ML081790257
| ML081790257 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/30/2008 |
| From: | Markley M NRC/NRR/ADRO/DORL/LPLIV |
| To: | |
| Markley M, NRR/DORL/LPL4, 301-415-5723 | |
| References | |
| TAC MD5577 | |
| Download: ML081790257 (60) | |
Text
(4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or when associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.
3.
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is, subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A.
Maximum Power Level Omaha Public Power District is authorized to operate the Fort Calhoun Station, Unit 1, at steady state reactor core power levels not in excess of 1500 megawatts thermal (rate power).
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. are hereby incorporated in the license. Omaha Public Power District shall l
operate the facility in accordance with the Technical Specifications.
C.
Security and Safeguards Contingency Plans The Omaha Public Power District shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: Fort Calhoun Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, submitted by letter dated May 19, 2006.
Renewed Operating License No. DPR-40 Amendment No.
257 257 D.
Fire Protection Program Omaha Public Power District shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Safety Analysis Report for the facility and as approved in the NRC safety evaluation reports (SERs) dated February 14 and August 23, 1978; November 17, 1980; April 8 and August 12, 1982; July 3 and November 5, 1985; July 1, 1986; December 20, 1988; November 14,1990; March 17, 1993; and January 14, 1994, subject to the following provision:
Omaha Public Power District may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
E.
Updated Final Safety Analysis Report The Omaha Public Power District Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the period of extended operation. The Omaha Public Power District shall complete these activities no later than August 9, 2013, and shall notify the NRC In writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4) following issuance of this renewed license. Until that update is complete, the Omaha Public Power District may make changes to the programs and activities described in the supplement without prior Commission approval, provided that the Omaha Public Power District evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
F.
Appendix B The Additional Conditions contained in Appendix B, as revised through Amendment No. 257, are hereby incorporated into this license. Omaha Public Power District shall operate the facility in accordance with the Appendix B Additional Conditions.
Renewed Operating License No. DPR-40 Amendment No. 257
TECHNICAL SPECIFICATION TECHNICAL SPECIFICATIONS TABLE OF CONTENTS DEFINITIONS 1.0 SAFETY LIMITS 1.1 Safety Limits (SLs) 1.1.1 Reactor Core SLs 1.1.2 Reactor Coolant System Pressure SL 1.2 Safety Limit Violations 1.3 DELETED 2.0 LIMITING CONDITIONS FOR OPERATION 2.0.1 General Requirements 2.1 Reactor Coolant System 2.1.1 Operable Components 2.1.2 Heatup and Cooldown Rate 2.1.3 Reactor Coolant Radioactivity 2.1.4 Reactor Coolant System Leakage Limits 2.1.5 Maximum Reactor Coolant Oxygen and Halogens Concentrations 2.1.6 Pressurizer and Main Steam Safety Valves 2.1.7 Pressurizer Operability 2.1.8 Reactor Coolant System Vents 2.2 Chemical and Volume Control System 2.3 Emergency Core Cooling System 2.4 Containment Cooling 2.5 Steam and Feedwater System 2.6 Containment System 2.7 Electrical Systems 2.8 Refueling 2.9 Radioactive Waste Disposal System 2.10 Reactor Core 2.10.1 Minimum Conditions for Criticality 2.10.2 Reactivity Control Systems and Core Physics Parameter Limits 2.10.3 DELETED 2.10.4 Power Distribution Limits 2.11 DELETED 2.12 Control Room Ventilation System TOC - Page 1 Amendment No. 11,15,27,32,38,52,54, 57,67,80,81,86,146,152,167,169,182, 188, 252, 257
TECHNICAL SPECIFICATION TABLE OF CONTENTS (Continued) 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.2 Organization 5.3 Facility Staff Qualifications 5.4 Training 5.5 Not Used 5.6 Not Used 5.7 Not Used 5.8 Procedures 5.9 Reporting Requirements 5.9.1 Not Used 5.9.2 Not Used 5.9.3 Special Reports 5.9.4 Unique Reporting Requirements 5.9.5 Core Operating Limits Report 5.9.6 RCS Pressure-Temperature Limits Report (PTLR) 5.10 Record Retention 5.11 Radiation Protection Program 5.12 DELETED 5.13 Secondary Water Chemistry 5.14 Systems Integrity 5.15 Post-Accident Radiological Sampling and Monitoring 5.16 Radiological Effluents and Environmental Monitoring Programs 5.16.1 Radioactive Effluent Controls Program 5.16.2 Radiological Environmental Monitoring Program 5.17 Offsite Dose Calculation Manual (ODCM) 5.18 Process Control Program (PCP) 5.19 Containment Leakage Rate Testing Program 5.20 Technical Specification (TS) Bases Control Program 5.21 Containment Tendon Testing Program 5.22 Diesel Fuel Oil Testing Program 5.23 Steam Generator (SG) Program 5.24 Control Room Habitability Program 6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS 6.1 DELETED 6.2 DELETED 6.3 DELETED 6.4 DELETED TOC - Page 3 Amendment No. 32,34,43,54,55,57, 73,80,86,89,93,99,141,152,157,184,185, 221 236, 237,246, 252, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling 2.8.2 Refueling Operations - Containment 2.8.2(3)
Ventilation Isolation Actuation Signal (VIAS)
Applicability Applies to operation of the Ventilation Isolation Actuation Signal (VIAS) during CORE ALTERATIONS and REFUELING OPERATIONS inside containment.
Objective To minimize the consequences of an accident occurring during CORE ALTERATIONS or REFUELING OPERATIONS that could affect public health and safety.
Specification VIAS, including manual actuation capability, shall be OPERABLE with one gaseous radiation monitor OPERABLE.
Required Actions (1)
Without one radiation monitor OPERABLE, or VIAS manual actuation capability inoperable, immediately suspend CORE ALTERATIONS and REFUELING OPERATIONS.
2.8.2(4)
Control Room Ventilation System (CRVS)
Applicability Applies to operation of the CRVS during CORE ALTERATIONS and REFUELING OPERATIONS inside containment.
Objective To minimize the consequences of a fuel handling accident to the control room staff.
Specification The CRVS shall be IN OPERATION and in the Filtered Air mode.
Notes--------------------------------------------------------------
- 1. The control room envelope (CRE) may be opened intermittently under administrative control.
- 2. Place in toxic gas protection mode immediately if automatic transfer to toxic gas protection mode is not functional.
Required Actions (1)
If a CRVS train is not IN OPERATION in Filtered Air mode, immediately place the opposite train IN OPERATION in Filtered Air mode OR immediately suspend CORE ALTERATIONS and REFUELING OPERATIONS.
2.8 - Page 7 Amendment No. 188,201, 204, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling 2.8.2 Refueling Operations - Containment 2.8.2(4)
Control Room Ventilation System (CRVS) (Continued)
Required Actions (Continued)
(2)
If one or more CRVS trains are inoperable due to an inoperable control room envelope (CRE) boundary, immediately suspend CORE ALTERATIONS and REFUELING OPERATIONS.
2.8.3 Refueling Operations - Spent Fuel Pool 2.8.3(1)
Spent Fuel Assembly Storage Applicability Applies to storage of spent fuel assemblies whenever any irradiated fuel assembly is stored in Region 2 (including peripheral cells) of the spent fuel pool. The provisions of Specification 2.0.1 for Limiting Conditions for Operation are not applicable.
Objective To minimize the possibility of an accident occurring during REFUELING OPERATIONS that could affect public health and safety.
Specification The combination of initial enrichment and burnup of each spent fuel assembly stored in Region 2 (including peripheral cells) of the spent fuel pool shall be within the acceptable burnup domain of Figure 2-10.
Required Actions (1)
With the requirements of the LCO not met, initiate action to move the noncomplying fuel assembly immediately.
2.8 - Page 8 Amendment No. 188, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling 2.8.3 Refueling Operations - Spent Fuel Pool 2.8.3(5)
Control Room Ventilation System (CRVS)
Applicability Applies to operation of the CRVS during REFUELING OPERATIONS in the spent fuel pool area. The provisions of Specification 2.0.1 for Limiting Conditions for Operation are not applicable.
Objective To minimize the consequences of a fuel handling accident to the control room staff Specification (1)
The CRVS shall be IN OPERATION and in the Filtered Air mode.
(2)
A spent fuel pool area radiation monitor shall be IN OPERATION.
Notes--------------------------------------------------------
- 1. The control room envelope (CRE) may be opened intermittently under administrative control.
- 2. Place in toxic gas protection mode immediately if automatic transfer to toxic gas protection mode is not functional.
Required Actions (1)
If a CRVS train is not IN OPERATION in Filtered Air mode, immediately place the opposite train IN OPERATION in Filtered Air mode OR immediately suspend REFUELING OPERATIONS.
(2)
If a spent fuel pool area radiation monitor is not IN OPERATION, immediately suspend REFUELING OPERATIONS.
(3)
If one or more CRVS trains are inoperable due to an inoperable control room envelope (CRE) boundary, immediately suspend REFUELING OPERATIONS.
2.8 - Page 13 Amendment No. 188, 201 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Bases (Continued) 2.8.2(3)
Ventilation Isolation Actuation Signal (VIAS) (Continued)
Requiring one (1) radiation monitor to be OPERABLE and aligned to monitor the containment atmosphere [or stack effluents] is a conservative measure to reduce exposure. Radiation monitoring will assure operators are alerted if a radiological incident occurs in containment to enable implementation of administrative controls as specified in the Bases for 2.8.2(1) "Containment Penetrations." During CORE ALTERATIONS and REFUELING OPERATIONS, the OPERABILITY of the control room ventilation system is addressed by Specification 2.8.2(4). The control room ventilation system is placed in Filtered Air mode as a conservative measure to reduce control room operator exposure.
Specification 2.8.2(4) allows the radiological consequences analysis for a fuel handling accident to credit the Filtered Air mode at the time of the accident.
When VIAS is inoperable, CORE ALTERATIONS and REFUELING OPERATIONS in containment are immediately suspended. This effectively precludes a fuel handling accident from occurring. When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner. Suspension of CORE ALTERATIONS and REFUELING OPERATIONS shall not preclude completion of movement of a component to a safe, conservative position.
2.8.2(4)
Control Room Ventilation System (CRVS)
Operating the CRVS in the Filtered Air mode is a conservative measure to reduce control room operator exposure. This allows the radiological consequences analysis for a fuel handling accident to credit the Filtered Air mode at the time of the accident. If a CRVS train is not IN OPERATION in Filtered Air mode, the opposite train must immediately be placed IN OPERATION in Filtered Air mode. This action ensures that the remaining train is OPERABLE, and that any active failure will be readily detected. An alternative is to immediately suspend activities (CORE ALTERATIONS and REFUELING OPERATIONS) that could result in a release of radioactivity that might require isolation of the control room envelope (CRE).
Similarly, with one or more CRVS trains inoperable due to an inoperable CRE boundary, action must be taken immediately to suspend activities (CORE ALTERATIONS and REFUELING OPERATIONS) that could result in a release of radioactivity that might require isolation of the CRE.
These actions place the unit in a condition that minimizes the accident risk.
When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner. Suspension of CORE ALTERATIONS and REFUELING OPERATIONS shall not preclude completion of movement of a component to a safe, conservative position.
2.8 - Page 23 Amendment No.188,201,204, 239, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Bases (Continued) 2.8.2(4)
Control Room Ventilation System (CRVS) (Continued)
The Specification is modified by two notes. The first note allows the CRE boundary to be opened intermittently under administrative controls. This only applies to openings in the CRE boundary that can be rapidly restored to the design condition, such as doors, hatches, floor plugs and access panels. For entry and exit through doors, the administrative control of the opening is performed by the person(s) entering or exiting the area. For other openings, these controls should be proceduralized and consist of stationing a dedicated individual at the opening who is in continuous communication with the operators in the CRE. This individual will have a method to rapidly close the opening and to restore the CRE boundary to a condition equivalent to the design condition when a need for CRE isolation is indicated.
The second note requires the CRVS to be in toxic gas protection mode if automatic transfer to toxic gas protection mode is not functional. CORE ALTERATIONS and REFUELING OPERATIONS must be suspended immediately. Toxic gas is monitored at the outside air intake duct. Actuation of the system to toxic gas protection mode trips CRVS fans and isolates the outside air dampers. The CRVS is then placed in recirculation mode. In recirculation mode, the filter trains are bypassed.
Fire and smoke detection is provided at the outlet of the recirculation fans to protect against smoke developed from sources in the outside air stream or from sources inside the control room. As in toxic gas protection mode, CRVS fans are tripped and the outside air dampers are isolated.
2.8.3(1)
Spent Fuel Assembly Storage The spent fuel pool is designed for noncriticality by use of neutron absorbing material.
The restrictions on the placement of fuel assemblies within the spent fuel pool, according to Figure 2-10, and the accompanying LCO, ensures that the keff of the spent fuel pool always remains < 0.95 assuming the pool to be flooded with unborated water.
A spent fuel assembly may be transferred directly from the reactor core to the spent fuel pool Region 2 provided an independent verification of assembly burnups has been completed and the assembly burnup meets the acceptance criteria identified in Figure 2-10. When the configuration of fuel assemblies stored in Region 2 (including the peripheral cells) is not in accordance with Figure 2-10, immediate action must be taken to make the necessary fuel assembly movement(s) to bring the configuration into compliance with Figure 2-10. Acceptable fuel assembly burnup is not a prerequisite for Region 1 storage because Region 1 will maintain any type of fuel assembly that the plant is licensed for in a safe, coolable, subcritical geometry.
2.8 - Page 24 Amendment No. 188,201,204, 239, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Bases (Continued) 2.8.3(1)
Spent Fuel Assembly Storage (Continued)
The provisions of Specification 2.0.1 for Limiting Conditions for Operations are not applicable. If moving fuel assemblies while in MODES 4 or 5, LCO 2.0.1 would not specify any actions. If moving fuel assemblies in MODES 1, 2, or 3, the fuel movement is independent of reactor operation. Therefore, inability to suspend movement of fuel assemblies is not sufficient reason to require a reactor shutdown. When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner.
2.8.3(2)
Spent Fuel Pool Water Level The minimum water level in the spent fuel pool meets the assumption of iodine decontamination factors following a fuel handling accident. When the water level is lower than the required level, the movement of irradiated fuel assemblies in the spent fuel pool is immediately suspended. This effectively precludes a fuel handling accident from occurring in the spent fuel pool. Suspension of REFUELING OPERATION shall not preclude completion of movement of a component to a safe, conservative position. The provisions of Specification 2.0.1 for Limiting Conditions for Operations are not applicable.
If moving fuel assemblies while in MODES 4 or 5, LCO 2.0.1 would not specify any actions. If moving fuel assemblies in MODES 1, 2, or 3, the fuel movement is independent of reactor operation. Therefore, inability to suspend movement of fuel assemblies is not sufficient reason to require a reactor shutdown. When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner.
2.8.3(3)
Spent Fuel Pool Boron Concentration The basis for the 500 ppm boron concentration requirement with Boral poisoned storage racks is to maintain the keff below 0.95 in the event a misloaded unirradiated fuel assembly is located next to a spent fuel assembly. A misloaded unirradiated fuel assembly at maximum enrichment condition, in the absence of soluble poison, may result in exceeding the design effective multiplication factor. Soluble boron in the spent fuel pool water, for which credit is permitted under these conditions, would assure that the effective multiplication factor is maintained substantially less than the design condition.
This LCO applies whenever unirradiated fuel assemblies are stored in the spent fuel pool.
The boron concentration is periodically sampled in accordance with Specification 3.2.
Sampling is performed prior to movement of unirradiated fuel to the spent fuel pool and periodically when unirradiated fuel is stored in the spent fuel pool.
2.8 - Page 25 Amendment No. 188,201,204, 239, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Bases (Continued) 2.8.3(3)
Spent Fuel Pool Boron Concentration (Continued)
The provisions of Specification 2.0.1 for Limiting Conditions for Operations are not applicable. If moving fuel assemblies while in MODES 4 or 5, LCO 2.0.1 would not specify any actions. If moving fuel assemblies in MODES 1, 2, or 3, the fuel movement is independent of reactor operation. Therefore, inability to suspend movement of fuel assemblies is not sufficient reason to require a reactor shutdown.
When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner. Suspension of refueling operations shall not preclude completion of movement of a component to a safe, conservative position.
2.8.3(4)
Spent Fuel Pool Area Ventilation The spent fuel pool area ventilation system contains a charcoal filter to prevent release of significant radionuclides to the outside atmosphere. The system does not automatically realign and therefore must be IN OPERATION prior to REFUELING OPERATIONS in the spent fuel pool. When the spent fuel pool area ventilation system is not IN OPERATION, the movement of irradiated fuel assemblies in the spent fuel pool is immediately suspended. This effectively precludes a fuel handling accident from occurring in the spent fuel pool. When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner. Suspension of REFUELING OPERATIONS shall not preclude completion of movement of a component to a safe, conservative position.
The provisions of Specification 2.0.1 for Limiting Conditions for Operations are not applicable. If moving fuel assemblies while in MODES 4 or 5, LCO 2.0.1 would not specify any actions. If moving fuel assemblies in MODES 1, 2, or 3, the fuel movement is independent of reactor operation. Therefore, inability to suspend movement of fuel assemblies is not sufficient reason to require a reactor shutdown.
2.8.3(5)
Control Room Ventilation System (CRVS)
Operating the CRVS in the Filtered Air mode and requiring a radiation monitor to be IN OPERATION are conservative measures to reduce control room operator exposure. This allows the radiological consequences analysis for a fuel handling accident to credit the Filtered Air mode at the time of the accident.
Radiation monitoring will assure operators are alerted if a radiological incident occurs.
This specification can be satisfied by using a permanent spent fuel pool area radiation monitor or a portable area radiation monitor.
2.8 - Page 26 Amendment No. 239, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Bases (Continued) 2.8.3(5)
Control Room Ventilation System (CRVS) (Continued)
If a CRVS train is not IN OPERATION in Filtered Air mode, the opposite train must immediately be placed IN OPERATION in Filtered Air mode. This action ensures that the remaining train is OPERABLE, and that any active failure will be readily detected. An alternative is to immediately suspend activities (REFUELING OPERATIONS) that could result in a release of radioactivity that might require isolation of the control room envelope (CRE).
Similarly, with one or more CRVS trains inoperable due to an inoperable CRE boundary, action must be taken immediately to suspend activities (REFUELING OPERATIONS) that could result in a release of radioactivity that might require isolation of the CRE.
These actions place the unit in a condition that minimizes the accident risk.
When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner. Suspension of REFUELING OPERATIONS shall not preclude completion of movement of a component to a safe, conservative position.
The Specification is modified by two notes. The first note allows the control room envelope (CRE) boundary to be opened intermittently under administrative controls. This only applies to openings in the CRE boundary that can be rapidly restored to the design condition, such as doors, hatches, floor plugs and access panels. For entry and exit through doors, the administrative control of the opening is performed by the person(s) entering or exiting the area. For other openings, these controls should be proceduralized and consist of stationing a dedicated individual at the opening who is in continuous communication with the operators in the CRE. This individual will have a method to rapidly close the opening and to restore the CRE boundary to a condition equivalent to the design condition when a need for CRE isolation is indicated.
The second note requires the CRVS to be in toxic gas protection mode if automatic transfer to toxic gas protection mode is not functional. CORE ALTERATIONS and REFUELING OPERATIONS must be suspended immediately. Toxic gas is monitored at the outside air intake duct. Actuation of the system to toxic gas protection mode trips CRVS fans and isolates the outside air dampers. The CRVS is then placed in recirculation mode. In recirculation mode, the filter trains are bypassed.
Fire and smoke detection is provided at the outlet of the recirculation fans to protect against smoke developed from sources in the outside air stream or from sources inside the control room. As in toxic gas protection mode, CRVS fans are tripped and the outside air dampers are isolated.
2.8 - Page 27 Amendment No. 239, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Bases (Continued) 2.8.3(6)
Spent Fuel Cask Loading (1)
Soluble Boron The basis for the 800 ppm minimum boron concentration requirement during spent fuel cask loading operations is to maintain the keff in the cask system less than or equal to 0.95 in the event a mis-loaded unirradiated fuel assembly is located anywhere in the cask with up to 31 other fuel assemblies meeting the burnup and enrichment requirements of LCO 2.8.3(6)(2). This boron concentration also ensures the keff in the cask system will be less than or equal to 0.95 if an unirradiated fuel assembly is dropped in the space between the spent fuel racks and the cask loading area during cask loading operations next to a spent fuel assembly. A mis-loaded or dropped irradiated fuel assembly at maximum enrichment condition, in the absence of soluble poison, may result in exceeding the design effective multiplication factor. Soluble boron in the spent fuel pool water, for which credit is permitted during spent fuel cask loading operations, assures that the effective multiplication factor is maintained substantially less than the design basis limit.
This LCO applies whenever a fuel assembly is located in a spent fuel cask submerged in the spent fuel pool. The boron concentration is periodically sampled in accordance with Specification 3.2. Sampling is performed prior to movement of fuel into the spent fuel cask and periodically thereafter during cask loading operations, until the cask is removed from the spent fuel pool.
The provisions of Specification 2.0.1 for Limiting Conditions for Operations are not applicable. If moving fuel assemblies while in MODES 4 or 5, LCO 2.0.1 would not specify any actions. If moving fuel assemblies in MODES 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of fuel assemblies is not sufficient reason to require a reactor shutdown.
When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner. Suspension of refueling operations shall not preclude completion of movement of a component to a safe, conservative position.
2.8 - Page 28 Amendment No. 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Bases (Continued) 2.8.3(6)
Spent Fuel Cask Loading (Continued)
(2) Burnup vs. Enrichment The spent fuel cask is designed for subcriticality by use of neutron absorbing material. The restrictions on the placement of fuel assemblies within the spent fuel pool, according to Figure 2-11, and the accompanying LCO, ensure that the keff of the spent fuel pool always remains 0.95 assuming the pool to be flooded with borated water and <1.0 assuming the pool is flooded with unborated water, in accordance with 10 CFR 50.68(b)(4).
A spent fuel assembly may be transferred directly from the spent fuel racks to the spent fuel cask provided an independent verification of assembly burnups has been completed and the assembly burnup meets the acceptance criteria identified in Figure 2-11. If any fuel assembly located in the spent fuel cask is not in accordance with Figure 2-11, immediate action must be taken to make the remove of non-complying fuel assembly from the spent fuel cask and return it to the spent fuel rack.
The provisions of Specification 2.0.1 for Limiting Conditions for Operations are not applicable. If moving fuel assemblies while in MODES 4 or 5, LCO 2.0.1 would not specify any actions. If moving fuel assemblies in MODES 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of fuel assemblies is not sufficient reason to require a reactor shutdown. When "immediately" is used as a completion time, the required action should be pursued without delay and in a controlled manner.
References (1)
USAR Section 9.5 (2)
USAR Section 9.10 (3)
USAR Section 14.18 2.8 - Page 29 Amendment No. 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System 2.12.1 Control Room Air Filtration System - Operating Applicability Applies to the operational status of the control room air filtration system when the reactor coolant temperature Tcold 210°F.
Objective To assure operability of equipment required to filter control room air following a Design Basis Accident.
Specification Two control room air filtration trains shall be OPERABLE.
Note------------------------------------------------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
Required Actions (1)
With one control room air filtration train inoperable for reasons other than (2),
restore the inoperable train to OPERABLE status within 7 days.
(2)
With one or more control room air filtration trains inoperable due to inoperable CRE boundary:
- a.
initiate mitigating actions immediately, AND
- b.
verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, AND
- c.
restore CRE boundary to OPERABLE status within 90 days.
(3)
With the required actions of (1) or (2) not met, be in HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
(4)
With two control room air filtration trains inoperable for reasons other than (2),
enter LCO 2.0.1 immediately.
2.12 - Page 1 Amendment No. 15,128,130, 188, 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System 2.12.2 Control Room Air Conditioning System Applicability Applies to the operational status of the control room air conditioning system when the reactor coolant temperature Tcold 210°F.
Objective To assure operability of equipment required to maintain air temperature within the control room following a Design Basis Accident.
Specification Two control room air conditioning trains shall be OPERABLE.
Required Actions (1)
With one control room air conditioning train inoperable, restore the inoperable train to OPERABLE status within 30 days.
(2)
With the required actions of (1) not met, be in HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and COLD SHUTDOWN within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
(3)
With two control room air conditioning trains inoperable, enter LCO 2.0.1 immediately.
2.12 - Page 2 Amendment No. 188 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System Bases 2.12 Control Room Ventilation System The control room ventilation system (CRVS) provides a protected environment from which occupants can control the unit following an uncontrolled release of radioactivity, hazardous chemicals, or smoke. The CRVS contains two independent, redundant control room air filtration trains that filter the air in the control room envelope (CRE), two independent, redundant air conditioning units that circulate and cool the air in the CRE, and a CRE boundary that limits the inleakage of unfiltered air.
The CRE is the area within the confines of the CRE boundary that control room occupants inhabit to control the unit during normal and accident conditions. This area encompasses the control room, and may encompass other non-critical areas to which frequent personnel access or continuous occupancy is not necessary in the event of an accident. The CRE is protected during normal operation, natural events, and accident conditions. The CRE boundary is the combination of walls, floor, roof, ducting, doors, penetrations and equipment that physically form the CRE. The OPERABILITY of the CRE boundary must be maintained to ensure that the inleakage of unfiltered air into the CRE will not exceed the inleakage assumed in the licensing basis analysis of design basis accident (DBA) consequences to CRE occupants. The CRE and its boundary are defined in the Control Room Envelope Habitability Program.
Actuation of the CRVS places the system into either of two separate states of the emergency mode of operation, depending on the initiation signal. Actuation of the system to the emergency radiation state of the emergency mode of operation closes the unfiltered outside air intake and unfiltered exhaust dampers, and aligns the system for recirculation of the air within the CRE through the redundant trains of HEPA and charcoal filters. The emergency radiation state also initiates filtered ventilation of the outside air supply to the CRE.
The actions taken in the toxic gas isolation state are similar, except that the signal switches the CRVS to an isolation mode, minimizing outside air entering the CRE through the CRE boundary. Toxic gas is monitored at the outside air intake duct.
Actuation of the system to toxic gas protection mode trips CRVS fans and isolates the outside air dampers. The CRVS is then placed in recirculation mode. In recirculation mode, the filter trains are bypassed.
Fire and smoke detection is provided at the outlet of the recirculation fans to protect against smoke developed from sources in the outside air stream or from sources inside the control room. As in toxic gas protection mode, CRVS fans are tripped and the outside air dampers are isolated.
2.12 - Page 3 Amendment No. 188 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System Bases (Continued) 2.12 Control Room Ventilation System (Continued)
The radiation monitoring system provides an airborne radiation monitor (RM-065),
which starts after a ventilation isolation actuation signal (VIAS) to verify control room habitability following a design basis accident. The air entering the CRE is continuously monitored by toxic gas detectors. One detector output above the setpoint will cause actuation of the toxic gas isolation state. The actions of the toxic gas isolation state are more restrictive, and will override the actions of the emergency radiation state.
The CRVS provides protection from smoke and hazardous chemicals to the CRE occupants. The analysis of hazardous chemical releases demonstrates that the toxicity limits are not exceeded in the CRE following a hazardous chemical release (Ref. 3).
The evaluation of a smoke challenge demonstrates that it will not result in the inability of the CRE occupants to control the reactor either from the control room or from the remote shutdown panels (Ref. 4).
The worst case single active failure of a component of the CRVS, assuming a loss of offsite power, does not impair the ability of the system to perform its design function.
The CRVS satisfies Criterion 3 of 10 CFR 50.36(d)(2)(ii).
2.12.1 Control Room Air Filtration System - Operating Each control room air filtration system (CRAFS) train contains a heater and demister, a high efficiency particulate air (HEPA) filter, an activated charcoal adsorber section for removal of gaseous activity (principally iodines), and a fan. Ductwork, valves or dampers, doors, barriers, and instrumentation also form part of the system, as well as demisters that remove water droplets from the air stream. A second bank of HEPA filters follows the adsorber section to collect carbon fines and provides back-up in case of failure of the main HEPA filter bank.
The CRAFS is an emergency system, part of which may also operate during normal unit operations in the standby mode of operation. Upon receipt of a VIAS, normal air supply to the CRE is diverted to the filter trains, and the stream of ventilation air is recirculated through the filter trains of the system. The demisters remove any entrained water droplets present to prevent excessive loading of the HEPA filters and charcoal adsorbers. Continuous operation of each train for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per month, with the heaters on, reduces moisture buildup on the HEPA filters and adsorbers. Both the demister and heater are important to the effectiveness of the charcoal adsorbers.
2.12 - Page 4 Amendment No. 188 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System Bases (Continued) 2.12.1 Control Room Air Filtration System - Operating (Continued)
Outside air is filtered, and then added to the air being recirculated from the CRE.
Pressurization of the CRE minimizes infiltration of unfiltered air though the CRE boundary from all the surrounding areas adjacent to the CRE boundary.
A single CRAFS train operating at a flow rate of 1000 cfm will pressurize the CRE to about 0.125 inches water gauge relative to external areas adjacent to the CRE boundary, and provides an air exchange rate in excess of 60% per hour. The CRAFS operation in maintaining the CRE habitable is discussed in USAR, Section 9.10 (Ref. 1).
Redundant supply and recirculation trains provide the required filtration should an excessive pressure drop develop across the other filter train. Normally open isolation dampers are arranged in series pairs so that the failure of one damper to shut will not result in a breach of isolation. However, the recirculation duct does not require redundant dampers to meet single failure proof criteria. Damper PCV-6682 meets the acceptance criteria for the damper repair option described in Standard Review Plan 6.4, Appendix A. A release of radioactivity requires PCV-6682 to open, should PCV-6682 fail to open, it can be repaired or repositioned open before control room doses exceed the allowable limits of General Design Criterion 19. The CRAFS is designed in accordance with Seismic Category 1 requirements.
The CRAFS is designed to maintain a habitable environment in the CRE for 30 days of continuous occupancy after a Design Basis Accident (DBA) without exceeding a 5 rem total effective dose equivalent (TEDE). The CRAFS components are arranged in redundant, safety related ventilation trains. The location of components and ducting within the CRE ensures an adequate supply of filtered air to all areas requiring access.
The CRAFS provides airborne radiological protection for the CRE occupants as demonstrated by the CRE occupant dose analyses for the most limiting design basis accident fission product release presented in the USAR, Section 14.15 (Ref. 2).
2.12 - Page 5 Amendment No. 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System Bases (Continued) 2.12.1 Control Room Air Filtration System - Operating (Continued)
Two independent and redundant trains of the CRAFS are required to be OPERABLE to ensure that at least one is available if a single active failure disables the other train.
Total system failure, such as from a loss of both filtration trains or from an inoperable CRE boundary, could result in exceeding a dose of 5 rem TEDE to the CRE occupants in the event of a large radioactive release.
Each CRAFS train is considered OPERABLE when the individual components necessary to limit CRE occupant exposure are OPERABLE. A CRAFS train is considered OPERABLE when the associated:
- a.
Fan is OPERABLE,
- b.
HEPA filters and charcoal adsorber are not excessively restricting flow, and are capable of performing their filtration function, and
- c.
Heater, demister, ductwork, valves, and dampers are OPERABLE, and air circulation can be maintained.
In order for the CRAFS trains to be considered OPERABLE, the CRE boundary must be maintained such that CRE occupant dose from a large radioactive release does not exceed the calculated dose in the licensing basis consequence analyses for DBAs, and that CRE occupants are protected from hazardous chemicals and smoke.
The LCO is modified by a Note allowing the CRE boundary to be opened intermittently under administrative controls. This Note only applies to openings in the CRE boundary that can be rapidly restored to the design condition, such as doors, hatches, floor plugs and access panels. For entry and exit through doors, the administrative control of the opening is performed by the person(s) entering or exiting the area. For other openings, these controls should be proceduralized and consist of stationing a dedicated individual at the opening who is in continuous communication with the operators in the CRE. This individual will have a method to rapidly close the opening and to restore the CRE boundary to a condition equivalent to the design condition when a need for CRE isolation is indicated.
APPLICABILITY With the reactor coolant temperature Tcold 210°F, the CRAFS must be OPERABLE to ensure that the CRE will remain habitable during and following a DBA.
2.12 - Page 6 Amendment No. 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System Bases (Continued) 2.12.1 Control Room Air Filtration System - Operating (Continued)
ACTIONS (1)
With one CRAFS train inoperable, for reasons other than an inoperable CRE boundary, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE CRAFS train is adequate to perform the CRE occupant protection function. However, the overall reliability is reduced because a failure in the OPERABLE CRAFS train could result in loss of CRAFS function. The 7 day Completion Time is based on the low probability of a DBA occurring during this time period, and the ability of the remaining train to provide the required capability.
(2)a, (2)b, and (2)c If the unfiltered inleakage of potentially contaminated air past the CRE boundary and into the CRE can result in CRE occupant radiological dose greater than the calculated dose of the licensing basis analyses of DBA consequences (allowed to be up to 5 rem TEDE), or inadequate protection of CRE occupants from hazardous chemicals or smoke, the CRE boundary is inoperable. Actions must be taken to restore an OPERABLE CRE boundary within 90 days.
During the period that the CRE boundary is considered inoperable, action must be initiated to implement mitigating actions to lessen the effect on CRE occupants from the potential hazards of a radiological or chemical event or a challenge from smoke.
Actions must be taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to verify that in the event of a DBA, the mitigating actions will ensure that CRE occupant radiological exposures will not exceed the calculated dose of the licensing basis analyses of DBA consequences, and that CRE occupants are protected from hazardous chemicals and smoke. These mitigating actions (i.e., actions that are taken to offset the consequences of the inoperable CRE boundary) should be preplanned for implementation upon entry into the condition, regardless of whether entry is intentional or unintentional. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is reasonable based on the low probability of a DBA occurring during this time period, and the use of mitigating actions. The 90 day Completion Time is reasonable based on the determination that the mitigating actions will ensure protection of CRE occupants within analyzed limits while limiting the probability that CRE occupants will have to implement protective measures that may adversely affect their ability to control the reactor and maintain it in a safe shutdown condition in the event of a DBA. In addition, the 90 day Completion Time is a reasonable time to diagnose, plan and possibly repair, and test most problems with the CRE boundary.
2.12 - Page 7 Amendment No. 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System Bases (Continued) 2.12.1 Control Room Air Filtration System - Operating (Continued)
(3)
With reactor coolant temperature Tcold 210°F, if the inoperable CRAFS or CRE boundary cannot be restored to OPERABLE status within the required Completion Time, the unit must be placed in a MODE that minimizes the accident risk. To achieve this status, the unit must be placed in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. 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.
(4)
If both CRAFS trains are inoperable with reactor coolant temperature Tcold 210°F for reasons other than an inoperable CRE boundary (i.e., Condition 2), the CRAFS may not be capable of performing the intended function and the unit is in a condition outside the accident analyses. Therefore, LCO 2.0.1 must be entered immediately.
2.12.2 Control Room Air Conditioning System The control room air conditioning system is required to ensure the control room temperature will not exceed equipment OPERABILITY requirements. The reactor protective system panels and the engineered safety features panels were designed for, and the instrumentation was tested at, 120°F. The temperature inside the control cabinets is at most 15°F warmer than the temperature of the control room due to heat produced by the electronic circuitry. Therefore, the temperature of the control room will not affect OPERABILITY of the control cabinets as long as it doesn't exceed 105°F.
During non-emergency operation, the control room temperature may be maintained by using Component Cooling Water (CCW). During design basis accident conditions, the CCW isolation valves to air conditioning units (VA-46A and VA-46B) are automatically closed on a VIAS. This prevents CCW that has been heated by components following a design basis accident from adding heat to the control room. When VIAS is in override, closing these valves maintains the OPERABILITY of the associated air conditioning unit.
2.12 - Page 8 Amendment No. 257
TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Ventilation System Bases (Continued) 2.12.2 Control Room Air Conditioning System (Continued)
With the reactor coolant temperature Tcold 210°F, two trains of the control room air conditioning system are required to be OPERABLE. If one train is inoperable it shall be restored to OPERABLE status within 30 days. In this condition the remaining train is adequate to maintain the control room temperature. With both trains inoperable, the control room air conditioning system may not be capable of performing its intended function and LCO 2.0.1 must be entered immediately.
References (1)
USAR Section 9.10 (2)
USAR Section 14.15 (3)
USAR Section 14.23 (4)
Engineering Analysis (EA)-FC-01-013, Effects of Secondary Environment Resulting from a Fire Event 2.12 - Page 9 Amendment No. 257
TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.1 Instrumentation and Control (Continued)
The Control Room Envelope (CRE) surveillance requirement (SR) verifies the OPERABILITY of the CRE boundary by testing for unfiltered air inleakage past the CRE boundary and into the CRE. The details of the testing are specified in the Control Room Envelope Habitability Program.
The CRE is considered habitable when the radiological dose to CRE occupants calculated in the licensing basis analyses of DBA consequences is no more than 5 rem TEDE and the CRE occupants are protected from hazardous chemicals and smoke. This SR verifies that the unfiltered air inleakage into the CRE is no greater than the flow rate assumed in the licensing basis analyses of DBA consequences. When unfiltered air inleakage is greater than the assumed flow rate, Technical Specification (TS) 2.12.1(2) must be entered. TS 2.12.1(2)c allows time to restore the CRE boundary to OPERABLE status provided mitigating actions can ensure that the CRE remains within the licensing basis habitability limits for the occupants following an accident.
Compensatory measures are discussed in Regulatory Guide 1.196, Section C.2.7.3, (Ref. 1) which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref.
2). These compensatory measures may also be used as mitigating actions as required by TS 2.12.1(2)b. Temporary analytical methods may also be used as compensatory measures to restore OPERABILITY (Ref. 3). Options for restoring the CRE boundary to OPERABLE status include changing the licensing basis DBA consequence analysis, repairing the CRE boundary, or a combination of these actions. Depending upon the nature of the problem and the corrective action, a full scope inleakage test may not be necessary to establish that the CRE boundary has been restored to OPERABLE status.
References
- 1.
- 2.
NEI 99-03, "Control Room Habitability Assessment," June 2001
- 3.
Letter from Eric J. Leeds (NRC) to James W. Davis (NEI) dated January 30, 2004, "NEI Draft White Paper, Use of Generic Letter 91-18 Process and Alternative Source Terms in the Context of Control Room Habitability." (Adams Accession No. ML040300694).
3.1 - Page 3 Amendment No. 257
TECHNICAL SPECIFICATIONS TABLE 3-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM Channel Description Surveillance Function Frequency Surveillance Method
- 1. Power Range Safety Channels
- a. Check:
- 1)
Neutron Flux
- 2)
Thermal Power S
a.
- 1)
CHANNEL CHECK
- 2)
CHANNEL CHECK
- b. Adjustment D(3)
- b. Channel adjustment to agree with heat balance calculation.
- c. Test Q(1)
- c. CHANNEL FUNCTIONAL TEST
- 2. Wide-Range Logarithmic Neutron Monitors
- a. Check S
- a. CHANNEL CHECK
- b. Test(2)
P
- b. CHANNEL FUNCTIONAL TEST
- 3. Reactor Coolant Flow
- a. Check S
- a. CHANNEL CHECK
- b. Test Q(1)
- b. CHANNEL FUNCTIONAL TEST
- c. Calibrate R
- c. CHANNEL CALIBRATION 3.1 - Page 4 Amendment No. 60, 163,182 257
TECHNICAL SPECIFICATIONS TABLE 3-1 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM Channel Description Surveillance Function Frequency Surveillance Method
- 4. Thermal Margin/Low Pressure
- a. Check
- 1) Pressure Setpoint S
a.
- 1) CHANNEL CHECK
- 2) Pressure Input
- 2) CHANNEL CHECK
- b. Test Q(1)
- b. CHANNEL FUNCTIONAL TEST
- c. Calibrate:
- 1) Temperature Input R
c.
- 1) CHANNEL CALIBRATION
- 2) Pressure Input
- 2) CHANNEL CALIBRATION
- 5. High-Pressurizer Pressure
- a. Check S
- a. CHANNEL CHECK
- b. Test Q(1)
- b. CHANNEL FUNCTIONAL TEST
- c. Calibrate R
- c. CHANNEL CALIBRATION 3.1 - Page 5 Amendment No. 163, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-1 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM Channel Description Surveillance Function Frequency Surveillance Method
- 6. Steam Generator Level
- a. Check S
- a. CHANNEL CHECK
- b. Test Q(1)
- b. CHANNEL FUNCTIONAL TEST
- c. Calibrate R
- c. CHANNEL CALIBRATION
- 7. Steam Generator Pressure
- a. Check S
- a. CHANNEL CHECK
- b. Test Q(1)
- b. CHANNEL FUNCTIONAL TEST
- c. Calibrate R
- c. CHANNEL CALIBRATION
- 8. Containment Pressure
- a. Test Q(1)
- a. CHANNEL FUNCTIONAL TEST
- b. Calibrate R
- b. CHANNEL CALIBRATION
- 9. Loss of Load
- a. Test P
- a. CHANNEL FUNCTIONAL TEST
- 10. Manual Trips
- a. Test P
- a. CHANNEL FUNCTIONAL TEST
- 11. Steam Generator Differential Pressure
- a. Check S
- a. CHANNEL CHECK
- b. Test Q(1)
- b. CHANNEL FUNCTIONAL TEST
- c. Calibrate R
- c. CHANNEL CALIBRATION 3.1 - Page 6 Amendment No. 77,163, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-1 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM Channel Description Surveillance Function Frequency Surveillance Method
- 12. Reactor Protection System Logic Units
- a. Test Q(1)
- a. CHANNEL FUNCTIONAL TEST
- 13. Axial Power Distribution
- a. Check:
S a.
- 1) Axial Shape Index Indication
- 1) CHANNEL CHECK
- 2) Upper Trip Setpoint Indication
- 2) CHANNEL CHECK
- 3) Lower Trip Setpoint Indication
- 3) CHANNEL CHECK
- b. Test Q(1)
- b. CHANNEL FUNCTIONAL TEST
- c. Calibrate R
- c. CHANNEL CALIBRATION NOTES:
(1)
The quarterly tests will be done on only one of four channels at a time to prevent reactor trip.
(2)
Calibrate using built-in simulated signals.
(3)
Not required unless the reactor is in the power operating condition and is therefore not required during plant startup and shutdown periods.
3.1 - Page 7 Amendment No. 77,122,163, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-2 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method
- 1.
Pressurizer Pressure Low
- a.
Check S
- a.
CHANNEL CHECK
- b.
Test Q(1)P(4)
- b.
CHANNEL FUNCTIONAL TEST
- c.
Calibrate R
- c.
CHANNEL CALIBRATION
- 2.
Pressurizer Low
- a.
Calibrate R
- a.
CHANNEL CALIBRATION Pressure Blocking Circuit
- 3.
Safety Injection
- a.
Test Q
- a.
CHANNEL FUNCTIONAL TEST Actuation Logic (Simulation of PPLS or CPHS 2/4 Logic)
- b.
Test R(7)
- b.
CHANNEL FUNCTIONAL TEST 3.1 - Page 8 Amendment No. 54,163, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method
- 4.
Containment Pressure
- a.
Test Q
- a.
CHANNEL FUNCTIONAL TEST High Signal
- b.
Calibrate R
- b.
CHANNEL CALIBRATION
- 5.
- a.
Test Q
- a.
CHANNEL FUNCTIONAL TEST Actuation Logic (Simulation of PPLS, CPHS, and SGLS(8) 2/4 Logic)
- b.
Test R(7)
- b.
CHANNEL FUNCTIONAL TEST
- 6.
Containment Radiation
- a.
Check D
- a.
CHANNEL CHECK High Signal (2) 3.1 - Page 9 Amendment No. 152,163,173,182,255 257
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method
- 6.
(continued)
- b.
Test Q
- b.
CHANNEL FUNCTIONAL TEST
- c.
Calibrate R
- c.
Secondary and Electronic Calibration performed at refueling frequency.
Primary calibration performed with exposure to radioactive sources only when required by the secondary and electronic calibration.
- 7.
Manual Safety Injection
- a.
Test R
- a.
CHANNEL FUNCTIONAL TEST Actuation
- 8.
Manual Containment
- a.
Check R
- a.
Observe isolation valves closure.
Isolation Actuation
- b.
Test R
- b.
CHANNEL FUNCTIONAL TEST
- 9.
Manual Containment
- a.
Test R
- a.
CHANNEL FUNCTIONAL TEST Spray Actuation
- 10. Automatic Load
- a.
Test Q
- a.
CHANNEL FUNCTIONAL TEST Sequencers
- 11. Diesel Testing See Technical Specification 3.7 3.1 - Page 10 Amendment No. 54,111,152,163,173,182 257
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method
- 12. Diesel Fuel Transfer
- a.
Test M
- a.
Pump run to refill day tank.
Pump
- 13. SIRW Tank Low
- a.
Check S
- a.
CHANNEL CHECK Level Signal
- b.
Test Q
- b.
CHANNEL FUNCTIONAL TEST
- c.
Calibrate R
- c.
CHANNEL CALIBRATION
- 14. Safety Injection
- a.
Check S(5)
- a.
Verify that level and pressure Tank Level and Pressure are within limits.
3.1 - Page 11 Amendment No. 111,163,171, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method
- 14. (continued)
- b.
Calibrate R
- b.
CHANNEL CALIBRATION
- 15. Boric Acid Tank Level
- a.
Check W
- a.
Verify that level is within limits.
- 16. Boric Acid Tank
- a.
Check W
- a.
Verify that temperature is within limits.
Temperature
- 17. Steam Generator Low
- a.
Check S
- a.
CHANNEL CHECK Pressure Signal (SGLS)
- b.
Test Q(3)
- b.
CHANNEL FUNCTIONAL TEST
- c.
Calibrate R
- c.
CHANNEL CALIBRATION 3.1 - Page 12 Amendment No. 131,163,172, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method
- 18. SIRW Tank Temperature a.
Check D(6)
- a.
Verify that temperature is within limits.
- b.
Test R
- b.
Measure temperature of SIRW tank with standard laboratory instruments.
- 19. Manual Recirculation
- a.
Test R
- a.
CHANNEL FUNCTIONAL TEST Actuation
- 20. Recirculation Actuation
- a.
Test Q
- a.
CHANNEL FUNCTIONAL TEST Logic
- b.
Test R(7)
- b.
CHANNEL FUNCTIONAL TEST
- 21. 4.16 KV Emergency Bus
- a.
Check S
- a.
Verify voltage readings are above Low Voltage (Loss of alarm initiation on degraded voltage Voltage and Degraded level - supervisory lights "on".
Voltage) Actuation Logic
- b.
Test Q
- b.
CHANNEL FUNCTIONAL TEST (Undervoltage relay)
- c.
Calibrate R
- c.
CHANNEL CALIBRATION
- 22. Manual Emergency Off-site
- a.
Test R
- a.
CHANNEL FUNCTIONAL TEST Power Low Trip Actuation 3.1 - Page 13 Amendment No. 41,153,163,172,182,249 257
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method
- a.
Check:
S
- a.
- 1) CHANNEL CHECK Water Level Low (Wide Range)
- 2) CHANNEL CHECK Pressure Low
- b.
Test:
QR(7)
- b.
- 1) Actuation Logic
- 1) CHANNEL FUNCTIONAL TEST
- c.
Calibrate:
R
- c.
- 1) CHANNEL CALIBRATION Water Level Low (Wide Range)
- 2) CHANNEL CALIBRATION Pressure Low
- 3) CHANNEL CALIBRATION Differential Pressure High
- 24. Manual Auxiliary Feedwater
- a.
Test R
- a.
CHANNEL FUNCTIONAL TEST Actuation NOTES:
(1)
Not required unless pressurizer pressure is above 1700 psia.
(2)
CRHS monitors are the containment atmosphere gaseous radiation monitor and the Auxiliary Building Exhaust Stack gaseous radiation monitor.
(3)
Not required unless steam generator pressure is above 600 psia.
(4)
QP - Quarterly during designated modes and prior to taking the reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery).
(5)
Not required to be done on a SIT with inoperable level and/or pressure instrumentation.
(6)
Not required when outside ambient air temperature is greater than 50°F and less than 105°F.
(7)
Tests backup channels such as derived circuits and equipment that cannot be tested when the plant is at power.
(8)
SGLS is required for containment spray pump actuation only. SGLS lockout relays are not actuated for this test.
3.1 - Page 14 Amendment No. 41,54,65,122,163,171,172,182,255 257
TECHNICAL SPECIFICATIONS TABLE 3-3 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method
- 1.
Primary CEA Position
- a.
Check S
- a.
Comparison of output data with secondary CEAPIS.
Indication System
- b.
Test M
- b.
Test of power dependent insertion limits, deviation, and sequence monitoring systems.
- c.
Calibrate R
- c.
Physically measured CEDM position used to verify system accuracy. Calibrate CEA position interlocks.
- 2.
Secondary CEA Position
- a.
Check S
- a.
Comparison of output data with primary CEAPIS.
Indication System
- b.
Test M
- b.
Test of power dependent insertion limit, deviation, out-of-sequence, and overlap monitoring systems.
- c.
Calibrate R
- c.
Calibrate secondary CEA position indication system and CEA interlock alarms.
- 3.
Area and Post-Accident
- a.
Check D
- a.
CHANNEL CHECK Radiation Monitors(1)
- b.
Test Q
- b.
CHANNEL FUNCTIONAL TEST
- c.
Calibrate R
- c.
Secondary and Electronic calibration performed at refueling frequency. Primary calibration with exposure to radioactive sources only when required by the secondary and electronic calibration.
RM-091 A/B - Calibration by electronic signal substitution is acceptable for all range decades above 10 R/hr. Calibration for at least one decade below 1-R/hr. shall be by means of calibrated radiation source.
(1)Post Accident Radiation Monitors are: RM-063, RM-064, and RM-091A/B. Area Radiation Monitors are: RM-070 thru RM-082, RM-084 thru RM-089, and RM-095 thru RM-098.
3.1 - Page 15 Amendment No. 8,81,86,93,137,152,164,171 257
TECHNICAL SPECIFICATIONS TABLE 3-3 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method
- 4.
DELETED
- 5.
Primary to Secondary
- a.
Check D
- a.
CHANNEL CHECK Leak-Rate Detection Radiation Monitors
- b.
Test Q
- b.
CHANNEL FUNCTIONAL TEST (RM-054A/B, RM-057)
- c.
Calibrate R
- c.
Secondary and Electronic calibration performed at refueling frequency. Primary Calibration performed with exposure to radioactive sources only when required by the secondary and electronic calibration.
- 6.
Pressurizer Level
- a.
Check S
- a.
Verify that level is within limits.
- b.
Check M
- b.
CHANNEL CHECK
- c.
Calibrate R
- c.
CHANNEL CALIBRATION
- 7.
CEA Drive System
- a.
Test R
- a.
Verify proper operation of all CEDM system Interlocks interlocks, using simulated signals where necessary.
- b.
Test P
- b.
If haven't been checked for three months and plant is shutdown.
3.1 - Page 16 Amendment No. 152,171, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-3 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method
- 8.
Dropped CEA Indication
- a.
Test R
- a.
Insert a negative rate of change power signal to all four Power Range Safety Channels to test alarm.
- b.
Test R
- b.
Insert CEA's below lower electrical limit to test dropped CEA alarm.
- 9.
Calorimetric Instrumen-
- a.
Calibrate R
- a.
CHANNEL CALIBRATION tation
- 10. Control Room Ventilation
- a.
Test R
- a.
Check damper operation for DBA mode.
System
- b.
Test In accordance
- b.
Perform required control room envelope (CRE) with CRE unfiltered air inleakage testing in accordance with the Habitability Program CRE Habitability Program.
- 11. Containment Humidity
- a.
Test R
- a.
CHANNEL FUNCTIONAL TEST Detector
- 12. Interlocks-Isolation Valves
- a.
Test R
- a.
CHANNEL FUNCTIONAL TEST on Shutdown Cooling Line
- 13. Control Room Air Conditioning a.
Test R
- a.
Verify each train has the capability to remove the System assumed heat load through combination of testing and calculations.
3.1 - Page 17 Amendment No. 16,32,123,157,182, 188 257
TECHNICAL SPECIFICATIONS TABLE 3-3 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method
- 14. Not Used
- a.
Check R(1)
- a.
Calculation of reactor coolant flow rate.
Flow
- 16. Pressurizer Pressure
- a.
Check S
- a.
CHANNEL CHECK
- 17. Reactor Coolant Inlet
- a.
Check S
- a.
CHANNEL CHECK Temperature
- 18. Low-Temperature Set-
- a.
Test PM
- a.
CHANNEL FUNCTIONAL TEST (excluding point Power-Operated actuation)
Relief Valves
- b.
Calibrate R
- b.
CHANNEL CALIBRATION (1)
Required to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after 95.00% reactor thermal power following power escalation.
3.1 - Page 18 Amendment No. 8,32,39,96,182,193, 228 257
TECHNICAL SPECIFICATIONS TABLE 3-3 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method
- 19. Auxiliary Feedwater Flow
- a.
Check M
CHANNEL CHECK
- b.
Calibrate R
CHANNEL CALIBRATION
- 20. Subcooled Margin Monitor
- a.
Check M
CHANNEL CHECK
- b. Calibrate R
CHANNEL CALIBRATION
- 21. PORV Operation and Acoustic a.
Test M
CHANNEL FUNCTIONAL TEST Position Indication
- b.
Calibrate R
CHANNEL CALIBRATION
- 22. PORV Block Valve Operation
- a.
Check Q
Cycle valve. Valve is exempt from and Position Indication testing when it has been closed to comply with LCO Action Statement 2.1.6(5)a.
- b.
Calibrate R
Check valve stroke against limit switch position.
- 23. Safety Valve Acoustic
- a.
Test M
CHANNEL FUNCTIONAL TEST Position Indication
- b.
Calibration R
CHANNEL CALIBRATION
- 24. PORV/Safety Valve Tail
- a.
Check M
CHANNEL CHECK Pipe Temperature
- b.
Calibrate R
CHANNEL CALIBRATION 3.1 - Page 19 Amendment No. 39,54,110,161, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-3 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method
- 25. Containment Purge Isolation
- a. Check M
- a.
Verify valve position using control Valves (PCV-742A, B, C, & D) room indication.
- 26. Not Used
- 27. Containment Water Level
- a. Check M
- a.
CHANNEL CHECK Narrow Range (LT-599
& LT-600)
- b. Calibrate R
- b.
CHANNEL CALIBRATION Wide Range (LT-387 &
- a. Check M
- a.
CHANNEL CHECK LT-388)
- b. Calibrate R
- b.
CHANNEL CALIBRATION
- 28. Containment Wide Range
- a. Check M
- a.
CHANNEL CHECK Pressure Indication
- b. Calibrate R
- b.
CHANNEL CALIBRATION
- 29. Not Used 3.1 - Page 20 Amendment No. 54,68,82,87,107,182,183, 234 248, 257
TECHNICAL SPECIFICATIONS TABLE 3-3 (Continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method
- 30. Core Exit Thermo-
- a. Check M
- a.
CHANNEL CHECK couple
- b. Calibrate R
- b.
CHANNEL CALIBRATION
- 31. Heated Junction Thermocouple (YE-116A and YE-116B)
- a. Check M
- a.
CHANNEL CHECK
- b. Calibrate R
- b.
CHANNEL CALIBRATION PM -
Prior to scheduled cold leg cooldown below 300°F; monthly whenever temperature remains below 300°F and reactor vessel head is installed.
3.1 - Page 21 Amendment No. 87,107,110,122,182, 183 257
TECHNICAL SPECIFICATIONS TABLE 3-3A MINIMUM FREQUENCY FOR CHECKS, CALIBRATIONS AND FUNCTIONAL TESTING OF ALTERNATE SHUTDOWN PANELS (AI-185 AND AI-212)
AND EMERGENCY AUXILIARY FEEDWATER PANEL (AI-179) INSTRUMENTATION AND CONTROL CIRCUITS Surveillance Channel Description Function Frequency Surveillance Method
- 1.
WIDE RANGE
- a. CHECK M
- a.
CHANNEL CHECK LOGARITHMIC POWER AND SOURCE RANGE MONITORS
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION (AI-212)
- 2.
REACTOR COOLANT COLD
- a. CHECK M
- a.
CHANNEL CHECK LEG TEMPERATURE (AI-185)
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION
- 3.
REACTOR COOLANT HOT
- a. CHECK M
- a.
CHANNEL CHECK LEG TEMPERATURE (AI-185)
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION
- 4.
PRESSURIZER LEVEL
- a. CHECK M
- a.
CHANNEL CHECK (AI-185)
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION
- 5.
VOLUME CONTROL
- a. CHECK M
- a.
CHANNEL CHECK TANK LEVEL (AI-185)
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION
- 6.
ASP CONTROL
- a. TEST R
- a.
CHANNEL FUNCTIONAL TEST CIRCUITS (AI-185) 3.1 - Page 22 Amendment No. 125, 182 257
TECHNICAL SPECIFICATIONS TABLE 3-3A (Continued)
MINIMUM FREQUENCY FOR CHECKS, CALIBRATIONS AND FUNCTIONAL TESTING OF ALTERNATE SHUTDOWN PANELS (AI-185 AND AI-212)
AND EMERGENCY AUXILIARY FEEDWATER PANEL (AI-179) INSTRUMENTATION AND CONTROL CIRCUITS Surveillance Channel Description Function Frequency Surveillance Method
- 7.
- a. CHECK M
- a.
CHANNEL CHECK LEVEL, WIDE RANGE (AI-179)
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION
- 8.
- a. CHECK M
- a.
CHANNEL CHECK LEVEL, NARROW RANGE (AI-179)
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION
- 9.
- a. CHECK M
- a.
CHANNEL CHECK PRESSURE (AI-179)
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION
- 10. PRESSURIZER PRESSURE
- a. CHECK M
- a.
CHANNEL CHECK (AI-179)
- b. CALIBRATE R
- b.
CHANNEL CALIBRATION
- 11. EAFW CONTROL
- a. TEST R
- a.
CHANNEL FUNCTIONAL TEST CIRCUITS (AI-179) 3.1 - Page 23 Amendment No. 125, 182 257
TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.2 Equipment and Sampling Tests Applicability Applies to plant equipment and conditions related to safety.
Objective To specify the minimum frequency and type of surveillance to be applied to critical plant equipment and conditions.
Specifications Equipment and sampling tests shall be conducted as specified in Tables 3-4 and 3-5.
Basis The equipment testing and system sampling frequencies specified in Tables 3-4 and 3-5 are considered adequate, based upon experience, to maintain the status of the equipment and systems so as to assure safe operation. Thus, those systems where changes might occur relatively rapidly are sampled frequently and those static systems not subject to changes are sampled less frequently.
The control room air filtration system (CRAFS) consists of redundant high efficiency particulate air filters (HEPA) and charcoal adsorbers. HEPA filters are installed before and after the charcoal adsorbers. The charcoal adsorbers are installed to reduce the potential intake of iodine to the control room. The in-place test results will confirm system integrity and performance. The laboratory carbon sample test results should indicate methyl iodide removal efficiency of at least 99.825 percent for expected accident conditions.
CRAFS standby systems should be checked periodically to ensure that they function properly. Since the environment and normal operating conditions on this system are not severe, testing each train once every month provides an adequate check on this system.
Monthly heater operations dry out any moisture accumulated in the charcoal from humidity in the ambient air. Each CRAFS train must be operated for 10 continuous hours with the heaters energized. The monthly Frequency is based on the known reliability of the equipment, and the two train redundancy available.
Each CRAFS train is verified to start and operate on an automatic and manual actuation signal. The Frequency of 18 months is based on industry operating experience and is consistent with the typical refueling cycle.
3.2 - Page 1 Amendment No. 15,67,122,128 257
TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.2 Equipment and Sampling Tests (continued)
The spent fuel storage-decontamination areas air treatment system is designed to filter the building atmosphere to the auxiliary building vent during refueling operations. The charcoal adsorbers are installed to reduce the potential release of radioiodine to the environment. In-place testing is performed to confirm the integrity of the filter system. The charcoal adsorbers are periodically sampled to insure capability for the removal of radioactive iodine.
The Safety Injection (SI) pump room air treatment system consists of charcoal adsorbers which are installed in normally bypassed ducts. This system is designed to reduce the potential release of radioiodine in SI pump rooms during the recirculation period following a DBA. The in-place and laboratory testing of charcoal adsorbers will assure system integrity and performance.
Pressure drops across the combined HEPA filters and charcoal adsorbers, of less than 9 inches of water for the control room filters (VA-64A & VA-64B) and of less than 6 inches of water for each of the other air treatment systems will indicate that the filters and adsorbers are not clogged by amounts of foreign matter that would interfere with performance to established levels.
The hydrogen purge system provides the control of combustible gases (hydrogen) in containment for a post-LOCA environment. The surveillance tests provide assurance that the system is operable and capable of performing its design function. VA-80A or VA-80B is capable of controlling the expected hydrogen generation (67 SCFM) associated with 1)
Zirconium - water reactions, 2) radiolytic decomposition of sump water and 3) corrosion of metals within containment. The system should have a minimum of one blower with associated valves and piping (VA-80A or VA-80B) available at all times to meet the guidelines of Regulatory Guide 1.7 (1971).
If significant painting, fire or chemical release occurs such that the HEPA filters or charcoal adsorbers could become contaminated from the fumes, chemicals or foreign materials, testing will be performed to confirm system performance.
Demonstration of the automatic and/or manual initiation capability will assure the system's availability.
Verifying Reactor Coolant System (RCS) leakage to be within the LCO limits ensures the integrity of the Reactor Coolant Pressure Boundary (RCPB) is maintained. Pressure boundary leakage would at first appear as unidentified leakage and can only be positively identified by inspection. Unidentified leakage is determined by performance of an RCS water inventory balance. Identified leakage is then determined by isolation and/or inspection. Since Primary to Secondary Leakage of 150 gallons per day cannot be measured accurately by an RCS water inventory balance, note "***" for line item 8a on Table 3-5 states that the Reactor Coolant System Leakage surveillance is not applicable to Primary to Secondary Leakage. Primary to secondary leakage is measured by performance of effluent monitoring within the secondary stem and feedwater systems.
3.2 - Page 2 Amendment No. 15,67,128,138,169,246 257
TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.2 Equipment and Sampling Tests (continued)
Failure to meet any of the above limits is cause for rejecting the new fuel oil, but does not represent a failure to meet the LCO concern since the fuel oil is not added to the storage tanks. Within 31 days following the initial new fuel oil sample, the fuel oil is analyzed to establish that the other properties specified in Table 1 of ASTM D975-98b (Ref. 3) are met for new fuel oil when tested in accordance with ASTM D975-98b (Ref. 2), except that the analysis for sulfur may be performed in accordance with ASTM D129-00 (Ref. 2) or ASTM D2622-87 (Ref. 2). The 31 day period is acceptable because the fuel oil properties of interest, even if they were not within stated limits, would not have an immediate effect on DG operation. This Surveillance ensures the availability of high quality fuel oil for the DGs.
Fuel oil degradation during long term storage shows up as an increase in particulate, due mostly to oxidation. The presence of particulate does not mean the fuel oil will not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel oil injection equipment, however, which can cause engine failure. Particulate concentrations should be determined in accordance with ASTM 6217-98 (Ref. 2) with the exception that the filters specified in the ASTM method may have a nominal pore size of up to 3 microns. This method involves a gravimetric determination of total particulate concentration in the fuel oil and has a limit of 10 mg/l. It is acceptable to obtain a field sample for subsequent laboratory testing in lieu of field testing. For those designs in which the total stored fuel oil volume is contained in two or more interconnected tanks, each tank must be considered and tested separately. The Surveillance interval of this test takes into consideration fuel oil degradation trends that indicate that particulate concentration is unlikely to change significantly between Surveillance intervals.
Table 3-5, Item 9d ensures that, without the aid of the refill compressor, sufficient air start capacity for each DG is available. The system design requirements provide for a minimum of five engine start cycles without recharging. A start cycle is defined as the cranking time required to accelerate the DG to firing speed. The pressure specified in this Surveillance Requirement is intended to reflect the lowest value at which the five starts can be accomplished. The 31 day Surveillance interval takes into account the capacity, capability, redundancy, and diversity of the AC sources and other indications available in the control room, including alarms, to alert the operator to below normal air start pressure.
Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water environment in order to survive. Removal of water from the fuel storage tanks once every 92 days per Table 3-5, Item 9e, eliminates the necessary environment for bacterial survival. This is the most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water entrainment in the fuel oil during DG operation. Water may come from any of several sources, including condensation, ground water, rain water, and contaminated fuel oil, and from breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance interval is established to ensure excessive water does not accumulate in the fuel oil system, which meets the intent of Regulatory Guide 1.137 (Ref. 4). This Surveillance Requirement is for preventative maintenance. The presence of water does not necessarily represent failure of this Surveillance Requirement provided the accumulated water is removed during performance of the Surveillance.
3.2 - Page 4 Amendment No. 229 257
TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.2 Equipment and Sampling Tests (continued)
Table 3-5, Item 8b verifies that primary to secondary LEAKAGE is less or equal to 150 gallons per day through any one SG. Satisfying the primary to secondary LEAKAGE limit ensures that the operational LEAKAGE performance criterion in the Steam Generator Program is met. If this surveillance requirement is not met, compliance with LCO 3.17, "Steam Generator Tube Integrity," should be evaluated. The 150 gallons per day limit is measured at room temperature as described in Reference 5. The operational LEAKAGE rate limit applies to LEAKAGE through any one SG. If it is not practical to assign the LEAKAGE to an individual SG, all the primary to secondary LEAKAGE should be conservatively assumed to be from one SG.
The Surveillance is modified by a Note which states that the Surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation. For RCS primary to secondary LEAKAGE determination, steady state is defined as stable RCS pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows.
The Surveillance Frequency of daily is a reasonable interval to trend primary to secondary LEAKAGE and recognizes the importance of early leakage detection in the prevention of accidents. The primary to secondary LEAKAGE is determined using continuous process radiation monitors or radiochemical grab sampling in accordance with the EPRI guidelines (Ref. 5).
References
- 1)
USAR, Section 9.10
- 2)
ASTM D4057-95(2000), ASTM D975-98b, ASTM D4176-93, ASTM D129-00, ASTM D2622-87, ASTM D287-82, ASTM 6217-98, ASTM D2709-96
- 3)
ASTM D975-98b, Table 1
- 4)
- 5)
EPRI, "Pressurized Water Reactor Primary-to-Secondary Leak Guidelines."
3.2 - Page 5 Amendment No. 229, 246 257
TECHNICAL SPECIFICATIONS TABLE 3-4 MINIMUM FREQUENCIES FOR SAMPLING TESTS Type of Measurement Sample and Analysis and Analysis Frequency
- 1.
Reactor Coolant (a) Power Operation (1) Gross Radioactivity 1 per 3 days (Operating Mode 1)
(Gamma emitters)
(2) Isotopic Analysis for (i) 1 per 14 days DOSE EQUIVALENT I-131 (ii) 1 per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />(1) whenever the radioactivity exceeds 1.0 Ci/gm DOSE EQUIVALENT I-131.
(iii) 1 sample between 2-8 hours following a thermal power change exceeding 15% of the rated thermal power within a 1-hour period.
(3) E Determination 1 per 6 months(2)
(4) Dissolved oxygen 1 per 3 days and chloride (b) Hot Standby (1) Gross Radioactivity 1 per 3 days (Operating Mode 2)
(Gamma emitters)
Hot Shutdown (2) Isotopic Analysis for (i) 1 per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />(1) whenever (Operating Mode 3)
DOSE EQUIVALENT I-131 the radioactivity exceeds 1.0 Ci/gm DOSE EQUIVALENT I-131.
(ii) 1 sample between 2-8 hours following a thermal power change exceeding 15% of the rated thermal power change exceeding 15% of the rated thermal power within a 1-hour period.
(3) Dissolved oxygen 1 per 3 days and chloride 3.2 - Page 6 Amendment No. 28,67,124,133,157 257
TECHNICAL SPECIFICATIONS TABLE 3-4 (Continued)
MINIMUM FREQUENCIES FOR SAMPLING TESTS Type of Measurement Sample and Analysis and Analysis Frequency
- 1.
Reactor Coolant (Continued)
(c)
Cold Shutdown (1) Chloride 1 per 3 days (Operating Mode 4)
(d) Refueling Shutdown (1) Chloride 1 per 3 days(3)
(Operating Mode 5)
(2) Boron Concentration 1 per 3 days(3)
(e) Refueling Operation (1) Chloride 1 per 3 days(3)
(2) Boron Concentration 1 per 3 days(3)
- 2.
SIRW Tank Boron Concentration M
- 3.
Concentrated Boric Boron Concentration W
Acid Tanks
- 4.
SI Tanks Boron Concentration M
- 5.
Spent Fuel Pool Boron Concentration See Footnote 4 below
- 6.
Steam Generator Blowdown Isotopic Analysis for Dose W(5)
(Operating Modes 1 and 2)
Equivalent I-131 (1) Until the radioactivity of the reactor coolant is restored to 1 Ci/gm DOSE EQUIVALENT I-131.
(2) Sample to be taken after a minimum of 2 EFPD and 20 days of power operation have elapsed since reactor was subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
(3) Boron and chloride sampling/analyses are not required when the core has been off-loaded. Reinitiate boron and chloride sampling/analyses prior to reloading fuel into the cavity to assure adequate shutdown margin and allowable chloride levels are met.
(4) Prior to placing unirradiated fuel assemblies in the spent fuel pool or placing fuel assemblies in a spent fuel cask in the spent fuel pool, and weekly when unirradiated fuel assemblies are stored in the spent fuel pool, or every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> when fuel assemblies are in a spent fuel storage cask in the spent fuel pool.
(5) When Steam Generator Dose Equivalent I-131 exceeds 50 percent of the limits in Specification 2.20, the sampling and analysis frequency shall be increased to a minimum of 5 times per week. When Steam Generator Dose Equivalent I-131 exceeds 75 percent of this limit, the sampling and analysis frequency shall be increased to a minimum of once per day.
3.2 - Page 7 Amendment No. 28,67,86,124,133,152 172,188, 239 257
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Frequency Reference
- 1.
Control Element Drop times of all full-length CEA's Prior to reactor criticality after each 7.5.3 Assemblies removal of the reactor vessel closure head
- 2.
Control Element Partial movement of all CEA's Q
7 Assemblies (Minimum of 6 in)
- 3.
Pressurizer Safety Verify each pressurizer safety valve R
7 Valves is OPERABLE in accordance with the Inservice Testing Program. Following testing, lift settings shall be 2485 psig
+/-1% and 2530 psig +/-1% respectively.
- 4.
Main Steam Safety Set Point R
4 Valves
- 5.
DELETED
- 6.
DELETED
- 7.
DELETED 8a.
Reactor Coolant Evaluate D*
4 System Leakage***
8b.
Primary to Secondary Continuous process D*
4 Leakage****
radiation monitors or radiochemical grab sampling 9a Diesel Fuel Supply Fuel Inventory M
8.4 9b.
Diesel Lubricating Oil Lube Oil Inventory M
8.4 Inventory 9c.
Diesel Fuel Oil Test Properties In accordance with the Diesel Fuel 8.4 Properties Oil Testing Program 9d.
Required Diesel Air Pressure M
8.4 Generator Air Start Receiver Bank Pressure 3.2 - Page 8 Amendment No. 15,24,128,160,166,169,171,219,229, 246 257
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS Whenever the system is at or above operating temperature and pressure.
Not applicable to primary to secondary LEAKAGE.
Verify primary to secondary LEAKAGE is 150 gallons per day through any one SG.
This surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
3.2 - Page 9 Amendment No. 246 257
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Frequency Reference 9e.
Check for and Check for Water and Remove Q
8.4 Remove Accumulated Water from Each Fuel Oil Storage Tank 10a.
Charcoal and HEPA
- 1.
In-Place Testing**
9.10 Filters for Control Charcoal adsorbers and HEPA On a refueling frequency or every 720 Room Air Filtration filter banks shall be leak hours of system operation or after each System (CRAFS) tested and show >99.95%
complete or partial replacement of the Freon (R-11 or R-112) and charcoal adsorber/HEPA filter banks, or cold DOP particulates after any major structural maintenance on removal, respectively.
the system housing or following significant painting, fire or chemical releases in a ventilation zone communicating with the system.
- 2.
Laboratory Testing**
Verify, within 31 days after removal, On a refueling frequency or every 720 that a laboratory test of a sample of hours of system operation or after any the charcoal adsorber, when obtained structural maintenance on the HEPA filter or in accordance with Regulatory charcoal adsorber housing or following Position C.6.b of Regulatory Guide significant painting, fire or chemical release in 1.52, Revision 2, March 1978, shows a ventilation zone communicating with the methyliodide penetration less than system.
0.175% when tested in accordance with ASTM D3803-1989 at a temperature of 30C (86F) and a relative humidity of 70%.
- Tests shall be performed in accordance with applicable section(s) of ANSI N510-1980.
3.2 - Page 10 Amendment No. 15,24,128,169,198,229,246 257
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Frequency Reference 10a.
(continued)
- 3.
Overall System Operation
- a.
Each train shall be operated.
Ten continuous hours every month with heaters operating.
- b.
The pressure drop across the R
combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 9 inches of water at system design flow rate.
- c.
Fan shall be shown to operate R
within + 10% design flow.
- 4.
Automatic and manual initiation of R
each train shall be demonstrated.
10b.
Charcoal Adsorbers
- 1. In-Place Testing**
for Spent Fuel Charcoal adsorbers shall be On a refueling frequency or every 720 6.2 Storage Pool Area leak tested and shall show hours of system operation, or after 9.10
>99% Freon (R-11 or R-112) each complete or partial replacement of removal.
the charcoal adsorber bank, or after any major structural maintenance on the system housing or following significant painting, fire or chemical release in a ventilation zone communicating with the system.
- 2.
Laboratory Testing Verify, within 31 days after removal, On a refueling frequency or every 720 that a laboratory test of a sample of hours of system operation or after any the charcoal adsorber, when obtained structural maintenance on the HEPA filter or in accordance with Regulatory charcoal adsorber housing or following Position C.6.b of Regulatory Guide significant painting, fire or chemical release in 1.52, Revision 2, March 1978, shows a ventilation zone communicating with the methyliodide penetration less than system.
10% when tested in accordance with ASTM D3803-1989 at a temperature of 30°C (86°F) and a relative humidity of 95%.
- Tests shall be performed in accordance with applicable section(s) of ANSI N510-1980.
3.2 - Page 11 Amendment No. 15,24,52,128,154,169,198,229, 246 257
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Frequency Reference 10b.
(continued)
- 3.
Overall System Operation
- a.
Operation of each circuit Ten hours every month.
shall be demonstrated.
- b.
Volume flow rate through R
charcoal filter shall be shown to be between 4500 and 12,000 cfm.
- 4.
Manual initiation of the R
system shall be demon-strated.
10c.
Charcoal Adsorbers
- 1.
In-Place Testing**
On a refueling frequency or every 9.10 for S.I. Pump Room Charcoal adsorbers shall be 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation, or 6.2 leak tested and shall show after each complete or partial
>99% Freon (R-11 or R-112) replacement of the charcoal adsorber bank, removal.
or after any major structural maintenance on the system housing or following significant painting, fire or chemical release in any ventilation zone communicating with the system.
- 2.
Laboratory Testing Verify, within 31 days after removal, On a refueling frequency or following 720 that a laboratory test of a sample of hours of system operation or after any the charcoal adsorber, when obtained structural maintenance on the HEPA filter or in accordance with Regulatory charcoal adsorber housing or following Position C.6.b of Regulatory Guide significant painting, fire or chemical release in 1.52, Revision 2, March 1978, shows a ventilation zone communicating with the system.
methyliodide penetration less than 10% when tested in accordance with ASTM D3803-1989 at a temperature of 30°C (86°F) and a relative humidity of 95%.
- 3.
Overall System Operation
- a. Operation of each circuit Ten hours every month.
shall be demonstrated.
- b. Volume flow rate shall be R
shown to be between 3000 and 6000 cfm.
- Tests shall be performed in accordance with applicable section(s) of ANSI N510-1980.
3.2 - Page 12 Amendment No. 15,24,52,128,169,198, 229, 246 257
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Frequency Reference 10c.
(continued)
- 4.
Automatic and/or manual initi-R ation of the system shall be demonstrated.
- 11.
Containment
- 1.
Demonstrate damper action.
1 year, 2 years, 5 years, and every 5 9.10 Ventilation System years thereafter.
Fusible Linked Dampers
- 2.
Test a spare fusible link.
- 12.
Diesel Generator Calibrate R
8.4.3 Under-Voltage Relays
- 13.
Motor Operated Verify the contactor pickup value at R
Safety Injection
<85% of 460 V.
Loop Valve Motor Starters (HCV-311, 314, 317, 320, 327, 329, 331, 333, 312, 315, 318, 321)
- 14.
Pressurizer Heaters Verify control circuits operation R
for post-accident heater use.
- 15.
Spent Fuel Pool Test neutron poison samples for 1, 2, 4, 7, and 10 years after Racks dimensional change, weight, neutron installation, and every 5 years attenuation change and specific thereafter.
gravity change.
- 16.
- 1.
Verify all manual isolation During each refueling outage just Gas Vent System valves in each vent path are prior to plant start-up.
in the open position.
- 2.
Cycle each automatic valve in the R
vent path through at least one complete cycle of full travel from the control room. Verification of valve cycling may be determined by observation of position indicating lights.
- 3.
Verify flow through the reactor R
coolant vent system vent paths.
3.2 - Page 13 Amendment No. 41,54,60,75,77,80,155,169,182,218,229,246 257
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS Test Frequency
- 17.
DELETED
- 18.
- 1.
Verify required shutdown cooling loops are S (when shutdown cooling is required by TS 2.8).
OPERABLE and one shutdown cooling loop is IN OPERATION.
- 2.
Verify correct breaker alignment and indicated W (when shutdown cooling is required by TS 2.8).
power is available to the required shutdown cooling pump that is not IN OPERATION.
3.2 - Page 14 Amendment No. 138,169,188, 246, 250 257
TECHNICAL SPECIFICATIONS TABLE 3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS Test Frequency
- 19.
Refueling Water Level Verify refueling water level is 23 ft. above Prior to commencing, and daily during CORE ALTERATIONS the top of the reactor vessel flange.
and/or REFUELING OPERATIONS inside containment.
- 20.
Spent Fuel Pool Level Verify spent fuel pool water level is 23 ft.
Prior to commencing, and weekly during REFUELING above the top of irradiated fuel assemblies seated OPERATIONS in the spent fuel pool.
in the storage racks.
- 21.
Containment Penetrations Verify each required containment penetration is Prior to commencing, and weekly during CORE ALTERATIONS in the required status.
and/or REFUELING OPERATIONS in containment.
- 22.
Spent Fuel Assembly Verify by administrative means that initial Prior to storing the fuel assembly in Region 2 (including Storage enrichment and burnup of the fuel assembly is in peripheral cells).
accordance with Figure 2-10.
- 23.
P-T Limit Curve Verify RCS Pressure, RCS temperature, and This test is only required during RCS heatup and cooldown RCS heatup and cooldown rates are within operations and RCS inservice leak and hydrostatic testing.
the limits specified by the P-T limit Figure(s)
While these operations are occurring, this test shall be performed shown in the PTLR.
every 30 minutes.
- 24.
Spent Fuel Cask Loading Verify by administrative means that initial Prior to placing the fuel assembly in a spent fuel cask in enrichment and burnup of the fuel assembly the spent fuel pool.
is in accordance with Figure 2-11.
3.2 - Page 15 Amendment No. 188, 221, 239, 246 257
TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.24 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Ventilation System (CRVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
- a.
The definition of the CRE and the CRE boundary.
- b.
Requirements for maintaining CRE boundary in its design condition including configuration control and preventive maintenance.
- c.
Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d.
Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by the CRVS, operating within the tolerance for design flow rate, at a Frequency of 18 months. The results shall be trended and used as part of an 18 month assessment of the CRE boundary.
- e.
The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f.
The provisions of SR 3.0.1 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered leakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
5.0 - Page 21 Amendment No. 257
TECHNICAL SPECIFICATIONS Appendix B-Continued Additional Conditions Renewed Facility Operating License No. DPR-40 Amendment Number Additional Conditions Implementation Date 257 (4) Upon implementation of Amendment No. 257 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by TS 3.1, Table 3-3, Item 10.b. in accordance with TS 5.24c.(i), the assessment of CRE habitability as required by Specification 5.24c.(ii), and the measurement of CRE pressure as required by Specification 5.24d, shall be considered met. Following implementation:
(a) The first performance of TS 3.1, Table 3-3, Item 10.b., in accordance with Specification 5.24c.(i), shall be within the next 18 months as the time period since the most recent successful tracer gas test is greater than 6 years.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.24c(ii), shall be within the next 9 months as the time period since the most recent successful tracer gas test is greater than 3 years.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.24d., shall be within the next 138 days.
The amendment is effective as of the date of its issuance and shall be implemented within 270 days of the date of issuance.
Appendix B - Page 2 Amendment No. 257