ML16161A282
| ML16161A282 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/24/1998 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML16161A283 | List: |
| References | |
| NUDOCS 9805010220 | |
| Download: ML16161A282 (18) | |
Text
UNITED STATES, NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CORPORATION DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 229 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility)
Facility Operating License No. DPR-38 filed by the Duke Energy Corporation (the licensee) dated August 28, 1997, as supplemented January 22, February 19, March 19, and April 6, 13, and 17, 1998, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to.the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:
9805010220 980424 PDR ADOCK 05000269 IF PDR
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 229
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
In addition, Paragraph 3.K of the Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.K Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 229, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Additional Conditions.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
- 1. Technical Specification Changes
- 2. Appendix C Changes Date of Issuance:
April 24, 1998
APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-38 Duke Energy Corporation shall comply with the following conditions on the schedules noted below:
Amendment Number Additional Conditions Implementation Date The licensee will:
229 (1) Provide comparisons of critical characteristics for Conditon 1:
the new equipment that is installed by the ECCW July 15, 1998 upgrade with data from testing or from recorded earthquakes, in accordance with Section 2.3.4, Part I of GIP-2 and Section 1.2.3.4, paragraphs 2, 3, and 4 of the staffs SSER dated May 22, 1992, that is needed by the staff to complete its review of associated seismic issues or will qualify the new equipment using the existing methods in Section 3 of the Oconee UFSAR.
229 (2) Add the Oconee Unit 2 equipment in the ECCW Condition 2:
System that is necessary for safe shutdown per 4 months of the GIP-2 to the USI A-46 SSEL and include its completion of the evaluation in a revision to the USI A-46 submittal.
Unit 2 refueling outage.
Amendment No. 229
'p~t REG(&Z.1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CORPORATION DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 230 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility)
Facility Operating License No. DPR-47 filed by the Duke Energy Corporation (the licensee) dated August 28, 1997, as supplemented January 22, February 19, March 19, and April 6, 13, and 17, 1998, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter 1; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-4 7 is hereby amended to read as follows:
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 230
, are hereby incorporated in the license. The licensee shall operate the facility inccordance with the Technical Specifications.
In addition, Paragraph 3.K of the Facility Operating License No. DPR-47 is hereby amended to read as follows:
3.K Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 230, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Additional Conditions.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
- 1. Technical Specification Changes
- 2. Appendix C Changes Date of Issuance:
April 24, 1998
APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-47 Duke Energy Corporation shall comply with the following conditions on the schedules noted below:
Amendment Number Additional Conditions Implementation Date The licensee will:
230 (1) Provide comparisons of critical characteristics for Conditon 1:
the new equipment that is installed by the ECCW July 15, 1998 upgrade with data from testing or from recorded earthquakes, in accordance with Section 2.3.4, Part I of GIP-2 and Section 1.2.3.4, paragraphs 2, 3, and 4 of the staffs SSER dated May 22, 1992, that is needed by the staff to complete its review of associated seismic issues or will qualify the new equipment using the existing methods in Section 3 of the Oconee UFSAR.
230 (2) Add the Oconee Unit 2 equipment in the ECCW Condition 2:
System that is necessary for safe shutdown per 4 months of the GIP-2 to the USI A-46 SSEL and include its completion of the evaluation in a revision to the USI A-46 submittal.
Unit 2 refueling outage.
Amendment No. 230
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055-001 DUKE ENERGY CORPORATION DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 226 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility)
Facility Operating License No. DPR-47 filed by the Duke Energy Corporation (the licensee) dated August 28, 1997, as supplemented January 22, February 19, March 19, and April 6, 13, and 17, 1998, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 226, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
In addition, Paragraph 3.K of the Facility Operating License No. DPR-55 is hereby amended to read as follows:
3.K Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 226, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Additional Conditions.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
- 1. Technical Specification Changes
- 2. Appendix C Changes Date of Issuance:
Apr il 24, 1998
APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-55 Duke Energy Corporation shall comply with the following conditions on the schedules noted below:
Amendment Number Additional Conditions Implementation Date The licensee will:
226 (1) Provide comparisons of critical characteristics for Conditon 1:
the new equipment that is installed by the ECCW July 15, 1998 upgrade with data from testing or from recorded earthquakes, in accordance with Section 2.3.4, Part I of GIP-2 and Section 1.2.3.4, paragraphs 2, 3, and 4 of the staffs SSER dated May 22, 1992, that is needed by the staff to complete its review of associated seismic issues or will qualify the new equipment using the existing methods in Section 3 of the Oconee UFSAR.
226 (2) Add the Oconee Unit 2 equipment in the ECCW Condition 2:
System that is necessary for safe shutdown per 4 months of the GIP-2 to the USI A-46 SSEL and include its completion of the evaluation in a revision to the USI A-46 submittal.
Unit 2 refueling outage.
Amendment No. 226
ATTACHMENT TO LICENSE AMENDMENT NO. 229 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 230 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO.
226 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Insert iv iv 3.19-1 3.19-2 3.19-3 3.19-4 3.19-5 4.1-9 4.1-9 4.1-9(a) 4.1-9(a)
Section Page 3.10 GAS STORAGE TANK AND EXPLOSIVE GAS MIXTURE 3.10-1 3.11 (Not Used) 3.11-1 3.12 REACTOR BUILDING POLAR CRANE AND AUXILIARY HOIST 3.12-1 3.13 SECONDARY SYSTEM ACTIVITY 3.13-1 3.14 SNUBBERS 3.14-1 3.15 CONTROL ROOM PRESSURIZATION AND FILTERING SYSTEM 3.15-1 AND PENETRATION ROOM VENTILATION SYSTEMS 3.16 HYDROGEN PURGE SYSTEM 3.16-1 3.17 (NOTUSED) 3.18 STANDBY SHUTDOWN FACILITY 3.18-1 3.19 EMERGENCY CONDENSER CIRCULATING WATER 3.19-1 4
SURVEILLANCE REQUIREMENTS 4.0-1 4.0.
SURVEILLANCE STANDARDS 4.0-1 4.1 OPERATIONAL SAFETY REVIEW 4.1-1 4.2 STRUCTURAL INTEGRITY OF ASME CODE CLASS 1, 2 4.2-1 AND 3 COMPONENTS 4.3 TESTING FOLLOWING OPENING OF SYSTEM
. 4.3-1 4.4 REACTOR BUILDING 4.4-1 4.4.1 Containment Leakage Tests 4.4-1 4.4.2 Structural Integrity 4.4-14 4.4.3 Hydrogen Pure System 4.4-17 4.4.4 Reactor Building Purge System 4.4-20 4.5 EMERGENCY CORE COOLING SYSTEMS AND REACTOR
.4.5-1 BUILDING COOLING SYSTEMS PERIODIC TESTING 4.5.1 Emergency Core Cooling Systems 4.5-1 4.5.2 Reactor Building Cooling Systems 4.5-4 4.5.3 Containment Heat Removal Capability 4.5-6 4.5.4 Penetration Room Ventilation System 4.5-7 4.5.5 Low Pressure Inection System Leakage 4.5-9 4.6 EMERGENCY POWER PERIODIC TESTING 4.6-1 4.7 REACTOR CONTROL ROD SYSTEM TESTS 4.7-1 4.7.1 Control Rod Trip Insertion Time 4.7-1 4.7.2 Control Rod Program Verification 4.7-2 4.8 MAIN STEAM STOP VALVES 4.8-1 Oconee 1, 2, and 3 iv AmendmentNo. 229 (Unit 1)
Amendment No. 230 (Unit 2)
Amendment No. 226 (Unit 3)
3.19 EMERGENCY CONDENSER CIRCULATING WATER Applicability Applies to the first siphon portion of the Emergency Condenser Circulating Water (ECCW) System, the Essential Siphon Vacuum (ESV) System, and the Siphon Seal Water (SSW) System whenever operability of the Low Pressure Service Water (LPSW) System is required.
Applicability of this Specification for each Oconee unit will begin following completion of the Service Water upgrade on the respective unit.
Objective Supports operability of the LPSW pumps by specifying operability requirements for the systems required to maintain siphon flow capability.
Specification 3.19.1 ECCW Siphon Headers for Unit 1&2 LPSW
- a.
Whenever the shared Unit 1&2 LPSW System is required to be operable, at least two ECCW siphon headers shall be operable from among the four ECCW siphon headers on Unit 1 and Unit 2.
- b.
For each ECCW siphon header required to be operable per Specification 3.19.1.a; the ESV System shall be operable with an ESV pump and its supporting SSW flow operating, with ESV aligned to the ECCW siphon header, and, at least one CCW pump discharge valve shall be open on that ECCW header.
- c.
If only one ECCW siphon header is operable and two ECCW siphon headers are not restored to meet the requirements of Specification 3.19.1.a within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, then the reactor(s) shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the requirements of Specification 3.19.1.a are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following hot shutdown, the reactor(s) shall be placed in a condition with RCS pressure below 350 psig and RCS temperature below 250aF within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Oconee Units 1, 2, and 3 3.19-1 Amendment No. 229 (Unit 1)
Amendment No. 230 (Unit 2)
Amendment No. 226 (Unit 3)
3.19.2 ECCW Siphon Headers for Unit 3 LPSW
- a.
Whenever the Unit 3 LPSW System is required to be operable, at least two ECCW siphon headers shall be operable from among the four siphon headers on Unit 2 and Unit 3.
- b.
For each ECCW siphon header required to be operable per Specification 3.19.2.a; the ESV System Shall be operable with an ESV pump and its supporting SSW flow operating, with ESV aligned to the ECCW siphon header, and, at least one CCW pump discharge valve shall be open on that ECCW header.
- c.
If only one ECCW siphon header is operable to supply suction to the Unit 3 LPSW system and two ECCW siphon headers are not restored to meet the requirements of Specification 3.19.2.a within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, then the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the requirements of Specification 3.19.2.a are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following hot shutdown, the reactor shall be placed in a condition with RCS pressure below 350 psig and RCS temperature below 250*F within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.19.3 A Unit 2 ECCW siphon header shall not simultaneously serve to support operability of both the Unit 1&2 LPSW System and the Unit 3 LPSW System.
3.19.4 Lake level requirements to support operability of the LPSW System shall be contained in the ONS Selected Licensee Commitment Manual.
BASES:
The Low Pressure Service Water (LPSW) pumps receive their suction supply from the Condenser Circulating Water (CCW) crossover header. During normal operation, the CCW pumps from all Oconee units can provide the water supply to the CCW crossover header.
During certain events involving loss of off-site power, the CCW pumps will receive a load shed signal, and the Emergency Condenser Circulating Water (ECCW) first siphon must be capable of supplying suction to the LPSW pumps. The ECCW first siphon Oconee Units 1, 2, and 3 3.19-2 AmendmentNo.
229 (Unit1)
Amendment No.
230 (Unit 2)
Amendment No.
226 (Unit 3)
takes suction from the CCW intake canal and supplies flow to the CCW crossover header where the LPSW System takes its suction.
The LPSW System provides a heat sink for the removal of process and operating heat from safety related components during an accident or transient. During normal operation and normal shutdown, the LPSW System also provides this function for various safety related components. The LPSW System cannot perform these functions, in the event of a loss of offsite power, if the ECCW System is not available to support.LPSW System operability.
Therefore, the applicability of this specification is any time LPSW System operability is required.
Due to the piping configuration, each CCW inlet header on a given Oconee unit is independent of the other header for the purposes of siphoning water from the intake canal to the CCW crossover header. If one CCW inlet header is incapable of supplying siphon flow, it would not prevent the other CCW inlet header on that Oconee unit from supplying siphon flow. Therefore, each CCW inlet header may be considered to be an independent "ECCW siphon header".
An "ECCW siphon header" provides an open flow path from the intake canal to the CCW crossover header. A single open CCW pump discharge valve supplying a single 11 ft. diameter CCW inlet header on a given Oconee unit may qualify as an ECCW siphon header if the applicable CCW crossover tie valve is open to align the ECCW siphon header to the suction of the LPSW pumps. Each Oconee unit has two CCW inlet headers that can supply flow to the CCW crossover header. Therefore, each Oconee unit can potentially provide up to two ECCW siphon headers.
The ECCW siphon supply to LPSW must be capable of withstanding a single active failure. For example, failure of the ESV pump or float valve for a given ECCW siphon header could cause siphon flow in that header to eventually fail due to air accumulation.
Therefore, two ECCW siphon headers are required to be operable for each LPSW system. By requiring two ECCW siphon headers to be operable, no single active failure will cause a loss of function for the ECCW supply to the LPSW pumps.
Based on analysis of the net positive suction head (NPSH) for the LPSW pumps, the Unit 1&2 LPSW pumps cannot be supplied with adequate suction from a Unit 3 siphon header using worst case assumptions. Therefore, the siphon headers for the Unit 1&2 LPSW pumps must come from either Unit 1 or Unit 2. Similarly, the Unit 3 LPSW pumps cannot be supplied adequate NPSH from a Unit 1 Oconee Units 1, 2, and 3 3.19-3 Amendment No. 229 (Unit 1)
Amendment No. 230 (Unit 2)
Amendment No. _2j (Unit 3)
siphon header, so the siphon headers for the Unit 3 LPSW pumps must be supplied from Unit 2 or Unit 3. A Unit 2 ECCW siphon header shall not simultaneously serve to support operability of both the Unit 1&2 LPSW System and the Unit 3 LPSW System. Under certain conditions of low lake level and high LPSW System demand, a Unit 2 ECCW siphon header is not capable of simultaneously providing adequate NPSH to both the Unit 1&2 LPSW System and the Unit 3 LPSW System.
Lake level requirements to support operability of the LPSW System shall be contained in the ONS Selected Licensee Commitment (SLC)
Manual. SLC 16.9.7 currently contains the lake level requirements which are necessary to support operability of the LPSW System in conjunction with this specification.
For any ECCW siphon header to be considered operable, one Essential Siphon Vacuum (ESV) pump must be operating and aligned to the header, to ensure that the CCW piping remains sufficiently primed during normal operation. This configuration maintains the initial conditions used during testing and assumed in accident analyses. The ESV pump must be capable of restarting after restoration of emergency power following a loss of off-site power. This ensures that the siphon supply to LPSW can be maintained by removing any air that may leak into the CCW piping or any air that is degassed from the lake water.
To operate any ESV pump, it must have a continuous supply of seal water from the SSW System. The safety function of the SSW System is to supply seal water to the ESV pumps, but the SSW System also supplies seal/cooling water to the CCW pumps. SSW is fed from the LPSW System. The SSW System consists of two headers. One SSW header is sufficient to provide sealing flow to ESV pumps and CCW pumps. A solenoid valve is provided to isolate SSW flow to each ESV pump. This solenoid valve must be operable to ensure that SSW flow is provided to its respective ESV pump.
To maintain separation between the ESV System headers on a given unit, the cross-connect between the ESV pumps' suction shall be closed. Operability of the ESV System also requires that the float valve on the respective ECCW siphon header be operable.
When the potential for freezing exists, the heat tracing on the ESV float valve must also be operable. To support continued operability of the ESV System during a LOCA/LOOP, instrumentation must be available to ensure that the ESV vacuum tank will be drained, and the SSW duplex strainers will be rotated, on an as needed basis. The instrumentation used to support these two activities is ESV vacuum tank level, and SSW to ESV pump flow, Oconee Units 1, 2, and 3 3.19-4 AmendmentNo. 229 (Unit 1)
Amendment No. 230 (Unit 2)
Amendment No. 226 (Unit 3)
respectively. Other instrumentation is provided to monitor proper operation of the ESV System, but is not required for ESV System operability.
Surveillance testing for the ECCW, ESV, and SSW systems is conducted by performing tests listed in Table 4.1-2. The Emergency Condenser Circulating Water System test is conducted every 18 months. This test verifies that air in-leakage to the ECCW siphon headers will not exceed ESV pump capability.
The Essential Siphon Vacuum System Test is performed quarterly to verify adequate performance of the ESV system. This includes a functional test to ensuA the ESV float valves are capable of opening, a test of the ESV pumps performance, a test of ESV Pumps to ensure that they can be automatically restarted upon restoration of emergency power after a loss of off-site power, and a test of active valves which support operability of the ESV System.
Applicability of this Specification as described above for each Oconee unit will begin following completion of the Service Water upgrades on the respective unit. The Service Water upgrade is scheduled for completion in the Unit 2 EOC 16 refueling outage, in the Unit 3 EOC 17 refueling outage, and in the Unit 1 EOC 18 refueling outage.
Oconee Units 1, 2, and 3 3.19-5 Amendment No. 229 (Unit 1)
Amendment No. 230 (Unit 2)
Amendment No. 226 (Unit 3)
Table 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY Item Test Frequency
- 1.
Control Rod Movement )
Movement of Each Rod Monthly
- 2.
Pressurizer Safety Valves Setpoint 18 months(
- 3.
Main Steam Safety Valves Setpoint 18 months(4)
- 4.
Refueling System Interlocks()
Functional Prior to Refueling
- 5.
Main Steam Stop Valves 8 Movement of Each Stop Monthly Valve
- 6.
Evaluate Daily Leakage
- 7.
Emergency Condenser Functional 18 months Circulating Water System Test
- 8.
High Pressure Service Functional Monthly Water Pumps and Power Supplies
- 9.
Spent Fuel Cooling System Functional Prior to Refueling
- 10.
High Pressure and Low ()
Vent Pump Casings Monthly and Prior Pressure Injection System to Testing
- 11.
Emergency Feedwater Functional 18 months Pump Automatic Start and Automatic Valve Actuation Feature
- 12.
(Reserved)
- 13.
Essential Siphon Vacuum
- Functional Quarterly System Test Oconee 2,and 3 4.1-9 Amendment No. 229 (Unit 1)
Amendment No. 2 (Unit 2)
Amendment No. 226 (Unit 3)
Applicable only when the reactor is critical.
(
Applicable only when the reactor coolant is above 200F and at a steady-state temperature and pressure.
Operating pumps excluded.
Number of safety valves to be tested every 18 months shall be in accordance with ASME CodesSection XI, Article IWV-3 511, such that each valve is tested at least once every 5 years.
Applicable only to the interlocks associated with the Reactor Building Purge System.
(
Verification of the Emergency Condenser Circulating Water (ECCW) System function to supply siphon suction to the Low Pressure Service Water System shall be performed to ensure operability of the LPSW System.
) (Reserved)
(8) Applicability of these surveillances for each Oconee unit will begin following completion of the Service Water upgrade on the respective unit.
Oconee 1, 2, and 3 4.1-9 a Amendment No. 229 (Unit 1)
Amendment No. 2 (Unit 2)
Amendment No. ??F (Unit 3)