ML15309A010

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Ufsar/Selected Licensee Commitments Change
ML15309A010
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 10/29/2015
From: Batson S
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ONS-201-110
Download: ML15309A010 (17)
v • d • e


Text

SDUKE ENERGY° ScottL. Batson, Vice President Oconee Nuclear Station Duke Energy ONOIVP 7800 Rochester Hwy Seneca, SC 29672 o: 864.87"3.3274 ONS-201 5-110 10 CER 50.71(e) f 864.873.4208 Scott Batson@duke-energy,com October 29, 2015 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2746

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station Docket Numbers 50-269, 50-270, and 50-287 ............

UFSAR/Selected Licensee Commitments Change Pursuant to 10 CFR 50.71(e), please find attached the latest revision to the Oconee Nuclear Station Selected Licensee Commitments (SLC) Manual. The SLC Manual constitutes Chapter 16 of the Updated Final Safety Analysis Report (UFSAR).

Any questions regarding this information should be directed to Sandra Severance, Regulatory Affairs, at (864) 873-3466.

I certify that I am a duly authorized officer of Duke Energy Carolinas, LLC, and that the information contained herein accurately represents changes made to Chapter 16 of the UFSAR since the previous submittal. I declare under penalty of perjury that the foregoing is true and correct. Executed on October 29, 2015.

Sincerely, Scott L. Batson Vice President Oconee Nuclear Station Attachment www.duke-energy.com

U. S. Nuclear Regulatory Commission October 29, 2015 Page 2 cc: Mr. Leonard D. Wert, Jr.

Administrator, Region II (Acting)

U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. James R. Hall, Senior Project Manager (ONS)

(By electronic mail only)

U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2746 Mr. Jeffrey A. Whited, Project Manager (By electronic mail only)

U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8B1A Rockville, MD 20852-2746 Mr. Eddy L. Crowe Senior Resident Inspector Oconee Nuclear Station

ONS-2015-1 10 October 29, 2015 Attachment Revised Oconee Nuciear Station SLC Manuai Pages SLC List of Effective Pages (LOEPs), Rev. 004 LOEP 1-4 SLC Table of Contents (TOC), Rev. 001 16.0 -1 thru 7 SLC 16.7.16, Spent Fuel Pool - Wide Range Level 16.7.16-1 thru 3 Instrumentation, Rev. 000

Oconee Nuclear Station Selected Licensee Commitments Revised 10/14/15 List of Effective Pages Pacie Revision Number Implementation Date 16.0 000 05/21/15 16.1 000 10/15/07 16.2 000 08/25/14 16.3 001 06/29/15 16.4 -- PENDING 16.5.1 000 11/26/12 16.5.2 000 11/15/12 16.5.3 000 02/21/07 16.5.4 000 11/15/12 16.5.5 -- Deleted 5/16/09 16.5.6 -- Deleted 02/10/14 16.5.7 000 12/13/06 16.5.8 000 01/31/07 16.5.8a -- Deleted 5/19/05 16.5.9 000 11/15/12 16.5.10 000 10/08/03 16.5.11 000 01/31/00 16.5.12 000 03/27/99 16.5.13 000 03/27/99 16.6.1 000 07/23/12 16.6.2 000 01/31/07 16.6.3 000 11/15/12 16.6.4 000 11/15/12 16.6.5 000 12/14/00 16.6.6 000 11/15/12 16.6.7 000 03/27/99 16.6.8 000 03/27/99 16.6.9 000 11/15/12 16.6.10 000 11/15/12 16.6.11 000 11/15/12 16.6.12 000 11/15/12 16.6.13 000 03/31/08 16.6.14 000 04/21/14 16.6.15 000 11/15/12 16.7.1 000 11/15/12 Oconee Nuclear StationLEP1Rvso04 LOEP 1 Revision 004

Oconee Nuclear Station Selected Licensee Commitments Revised 10/14/15 List of Effective Pages PaQe Revision Number Implementation Date 16.7.2 000 11/15/12 16.7.3 000 11/15/12 16.7.4 000 07/14/05 16.7.5 000 11/15/12 16.7.6 000 04/08/14 16.7.7 000 11/15/12 16.7.8 000 03/27/99 16.7.9 000 10/23/03 16.7.10 000 11/15/12 16.7.11 000 11/15/12 16.7.12 000 06/30/04

16. 7.13 000 12105/12 16.7.14 000 11/15/12 16 .7.15 000 04/08/14 16 .7.16 000 10/14/15 16.8.1 000 08/09/01 16.8.2 000 02/10/05 16.8.3 000 10/20/09 16.8.4 000 02/10/05 16.8.5 000 05/21/15 16.8.6 000 01/04/07 16.8.7 000 01/31/00 16.8.8 000 01/31/00 16.8.9 000 06/21/05 16.9.1 000 12/05/12 16.9.2 000 12/31/12 16.9.3 000 12/31/12 16.9.4 000 12/01/14 16.9.5 000 12/31/12 16.9.6 001 08/03/15 16.9.7 000 07/23/12 16.9.8 000 02/15/06 16.9.8a 000 02/07/05 16.9.9 000 0 1/30/15 16.9.9a 000 0 1/30/15 Oconee Nuclear StationLEP2Rvso04 LOEP 2 Revision 004

Oconee Nuclear Station Selected Licensee Commitments Revised 10/14/15 List of Effective Pages PaeRevision Number Implementation Date 16.9.10 000 01/12/04 16.9.11 001 06/29/15 16.9.1lla 000 10/20/14 16.9.12 001 09/21/15 16.9.13 000 01/31/07 16.9.14 000 10/28/04 16.9.15 000 03/27/99 16.9.16 000 10/15/14 16.9.17 000 05/23/01 16.9.18 000 07/15/14 16.9.19 000 03/31/05 16.9.20 000 05/28/14 16.9.21 000 07/09/09 16.9.22 000 06/13/14 16.9.23 pending PENDING 16.9.24 pending PENDING 16.10.1 000 11/15/12 16.10.2 000 12/02/03 16.10.3 000 03/27/99 16.10.4 000 11/15/12 16.10.5 -- Deleted 08/24/04 16.10.6 000 03/27/99 16.10.7 001 09/21/15 16.10.8 000 11/27/06 16.10.9 000 11/25/09 16.11.1 000 03/15/11 16.11.2 000 01/31/00 16.11.3 000 11/20/08 16.11.4 000 06/30/14 16.11.5 000 10/30/02 16.11.6 000 11/08/13 16.11.7 000 01/31/00 16.11.8 000 12/21/09 16.11.9 000 03/22/10 16.11.10 000 05/14/14 Oconee Nuclear Station LE3Rvso LOEP 3 0 Revision 004

Oconee Nuclear Station Selected Licensee Commitments Revised 10/14/15 List of Effective Pages Pa~ge_ Revision Number Implementation Date 16.11.11 000 03/27/99 16.11.12 000 04/10/03 16.11.13 000 03/27/99 16.11.14 000 03/27/99 16.12.1 000 03/27/99 16.12.2 000 05/03/07 16.12.3 000 05/01/03 16.12.4 000 03/27/99 16.12.5 000 03/27/99 16.12.6 000 11/08/07 16.13.1 000 10/06/14 16.13.2 000 12/15/04 16.13.3 000 12/15/04 16.13.4 000 03/27/99 16.13.5 -- Deleted 11/30/99 16.13.6 000 03/27/99 16.13.7 000 12/15/04 16.13.8 000 03/27/99 16.13.9 000 03/27/99 16.13.10 000 03/27/99 16.13.11 000 03/27/99 16.14.1 000 11/15/12 16.14.2 000 07/23/12 16.14.3 000 03/27/99 16.14.4 -- Deleted 03/15/11 16.14.4.a 000 03/15/11 16.15.1 000 04/12/06 16.15.2 000 11/15/12 16.15.3 000 11/15/12 Note: With the introduction of Fusion in June 2015, all controlled documents require a three-digit revision number. Thus, the revision numbers were set to "000" in the summer of 2015. As such, the revision dates for Revision 000 are based on the implementation dates for revisions in effect prior to this change.

Oconee Nuclear Station LOEP 4 LE4Rvso Revision 004 0

TABLE OF CONTENTS SECTION TITLE PAGE NOO 16.0 SELECTED LICENSEE COMMITMENTS 16.1-1

16.1 INTRODUCTION

16.1-1 16.2 APPLICABILITY 16.2-1 16.3 DEFINITIONS 16.3-1 16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS Pending 16.5 REACTOR COOLANT SYSTEM 16.5.1-1 16.5.1 Reactor Coolant System Vents 16.5.1-1 16.5.2 Low Temperature Overpressure Protection (LTOP) System 16.5.2.1 16.5.3 Loss of Decay Heat Removal 16.5.3-1 16.5.4 Reactor Coolant System (RCS) Boron Sampling 16.5.4-1 16.5.5 [DELETED] 16.5.5-1 16.5.6 [DELETED] 16.5.6-1 16.5.7 Chemistry Requirements 16.5.7-1 16.5.8 Pressurizer 16.5.8-1 16.5.8a [DELETED] 16.5.8a-1 16.5.9 Testing Following Opening of System (Core Barrel Bolt Inspections) 16.5.9.1 16.5.10 Loss of Reactor Coolant 16. 5. 10-1 16.5.11 Subcriticality 16.5.11-1 16.5.12 RCS Leakage Testing Following Opening of System 16.5.12-1 16.5.13 High Pressure Injection and the Chemical Addition Systems 16. 5. 13-1 16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES 16.6.1-1 (NON-ESF SYSTEMS) 16.6.1 Containment Leakage Tests 16.6.1-1 16.6.2 Reactor Building Post-Tensioning System 16.6.2-1 16.6.3 Containment Heat Removal Verification Frequency 16.6.3-1 16.0-1 16.0-1Rev.

001

TABLE OF CONTENTS (continued)

SECTION TITLE PAGE N.O 16.6.4 Low Pressure Injection System Leakage 16.6.4-1 16.6.5 Core Flood Tank Discharge Valve Breakers 16.6.5-1 16.6.6 Core Flooding System Test 16.6.6-1 16.6.7 BWST Outlet Valve Control 16.6.7-1 16.6.8 LPI System Valve Test Restrictions 16.6.8-1 16.6.9 Containment Purge Valve Testing 16.6.9-1 16.6.10 Trisodium Phosphate (TSP) 16.6.10-1 16.6.11 Containment Debris Sources 16.6.11-1 16.6.12 Additional High Pressure Injection (HPI) Requirements 16.6.12-1 16.6.13 Additional Requirements to Support Low Pressure Injection (LPI) 16.6.13-1 Operability 16.6.14 Control of HPI and LPI/RBS Pump Room Temperatures 16.6.14-1 16.6.15 High Pressure Injection (HPI) and Liquid Waste Disposal (LWD) 16.6.15-1 Leakage 16.7 INSTRUMENTATION 16.7.1-1 16.7.1 Accident Monitoring Instrumentation 16.7.1-1 16.7.2 Anticipated Transient Without Scram 16.7.2-1 16.7.3 Emergency Feedwater System 16.7.3-1 16.7.4 Hydrogen Analyzers 16.7.4-1 "16.7.5 Steam Generator Overfill Protection 16.7.5-1 16.7.6 Diverse Actuation Systems 16.7.6-1 16.7.7 Position Indicator Channels 16.7.7-1 16.7.8 Incore Instrumentation 16.7.8-1 16.7.9 RCP Monitor 16.7.9-1 16.7.10 Core Flood Tank Instrumentation 16.7.10-1 16.7.11 Display Instrumentation 16.7.11-1 16.0-2 Rev. 001 16.0-2

TABLE OF CONTENTS (continued)

SECTION TITLE PAGE N._O 16.7.12 16.7.12-1 SSF Diesel Generator (DG) Air Start System Pressure Instrumentation 16.7.13 SSF Instrumentation 16.7.13-1 16.7.14 Rod Withdrawal Alarm Limit 16.7.14-1 16.7.15 Engineered Safeguards Protective System (ESPS) Voter Trouble Alarm 16.7.15-1 16.7.16 Spent Fuel Pool - Wide Range Level Instrumentation 16.7.16-1 16.8 ELECTRIC POWER SYSTEMS 16.8.1-1 16.8.1 Control of Room Temperatures for Station Blackout 16.8.1-1 16.8.2 Additional Requirements to Support Keowee Hydro Unit (KHU) 16.8.2-1 OPERABILITY 16.8.3 Power Battery Parameters 16.8.3-1 16.8.4 Keowee Operational Restrictions 16.8.4-1 16.8.5 [DELETED] 16.8.5-1 16.8.6 Lee/Central Alternate Power System 16.8.6-1 16.8.7 Auctioneering Diodes 16.8.7-1 16.8.8 External Grid Trouble Protection 16 .8. 8-1 16.8.9 Keowee Governor Speed Out Of Tolerance (OOT) Alarm 16 .8. 9-1 16.9 AUXILIARY SYSTEMS 16.9.1-1 16.9.1 Fire Suppression Water System 16 .9. 1-1 16.9.2 Sprinkler and Spray Systems 16.9.2-1 16.9.3 Keowee CO 2 Systems 16.9.3-1 16.9.4 Fire Hose Stations 16.9.4-1 16.9.5 Fire Barriers 16.9.5-1 16.9.6 Fire Detection Instrumentation 16.9.6-1 16.9.7 Keowee Lake Level 16.9.7-1 16.9.8 Control Room Ventilation System (CRVS) Booster Fans 16 .9. 8-1 16.0-3 Rev. 001 I

TABLE OF CONTENTS (continued)

SECTION TITLE PAGE N__O 16.9.8a-1 16.9.8a HPSW System Requirements to Support Loss of LPSW 16.9.9 Protected Service Water (PSW) System 16.9.9-1 16.9.9a Protected Service Water (P3W) Battery Cell Parameters 1 6.9.9a-1 16.9.10 Component Cooling and HPI Seal Injection to Reactor 16.9.10-1 Coolant Pumps 16.9.11 Turbine Building Flood Protection Measures 16.9.11-1 16.9.1lla Auxiliary Building Flood Protection Measures 16. 9.11a-I 16.9.12 Additional Low Pressure Service Water (LPSW) And 16.9.12-1 Siphon Seal Water (SSW) System Operability Requirements 16.9.13 Spent Fuel Cooling System 16 .9. 13-1 16.9.14 SSF Diesel Generator (DG) Inspection Requirements 16 .9. 14-1 16.9.15 Radioactive Material Sources 16.9.15-1 16.9.16 Reactor Building Polar Crane and Auxiliary Hoist 16.9.16-1 (RCS System Open) 16.9.17 Reactor Building Polar Crane (RCS at elevated 16.9.17-1 temperature and pressure) 16.9.18 Snubbers 16.9.18-1 16.9.19 Gravity Induced Reverse Flow to Standby Shutdown Facility (SSF) 16.9.19-1 Through a Unit 2 Condensate Cooler 16.9.20 Diesel Driven Service Air Compressors 16.9.20-1 16.9.21 Standby Shutdown Facility External Flood Protection 16.9.21-1 16.9.22 Protected Service Water System Unavailability 16.9.22-1 16.10 COMMITMENTS RELATED TO STEAM & POWER CONVERSION 16.10.1-1 SYSTEMS 16.10.1 Local Start of Turbine Driven Emergency Feedwater (EFW) Pump 16.10.1-1 16.10.2 Steam Generator Secondary Side Pressure and 16.10.2-1 Temperature (PIT) Limits 16.10.3 Emergency Feedwater (EFW) Pump and Valve Testing 16.10.3-1 16.0-4 Rev. 001 I

TABLE OF CONTENTS (continued)

SECTION TITLE PAGE N__O 16.10.4 Low Presssure Service Water System Testing 16.10.4-1 16.10.5 [DELETED] 16.10.5-1 16.10.6 Emergency Feedwater Controls 16.10.6-1 16.10.7 Alternate Source of Emergency Feedwater (EFW) 16.10.7-1 16.10.8 Upper Surge Tank (UST) Riser Branch Line Automatic Isolation Valves 16.10.8-1 16.10.9 Air Operated Valves (AOVs) Required to Support Standby Shutdown 16.10.9-1 Facility (SSF) During Station Blackout (SBO) 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.1-1 16.11.1 Radioactive Liquid effluents 16.11.1-1 16.11.2 Radioactive Gaseous Effluents 16.11.2-1 16.11.3 Radioactive Effluent Monitoring Instrumentation 16.11.3-1 16.11.4 Operational Safety Review 16.11.4-1 16.11.5 Solid Radioactive Waste 16.11.5-1 16.11.6 Radiological Environmental Monitoring 16.11.6-1 16.11.7 Dose calculations 16.11.7-1 16.11.8 Reports 16.11.8-1 16.11.9 Radioactive effluent release report 16.11.9-1 16.11.10 Radiological Environmental Operating Reports 16.11.10-1 16.11.11 Iodine Radiation Monitoring Filters 16.11.11-1 16.11.12 Radioactive Material in Outside Temporary 16.11.12-1 Tanks Exceeding Limit 16.11.13 Radioactive Material in Waste Gas Holdup 16.11.13-1 Tank Exceeding Limit 16.11.14 Explosive Gas Mixture 16.11.14-1 16.0-5 001 I 16.0-5Rev.

TABLE OF CONTENTS (continued)

SECTION TITLE PAGE N__O_

16.12 REFUELING OPERATIONS 16.12.1-1 16.12.1 Decay Time for Movement of Irradiated Fuel 16.12.1-1 16.12.2 Area Radiation Monitoring for Fuel Loading and Refueling 16.12.2-1 16.12.3 Communication Between Control Room and Refueling Personnel 16.12.3-1 16.12.4 Handling of Irradiated Fuel Assemblies 16.12.4-1 16.12.5 Loads Suspended over Spent Fuel in Spent Fuel Pool 16.12.5-1 16.12.6 Fuel Damage During Fuel Handling Operations in Containment 16.12.6-1 16.13 CONDUCT OF OPERATION 16.13.1-1 16.13.1 Minimum Station Staffing Requirements 16.13.1-1 16.13.2 [DELETED] 16.13.2-1 16.13.3 [DELETED] 16.13.3-1 16.13.4 Reactivity Anomaly 16.13.4-1 16.13.5 Deleted 16.13. 5-1 16.13.6 Retraining and Replacement of Station Personnel 16.13.6-1 16.13.7 Procedures for Control of Ph in Recirculated 16.13.7-1 Coolant after Loss-of-coolant Accident & Long-term Emergency Core Cooling Systems 16.13.8 Respiratory Protective Program 16.13.8-1 16.13.9 Startup Report 16.13.9-1 16.13.10 Core Operating Limits Reports 16.13.10-1 16.13.11 Procedure for Station Survey Following an Earthquake 16.13.11-1 16.14 CONTROL RODS AND POWER DISTRIBUTION 16.14.1-1 16.14.1 APSR Movement 16.14.1-1 16.14.2 Control Rod Program Verification 16.14.2-1 16.14.3 Power Mapping 16.14.3-1 Rev. 001 16.0-6

TABLE OF CONTENTS (continued)

SECTION TITLE PAGE N..OO 16.14.4 [DELETED] 16.14.4-1 16.14.4.a Engineering Work Station 16.1 4.4.a-1 16.15 VENTILATION FILTER TESTING PROGRAM 16.15.1-1 16.15.1 [DELETED] 16.15.1-1 16.15.2 Control Room Pressurization and Filtering System 16.15.2-1 16.15.3 Spent Fuel Pool Ventilation System 16.15.3-1 16.0-7 001 I 16.0-7Rev.

Spent Fuel Pool - Wide Range Level Instrumentation 16.7.16 16.7 INSTRUMENTATION 16.7.16 Spent Fuel Pool - Wide Range Level Instrumentation COMMITMENT Two Wide Range (WR) Spent Fuel Pool (SFP) Level Instrument Channels shall be FUNCTIONAL.

APPLICABILITY Whenever irradiated fuel assemblies are stored in the Spent Fuel Pool.

ACTIONS ___________

CONDITION REQUIRED ACTION COMPLETION TIME A. One required WR SFP A.1 Restore channel to 90 days level channel FUNCTIONAL status.

nonfunctional.

B. Required Action and B.1 Implement appropriate Immediately associated Completion compensatory actions.

Time of Condition A not met.

C. TWO required WR C.1 Initiate actions to restore 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SFP level channels one channel to nonfunctional. FUNCTI ONAL status.

AND C.2 Implement appropriate 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> compensatory actions.

Oconee Units 1, 2 & 3 16.7.16-1 1.7 61Rv Rev. 000 0

Spent Fuel Pool - Wide Range Level Instrumentation

16. 7. 16 SURVEILLANCE REQUIREMENTS__________

SURVEILLANCE FREQUENCY SR 16.7.16.1 Perform CHANNEL CHECK for SFP WR level 31 days channels.

SR 16.7.16.2 Perform CHANNEL FUNCTIONAL TEST for----------NOTE-----

SFP WR level channels. The provisions of SLC 16.2.7 do not apply.

Within 60 days of a planned refueling outage

+25%

BASES The Spent Fuel Pool (SFP) Wide Range (WR) level instrumentation is required by Reference 1.

The actions and functional testing requirements are specified in Reference 2 which was endorsed by the NRC in Reference 3. The channel checks are required to ascertain FUNCTIONAL status in support of the required actions. Performance of the CHANNEL CHECK once every 31 days for each SFP WR Level channel ensures that a gross failure of the instrumentation has not occurred. The Frequency is based on operating experience that demonstrates channel failure is rare. Performance of the CHANNEL FUNCTIONAL TEST verifies channel readings are within expected tolerances; transmitter signal strength is within expected limits and verifies proper operation of the battery backup capability. The CHANNEL FUNCTIONAL TEST and associated Frequency is consistent with vendor recommendations and meets the requirements specified in Reference 2. As specified in Reference 2, channel calibration shall be consistent with vendor recommendations or other documented basis. The instrumentation function is to provide accessible and reliable SFP wide range level monitoring capability during a Beyond Design Bases External Event (BDBEE). A BDBEE could result in a prolonged loss of power and SFP cooling, and result in the loss of SFP inventory due to boiling.

The level instrumentation provides remote (from SFP area) monitoring capability, in support of BOBEE mitigation efforts.

Oconee Units 1, 2 & 3 16.7.16-2 1..62Rv Rev. 000 0

1 Spent Fuel Pool - Wide Range Level Instrumentation

16. 7. 16 BASES (continued)

Compensatory actions for a single primary or back-up level channel out of service beyond 90 days could include one or more of the following:

  • Increased surveillance (channel check) to verify functionality of the remaining level channel
  • Implementation of equipment protection measures
  • Increased operator visual surveillance of the SFP level and area
  • Maintain elevated SEP level
  • Reduce SFP temperature
  • Supplemental operations staffing Compensatory actions for both the primary and back-up level channels out of service could include one or more of the following:
  • Increased operator visual surveillance of the SEP level and area
  • Maintain elevated SEP level
  • Reduce SEP temperature
  • Supplemental operations staffing
  • Pre-stage FLEX support equipment (nozzles, hoses, etc.) which are relied upon for SEP make-up. Pre-staged equipment would be located within Seismic Category I structures.

The listed compensatory actions are intended as examples of potential actions which could be considered (one or more), and are not intended to be a comprehensive listing.

REFERENCES:

1. NRC Order EA-1 2-051; Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation
2. NEI 12-02, Rev. 1; Industry Guidance for Compliance with Order EA-12-051
3. JLD-ISG-201 2-03; Compliance with Order EA-1 2-051, Reliable Spent Fuel Pool Instrumentation Oconee Units 1, 2 & 3 16.7.16-3 1 7 63Rv Rev. 000 0
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