report No. 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," (i.e ., the SPID report, November 2012) for the Oconee Nuclear Station (ONS). Duke Energy shall expand the Seismic Equipment List (SEL) to include the PSW system.

J. Upon implementation of the Amendment adopting TSTF-448, Revision 3, the determination of CRE unfiltered air in-leakage as required by TS SR 3.7.9.4, in accordance with TS 5.5.23.c.(i); the assessment of CRE habitability as required by TS 5.5.23.c.(ii); and the measurement of pressure as required by TS 5.5.23.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.9.4 in accordance with Specification 5.5.23.c.(i), shall be within the specified Frequency of 6 years, plus the 18 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years .

(b) The first performance of the periodic assessment of CRE habitability, TS 5.5.23.c.(ii), shall be within 3 years, plus the 9 month (25%) allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic measurement of CRE pressure, TS 5.5.23.d shall be within 24 months plus the 6 months allowed by SR 3.0.2, as measured from the most recent successful pressure measurement test, or within 6 months if not performed previously.

Renewed License No. DPR-55 Amendment No.

4. This renewed license is effective as of the date of issuance and shall expire at midnight on July 19, 2034.

FOR THE NUCLEAR REGULA TORY COMMISSION Original signed by Roy P. Zimmerman Roy Zimmerman , Acting Director Office of Nuclear Reactor Regulation

Attachment:

1) Appendix A- Technical Specifications Renewed License No. DPR-55 Date of Issuance: May 23, 2000 Renewed License No. DPR-55 Amendment No.

TABLE OF CONTENTS 4.0 DESIGN FEATURES ..... ...... .... .. .. ..... ..... .... .. ....... ... ... .. .... ........................ ....... ... .4.0-1 4.1 Site Location ........ ............. .. .. ... ... ......... .. ... ... .... ...... ........... ...... ..... .. ... .. ... ..... 4.0-1 4.2 Reactor Core ..... ......... ... .. .. ....... .... .... ..... ....... ....... .... .... .. ..... ......... .... ........... 4.0-1 4.3 Fuel Storage ......... .. ........................................................ ................. ..... ...... 4.0-1 4.4 Dry Spent Fuel Storage Cask Loading and Unloading .................. .. ........ .. .4.0-3 5.0 ADMINISTRATIVE CONTROLS ..................... ................ .......... ..... ... .............. ... 5.0-1 5.1 Responsibility ......... ........ .. ................................. .............. ......... ... .... ... .... ... .. 5.0-1 5.2 Organization ........ .. ............ .. ................. ...... ... ... ....................... ... .... ........ .. .. 5. 0-2 5.3 Station Staff Qualifications .. ......... .......... .. .. .... : .... ... ...... ....... ..... ....... .. .. ... .. .. 5. 0-5 5.4 Procedures .. .................. .... ...... ..... .. ............... .. .... .. .... .......... .. .. .... ...... ........ 5.0-6 5.5 Programs and Manuals .. ...... ...... .. .. .. ...... ............ ......... ... ............ ... ........ .. .. 5. 0-7 5.6 Reporting Requirements .. .. .................. .......... .. .... .... .................... ..... .... .... .5.0-25 OCONEE UNITS 1, 2, & 3 V Amendment Nos.

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