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| | number = ML071590185 | | | number = ML071590185 |
| | issue date = 06/06/2007 | | | issue date = 06/06/2007 |
| | title = Salem, Units, 1 and 2, Tech Spec Pages for Amendment 265 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation | | | title = Units, 1 and 2, Tech Spec Pages for Amendment 265 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation |
| | author name = | | | author name = |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 |
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| | docket = 05000311 | | | docket = 05000311 |
| | license number = DPR-075 | | | license number = DPR-075 |
| | contact person = Ennis R B, NRR/DORL, 415-1420 | | | contact person = Ennis R, NRR/DORL, 415-1420 |
| | case reference number = TAC MD2506 | | | case reference number = TAC MD2506 |
| | package number = ML071200374 | | | package number = ML071200374 |
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| | page count = 5 | | | page count = 5 |
| | project = TAC:MD2506 | | | project = TAC:MD2506 |
| | stage = Other | | | stage = Acceptance Review |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:-4 -(2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.265 .are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. | | {{#Wiki_filter: (2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.265 . are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. |
| (3) Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report "Special Low Power Test Program", dated August 22, 1980 (See Amendment No. 2 to DPR-75 for the Salem Nuclear Generating Station, Unit No. 2) prior to operating the facility at a power level above five percent.Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report,' PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation. | | (3) Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report "Special Low Power Test Program", |
| PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test. The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage.(4) Initial Test Program PSE&G shall conduct the post-fuel-loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. | | dated August 22, 1980 (See Amendment No. 2 to DPR-75 for the Salem Nuclear Generating Station, Unit No. 2) prior to operating the facility at a power level above five percent. |
| Major modifications are defined as: (a) Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential;(b) Modification of test objectives, methods or acceptance criteriaý for any, test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential;(c) Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 265 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE | | Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report,' PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation. PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test. The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage. |
| ..................... | | (4) Initial Test Program PSE&G shall conduct the post-fuel-loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as: |
| 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR ..............
| | (a) Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (b) Modification of test objectives, methods or acceptance criteriaý for any, test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (c) Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 265 |
| 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR ........3/4.2.4 QUADRANT POWER TILT RATIO ................. | | |
| 3/4.2.5 DNB PARAMETERS | | INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE ..................... ............ 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR .............. ............ 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR ........ .... 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO ................. ............ 3/4 2-13 3/4.2.5 DNB PARAMETERS ............................ ............ 3/4 2-16 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION ....... ............ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION ........................... ............ 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation ...... ..3/4 3-38 Remote Shutdown Instrumentation ........... .. 3/4 3-43 Accident Monitoring Instrumentation ....... .. 3/4 3-50 Radioactive Liquid Effluent Monitoring Instrumentation ........................... .. 3/4 3-53 Power Distribution Monitoring System ...... ............ 3/4 3-65 3/4.3.4 DELETED 265 SALEM - UNIT 2 IV Amendment No. |
| ............................ | | |
| 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION
| | TABLE 4.3-3 (Continued) |
| .......3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION | | RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECKS CHECKS CALIBRATION TEST REQUIRED |
| ........................... | | : 2. PROCESS MONITORS |
| 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation
| | : b. Noble Gas Effluent Monitors |
| ......Remote Shutdown Instrumentation | | : 1) Medium Range Auxiliary S M R Q 1, 2, 3 & 4 Building Exhaust System (Plant Vent) |
| ........... | | : 2) High Range Auxiliary S M R Q 1, 2, 3 & 4 Building Exhaust System (Plant Vent) |
| Accident Monitoring Instrumentation
| | : 3) Main Steamline S M R Q 1, 2, 3 & 4 Discharge (Safety Valves and Atmospheric Dumps) |
| .......Radioactive Liquid Effluent Monitoring Instrumentation | | : 4) Condenser Exh. Sys. S M R Q 1, 2, 3 & 4 |
| ........................... | | : 3. CONTROL ROOM |
| Power Distribution Monitoring System ......3/4.3.4 DELETED PAGE............
| | : a. Air Intake - Radiation Level S M R Q ** |
| 3/4............
| | ** ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS. |
| 3/4.... 3/4............ | | SALEM - UNIT 2 3/4 3-42 Amendment No265 I |
| 3/4............ | | |
| 3/4 2-1 2-5 2-9 2-13 2-16............ | | Pages 3/4 3-57 through 3/4 3-64 Deleted SALEM - UNIT 2 3/4 3-56 Amendment No.265 |
| 3/4 3-1............
| | |
| 3/4 3-14..3/4..3/4..3/4..3/4 3-38 3-43 3-50 3-53 3-65............
| | RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas hol1dup system shall be limited to less than or equal to 2% by volume. |
| 3/4 SALEM -UNIT 2 IV Amendment No.2 6 5 TABLE 4.3-3 (Continued)
| | APPLICABILITY: At all times.* |
| RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNELS SOURCE CHECKS CHECKS CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED INSTRUMENT
| | ACTION: |
| : 2. PROCESS MONITORS b. Noble Gas Effluent Monitors 1) Medium Range Auxiliary Building Exhaust System (Plant Vent)2) High Range Auxiliary Building Exhaust System (Plant Vent)3) Main Steamline Discharge (Safety Valves and Atmospheric Dumps)4) Condenser Exh. Sys.S M R Q S M R Q 1, 2, 3 & 4 1, 2, 3 & 4 1, 2, 3 & 4 S M R Q S M R Q 1, 2, 3 & 4 3. CONTROL ROOM a. Air Intake -Radiation Level S M R Q**** ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS. | | : a. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits within [[estimated NRC review hours::48 hours]]. |
| SALEM -UNIT 2 3/4 3-42 Amendment No265 I Pages 3/4 3-57 through 3/4 3-64 Deleted SALEM -UNIT 2 3/4 3-56 Amendment No.265 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas hol1dup system shall be limited to less than or equal to 2% by volume.APPLICABILITY: | | : b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay. |
| At all times.*ACTION: a. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits within 48 hours.b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.C. The provisions of Specification 3.0.3 are not applicable. | | C. The provisions of Specification 3.0.3 are not applicable. |
| SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously"* | | SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously"* monitoring the waste gases in the waste gas holdup system with the oxygen monitor. If hydrogen is not measured, the concentration of hydrogen shall be assumed to exceed 4% by volume. |
| monitoring the waste gases in the waste gas holdup system with the oxygen monitor. If hydrogen is not measured, the concentration of hydrogen shall be assumed to exceed 4% by volume.*Not applicable to portions of the Waste Gas System removed from service for maintenance provided that, the portions removed for maintenance are isolated, and purged of hydrogen to less than 4% by volume.**Note: If the oxygen monitoring instrumentation is inoperable, operation of the waste gas holdup system may continue provided grab samples are collected at least once per 24 hours and analyzed within the following 4 hours.SALEM -UNIT 2 3/4 11-15 SALE -UIT 23/4 1-15Amnendmient No.265}} | | *Not applicable to portions of the Waste Gas System removed from service for maintenance provided that, the portions removed for maintenance are isolated, and purged of hydrogen to less than 4% by volume. |
| | **Note: If the oxygen monitoring instrumentation is inoperable, operation of the waste gas holdup system may continue provided grab samples are collected at least once per [[estimated NRC review hours::24 hours]] and analyzed within the following [[estimated NRC review hours::4 hours]]. |
| | SALEM - UNIT 2 3/4 11-15 - UIT SALE 23/4 1-15Amnendmient No.265}} |
Letter Sequence Acceptance Review |
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MONTHYEARML0715901852007-06-0606 June 2007 Units, 1 and 2, Tech Spec Pages for Amendment 265 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation Project stage: Acceptance Review ML0712003932007-06-0606 June 2007 Units, 1 and 2, Issuance of License Amendments 282 and 265 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation Project stage: Approval 2007-06-06
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[Table view] Category:Amendment
MONTHYEARLR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies LR-N21-0048, One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators2021-06-18018 June 2021 One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators LR-N21-0006, Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions2021-02-16016 February 2021 Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report2020-12-0606 December 2020 License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation2015-03-27027 March 2015 License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan LR-N09-0034, License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical Specifications2009-04-0909 April 2009 License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical Specifications LR-N08-0046, Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-012008-03-11011 March 2008 Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-01 ML0715901852007-06-0606 June 2007 Units, 1 and 2, Tech Spec Pages for Amendment 265 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation LR-N07-0030, License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System2007-03-16016 March 2007 License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System ML0701900942007-01-11011 January 2007 License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement LR-N06-0201, Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process2006-06-0707 June 2006 Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process LR-N06-0055, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage Requiremen2006-04-0606 April 2006 Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage Requirements ML0601300252006-01-11011 January 2006 Technical Specifications Deletion of Reactor Coolant System Volume ML0525600402005-09-0909 September 2005 Units, 1 and 2 - Tech Spec Pages for Amendments 265 and 247 to Extend the Inspection Interval for Reactor Coolant Pump Flywheels LR-N05-0377, Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling System2005-08-11011 August 2005 Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling System LR-N05-0018, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational.2005-02-23023 February 2005 Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational. LR-N04-0021, Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis Report2004-04-26026 April 2004 Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis Report ML0400804432004-01-0707 January 2004 Tech Spec Pages for License Amendment, Request for Changes to License Condition 2.C.(10) LR-N03-0092, Request for Change to TSs Explosive Gas Mixture2003-06-0606 June 2003 Request for Change to TSs Explosive Gas Mixture LR-N03-0022, Revision to Request for Change to Technical Specifications2003-02-14014 February 2003 Revision to Request for Change to Technical Specifications LR-N03-0014, Request for Change to Technical Specifications Administrative and Editorial Changes2003-01-29029 January 2003 Request for Change to Technical Specifications Administrative and Editorial Changes LR-N02-0344, Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.2002-10-23023 October 2002 Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area. ML0200702422002-01-0404 January 2002 TS Pages to Amendment 249 & 229 Change to Technical Specifications 28 Volt D.C. Distribution 2023-06-23
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(2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.265 . are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report "Special Low Power Test Program",
dated August 22, 1980 (See Amendment No. 2 to DPR-75 for the Salem Nuclear Generating Station, Unit No. 2) prior to operating the facility at a power level above five percent.
Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report,' PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation. PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test. The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage.
(4) Initial Test Program PSE&G shall conduct the post-fuel-loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
(a) Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (b) Modification of test objectives, methods or acceptance criteriaý for any, test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (c) Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 265
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE ..................... ............ 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR .............. ............ 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR ........ .... 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO ................. ............ 3/4 2-13 3/4.2.5 DNB PARAMETERS ............................ ............ 3/4 2-16 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION ....... ............ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION ........................... ............ 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation ...... ..3/4 3-38 Remote Shutdown Instrumentation ........... .. 3/4 3-43 Accident Monitoring Instrumentation ....... .. 3/4 3-50 Radioactive Liquid Effluent Monitoring Instrumentation ........................... .. 3/4 3-53 Power Distribution Monitoring System ...... ............ 3/4 3-65 3/4.3.4 DELETED 265 SALEM - UNIT 2 IV Amendment No.
TABLE 4.3-3 (Continued)
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECKS CHECKS CALIBRATION TEST REQUIRED
- 2. PROCESS MONITORS
- b. Noble Gas Effluent Monitors
- 1) Medium Range Auxiliary S M R Q 1, 2, 3 & 4 Building Exhaust System (Plant Vent)
- 2) High Range Auxiliary S M R Q 1, 2, 3 & 4 Building Exhaust System (Plant Vent)
- 3) Main Steamline S M R Q 1, 2, 3 & 4 Discharge (Safety Valves and Atmospheric Dumps)
- 4) Condenser Exh. Sys. S M R Q 1, 2, 3 & 4
- 3. CONTROL ROOM
- a. Air Intake - Radiation Level S M R Q **
- ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS.
SALEM - UNIT 2 3/4 3-42 Amendment No265 I
Pages 3/4 3-57 through 3/4 3-64 Deleted SALEM - UNIT 2 3/4 3-56 Amendment No.265
RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas hol1dup system shall be limited to less than or equal to 2% by volume.
APPLICABILITY: At all times.*
ACTION:
- a. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br />.
- b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.
C. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously"* monitoring the waste gases in the waste gas holdup system with the oxygen monitor. If hydrogen is not measured, the concentration of hydrogen shall be assumed to exceed 4% by volume.
- Not applicable to portions of the Waste Gas System removed from service for maintenance provided that, the portions removed for maintenance are isolated, and purged of hydrogen to less than 4% by volume.
- Note: If the oxygen monitoring instrumentation is inoperable, operation of the waste gas holdup system may continue provided grab samples are collected at least once per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> and analyzed within the following 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />.
SALEM - UNIT 2 3/4 11-15 - UIT SALE 23/4 1-15Amnendmient No.265