ML023470038
| ML023470038 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/04/2002 |
| From: | Rosalyn Jones Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML023470038 (25) | |
Text
SDuke R. A. JONES L Powere Vice President A Duke Energy Company Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax December 4, 2002 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Subject:
Oconee Nuclear Station Docket Numbers 50-269, 270, and 287 License Amendment Request for Upper Surge Tank and Hotwell Inventory 3.7.6 Technical Specification Change (TSC) Number 2002-08 Pursuant to Title 10, Code of Federal Regulations, Part 50, Section 90 (10 CFR 50.90), Duke Energy (Duke) proposes to amend Appendix A, Technical Specifications, for Facility Operating Licenses DPR-38, DPR-47 and DPR-55 for Oconee Nuclear Station, Units 1, 2, and 3. Technical Specification (TS) 3.7.6, Condensate Storage Tank (CST), Upper Surge Tank (UST) and Hotwell (HW) currently requires a minimum combined inventory of 72,000 gallons for these three tanks. The proposed license amendment request (LAR) revises TS 3.7.6, to require a minimum combined inventory of 155,000 gallons for the UST and HW, and changes the title. Additionally, the proposed LAR removes credit for the CST as a source of the required inventory. This change reflects the inventory requirements specified in the Updated Final Safety Analysis Report (UFSAR), Section 10.4.7, approved by the NRC on June 11, 2002. The TS 3.7.6 requirement for a minimum of 30,000 gallons in the UST alone remains unchanged. This LAR also revises the Table of Contents to reflect the changed title of this specification.
All technical aspects of this amendment were reviewed during the review of UFSAR Section 10.4.7 and approved in the Safety Evaluation for this section dated June 11, 2002.
This LAR implements the inventory requirements of the approved UFSAR section and is in conformance with the Safety Evaluation. No other changes are requested in the LAR.
The revised Technical Specification pages are included in Attachment 1. Attachment 2 contains the markup of the www duke-energy com
U. S. Nuclear Regulatory Commission December 04, 2002 Page 2 current Technical Specification pages. The Technical Justification for the amendment request is included in . Attachments 4 and 5 contain the No Significant Hazards Consideration Evaluation and the Environmental Impact Analysis, respectively.
Approval of this proposed LAR is requested by May 1, 2003.
Implementation of these changes will not result in an undue risk to the health and safety of the public.
The Oconee Updated Final Safety Analysis Report has been reviewed and no changes are necessary to support this LAR.
This proposed change to the TS has been reviewed and approved by the Plant Operations Review Committee and Nuclear Safety Review Board.
Pursuant to 10 CFR 50.91, a copy of this proposed amendment is being sent to the South Carolina Department of Health and Environmental Control for review, and as deemed necessary and appropriate, subsequent consultation with the NRC staff.
If there are any additional questions, please contact Noel Clarkson at (864) 885-3077.
Very u y yours, R. A. ones, Vice President Oconee Nuclear Site
U. S. Nuclear Regulatory Commission December 04, 2002 Page 3 cc: Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C. 20555 Mr. L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. M. C. Shannon Senior Resident Inspector Oconee Nuclear Station Mr. Virgil R. Autry, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, SC 29201
U. S. Nuclear Regulatory Commission December 04, 2002 Page 4 R. A. Jones, being duly sworn, states that he is Vice President, Oconee Nuclear Site, Duke Energy Corporation, that he is authorized on the part of said Company to sign and file with the U. S. Nuclear Regulatory Commission this revision to the Renewed Facility Operating License Nos. DPR 38, DPR-47, DPR-55; and that all the statements and matters set forth herein are true and correct to the best of his R. *., Jne, Vice President Oconee uclear Site Subscribed and sworn to before me this day of
- L, 2002 Notary Public My Commission Expires:
M* Commission ExpIres Aug. 19s ,9Vt S - - - - *
.-7N....
ATTACHMENT 1 TECHNICAL SPECIFICATION Remove Page Insert Page Table of Contents iii Table of Contents iii Bases Table of Contents iii Bases Table of Contents iii 3.7.6-1 3.7.6-1 B 3.7.6-1 B 3.7.6-1 B 3.7.6-2 B 3.7.6-2 B 3.7.6-3 B 3.7.6-3,
TABLE OF CONTENTS 3.4.6 RCS Loops - MODE 4 ...................................................................... 3.4.6-1 3.4.7 RCS Loops - MODE 5, Loops Filled ................................................. 3.4.7-1 3.4.8 RCS Loops - MODE 5, Loops Not Filled .......................................... 3.4.8-1 3.4.9 Pressurizer ......................................................................................... 3.4.9-1 3.4.10 Pressurizer Safety Valves .................................................................. 3.4.10-1 3.4.11 RCS Specific Activity .......................................................................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP)
System .......................................................................................... 3.4.12-1 3.4.13 RCS Operational LEAKAGE ............................................................... 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage .................................... 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ........................................... 3.4.15-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ................................ 3.5.1-1 3.5.1 Core Flood Tanks (CFTs) ................................................................... 3.5.1-1 3.5.2 High Pressure Injection ...................................................................... 3.5.2-1 3.5.3 Low Pressure Injection ....................................................................... 3.5.3-1 3.5.4 Borated W ater Storage Tank (BW ST) ............................................... 3.5.4-1 3.6 CONTAINMENT SYSTEMS ....................................................................... 3.6.1-1 3.6.1 Containment ....................................................................................... 3.6.1-1 3.6.2 Containment Air Locks ....................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves ............................................................. 3.6.3-1 3.6.4 Containment Pressure ........................................................................ 3.6.4-1 3.6.5 Reactor Building Spray and Cooling System ...................................... 3.6.5-1 3.7 PLANT SYSTEMS ...................................................................................... 3.7.1-1 3.7.1 Main Steam Relief Valves (MSRVs) ................................................... 3.7.1-1 3.7.2 Turbine Stop Valves (TSVs) ............................................................... 3.7.2-1 3.7.3 Main Feedwater Control Valves (MFCVs), and Startup Feedwater Control Valves (SFCVs) ............................................. 3.7.3-1 3.7.4 Not used ............................................................................................. 3.7.4-1 3.7.5 Emergency Feedwater (EFW ) System ............................................... 3.7.5-1 3.7.6 Upper Surge Tank (UST) and Hotwell (HW ) ...................................... 3.7.6-1 3.7.7 Low Pressure Service W ater (LPSW ) System ................................... 3.7.7-1 3.7.8 Emergency Condenser Circulating W ater (ECCW) ........................... 3.7.8-1 3.7.9 Control Room Ventilation System (CRVS) Booster Fans ................................................................... 3.7.9-1 3.7.10 Penetration Room Ventilation System (PRVS) ................................... 3.7.10-1 3.7.11 Spent Fuel Pool W ater Level .............................................................. 3.7.11-1 3.7.12 Spent Fuel Pool Boron Concentration ................................................ 3.7.12-1 3.7.13 Fuel Assembly Storage ...................................................................... 3.7.13-1 OCONEE UNITS 1, 2, & 3 iii Amendment Nos. , , & I
TABLE OF CONTENTS B 3.4 REACTOR COOLANT SYSTEM (RCS) ............................................... B 3.4.1-1 B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ........................................ B 3.4.1-1 B 3.4.2 RCS Minimum Temperature for Criticality .................................... B 3.4.2-1 B 3.4.3 RCS Pressure and Temperature (P/T) Limits .............................. B 3.4.3-1 B 3.4.4 RCS Loops - MODES 1 and 2 ..................................................... B 3.4.4-1 B 3.4.5 RCS Loops - MODE 3 ................................................................. B 3.4.5-1 B 3.4.6 RCS Loops - MODE 4 ................................................................. B 3.4.6-1 B 3.4.7 RCS Loops - MODE 5, Loops Filled ............................................ B 3.4.7-1 B 3.4.8 RCS Loops - MODE 5, Loops Not Filled ..................................... B 3.4.8-1 B 3.4.9 Pressurizer ................................................................................... B 3.4.9-1 B 3.4.10 Pressurizer Safety Valves ............................................................ B 3.4.10-1 B 3.4.11 RCS Specific Activity ................................................................... B 3.4.11-1 B 3.4.12 Low Temperature Overpressure Protection (LTOP)
System .................................................................................... B 3.4.12-1 B 3.4.13 RCS Operational LEAKAGE ......................................................... B 3.4.13-1 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage .............................. B 3.4.14-1 B 3.4.15 RCS Leakage Detection Instrumentation ..................................... B 3.4.15-1 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) .......................... B 3.5.1-1 B 3.5.1 Core Flood Tanks (CFTs) ............................................................. B 3.5.1-1 B 3.5.2 High Pressure Injection (HPI) ....................................................... B 3.5.2-1 B 3.5.3 Low Pressure Injection (LPI) ........................................................ B 3.5.3-1 B 3.5.4 Borated Water Storage Tank (BWST) ......................................... B 3.5.4-1 B 3.6 CONTAINMENT SYSTEMS ................................................................. B 3.6.1-1 B 3.6.1 Containment ................................................................................. B 3.6.1-1 B 3.6.2 Containment Air Locks ................................................................. B 3.6.2-1 B 3.6.3 Containment Isolation Valves ....................................................... B 3.6.3-1 B 3.6.4 Containment Pressure .................................................................. B 3.6.4-1 B 3.6.5 Reactor Building Spray and Cooling System ................................ B 3.6.5-1 B 3.7 PLANT SYSTEMS ................................................................................ B 3.7.1-1 B 3.7.1 Main Steam Relief Valves (MSRVs) ............................................. B 3.7.1-1 B 3.7.2 Turbine Stop Valves (TSVs) ......................................................... B 3.7.2-1 B 3.7.3 Main Feedwater Control Valves (MFCVs), and Startup Feedwater Control Valves (SFCVs) ....................................... B 3.7.3-1 B 3.7.4 Atmospheric Dump Valve (ADV) Flow Paths ............................... B 3.7.4-1 B 3.7.5 Emergency Feedwater (EFW) System ......................................... B 3.7.5-1 B 3.7.6 Upper Surge Tank (UST) and Hotwell (HW) ................................ B 3.7.6-1 B 3.7.7 Low Pressure Service Water (LPSW) System ............................. B 3.7.7-1 B 3.7.8 Emergency Condenser Circulating Water (ECCW) ..................... B 3.7.8-1 OCONEE UNITS 1, 2, & 3 iii Amendment Nos. , & I
USTand HW 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Upper Surge Tank (UST) and Hotwell (HW)
LCO 3.7.6 The UST and HW shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> LCO not met.
AND A.2 Be in MODE 4 without 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reliance on steam generator for heat removal.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify combined inventory in the UST and HW 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is > 155,000 gal.
AND Inventory in the UST is > 30,000 gal.
OCONEE UNITS 1, 2, & 3 3.7.6-1 Amendment Nos. , ,& I
USTAND HW B 3.7.6 B 3.7 PLANT SYSTEMS B 3.7.6 Upper Surge Tank (UST) and Hotwell (HW) I BASES BACKGROUND The UST and HW provide a source of water to the steam generators for removing decay and sensible heat from the Reactor Coolant System (RCS). The UST and HW provide a passive flow of water to the Emergency Feedwater (EFW) System (LCO 3.7.5, "Emergency Feedwater (EFW) System"). For accident mitigation, heat removal is assumed to be through steam released to the atmosphere by the main steam safety valves and the atmospheric dump valves. However, the most likely steam flow path is to the condenser and hotwell by the non-safety grade path of the turbine bypass valves.
The emergency feedwater pumps are normally aligned to the upper surge tanks (UST). The UST provides the initial source of water for the EFW System. When that supply is exhausted, the pumps may be aligned to draw water from the hotwell. A minimum level of 6 feet (at least 30,000 gallons) is maintained in the UST to assure an adequate source of water to the EFW until other sources can be aligned. This minimum level of 6 feet includes an allowance for instrument uncertainty and depletion of inventory while transferring the EFW suction to an alternative source of water.
The UST and the piping connecting them to the EFW pumps has been analyzed and qualified to withstand a design basis seismic event. This includes piping up to the first normally closed valve. The hotwell and connected piping used for the TDEFW pump suction supply has been evaluated using a "seismic experience" approach and found capable of withstanding a seismic event. Although the evaluation methodology is not recognized for licensing basis, this secondary water supply is considered to be a "seismic assured source of water." Feedwater is also available from alternate source(s).
A description of the condensate/feedwater reserves available to the EFW System is found in the UFSAR, Section 10.4, (Ref. 1).
OCONEE UNITS 1, 2, & 3 B 3.7.6-1 Amendment Nos. , ,& I
UST AND HW B 3.7.6 BASES (continued)
APPLICABLE The UST and HW provide cooling water to remove decay heat I SAFETY ANALYSES following events in the accident analysis, as discussed in the UFSAR, Chapters 10 and 15 (Refs. 2 and 3, respectively).
The required inventory in the UST and HW is based on maintaining hot standby conditions for one hour, followed by a 50°F per hour cooldown to decay heat removal entry conditions. Although the EFW system capacity is sufficient to support a 50°F per hour cooldown rate, this rate is not achievable during certain events, such as a natural circulation cooldown.
The UST and HW satisfy Criteria 2 and 3 of 10 CFR 50.36 (Ref. 4).
LCO To satisfy LCO requirements, the UST and HW must contain the specified I volume of water available to the EFW System.
The OPERABILITY of UST and HW is determined by maintaining the tank volume at or above the minimum required volume.
APPLICABILITY In MODES 1, 2, 3, and in MODE 4, when steam generator is being relied upon for heat removal, the UST and HW are required to be OPERABLE. I I
In MODES 5 and 6, the UST and HW are not required because the EFW System is not required.
ACTIONS A.1 and A.2 If the requirements of the LCO are not met, the unit must be placed in a MODE in which the LCO does not apply, with the DHR System in operation. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in MODE 4, without reliance on steam generators for heat removal, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This allows an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the DHR System to be placed in service after entering MODE 4.
OCONEE UNITS 1, 2, & 3 B 3.7.6-2 Amendment Nos. , ,& I
UST AND HW B 3.7.6 BASES ACTIONS A.1 and A.2 (continued)
The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.6.1 REQUIREMENTS This SR verifies that the UST and HW contain the required volume of I cooling water. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is based on operating experience and the need for operator awareness of unit evolutions that may affect the UST and HW inventory between checks. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is considered adequate in view of other indications in the control room, including alarms to alert the operator to abnormal deviations in UST and I HW levels.
REFERENCES 1. UFSAR, Section 10.4.
- 2. UFSAR, Chapter 10.
- 3. UFSAR, Chapter 15.
- 4. 10 CFR 50.36.
OCONEE UNITS 1, 2, & 3 B 3.7.6-3 Amendment Nos. , , & I
ATTACHMENT 2 MARKUP OF TECHNICAL SPECIFICATION
TABLE OF CONTENTS 3.4.6 RCS Loops - MODE 4 ...................................................................... 3.4.6-1 3.4.7 RCS Loops - MODE 5, Loops Filled ................................................. 3.4.7-1 3.4.8 RCS Loops - MODE 5, Loops Not Filled .......................................... 3.4.8-1 3.4.9 Pressurizer ......................................................................................... 3.4.9-1 3.4.10 Pressurizer Safety Valves .................................................................. 3.4.10-1 3.4.11 RCS Specific Activity .......................................................................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP)
System .......................................................................................... 3.4.12-1 3.4.13 RCS Operational LEAKAGE ............................................................... 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage .................................... 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ........................................... 3.4.15-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ................................ 3.5.1-1 3.5.1 Core Flood Tanks (CFTs) ................................................................... 3.5.1-1 3.5.2 High Pressure Injection ..................................................................... 3.5.2-1 3.5.3 Low Pressure Injection ....................................................................... 3.5.3-1 3.5.4 Borated Water Storage Tank (BWST) ............................................... 3.5.4-1 3.6 CONTAINMENT SYSTEMS ....................................................................... 3.6.1-1 3.6.1 Containment ....................................................................................... 3.6.1-1 3.6.2 Containment Air Locks ....................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves ............................................................. 3.6.3-1 3.6.4 Containment Pressure ........................................................................ 3.6.4-1 3.6.5 Reactor Building Spray and Cooling System ...................................... 3.6.5-1 3.7 PLANT SYSTEMS ...................................................................................... 3.7.1-1 3.7.1 Main Steam Relief Valves (MSRVs) ................................................... 3.7.1-1 3.7.2 Turbine Stop Valves (TSVs) ............................................................... 3.7.2-1 3.7.3 Main Feedwater Control Valves (MFCVs), and Startup Feedwater Control Valves (SFCVs) ............................................. 3.7.3-1 3.7.4 Not used ............................................................................................. 3.7.4-1 3.7.5 Emergency Feedwater (EFW) System ............................................... 3.7.5-1 3.7.6 Condcnatc Storag .... TaRk (ST-), Upper Surge Tank (UST)7 and Hotwell (HW) 3.7.6-1 3.7.7 Low Pressure Service Water (LPSW) System ................................... 3.7.7-1 3.7.8 Emergency Condenser Circulating Water (ECCW) ........................... 3.7.8-1 3.7.9 Control Room Ventilation System (CRVS) Booster Fans ................................................................... 3.7.9-1 3.7.10 Penetration Room Ventilation System (PRVS) ................................... 3.7.10-1 3.7.11 Spent Fuel Pool Water Level .............................................................. 3.7.11-1 3.7.12 Spent Fuel Pool Boron Concentration ................................................ 3.7.12-1 3.7.13 Fuel Assembly Storage ...................................................................... 3.7.13-1 OCONEE UNITS 1, 2, & 3 iii Amendment Nos. 320,,20,, ,2OXXX, XXX, XXX I
TABLE OF CONTENTS B 3.4 REACTOR COOLANT SYSTEM (RCS) ............................................... B 3.4.1-1 B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ........................................ B 3.4.1-1 B 3.4.2 RCS Minimum Temperature for Criticality .................................... B 3.4.2-1 B 3.4.3 RCS Pressure and Temperature (P/T) Limits .............................. B 3.4.3-1 B 3.4.4 RCS Loops - MODES 1 and 2 ..................................................... B 3.4.4-1 B 3.4.5 RCS Loops - MODE 3 ................................................................ B 3.4.5-1 B 3.4.6 RCS Loops - MODE 4 ................................................................. B 3.4.6-1 B 3.4.7 RCS Loops - MODE 5, Loops Filled ............................................ B 3.4.7-1 B 3.4.8 RCS Loops - MODE 5, Loops Not Filled ..................................... B 3.4.8-1 B 3.4.9 Pressurizer ................................................................................... B 3.4.9-1 B 3.4.10 Pressurizer Safety Valves ............................................................ B 3.4.10-1 B 3.4.11 RCS Specific Activity ................................................................... B 3.4.11-1 B 3.4.12 Low Temperature Overpressure Protection (LTOP)
System .................................................................................... B 3.4.12-1 B 3.4.13 RCS Operational LEAKAGE ......................................................... B 3.4.13-1 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage .............................. B 3.4.14-1 B 3.4.15 RCS Leakage Detection Instrumentation ..................................... B 3.4.15-1
)
B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ......................... B 3.5.1-1 B 3.5.1 Core Flood Tanks (CFTs) ............................................................. B 3.5.1-1 B 3.5.2 High Pressure Injection (HPI) ....................................................... B 3.5.2-1 B 3.5.3 Low Pressure Injection (LPI) ........................................................ B 3.5.3-1 B 3.5.4 Borated Water Storage Tank (BWST) ......................................... B 3.5.4-1 B 3.6 CONTAINMENT SYSTEMS ................................................................. B 3.6.1-1 B 3.6.1 Containment ................................................................................. B 3.6.1-1 B 3.6.2 Containment Air Locks ................................................................. B 3.6.2-1 B 3.6.3 Containment Isolation Valves ....................................................... B 3.6.3-1 B 3.6.4 Containment Pressure ............................. B 3.6.4-1 B 3.6.5 Reactor Building Spray and Cooling System ................................ B 3.6.5-1 B 3.7 PLANT SYSTEMS ................................................................................ B 3.7.1-1 B 3.7.1 Main Steam Relief Valves (MSRVs) ............................................. B 3.7.1-1 B 3.7.2 Turbine Stop Valves (TSVs) ......................................................... B 3.7.2-1 B 3.7.3 Main Feedwater Control Valves (MFCVs), and Startup Feedwater Control Valves (SFCVs) ....................................... B 3.7.3-1 B 3.7.4 Atmospheric Dump Valve (ADV) Flow Paths ............................... B 3.7.4-1 B 3.7.5 Emergency Feedwater (EFW) System ......................................... B 3.7.5-1 B 3.7.6 Condn. atc Storage Tank (ST-), Upper Surge "TTank(UST), and Hotwell (HW) ............................................ B 3.7.6-1 B 3.7.7 Low Pressure Service Water (LPSW) System ............................. B 3.7.7-1 B 3.7.8 Emergency Condenser Circulating Water (ECCW) ..................... B 3.7.8-1 OCONEE UNITS 1, 2, & 3 iiiAmendment Nos. -30,--,0,& XXX,09, XXX.,091 & xxxS09
-=,ST--TTUST 7 and HW 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Cond..sat. Storage Tank (CSTT), Upper Surge Tank (UST), and Hotwell (HW)
LCO 3.7.6 The G-=S1TUST- and HW shall be OPERABLE.
APPLICABILITY: MODES 1,2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> LCO not met.
AND A.2 Be in MODE 4 without 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reliance on steam generator for heat removal.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify combined inventory in the UST,-GS4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and HW is > 155,00072,000 gal.
AND Inventory in the UST is > 30,000 gal.
OCONEE UNITS 1, 2, & 3 3.7.6-1 Amendment Nos. XXX30, XXXA", & XXXWG I
GSI+UST AND HW B 3.7.6 B 3.7 PLANT SYSTEMS B 3.7.6 R*....sato Storag. Ta*k (CST), Upper Surge Tank (UST); and Hotwell (HW)
BASES BACKGROUND The GST-,USTT and HW provide a source of water to the steam generators I for removing decay and sensible heat from the Reactor Coolant System (RCS). The UST and HW provide a passive flow of water to the Emergency Feedwater (EFW) System (LCO 3.7.5, "Emergency Feedwater (EFW) System"). The steam produc.d is released to the atmospho, ,by the main steam safety valve. (MSSV..)and the atmFo.pheri;c dump valves. Foraccidentmitigation, heat removal is assumed to be through steam releasedto the atmosphereby the main steam safety valves and the atmosphericdump valves. However, the most likely steam flow path is to the condenserand hotwell by the non-safety gradepath of the turbine bypass valves.
S.. . . 0 1 i * *
- i. i . .i . ..... m...... L..
The i reterredl means o iheat removal m I II f ml to liscnarqe I + +isI ........... I....
o mveI onden69l 0,,
th
- n...eatot. ,W 9 bypa6s vaive.
aa*o patn of tuernn, The emergency feedwater pumps are normally aligned to the upper surge tanks (UST). The UST provides the initial source of water for the EFW System. When that supply is exhausted, the pumps may be aligned to draw water from the hotwell. The UST can be repleRished by pumping from the condensate storage tank (CST) or .fro the Makeup DeMier*alized, Water System. A minimum level of 6 feet (at least 30,000 gallons) is maintained in the UST to assure an adequate source of water to the EFW until other sources can be aligned. This minimum level of 6 feet includes an allowance for instrument uncertainty and depletion of inventory while transferring the EFW suction to an alternative source of water.
The UST and the piping connecting them to the EFW pumps has been analyzed and qualified to withstand a design basis seismic event. This includes piping up to the first normally closed valve. The hotwell and connected piping used for the TDEFW pump suction supply has been I evaluated using a "seismic experience" approach and found capable of withstanding a seismic event. Although the evaluation methodology is not recognized for licensing basis, this secondary water supply is considered to be a "seismic assured source of water." Feedwater is also available from alternate source(s).
A description of the condensate/feedwater reserves available to the EFW System is found in the UFSAR, Section 10.4, (Ref. 1).
OCONEE UNITS 1, 2, & 3 B 3.7.6-1 Amendment Nos. XXXSOO, XXXWO,, & XXX32, I
GST-, UST AND HW B 3.7.6 I
BASES (continued)
APPLICABLE The GST-,USTT and HW provides cooling water to remove decay heat SAFETY ANALYSES following events in the accident analysis, as discussed in the UFSAR, Chapters 10 and 15 (Refs. 2 and 3, respectively).
Tho water inventorY froGm the CST- Will not be available durinig a station blacko~ut duo to unavailability of power to the CST transfer pumps.
-The required inventory in the AJS-T-,-UGST7 and HW has-net-beeR Gpccifieally analyzed regarding tho capability to permit cooling the Unit down and transferring to tho decay heat removal loops. The required inventery' permits, maintaining F=P' capability URNti either coo~ing capability uing the mnain condenser Gan be restored or until the Standby Shutdown Facility (SSR (L.C. 3.0\*-, "S'tandb ShutdoWn Facil. (S '-)") i ; placed in seP-ie.is based on maintaining hot standby conditions for one hour, followed by a 50°F per hour cooldown to decay heat removal entry conditions. Although the EFW system capacity is sufficient to support a 50°F per hour cooldown rate, this rate is not achievable during certain events, such as a natural circulation cooldown.
The GS-F-,-UST7 and HW satisfy Criteria 2 and 3 of 10 CFR 50.36 (Ref. 4). I LCO To satisfy LCO requirements, the UST*,USTGS-T- and HW must contain the specified volume of water available to the EFW System.
The OPERABILITY of GST-TUST7 and HW is determined by maintaining the tank volume at or above the minimum required volume.
APPLICABILITY In MODES 1, 2, 3, and in MODE 4, when steam generator is being relied upon for heat removal, the GST-;UST; and HW are required to be OPERABLE.
In MODES 5 and 6, the GST UST- and HW are not required because the EFW System is not required.
ACTIONS A.1 and A.2 Ifthe requirements of the LCO are not met, the unit must be placed in a MODE in which the LCO does not apply, with the DHR System in operation. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in MODE 4, without reliance on steam generators for heat removal, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This allows an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the DHR System to be placed in service after entering MODE 4.
OCONEE UNITS 1, 2, &3 B 3.7.6-3Amendment Nos. XXX3OW, XXX3W, & XXX300 I
GST-, USTAND HW B 3.7.6 BASES ACTIONS A.1 and A.2 (continued)
The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.6.1 REQUIREMENTS This SR verifies that the GST UST- and HW contain the required volume of cooling water. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is based on operating experience and the need for operator awareness of unit evolutions that may affect the I GST- UST- and HW inventory between checks. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is considered adequate in view of other indications in the control room, I including alarms to alert the operator to abnormal deviations in GST-,UST; and HW levels.
REFERENCES 1. UFSAR, Section 10.4.
- 2. UFSAR, Chapter 10.
- 3. UFSAR, Chapter 15.
- 4. 10 CFR 50.36.
OCONEE UNITS 1, 2, & 3 B 3.7.6-5Amendment Nos. XXXAOO, XXX-3OO, & XXX300 I
Attachment 3 Technical Justification
Attachment 3 Technical Justification
Background
The Upper Surge Tank (UST) and Hotwell (HW) provide a source of water to the steam generators for removing decay heat and sensible heat from the Reactor Coolant System (RCS) in the event of a loss of main feedwater. The UST and HW provide a passive flow of water to the Emergency Feedwater (EFW)
System. The steam produced is released to the atmosphere by the main steam safety valves and the atmospheric dump valves.
The EFW pumps are normally aligned to the UST. The UST provides the initial source of water for the EFW System.
When that supply is exhausted, the pumps may be aligned to draw water from the hotwell. A minimum level of 6 feet (30,000 gallons) is maintained in the UST to assure an adequate source of water to the EFW System until other sources can be aligned.
The UST and HW provide cooling water to remove decay heat following events in the accident analysis discussed in the UFSAR Chapters 10 and 15. The required inventory permits maintaining EFW capability until cooling capability is transferred to decay heat removal, the main condenser can be restored or the Standby Shutdown Facility is placed in service.
Description of the Technical Specification Change and Technical Justification This proposed change to TS 3.7.6 removes credit for Condensate Storage Tank (CST) inventory and increases the UST and HW combined inventory from 72,000 gallons to 155,000 gallons. This change reflects the revision to section 10.4.7 of the Update Final Safety Analysis Report (UFSAR), which was approved by the NRC on June 11, 2002. The EFW inventory requirements are based on maintaining hot standby conditions for one hour followed by a 50°F/hour cooldown to decay heat removal conditions.
The volumes maintained in the UST and the condenser hotwell satisfy the EFW inventory required to support a plant cooldown following a loss of main feedwater transient with or without offsite power available. Assuming automatic steam
Attachment 3 Technical Justification generator level control, the minimum Technical Specification required 30,000 gallon inventory in the UST will provide at least 40 minutes of EFW flow with all three EFW pumps operating simultaneously. This inventory requirement also assures that the plant operators have at least 20 minutes to act, following a UST low level alarm, before the UST is emptied. The EFW pumps will remain aligned to the UST as long as adequate inventory can be maintained. If the UST inventory cannot be maintained, EFW pump suction will be aligned to the hotwell. A combined inventory in the UST and condenser hotwell of 155,000 gallons is sufficient to permit cooldown of the primary coolant at a rate of 50 0 F/hour following a reactor trip to decay heat removal entry conditions assuming a maximum allowable, full power, UST and hotwell temperature of 130 0 F. During low power, startup conditions, a UST temperature of 150OF is allowed. This is justified based on the lower decay heat load. Although the EFW system capacity is sufficient to support a 50°F per hour cooldown rate, this rate is not achievable during certain events, such as a natural circulation cooldown.
As stated in the June 11, 2002, NRC Safety Evaluation, the revised section 10.4.7 of the UFSAR, which contains the above inventory requirement, is considered to be acceptable by the Staff. At the time which the revised, approved UFSAR section 10.4.7 was implemented, Duke Energy (Duke) implemented a Selected Licensee Commitment which controlled UST and hotwell inventories in accordance with the new UFSAR requirements.
Additionally, Duke, by letter dated April 30, 2002, agreed to submit a proposed change to TS to reflect the revised inventory requirements. This proposed TS change fulfills that commitment.
ATTACHMENT 4 NO SIGNIFICANT HAZARDS CONSIDERATION
Attachment 4 No Significant Hazards Consideration Pursuant to 10 CFR 50.91, Duke Power Company (Duke) has made the determination that this amendment request involves a No Significant Hazards Consideration by applying the standards established by the NRC regulations in 10 CFR 50.92. This ensures that operation of the facility in accordance with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated:
No. This revision to Technical Specification (TS) 3.7.6 changes the inventory requirements for the Upper Surge Tank (UST) and hotwell. These components provide a suction source to the Emergency Feedwater System (EFW).
This increase in inventory from 72,000 gallons to 155,000 gallons increases the required available inventory. This increase in inventory does not affect the probability or consequences of any previously evaluated accident.
(2) Create the possibility of a new or different kind of accident from any kind of accident previously evaluated:
No. This revision to the combined UST and hotwell inventory increases the required amount of water available to the EFW system. No new or different kind of accident is created by this change as only the required inventory is revised.
(3) Involve a significant reduction in a margin of safety.
No. The increase in required UST and hotwell inventory does not reduce the margin is safety. The increase provides the required inventory to ensure that the EFW can provide a Reactor Coolant System cooldown at a rate of 50°F/hour to decay heat removal entry conditions following a reactor trip.
Duke has concluded, based on the above, that there are no significant hazards considerations involved in this amendment request.
ATTACHMENT 5 ENVIRONMENTAL ASSESSMENT
ATTACHMENT 5 Environmental Assessment Pursuant to 10 CFR 51.22(b), an evaluation of the license amendment request (LAR) has been performed to determine whether or not it meets the criteria for categorical exclusion set forth in 10 CFR 51.22(c)9 of the regulations.
The LAR does not involve:
- 1) A significant hazards consideration.
This conclusion is supported by the determination of no significant hazards contained in Attachment 4.
- 2) A significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
This LAR will not change the types or amounts of any effluents that may be released offsite.
- 3) A significant increase in the individual or cumulative occupational radiation exposure.
This LAR will not increase the individual or cumulative occupational radiation exposure.
In summary, this LAR meets the criteria set forth in 10 CFR 51.22 (c)9 of the regulations for categorical exclusion from an environmental impact statement.