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{{#Wiki_filter:}} | {{#Wiki_filter:DCA Part 4 Volume 1 Revision 1.0 Generic Technical Specifications NuScale Nuclear Power Plants Volume 1: Specifications | ||
TABLE OF CONTENTS Revision 1.0 USE AND APPLICATION 1.1 Definitions................................................................................................................. 1.0 1.2 Logical Connectors................................................................................................... 1.0 1.3 Completion Times .................................................................................................... 1.0 1.4 Frequency ................................................................................................................ 1.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs ........................................................................................................................... 1.0 2.1 SL Violations ............................................................................................................ 1.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .............................. 1.0 3.0 SURVEILLANCE REQUIREMENTS (SR) APPLICABILITY .......................................... 1.0 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)............................................................................ 1.0 3.1.2 Core Reactivity ................................................................................................... 1.0 3.1.3 Moderator Temperature Coefficient (MTC) ........................................................ 1.0 3.1.4 Rod Group Alignment Limits .............................................................................. 1.0 3.1.5 Shutdown Group Insertion Limits ....................................................................... 1.0 3.1.6 Regulating Group Insertion Limits ...................................................................... 1.0 3.1.7 Rod Position Indication (RPI) ............................................................................. 1.0 3.1.8 PHYSICS TESTS Exceptions............................................................................. 1.0 3.1.9 Boron Dilution Control ........................................................................................ 1.0 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Enthalpy Rise Hot Channel Factor ..................................................................... 1.0 3.2.2 AXIAL OFFSET (AO).......................................................................................... 1.0 3.3 INSTRUMENTATION 3.3.1 Module Protection System (MPS) Instrumentation............................................. 1.0 3.3.2 Reactor Trip System (RTS) Logic and Actuation................................................ 1.0 3.3.3 Engineered Safety Features Actuation System (ESFAS) Logic and Actuation ..................................................................................................... 1.0 3.3.4 Manual Actuation Functions ............................................................................... 1.0 3.3.5 Remote Shutdown Station (RSS) ....................................................................... 1.0 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Resistance Critical Heat Flux (CHF) | |||
Limits .................................................................................................................. 1.0 3.4.2 RCS Minimum Temperature for Criticality .......................................................... 1.0 3.4.3 RCS Pressure and Temperature (P/T) Limits..................................................... 1.0 3.4.4 Reactor Safety Valves (RSVs) ........................................................................... 1.0 3.4.5 RCS Operational LEAKAGE............................................................................... 1.0 3.4.6 Chemical and Volume Control System (CVCS) Isolation Valves ....................... 1.0 3.4.7 RCS Leakage Detection Instrumentation ........................................................... 1.0 3.4.8 RCS Specific Activity .......................................................................................... 1.0 3.4.9 Steam Generator (SG) Tube Integrity ................................................................ 1.0 3.4.10 Low Temperature Overpressure Protection (LTOP) Valves ............................... 1.0 NuScale i Revision 1.0 | |||
TABLE OF CONTENTS Revision 3.0 LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS (continued) 3.5 PASSIVE CORE COOLING SYSTEMS (PCCS) 3.5.1 Emergency Core Cooling System (ECCS) ......................................................... 1.0 3.5.2 Decay Heat Removal System (DHRS) ............................................................... 1.0 3.5.3 Ultimate Heat Sink .............................................................................................. 1.0 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment ....................................................................................................... 1.0 3.6.2 Containment Isolation Valves ............................................................................. 1.0 3.7 PLANT SYSTEMS 3.7.1 Main Steam Isolation Valves (MSIVs) ................................................................ 1.0 3.7.2 Feedwater Isolation ............................................................................................ 1.0 3.8 REFUELING OPERATIONS 3.8.1 Nuclear Instrumentation ..................................................................................... 1.0 3.8.2 Decay Time ........................................................................................................ 1.0 4.0 DESIGN FEATURES 4.1 Site Location............................................................................................................. 1.0 4.2 Reactor Core ............................................................................................................ 1.0 4.3 Fuel Storage ............................................................................................................. 1.0 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility ........................................................................................................... 1.0 5.2 Organization ............................................................................................................. 1.0 5.3 Facility Staff Qualifications ....................................................................................... 1.0 5.4 Procedures ............................................................................................................... 1.0 5.5 Programs and Manuals ............................................................................................ 1.0 5.6 Reporting Requirements .......................................................................................... 1.0 5.7 High Radiation Area ................................................................................................. 1.0 NuScale ii Revision 1.0 | |||
Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions | |||
---------------------------------------------------------NOTE-------------------------------------------------------------- | |||
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases. | |||
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. | |||
ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be: | |||
: a. The use of diagnostic programs, or application of simulated or actual input combinations, to test digital computer hardware; and | |||
: b. Verification of the required logic output. | |||
An ACTUATION LOGIC TEST shall include each possible interlock logic state required for OPERABILITY of a logic circuit. The ACTUATION LOGIC TEST shall verify the OPERABILITY of each manual logic input device required for channel OPERABILITY. The ACTUATION LOGIC TEST shall be conducted such that it provides component overlap with the actuated device. The ACTUATION LOGIC TEST may be performed by means of any series of sequential, overlapping, or total steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step. | |||
AXIAL OFFSET (AO) AO shall be the difference in power generated in the top half of the core (Ptop) and the bottom half of the core (Pbottom), divided by the sum of the power generated in the core (Ptotal). | |||
AO = (Ptop - Pbottom) / Ptotal NuScale 1.1-1 Revision 1.0 | |||
Definitions 1.1 1.1 Definitions CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY. | |||
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step. | |||
CHANNEL CHECK A CHANNEL CHECK shall be the verification through the absence of alarms from the automatic analog and binary process signal monitoring features used to monitor channel behavior during operation. Deviation beyond the established acceptance criteria is alarmed to allow appropriate action to be taken. This determination shall include, where possible, comparison of channel indication and status to other indications or status derived from the independent channels measuring the same parameter. | |||
This determination can be made using computer software or be performed manually. | |||
CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal TEST (COT) into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step. | |||
NuScale 1.1-2 Revision 1.0 | |||
Definitions 1.1 1.1 Definitions CORE OPERATING LIMITS The COLR is the unit-specific document that provides REPORT (COLR) cycle specific parameter limits for the current reload cycle. | |||
These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Module operation within these parameter limits is addressed in individual Specifications. | |||
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same committed effective dose equivalent as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Table 2.1 of EPA Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, EPA-520/1-88-020, September 1988. | |||
DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same effective dose equivalent as the quantity and isotopic mixture of noble gases (Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138) actually present. The dose conversion factors used for this calculation shall be those listed in Table III.1 of EPA Federal Guidance Report No. 12, External Exposure to Radionuclides in Air, Water, and Soil, EPA 402-R-93-081, September 1993. | |||
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions). The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. | |||
INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f). | |||
NuScale 1.1-3 Revision 1.0 | |||
Definitions 1.1 1.1 Definitions LEAKAGE LEAKAGE shall be: | |||
: a. Identified LEAKAGE | |||
: 1. LEAKAGE from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE, or | |||
: 2. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System (primary to secondary LEAKAGE), | |||
: b. Unidentified LEAKAGE All LEAKAGE that is not identified LEAKAGE, and | |||
: c. Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in a RCS component body, pipe wall, or vessel wall. A fault in an RCS component body, pipe wall, or vessel wall is isolated if LEAKAGE through the isolation device is 0.5 gpm per nominal inch of valve size up to a maximum limit of 5 gpm. | |||
MODE A MODE shall correspond to any one inclusive combination of Reactivity Condition, Reactor Coolant Temperature, control rod assembly (CRA) capability, Chemical and Volume Control System (CVCS) and Containment Flood and Drain System (CFDS) configuration, and reactor vessel flange bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel. | |||
OPERABLE-OPERABILITY A system, subsystem, separation group, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, electrical power, cooling water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s). | |||
NuScale 1.1-4 Revision 1.0 | |||
Definitions 1.1 1.1 Definitions PASSIVELY COOLED - A module is in PASSIVE COOLING or is being PASSIVE COOLING PASSIVELY COOLED when: | |||
: a. Two or more reactor vent valves are open and one or more reactor recirculation valves is open, or | |||
: b. One or more trains of DHRS is in operation, or | |||
: c. Water level in the containment vessel is > 45 ft. | |||
PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are: | |||
: a. Described in Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, of the FSAR; | |||
: b. Authorized under the provisions of 10 CFR 50.59; or | |||
: c. Otherwise approved by the Nuclear Regulatory Commission. | |||
PRESSURE AND The PTLR is the unit-specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.4. | |||
RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 160 MWt. | |||
NuScale 1.1-5 Revision 1.0 | |||
Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming: | |||
: a. Moderator temperature is 420°F; and | |||
: b. All CRAs are fully inserted except for the single assembly of highest reactivity worth, which is assumed to be fully withdrawn. However, with all CRAs verified fully inserted by two independent means, it is not necessary to account for a stuck CRA in the SDM calculation. With any CRA(s) not capable of being fully inserted, the reactivity worth of these assemblies must be accounted for in the determination of SDM. | |||
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. | |||
NuScale 1.1-6 Revision 1.0 | |||
Definitions 1.1 Table 1.1-1 (page 1 of 1) | |||
MODES INDICATED REACTOR REACTIVITY COOLANT MODE TITLE CONDITION (keff) TEMPERATURES (°F) 1 Operations 0.99 All 420 2 Hot Shutdown < 0.99 Any 420 3 Safe Shutdown (a) < 0.99 All < 420 4 Transition (b)(c) < 0.95 N/A 5 Refueling (d) N/A N/A (a) Any CRA capable of withdrawal, any CVCS or CFDS connection to the module not isolated. | |||
(b) All CRAs incapable of withdrawal, CVCS and CFDS connections to the module isolated, and all reactor vent valves electrically isolated. | |||
(c) All reactor vessel flange bolts fully tensioned. | |||
(d) One or more reactor vessel flange bolts less than fully tensioned. | |||
NuScale 1.1-7 Revision 1.0 | |||
Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors. | |||
Logical connectors are used in Technical Specifications to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in Technical Specifications are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meaning. | |||
BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). | |||
The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors. | |||
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency. | |||
EXAMPLES The following examples illustrate the use of logical connectors. | |||
NuScale 1.2-1 Revision 1.0 | |||
Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued) | |||
EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify AND A.2 Restore In this example, the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed. | |||
NuScale 1.2-2 Revision 1.0 | |||
Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued) | |||
EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip OR A.2.1 Verify AND A.2.2.1 Reduce OR A.2.2.2 Perform OR A.3 Align This example represents a more complicated use of logical connectors. | |||
Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed. | |||
NuScale 1.2-3 Revision 1.0 | |||
Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use. | |||
BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s). | |||
DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the discovery of a situation (e.g., | |||
inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO. | |||
Unless otherwise specified, the Completion Time begins when a senior licensed operator on the operating shift crew with responsibility for plant operations makes the determination that an LCO is not met and an ACTIONS Condition is entered. The "otherwise specified" exceptions are varied, such as a Required Action Note or Surveillance Requirement Note that provides an alternative time to perform specific tasks, such as testing, without starting the Completion Time. While utilizing the Note, should a Condition be applicable for any reason not addressed by the Note, the Completion Time begins. Should the time allowance in the Note be exceeded, the Completion Time begins at that point. | |||
Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability. | |||
If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified. | |||
NuScale 1.3-1 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued) | |||
Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition, unless otherwise specified. | |||
However, when a subsequent train, subsystem, component, or variable, expressed in the Condition, is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability: | |||
: a. Must exist concurrent with the first inoperability; and | |||
: b. Must remain inoperable or not within limits after the first inoperability is resolved. | |||
The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either: | |||
: a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours; or | |||
: b. The stated Completion Time as measured from discovery of the subsequent inoperability. | |||
The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications. | |||
The above Completion Time extension does not apply to a Completion Time with a modified time zero. This modified time zero may be expressed as a repetitive time (i.e., once per 8 hours, where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase from discovery .... | |||
NuScale 1.3-2 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions. | |||
EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action B.1 Be in MODE 2. 6 hours and associated Completion AND Time not met. | |||
B.2 Be in MODE 3. 36 hours Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered. | |||
The Required Actions of Condition B are to be in MODE 2 within 6 hours AND in MODE 3 in 36 hours. A total of 6 hours is allowed for reaching MODE 2 and a total of 36 hours (not 42 hours) is allowed for reaching MODE 3 from the time that Condition B was entered. If MODE 2 is reached within 3 hours, the time allowed for reaching MODE 3 is the next 33 hours because the total time allowed for reaching MODE 3 is 36 hours. | |||
If Condition B is entered while in MODE 2, the time allowed for reaching MODE 3 is the next 36 hours. | |||
NuScale 1.3-3 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) | |||
EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One valve A.1 Restore valve to 7 days inoperable. OPERABLE status. | |||
B. Required Action B.1 Be in MODE 2. 6 hours and associated Completion AND Time not met. | |||
B.2 Be in MODE 3. 36 hours When a valve is declared inoperable, Condition A is entered. If the valve is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion time clocks for Required Actions B.1 and B.2 start. If the inoperable valve is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated. | |||
When a second valve is declared inoperable while the first valve is still inoperable, Condition A is not re-entered for the second valve. LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable valve. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered. | |||
While in LCO 3.0.3, if one of the inoperable valves is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A. | |||
While in LCO 3.0.3, if one of the inoperable valves is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired. | |||
NuScale 1.3-4 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) | |||
On restoring one of the valves to OPERABLE status the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. This Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. | |||
A 24 hour extension to the stated 7 days is allowed, provided this does not result in the second valve being inoperable for > 7 days. | |||
EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X A.1 Restore Function 7 days train X train to inoperable. OPERABLE status. | |||
B. One Function Y B.1 Restore Function Y 72 hours train train to inoperable. OPERABLE status. | |||
C. One Function X C.1 Restore Function 72 hours train X train to inoperable. OPERABLE status. | |||
AND OR One Function Y train C.2 Restore Function Y 72 hours inoperable. train to OPERABLE status. | |||
NuScale 1.3-5 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) | |||
When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered). | |||
If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A). | |||
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended. | |||
NuScale 1.3-6 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) | |||
EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours valves OPERABLE status. | |||
inoperable. | |||
B. Required B.1 Be in MODE 2. 6 hours Action and associated AND Completion Time not met. B.2 Be in MODE 3. 36 hours A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times. | |||
Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours provided this does not result in any subsequent valve being inoperable for > 4 hours. | |||
If the Completion Time of 4 hours (including the extension) expires while one or more valves are still inoperable, Condition B is entered. | |||
NuScale 1.3-7 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) | |||
EXAMPLE 1.3-5 ACTIONS | |||
-------------------------------------------NOTE---------------------------------------------- | |||
Separate Condition entry is allowed for each inoperable valve. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours valves OPERABLE inoperable. status. | |||
B. Required B.1 Be in MODE 2. 6 hours Action and associated AND Completion Time not met. B.2 Be in MODE 3. 36 hours The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was only applicable to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table. | |||
The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve. | |||
If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve which caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve. Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply. | |||
NuScale 1.3-8 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) | |||
EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per 8 hours inoperable. SR 3.x.x.x. | |||
OR A.2 Reduce THERMAL 8 hours POWER to 50% | |||
RTP. | |||
B. Required Action B.1 Be in MODE 2. 6 hours and associated Completion Time not met. | |||
Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a once per Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hours interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour interval. If Required Action A.1 is followed, and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2), | |||
Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours is not met, Condition B is entered. | |||
If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A. | |||
NuScale 1.3-9 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) | |||
EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem A.1 Verify affected 1 hour inoperable. subsystem isolated. AND Once per 8 hours thereafter AND A.2 Restore subsystem 72 hours to OPERABLE status. | |||
B. Required Action B.1 Be in MODE 2. 6 hours and associated Completion AND Time not met. | |||
B.2 Be in MODE 3. 36 hours Required Action A.1 has two Completion Times. The 1 hour Completion Time begins at the time the Condition is entered and each Once per 8 hours thereafter interval begins upon performance of Required Action A.1. | |||
NuScale 1.3-10 Revision 1.0 | |||
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) | |||
If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour, or any subsequent 8 hour interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired. | |||
IMMEDIATE When Immediately is used as a Completion Time, the Required Action COMPLETION should be pursued without delay and in a controlled manner. | |||
TIME NuScale 1.3-11 Revision 1.0 | |||
Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements. | |||
DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR. | |||
The specified Frequency is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) | |||
Applicability. The specified Frequency consists of the requirements of the Frequency column of each SR as well as certain Notes in the Surveillance column that modify performance requirements. | |||
Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are otherwise stated conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillances, or both. | |||
Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only required when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction. | |||
The use of met or performed in these instances conveys specific meanings. A Surveillance is met only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not met. Performance refers only to the requirement to specifically determine the ability to meet the acceptance criteria. | |||
Some Surveillances contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied: | |||
NuScale 1.4-1 Revision 1.0 | |||
Frequency 1.4 1.4 Frequency DESCRIPTION (continued) | |||
: a. The Surveillance is not required to be met in the MODE or other specified condition to be entered; or | |||
: b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to be failed; or | |||
: c. The Surveillance is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed. | |||
Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations. | |||
EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1 and 2. | |||
EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours, an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR in not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside the specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable. | |||
NuScale 1.4-2 Revision 1.0 | |||
Frequency 1.4 1.4 Frequency EXAMPLES (continued) | |||
If the interval specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable. | |||
EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours after 25% RTP AND 24 hours thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector AND indicates that both Frequency requirements must be met. Each time the reactor power is increased from a power level | |||
< 25% RTP to 25% RTP, the Surveillance must be performed within 12 hours. | |||
The use of once indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by AND). | |||
This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2. Thereafter indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the once performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP. | |||
NuScale 1.4-3 Revision 1.0 | |||
Frequency 1.4 1.4 Frequency EXAMPLES (continued) | |||
EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY | |||
-----------------------------NOTE------------------------- | |||
Not required to be performed until 12 hours after 25% RTP. | |||
Perform channel adjustment. 7 days The interval continues, whether or not the unit operation is < 25% RTP between performances. | |||
As the Note modifies the required performance of the Surveillance, it is construed to be part of the specified Frequency. Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours after power reaches 25% RTP to perform the Surveillance. | |||
The Surveillance is still considered to be performed within the specified Frequency. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was | |||
< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours (plus the extension allowed by SR 3.0.2) with power 25% RTP. | |||
Once the unit reaches 25% RTP, 12 hours would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply. | |||
NuScale 1.4-4 Revision 1.0 | |||
Frequency 1.4 1.4 Frequency EXAMPLES (continued) | |||
EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY | |||
-----------------------------NOTE------------------------- | |||
Only required to be met in MODE 1. | |||
Verify leakage rates are within limits. 24 hours Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an otherwise stated exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour interval (plus the extension allowed by SR 3.0.2), but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour Frequency were not met), SR 3.0.4 would require satisfying the SR. | |||
NuScale 1.4-5 Revision 1.0 | |||
Frequency 1.4 1.4 Frequency EXAMPLES (continued) | |||
EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY | |||
-----------------------------NOTE------------------------- | |||
Only required to be performed in MODE 1. | |||
Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1 or 2 (the assumed Applicability of the associated LCO) between performances. | |||
As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the specified Frequency. Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODE 2 to perform the Surveillance. | |||
The Surveillance is still considered to be performed within the specified Frequency if completed prior to entering MODE 1. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1. | |||
Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance were not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply. | |||
NuScale 1.4-6 Revision 1.0 | |||
Frequency 1.4 1.4 Frequency EXAMPLES (continued) | |||
EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY | |||
-----------------------------NOTE------------------------- | |||
Not required to be met in MODE 2. | |||
Verify parameter is within limits. 24 hours Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 2 (the assumed Applicability of the associated LCO is MODES 1 and 2). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an otherwise stated exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 2, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 2, even with the 24 hour Frequency exceeded, provided the MODE change does not result in entry into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour Frequency were not met), SR 3.0.4 would require satisfying the SR. | |||
NuScale 1.4-7 Revision 1.0 | |||
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODE 1 the critical heat flux ratio shall be maintained the 95/95 critical heat flux ratio criterion for the critical heat flux correlation(s) specified in Section 5.6.3. | |||
2.1.1.2 In MODE 1 the peak fuel centerline temperature shall be maintained 4901 - (1.37E-3 x Burnup, MWD/MTU) °F. | |||
2.1.2 RCS Pressure SL In MODES 1, 2, and 3 pressurizer pressure shall be maintained 2285 psia. | |||
2.2 Safety Limit Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 2 within 1 hour. | |||
2.2.2 If SL 2.1.2 is violated: | |||
2.2.2.1 In MODE 1, restore compliance and be in MODE 2 within 1 hour. | |||
2.2.2.2 In MODE 2 or 3, restore compliance within 5 minutes. | |||
NuScale 2.0-1 Revision 1.0 | |||
LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, [and] LCO 3.0.7[, | |||
and LCO 3.0.8]. | |||
LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and 3.0.6. | |||
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated. | |||
LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour to place the unit, as applicable, in: | |||
: a. MODE 2 within 7 hours; and | |||
: b. MODE 3 and PASSIVELY COOLED within 37 hours. | |||
Exceptions to this Specification are stated in the individual Specifications. | |||
Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required. | |||
LCO 3.0.3 is only applicable in MODES 1 and 2, and in MODE 3 when not PASSIVELY COOLED. | |||
LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made: | |||
: a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; NuScale 3.0-1 Revision 1.0 | |||
LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 (continued) | |||
: b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate (exceptions to this Specification are stated in the individual Specifications); or | |||
: c. When an allowance is stated in the individual value, parameter, or other Specification. | |||
This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. | |||
LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY. | |||
LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. | |||
Only the support system LCO ACTIONS are required to be entered. | |||
This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.8, Safety Function Determination Program (SFDP). If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. | |||
When a support systems Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2. | |||
NuScale 3.0-2 Revision 1.0 | |||
LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.7 Test Exception LCO 3.1.8 allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. | |||
When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications. | |||
[ ------------------------------ REVIEWERS NOTE ------------------------------------ | |||
A COL applicant who wants to adopt LCO 3.0.8 must perform or reference a risk assessment for the NuScale design that has been submitted to the NRC, and that was prepared consistent with the bounding generic risk assessment provided in TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System OPERABILITY, Revision 2-A. | |||
------------------------------------------------------------------------------------------------ ] | |||
[LCO 3.0.8 When one or more required barriers are unable to perform their related support function(s), any supported system LCO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support function(s), and risk is assessed and managed. This Specification may be concurrently applied to more than one train or subsystem of a multiple train or subsystem supported system provided at least one train or subsystem of the supported system is OPERABLE and the barriers supporting each of these trains or subsystems provide their related support function(s) for different categories of initiating events. | |||
If the required OPERABLE train or subsystem becomes inoperable while this Specification is in use, it must be restored to OPERABLE status within 24 hours or the provisions of this Specification cannot be applied to the trains or subsystems supported by the barriers that cannot perform their related support function(s). | |||
At the end of the specified period, the required barriers must be able to perform their related support function(s) or the supported system LCO(s) shall be declared not met.] | |||
NuScale 3.0-3 Revision 1.0 | |||
SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENTS (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified Conditions in the applicability of individual LCOs, unless otherwise stated in the SR. | |||
Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be a failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. | |||
SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. | |||
For Frequencies specified as once, the above interval extension does not apply. | |||
If a Completion Time requires periodic performance on a once per... | |||
basis, the above Frequency extension applies to each performance after the initial performance. | |||
Exceptions to this Specification are stated in the individual Specifications. | |||
SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery up to 24 hours or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. The delay period is only applicable when there is a reasonable expectation the Surveillance will be met when performed. | |||
A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed. | |||
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. | |||
When the Surveillance is performed within the delay period, and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. | |||
NuScale 3.0-4 Revision 1.0 | |||
SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of a LCO shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4. | |||
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. | |||
NuScale 3.0-5 Revision 1.0 | |||
SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) | |||
LCO 3.1.1 SDM shall be within the limits specified in the COLR. | |||
APPLICABILITY: MODE 1 with keff < 1.0, MODES 2, 3, and 4. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits. A.1 Initiate boration to restore 15 minutes SDM to within limits. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 ------------------------------NOTE-------------------------------- | |||
Not required to be performed in MODE 4. | |||
Verify SDM to be within limits specified in the COLR. In accordance with the Surveillance Frequency Control Program NuScale 3.1.1-1 Revision 1.0 | |||
Core Reactivity 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity LCO 3.1.2 The core reactivity balance shall be within +/-1% k/k of the normalized predicted values. | |||
APPLICABILITY: MODE 1. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity balance A.1 Re-evaluate core design and 7 days not within limit. safety analysis and determine that the reactor core is acceptable for continued operation. | |||
AND A.2 Establish appropriate 7 days operating restrictions. | |||
B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time not met. | |||
NuScale 3.1.2-1 Revision 1.0 | |||
Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ------------------------------NOTE-------------------------------- | |||
Predicted reactivity values may be adjusted to correspond to measured core reactivity prior to exceeding a fuel burnup of 60 effective full power days (EFPD) after each fuel loading. | |||
Verify overall core reactivity balance is within Once prior to | |||
+/-1% k/k of predicted values. exceeding 5% | |||
RTP after each refueling AND | |||
--------NOTE-------- | |||
Only required after 60 EFPD In accordance with the Surveillance Frequency Control Program NuScale 3.1.2-2 Revision 1.0 | |||
MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC) | |||
LCO 3.1.3 MTC shall be within limits specified in the COLR. | |||
APPLICABILITY: MODE 1 for upper MTC limit, MODES 1 and 2 for lower MTC limit, MODE 3 with any RCS temperature 200°F for lower MTC limit. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within limits. A.1 Be in MODE 2. 6 hours B. MTC not within lower B.1 Be in MODE 3 with all 48 hours limit. RCS temperatures | |||
< 200°F. | |||
NuScale 3.1.3-1 Revision 1.0 | |||
MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within the upper limit. Once prior to exceeding 5% | |||
RTP after each fuel loading SR 3.1.3.2 Verify MTC is within the lower limit. Once within 7 effective full power days (EFPDs) after reaching 40 EFPDs fuel burnup from beginning of cycle (BOC) | |||
AND Once within 7 EFPDs after reaching 2/3 fuel burnup from BOC AND | |||
--------NOTE------ | |||
Only required when projected end of cycle MTC is not within limit 7 EFPDs thereafter NuScale 3.1.3-2 Revision 1.0 | |||
Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and regulating control rod assemblies (CRAs) shall be OPERABLE. | |||
AND Individual CRA positions shall be within 6 steps of their group position. | |||
APPLICABILITY: MODE 1. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more CRAs A.1.1 Verify SDM to be within 1 hour inoperable. limits specified in the COLR. | |||
OR OR One or more CRAs not within alignment limits. A.1.2 Initiate boration to restore 1 hour SDM to within limit. | |||
AND A.2 Be in MODE 2. 6 hours NuScale 3.1.4-1 Revision 1.0 | |||
Rod Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 -----------------------------NOTE------------------------------- | |||
Not required to be performed for rods associated with an inoperable rod position indicator. | |||
Verify position of individual CRAs within alignment In accordance limit. with the Surveillance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement (trippability) by In accordance moving each rod not fully inserted in the with the core 4 steps in either direction. Surveillance Frequency Control Program SR 3.1.4.3 Verify each CRA drop time 2.2 seconds. Prior to reactor criticality after each removal of the upper reactor pressure vessel section NuScale 3.1.4-2 Revision 1.0 | |||
Shutdown Group Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Group Insertion Limits LCO 3.1.5 Each shutdown group shall be within insertion limits specified in the COLR. | |||
----------------------------------------NOTE------------------------------------------------- | |||
Not applicable to shutdown groups inserted while performing SR 3.1.4.2. | |||
APPLICABILITY: MODE 1. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Shutdown group not A.1.1 Verify SDM is within the 1 hour within limits. limits specified in the COLR. | |||
OR A.1.2 Initiate boration to restore 1 hour SDM to within limit. | |||
AND A.2 Restore shutdown group 2 hours to within limits. | |||
B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time not met. | |||
NuScale 3.1.5-1 Revision 1.0 | |||
Shutdown Group Insertion Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown group is within the insertion In accordance limits specified in the COLR. with the Surveillance Frequency Control Program NuScale 3.1.5-2 Revision 1.0 | |||
Regulating Group Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Regulating Group Insertion Limits LCO 3.1.6 Each regulating group shall be within the insertion limits specified in the COLR. | |||
--------------------------------------------NOTE--------------------------------------------- | |||
Not applicable to regulating groups inserted while performing SR 3.1.4.2. | |||
APPLICABILITY: MODE 1 with keff 1.0. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Regulating group A.1.1 Verify SDM is within the 1 hour insertion limits not met. limits specified in the COLR. | |||
OR A.1.2 Initiate boration to restore 1 hour SDM to within limits. | |||
AND A.2 Restore regulating group 2 hours to within limits. | |||
B. Required Action and B.1 Be in MODE 1 with 6 hours associated Completion keff < 1.0. | |||
Time not met. | |||
NuScale 3.1.6-1 Revision 1.0 | |||
Regulating Group Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify each regulating group is within the insertion In accordance with limits specified in the COLR. the Surveillance Frequency Control Program NuScale 3.1.6-2 Revision 1.0 | |||
Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication (RPI) | |||
LCO 3.1.7 The Control Rod Drive System (CRDS) Rod Position Indication (RPI) | |||
System and the Control Rod Assembly (CRA) Counter Position Indication (CPI) System shall be OPERABLE. | |||
APPLICABILITY: MODE 1. | |||
ACTIONS | |||
----------------------------------------------------------NOTE------------------------------------------------------------- | |||
Separate Condition entry is allowed for each inoperable CRDS rod position indicator and each CRA counter position indicator. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One RPI per CRDM A.1 Verify the position of the Once per 8 hours inoperable for one or CRA with inoperable more CRDMs. position indicators with the Module Control System (MCS). | |||
B. More than one RPI per B.1 Place the CRA under Immediately CRDM inoperable. manual control. | |||
AND B.2 Verify the position of the Once per 8 hours CRA with inoperable CRDS position indicators indirectly by using the incore detectors. | |||
AND NuScale 3.1.7-1 Revision 1.0 | |||
Rod Position Indication 3.1.7 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Restore inoperable rod 24 hours position indicators to OPERABLE status such that a maximum of one RPI per CRDM is inoperable. | |||
C. One or more control C.1 Verify the position of the 4 hours rod drive mechanisms CRA with inoperable (CRDMs) with position indicators by inoperable position using the MCS. | |||
indicators have been moved in excess of 6 steps in one direction since the last determination of the CRAs position. | |||
D. CRA CPI position D.1 Verify by administrative Once per 8 hours indicator inoperable for means all RPIs for the one or more CRAs. affected groups are OPERABLE. | |||
AND D.2 Verify the most withdrawn Once per 8 hours CRA and the least withdrawn CRA of the affected groups are 6 steps apart. | |||
E. Required Action and E.1 Be in MODE 2. 6 hours associated Completion Time not met. | |||
NuScale 3.1.7-2 Revision 1.0 | |||
Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each RPI agrees within 6 steps of the group Prior to criticality demand position for the full indicated range of CRA after coupling of travel. one or more CRA to the associated CRDM NuScale 3.1.7-3 Revision 1.0 | |||
PHYSICS TESTS Exceptions 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of: | |||
LCO 3.1.3, Moderator Temperature Coefficient (MTC), | |||
LCO 3.1.4, Rod Group Alignment Limits, LCO 3.1.5, Shutdown Group Insertion Limits, and LCO 3.1.6, Regulating Group Insertion Limits may be suspended provided: | |||
: a. SDM is within the limits specified in the COLR, and | |||
: b. THERMAL POWER is 5% RTP. | |||
APPLICABILITY: During PHYSICS TESTS initiated in MODE 1. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit. | |||
AND A.2 Suspend PHYSICS TESTS 1 hour exceptions. | |||
B. THERMAL POWER not B.1 Open reactor trip breakers. Immediately within limit. | |||
NuScale 3.1.8-1 Revision 1.0 | |||
PHYSICS TESTS Exceptions 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Verify THERMAL POWER is 5% RTP. In accordance with the Surveillance Frequency Control Program SR 3.1.8.2 Verify SDM is within the limits specified in the In accordance COLR. with the Surveillance Frequency Control Program NuScale 3.1.8-2 Revision 1.0 | |||
Boron Dilution Control 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 Boron Dilution Control LCO 3.1.9 Two CVCS demineralized water isolation valves shall be OPERABLE. | |||
AND Boric Acid Storage Tank boron concentration shall be within the limits specified in the COLR. | |||
AND Maximum CVCS makeup pump demineralized water flow path flowrate is within the limits specified in the COLR. | |||
APPLICABILITY: MODES 1, 2, and 3. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CVCS A.1 Restore CVCS 72 hours demineralized water demineralized water isolation valve isolation valves to inoperable. OPERABLE status. | |||
NuScale 3.1.9-1 Revision 1.0 | |||
Boron Dilution Control 3.1.9 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 --------------NOTE------------ | |||
associated Completion Flow path(s) may be Time not met. unisolated intermittently under administrative OR controls. | |||
Two CVCS demineralized water Isolate dilution source flow 1 hour isolation valves paths in the CVCS inoperable. makeup line by use of at least one closed manual or OR one closed and de-activated automatic valve. | |||
Boric Acid Storage Tank not within limits. | |||
OR CVCS makeup pump demineralized water flow path not configured to ensure maximum flowrate is within limits. | |||
NuScale 3.1.9-2 Revision 1.0 | |||
Boron Dilution Control 3.1.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify that CVCS makeup pump demineralized In accordance water flow path is configured to ensure that it with the remains within the limits specified in the COLR. Surveillance Frequency Control Program SR 3.1.9.2 Verify each automatic CVCS demineralized water In accordance isolation valve that is not locked, sealed, or with the otherwise secured in the isolated position, actuates Surveillance to the isolated position on an actual or simulated Frequency signal except for valves that are open under Control Program administrative controls. | |||
SR 3.1.9.3 Verify Boric Acid Storage Tank boron concentration In accordance to be within the limits specified in the COLR. with the Surveillance Frequency Control Program SR 3.1.9.4 Verify each CVCS makeup pump maximum In accordance flowrate is 25 gpm. with the Surveillance Frequency Control Program NuScale 3.1.9-3 Revision 1.0 | |||
FH 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Enthalpy Rise Hot Channel Factor ( F H ) | |||
LCO 3.2.1 FH shall be within the limits specified in the COLR. | |||
APPLICABILITY: MODE 1 with THERMAL POWER 25% RTP. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. FH not within limit. A.1 Reduce THERMAL POWER 6 hours to < 25% RTP. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify FH within limits specified in the COLR. Once after each refueling prior to THERMAL POWER exceeding 25% RTP AND In accordance with the Surveillance Frequency Control Program NuScale 3.2.1-1 Revision 1.0 | |||
AO 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 AXIAL OFFSET (AO) | |||
LCO 3.2.2 The AO shall be maintained within the limits specified in the COLR. | |||
APPLICABILITY: MODE 1 with THERMAL POWER 25% RTP. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AO not within limits. A.1 Reduce THERMAL POWER 6 Hours to < 25% RTP. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify AO within limits using all OPERABLE in-core In accordance instrumentation channels. with the Surveillance Frequency Control Program NuScale 3.2.2-1 Revision 1.0 | |||
MPS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Module Protection System (MPS) Instrumentation LCO 3.3.1 MPS instrumentation channels required for each Function in Table 3.3.1-1 shall be OPERABLE. | |||
APPLICABILITY: According to Table 3.3.1-1. | |||
ACTIONS | |||
---------------------------------------------------------NOTE-------------------------------------------------------------- | |||
Separate Condition entry is allowed for each Function. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place inoperable channel in 6 hours with one channel bypass or trip. | |||
inoperable. | |||
B. One or more Functions B.1 Place one inoperable 6 hours with two channels channel in bypass. | |||
inoperable. | |||
AND B.2 Place one inoperable 6 hours channel in trip. | |||
C. Required Action and C.1 Enter Condition referenced Immediately associated Completion in Table 3.3.1-1 for the Time of Condition A or B channel(s). | |||
not met. | |||
OR One or more Functions with three or more channels inoperable. | |||
NuScale 3.3.1-1 Revision 1.0 | |||
MPS Instrumentation 3.3.1 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Open reactor trip breakers. 6 hours Action C.1 and referenced in Table 3.3.1-1. | |||
E. As required by Required E.1 Reduce THERMAL POWER 6 hours Action C.1 and to below the N-2L interlock. | |||
referenced in Table 3.3.1-1. | |||
F. As required by Required F.1 --------------NOTE---------------- | |||
Action C.1 and CVCS flow path(s) may be referenced in unisolated intermittently Table 3.3.1-1. under administrative controls. | |||
Isolate the CVCS flow to the 6 hours Reactor Coolant System (RCS). | |||
G. As required by Required G.1 Open pressurizer heater 6 hours Action C.1 and breakers. | |||
referenced in Table 3.3.1-1. | |||
H. As required by Required H.1 Isolate demineralized water 1 hour Action C.1 and flow path to RCS. | |||
referenced in Table 3.3.1-1. | |||
I. As required by Required I.1 Be in MODE 2. 6 hours Action C.1 and referenced in AND Table 3.3.1-1. | |||
I.2 Be in MODE 3 and 36 hours PASSIVELY COOLED. | |||
NuScale 3.3.1-2 Revision 1.0 | |||
MPS Instrumentation 3.3.1 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required J.1 Open two reactor vent 1 hour Action C.1 and valves. | |||
referenced in Table 3.3.1-1. | |||
K. As required by Required K.1 Be in MODE 2. 6 hours Action C.1 and referenced in AND Table 3.3.1-1. | |||
K.2 Be in MODE 3. 36 hours L. As required by Required L.1 Be in MODE 2. 6 hours Action C.1 and referenced in AND Table 3.3.1-1. | |||
L.2 Be in MODE 3 with RCS 48 hours temperature below the T-2 interlock. | |||
M. As required by Required M.1 Be in MODE 2. 72 hours Action C.1 and referenced in AND Table 3.3.1-1. | |||
M.2 Be in MODE 3 and 96 hours PASSIVELY COOLED. | |||
AND M.3 Be in MODE 3 with RCS 96 hours temperaturebelow the T-2 interlock. | |||
AND NuScale 3.3.1-3 Revision 1.0 | |||
MPS Instrumentation 3.3.1 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME M. (continued) M.4 Isolate demineralized water 96 hours flow to the reactor coolant system. | |||
AND M.5 Open pressurizer heater 96 hours breakers. | |||
N. As required by Required N.1 Be in MODE 2. 6 hours Action C.1 and referenced in AND Table 3.3.1-1. | |||
N.2.1 Be in MODE 3 with RCS 48 hours temperature below the T-2 interlock. | |||
OR N.2.2 Be in MODE 3 with 48 hours Containment Water Level above the L-1 interlock. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK on each required In accordance with channel listed in Table 3.3.1-1. the Surveillance Frequency Control Program NuScale 3.3.1-4 Revision 1.0 | |||
MPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.3.1.2 -------------------------------NOTES--------------------------- | |||
: 1. Adjust Neutron Monitoring System (NMS) nuclear instrument channel when absolute difference is | |||
> 1% RTP. | |||
: 2. Not required to be performed until 12 hours after reaching 15% RTP. | |||
: 3. If the calorimetric heat balance is < 15% RTP, and if NMS nuclear instrumentation channel indicated power is: | |||
: a. lower than the calorimetric measurement by | |||
> 1%, then adjust the NMS nuclear instrumentation channel upward to match the calorimetric measurement. | |||
: b. higher than the calorimetric measurement, then no adjustment is required. | |||
Compare results of calorimetric heat balance to NMS In accordance with nuclear instrument channel output. the Surveillance Frequency Control Program SR 3.3.1.3 -------------------------------NOTE----------------------------- | |||
Neutron detectors are excluded from response time testing. | |||
Verify channel RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program NuScale 3.3.1-5 Revision 1.0 | |||
MPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.3.1.4 -------------------------------NOTE----------------------------- | |||
Neutron detectors are excluded from the CHANNEL CALIBRATION. | |||
Perform CHANNEL CALIBRATION on each In accordance with required channel listed in Table 3.3.1-1. the Surveillance Frequency Control Program SR 3.3.1.5 Verify associated Class 1E isolation devices are In accordance with OPERABLE. the Surveillance Frequency Control Program. | |||
NuScale 3.3.1-6 Revision 1.0 | |||
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 7) | |||
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS | |||
: 1. High Power Range Linear Power (a) (a) | |||
: a. RTS 1, 2 , 3 4 D (a) (a) | |||
: b. DWSI 1, 2 , 3 4 H | |||
: 2. High Power Range Positive and Negative Rate (b) | |||
: a. RTS 1 4 E (b) | |||
: b. DWSI 1 4 H | |||
: 3. High Intermediate Range Log Power Rate (c) (a) (a) | |||
: a. RTS 1 ,2 ,3 4 D (c) (a) (a) | |||
: b. DWSI 1 ,2 ,3 4 H | |||
: 4. High Source Range Count Rate (d) (a) (a) | |||
: a. RTS 1 ,2 ,3 4 D (d) (a) (a) | |||
: b. DWSI 1 ,2 ,3 4 H | |||
: 5. High Source Range Log Power Rate (d) (a) (a) | |||
: a. RTS 1 ,2 ,3 4 D (d) (a) (a) | |||
: b. DWSI 1 ,2 ,3 4 H | |||
: 6. High Subcritical Multiplication (d) (a) (a) | |||
: a. DWSI 1 ,2 ,3 4 H (a) When capable of CRA withdrawal. | |||
(b) Above the N-2H Interlock. | |||
(c) Below the N-2L Interlock. | |||
(d) When Intermediate Range Log Power less than N-1 interlock. | |||
NuScale 3.3.1-7 Revision 1.0 | |||
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 7) | |||
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS | |||
: 7. High Pressurizer Pressure (a) (a) | |||
: a. RTS 1, 2 , 3 4 D (e) | |||
: b. DHRS 1, 2, 3 4 I (f) (f) | |||
: c. Pressurizer Heater Trip 1, 2 , 3 4 G (a) (a) | |||
: d. DWSI 1, 2 , 3 4 H | |||
: 8. Low Pressurizer Pressure (g) | |||
: a. RTS 1 4 D (g) | |||
: b. DHRS 1 4 D (g) | |||
: c. CVCSI 1 4 F (g) | |||
: d. Pressurizer Heater Trip 1 4 G (g) | |||
: e. DWSI 1 4 H | |||
: 9. Low Low Pressurizer Pressure (a) | |||
: a. RTS 1, 2 4 D | |||
: b. DHRS 1, 2 4 I | |||
: c. CVCSI 1, 2 4 F | |||
: d. Pressurizer Heater Trip 1, 2 4 G (a) | |||
: e. DWSI 1, 2 4 H (a) When capable of CRA withdrawal. | |||
(e) When not PASSIVELY COOLED. | |||
(f) With pressurizer heater trip breakers closed. | |||
(g) With narrow range RCS hot temperature above the T-4 interlock. | |||
NuScale 3.3.1-8 Revision 1.0 | |||
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 7) | |||
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS | |||
: 10. High Pressurizer Level (a) (a) | |||
: a. RTS 1, 2 , 3 4 D | |||
: b. CVCSI 1, 2, 3 4 F (a) (a) | |||
: c. DWSI 1, 2 , 3 4 H | |||
: 11. Low Pressurizer Level (a) (a) | |||
: a. RTS 1, 2 , 3 4 D (f) (f) | |||
: b. Pressurizer Heater Trip 1, 2 , 3 4 G (a) (a) | |||
: c. DWSI 1, 2 , 3 4 H | |||
: 12. Low Low Pressurizer Level (h) | |||
: a. DHRS 1, 2, 3 4 N (h) | |||
: b. CIS 1, 2, 3 4 L (h) | |||
: c. CVCSI 1, 2, 3 4 F (f) (f) | |||
: d. Pressurizer Heater Trip 1, 2 , 3 4 G | |||
: 13. High Narrow Range RCS Hot Temperature | |||
: a. RTS 1 4 D (e) | |||
: b. DHRS 1, 2, 3 4 I (f) (f) | |||
: c. Pressurizer Heater Trip 1, 2 , 3 4 G | |||
: d. DWSI 1 4 H | |||
: 14. Low RCS Flow | |||
: a. DWSI 1, 2, 3 4 H (a) When capable of CRA withdrawal. | |||
(e) When not PASSIVELY COOLED. | |||
(f) With pressurizer heater trip breakers closed. | |||
(h) With RCS temperature above the T-2 interlock and containment water level below the L-1 interlock. | |||
NuScale 3.3.1-9 Revision 1.0 | |||
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7) | |||
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS | |||
: 15. Low Low RCS Flow (a) (a) | |||
: a. RTS 1, 2 , 3 4 D | |||
: b. CVCSI 1, 2, 3 4 F (a) (a) | |||
: c. DWSI 1, 2 , 3 4 H | |||
: 16. Low RPV Riser Level | |||
: a. ECCS 1, 2, 3 4 I | |||
: 17. High Main Steam Pressure (a) | |||
: a. RTS 1, 2 4 per SG D (e) | |||
: b. DHRS 1, 2, 3 4 per SG I (f) (f) | |||
: c. Pressurizer Heater Trip 1, 2 , 3 4 per SG G (a) | |||
: d. DWSI 1, 2 4 per SG H | |||
: 18. Low Main Steam Pressure (b) | |||
: a. RTS 1 4 per SG E (b) | |||
: b. DHRS 1 4 per SG E (b) | |||
: c. Pressurizer Heater Trip 1 4 per SG E (b) | |||
: d. DWSI 1 4 per SG H (a) When capable of CRA withdrawal. | |||
(b) With power above the N-2H interlock. | |||
(e) When not PASSIVELY COOLED. | |||
(f) With pressurizer heater trip breakers closed. | |||
NuScale 3.3.1-10 Revision 1.0 | |||
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 7) | |||
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS | |||
: 19. Low Low Main Steam Pressure (a) | |||
: a. RTS 1, 2 4 per SG D | |||
: b. DHRS 1, 2 4 per SG K (f) | |||
: c. Pressurizer Heater Trip 1, 2 4 per SG G (a) | |||
: d. DWSI 1, 2 4 per SG H | |||
: 20. High Steam Superheat | |||
: a. RTS 1 4 per SG D | |||
: b. DHRS 1 4 per SG D | |||
: c. Pressurizer Heater Trip 1 4 per SG G | |||
: d. DWSI 1 4 per SG H | |||
: 21. Low Steam Superheat | |||
: a. RTS 1 4 per SG D | |||
: b. DHRS 1 4 per SG D | |||
: c. Pressurizer Heater Trip 1 4 per SG G | |||
: d. DWSI 1 4 per SG H (a) When capable of CRA withdrawal. | |||
(f) With pressurizer heater trip breakers closed. | |||
NuScale 3.3.1-11 Revision 1.0 | |||
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 7) | |||
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS | |||
: 22. High Narrow Range Containment Pressure (a) (a) | |||
: a. RTS 1, 2 , 3 4 D (e) | |||
: b. DHRS 1, 2, 3 4 I (i) | |||
: c. CIS 1, 2, 3 4 L (i) | |||
: d. CVCSI 1, 2, 3 4 F (f) (f) | |||
: e. Pressurizer Heater Trip 1, 2 , 3 4 G (a) (a) | |||
: f. DWSI 1, 2 , 3 4 H | |||
: 23. High Containment Water Level (e) | |||
: a. ECCS 1, 2, 3 4 I | |||
: 24. High RCS Pressure - Low Temperature Overpressure Protection (k) | |||
: a. LTOP 3 4 J | |||
: 25. Low AC Voltage to ELVS Battery Chargers (a) (a) | |||
: a. RTS 1, 2 , 3 4 per bus M (e) | |||
: b. DHRS 1, 2, 3 4 per bus M | |||
: c. CIS 1, 2, 3 4 per bus M (a) (a) | |||
: d. DWSI 1, 2 , 3 4 per bus M (f) | |||
: e. Pressurizer Heater Trip 1, 2 4 per bus M (a) When capable of CRA withdrawal. | |||
(e) When not PASSIVELY COOLED. | |||
(f) With pressurizer heater trip breakers closed. | |||
(i) With RCS temperature above the T-3 interlock. | |||
(k) With wide range RCS cold temperature below the LTOP enable temperature specified in the PTLR (T-1 interlock) and more than one reactor vent valve closed. | |||
NuScale 3.3.1-12 Revision 1.0 | |||
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7) | |||
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS | |||
: 26. High Under-the-Bioshield Temperature (a) (a) | |||
: a. RTS 1, 2 , 3 4 M | |||
: b. DHRS 1, 2, 3 4 M | |||
: c. CIS 1, 2, 3 4 M (a) (a) | |||
: d. DWSI 1, 2 , 3 4 M (f) (f) | |||
: e. Pressurizer Heater Trip 1, 2 , 3 4 M (a) When capable of CRA withdrawal. | |||
(f) With pressurizer heater trip breakers closed. | |||
NuScale 3.3.1-13 Revision 1.0 | |||
Reactor Trip System Logic and Actuation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Reactor Trip System (RTS) Logic and Actuation LCO 3.3.2 Reactor Trip System (RTS) Logic and Actuation shall be OPERABLE. | |||
APPLICABILITY: MODE 1, MODES 2 and 3 when capable of CRA withdrawal. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One reactor trip breaker A.1 Open the inoperable RTB. 48 hours (RTB) inoperable. | |||
B. One division of RTS logic B.1 Restore division of RTS 6 hours and actuation inoperable. logic and actuation to OPERABLE status. | |||
C. Required Action and C.1 Open all RTBs. Immediately associated Completion Time not met. | |||
OR Both divisions of RTS logic and actuation inoperable. | |||
OR More than one RTB inoperable. | |||
NuScale 3.3.2-1 Revision 1.0 | |||
Reactor Trip System Logic and Actuation 3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1 ------------------------------NOTE------------------------------ | |||
Not required to be met for reactor trip breakers that are open. | |||
Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2 ------------------------------NOTES------------------------------ | |||
: 1. Neutron detectors are excluded from response time testing. | |||
: 2. Not required to be met for reactor trip breakers that are open. | |||
Verify RTS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.2.3 ------------------------------NOTE------------------------------ | |||
Not required to be met for Class 1E isolation devices that have isolated 1E circuits from non-1E power. | |||
Verify associated Class 1E isolation devices are In accordance with OPERABLE. the Surveillance Frequency Control Program SR 3.3.2.4 ------------------------------NOTE------------------------------ | |||
Not required to be met for reactor trip breakers that are open. | |||
Verify each RTB actuates to the open position on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program NuScale 3.3.2-2 Revision 1.0 | |||
ESFAS Logic and Actuation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Engineered Safety Features Actuation System (ESFAS) Logic and Actuation LCO 3.3.3 Engineered Safety Features Actuation System (ESFAS) Logic and Actuation divisions required for each Function in Table 3.3.3-1 shall be OPERABLE. | |||
APPLICABILITY: According to Table 3.3.3-1. | |||
ACTIONS | |||
-----------------------------------------------------------NOTE------------------------------------------------------------ | |||
Separate Condition entry is allowed for each Function. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more divisions of A.1 Open two reactor vent 1 hour the LTOP Logic and valves (RVVs). | |||
Actuation Function inoperable. | |||
B. One division of required B.1 Enter the Condition 6 hours ESFAS function in Referenced in Table 3.3.3-1 inoperable Table 3.3.3-1 for the other than LTOP function(s). | |||
function. | |||
NuScale 3.3.3-1 Revision 1.0 | |||
ESFAS Logic and Actuation 3.3.3 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 Be in MODE 2. 6 hours Action B.1 and referenced in AND Table 3.3.3-1. | |||
C.2 Be in MODE 3 and 36 hours OR PASSIVELY COOLED. | |||
Both divisions of ECCS actuation function inoperable. | |||
OR Both divisions of DHRS actuation function inoperable. | |||
D. As required by Required D.1 Be in MODE 2. 6 hours Action B.1 and referenced in AND Table 3.3.3-1. | |||
D.2 Be in MODE 3 with RCS 48 hours OR temperature below the T-2 interlock. | |||
Both divisions of Containment Isolation actuation function inoperable. | |||
NuScale 3.3.3-2 Revision 1.0 | |||
ESFAS Logic and Actuation 3.3.3 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 ---------------NOTE--------------- | |||
Action B.1 and Flow path(s) may be referenced in unisolated intermittently Table 3.3.3-1. under administrative controls. | |||
OR -------------------------------------- | |||
Both divisions of Isolate the flow path from 1 hour Demineralized Water the demineralized water Supply Isolation storage tank to the reactor actuation function coolant system by use of at inoperable. least one closed manual or one closed and de-activated automatic valve. | |||
F. As required by Required F.1 ----------------NOTE-------------- | |||
Action B.1 and Flow path(s) may be referenced in unisolated intermittently Table 3.3.3-1. under administrative controls. | |||
OR -------------------------------------- | |||
Both divisions of CVCS Isolate CVCS charging and 1 hour Isolation actuation letdown flow paths to the function inoperable. Reactor Coolant System by use of at least one closed manual or one closed and de-activated automatic valve. | |||
G. As required by Required G.1 ----------------NOTE-------------- | |||
Action B.1 and Heater(s) may be energized referenced in intermittently under manual Table 3.3.3-1. controls. | |||
OR De-energize Pressurizer 6 hours Both divisions of Heaters. | |||
Pressurizer Heater de-energization function inoperable. | |||
NuScale 3.3.3-3 Revision 1.0 | |||
ESFAS Logic and Actuation 3.3.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.3.2 ---------------------------------NOTES---------------------------- | |||
: 1. Neutron detectors are excluded from response time testing. | |||
: 2. Not required to be met for components that are in their actuated position or under administrative controls. | |||
Verify required RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.3.3 ---------------------------------NOTE------------------------------ | |||
Not required to be met for Class 1E isolation devices that have isolated 1E circuits from non-1E power. | |||
Verify associated Class 1E isolation devices are In accordance with OPERABLE. the Surveillance Frequency Control Program SR 3.3.3.4 ---------------------------------NOTE------------------------------ | |||
Not required to be met for pressurizer heater trip breakers that are open or breakers closed under administrative controls. | |||
Verify each pressurizer heater trip breaker (PHTB) In accordance with actuates to the open position on an actual or the Surveillance simulated actuation signal. Frequency Control Program NuScale 3.3.3-4 Revision 1.0 | |||
ESFAS Logic and Actuation 3.3.3 Table 3.3.3-1 (page 1 of 1) | |||
ESFAS Logic and Actuation Functions APPLICABLE MODES OR OTHER ACTUATION SPECIFIED REQUIRED FUNCTION CONDITIONS DIVISIONS CONDITIONS (a) | |||
: 1. Emergency Core 1, 2, 3 2 C Cooling System (ECCS) | |||
(a) | |||
: 2. Decay Heat 1, 2, 3 2 C Removal System (DHRS) | |||
(b) | |||
: 3. Containment 1, 2, 3 2 D Isolation System (CIS) | |||
: 4. Demineralized 1, 2, 3 2 E Water Supply Isolation (DWSI) | |||
: 5. CVCS Isolation 1, 2, 3 2 F (CVCSI) | |||
(c) (c) | |||
: 6. Pressurizer Heater 1, 2 , 3 2 G Trip (d) | |||
: 7. Low Temperature 3 2 A Overpressure Protection (LTOP) | |||
(a) Not PASSIVELY COOLED. | |||
(b) With any RCS temperature above the T-2 interlock. | |||
(c) Not required when Pressurizer Heater trip breakers are open and deactivated. | |||
(d) With wide range RCS cold temperature below the LTOP enable temperature specified in the PTLR (T-1 interlock) and more than one reactor vent valve closed. | |||
NuScale 3.3.3-5 Revision 1.0 | |||
Manual Actuation Functions 3.3.4 3.3 INSTRUMENTATION 3.3.4 Manual Actuation Functions LCO 3.3.4 Each manual actuation division for each Function in Table 3.3.4-1 shall be OPERABLE. | |||
APPLICABILITY: According to Table 3.3.4-1. | |||
ACTIONS | |||
------------------------------------------------------------NOTE----------------------------------------------------------- | |||
Separate Condition entry is allowed for each Function. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition 48 hours with one manual referenced in Table 3.3.4-1 actuation division for the function(s). | |||
inoperable. | |||
B. One or more Functions B.1 Enter the Condition 6 hours with two manual referenced in Table 3.3.4-1 actuation divisions for the function(s). | |||
inoperable. | |||
C. As required by Required C.1 Open reactor trip breakers. Immediately Action A.1 or B.1 and referenced in Table 3.3.4-1. | |||
D. As required by Required D.1 Be in MODE 2. 24 hours Action A.1 or B.1 and referenced in AND Table 3.3.4-1. | |||
D.2 Be in MODE 3 and 72 hours PASSIVELY COOLED. | |||
NuScale 3.3.4-1 Revision 1.0 | |||
Manual Actuation Functions 3.3.4 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 ----------------NOTE-------------- | |||
Action A.1 or B.1 and Flow path(s) may be referenced in unisolated intermittently Table 3.3.4-1. under administrative controls. | |||
Isolate the flow path from the 1 hour demineralized water storage tank to the Reactor Coolant System by use of at least one closed manual or one closed and de-activated automatic valve. | |||
F. As required by Required F.1 ---------------NOTE------------ | |||
Action A.1 or B.1 and Flow path(s) may be referenced in unisolated intermittently Table 3.3.4-1. under administrative controls. | |||
Isolate the flow paths from 1 hour the CVCS to the Reactor Coolant System by use of at least one closed manual or one closed and de-activated automatic valve. | |||
G. As required by Required G.1 -------------NOTE------------- | |||
Action A.1 or B.1 and Heater(s) may be energized referenced in intermittently under Table 3.3.4-1. administrative controls. | |||
De-energize affected 24 hours pressurizer heaters. | |||
NuScale 3.3.4-2 Revision 1.0 | |||
Manual Actuation Functions 3.3.4 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required H.1 Open two reactor vent Immediately Action A.1 or B.1 and valves. | |||
referenced in Table 3.3.4-1. | |||
I. As required by Required I.1 Be in MODE 2. 6 hours Action A.1 or B.1 and Referenced in AND Table 3.3.4 1. | |||
I.2 Be in MODE 3 with RCS 48 hours temperature below the T-2 interlock. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform actuation device operational test. In accordance with the Surveillance Frequency Control Program NuScale 3.3.4-3 Revision 1.0 | |||
Manual Actuation Functions 3.3.4 Table 3.3.4-1 (page 1 of 1) | |||
Manual Actuation Functions APPLICABLE MODES MANUALLY OR OTHER ACTUATED SPECIFIED REQUIRED FUNCTION CONDITIONS DIVISIONS CONDITIONS (a) (a) | |||
: 1. Reactor Trip 1, 2 , 3 2 C System (b) | |||
: 2. Emergency Core 1, 2, 3 2 D Cooling System (b) | |||
: 3. Decay Heat 1, 2, 3 2 D Removal System (c) | |||
: 4. Containment 1, 2, 3 2 I Isolation System | |||
: 5. Demineralized 1, 2, 3 2 E Water Supply Isolation | |||
: 6. CVCS Isolation 1, 2, 3 2 F System (d) (d) | |||
: 7. Pressurizer Heater 1, 2 , 3 2 G Trip (e) | |||
: 8. Low Temperature 3 2 H Overpressure Protection (a) When capable of CRA withdrawal. | |||
(b) When not PASSIVELY COOLED. | |||
(c) With any RCS temperature above the T-2 interlock. | |||
(d) Not required when pressurizer heater trip breakers are open and deactivated. | |||
(e) With wide range RCS cold temperature below the LTOP enable temperature specified in the PTLR (T-1 interlock) and more than one reactor vent valve closed. | |||
NuScale 3.3.4-4 Revision 1.0 | |||
RSS 3.3.5 3.3 INSTRUMENTATION 3.3.5 Remote Shutdown Station (RSS) | |||
LCO 3.3.5 Instrumentation in the RSS shall be OPERABLE. | |||
APPLICABILITY: MODES 1 and 2, MODE 3 and not PASSIVELY COOLED. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Instrumentation in the A.1 Restore to OPERABLE 30 days RSS inoperable. status. | |||
B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time not met. AND B.2 Be in MODE 3 and 36 hours PASSIVELY COOLED. | |||
NuScale 3.3.5-1 Revision 1.0 | |||
RSS 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform transfer protocol of required functions. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2 Verify that the RSS communicates indication with In accordance with each required function of the Module Control the Surveillance System and Plant Control System. Frequency Control Program SR 3.3.5.3 Verify the OPERABILITY of the RSS hardware and In accordance with software. the Surveillance Frequency Control Program NuScale 3.3.5-2 Revision 1.0 | |||
RCS Pressure, Temperature, and Flow Resistance CHF Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Resistance Critical Heat Flux (CHF) Limits LCO 3.4.1 Each RCS CHF parameter shall be within the limits specified in the COLR: | |||
: a. Pressurizer pressure, | |||
: b. RCS cold temperature, and | |||
: c. RCS flow resistance. | |||
APPLICABILITY: MODE 1. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS pressurizer A.1 Restore RCS CHF 2 hours pressure or RCS cold parameter(s) to within limit. | |||
temperature CHF parameters not within limits. | |||
B. RCS flow resistance not B.1 Evaluate flow resistance 7 days within limits effect on safety analysis and verify that the reactor coolant system flow rate is acceptable for continued operation. | |||
C. Required Action and C.1 Be in Mode 2. 6 hours associated Completion Time not met. | |||
NuScale 3.4.1-1 Revision 1.0 | |||
RCS Pressure, Temperature, and Flow Resistance CHF Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to In accordance with the limit specified in the COLR. the Surveillance Frequency Control Program SR 3.4.1.2 Verify RCS cold temperature is less than or equal to In accordance with the limit specified in the COLR. the Surveillance Frequency Control Program SR 3.4.1.3 --------------------------------NOTE----------------------------- | |||
Not required to be performed until 96 hours after exceeding 50% RTP. | |||
Verify RCS flow resistance is within the limits Once prior to specified in the COLR. exceeding 75% | |||
RTP after each refueling NuScale 3.4.1-2 Revision 1.0 | |||
RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 All RCS temperatures shall be 420°F. | |||
APPLICABILITY: MODE 1. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS A.1 Be in MODE 2. 30 minutes temperatures not within limit. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify all RCS temperatures 420°F. In accordance with the Surveillance Frequency Control Program NuScale 3.4.2-1 Revision 1.0 | |||
RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR. | |||
APPLICABILITY: At all times. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE------------- A.1 Restore parameters to 30 minutes Required Action A.2 shall within limits. | |||
be completed whenever this Condition is entered. AND A.2 Determine RCS is 72 hours Requirements of LCO not acceptable for continued met in MODE 1, 2, or 3. operation. | |||
B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time of Condition A not AND met. | |||
B.2 Be in MODE 3 with RCS 36 hours pressure < 500 psia. | |||
C. --------------NOTE ------------ C.1 Initiate action to restore Immediately Required Action C.2 shall parameter(s) to within limits. | |||
be completed whenever this Condition is entered. AND C.2 Determine RCS is Prior to entering Requirements of LCO not acceptable for continued MODE 3 met any time in other than operation. | |||
MODE 1, 2, or 3. | |||
NuScale 3.4.3-1 Revision 1.0 | |||
RCS P/T Limits 3.4.3 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME D. Containment flooding D.1 Be in MODE 2. Immediately initiated while RCS temperature greater than AND allowed by PTLR. | |||
D.2 Be in MODE 3 with RCS 36 hours temperature less than or equal to the containment flooding RCS temperature limit allowed by the PTLR. | |||
AND D.3 Determine RCS is Prior to entering acceptable for continued MODE 2 from operation. MODE 3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 --------------------------------NOTE----------------------------- | |||
Only required to be performed during RCS heatup and cooldown operations and inservice leak and hydrostatic testing. | |||
Verify RCS pressure, RCS temperature, and RCS In accordance with heatup and cooldown rates are within limits specified the Surveillance in the PTLR. Frequency Control Program NuScale 3.4.3-2 Revision 1.0 | |||
RSVs 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 Reactor Safety Valves (RSVs) | |||
LCO 3.4.4 Two RSVs shall be OPERABLE. | |||
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS cold temperature above the low temperature overpressure protection (LTOP) interlock T-1. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RSV inoperable. A.1 Restore valve to 72 hours OPERABLE status. | |||
B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time not met. AND OR B.2 Be in MODE 3 with RCS 36 hours cold temperature below Two RSVs inoperable. LTOP enable interlock T-1 temperature. | |||
NuScale 3.4.4-1 Revision 1.0 | |||
RSVs 3.4.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RSV is OPERABLE in accordance with In accordance with the INSERVICE TESTING PROGRAM. Following the INSERVICE testing, lift settings shall be within 1% of the nominal TESTING setpoints of 2075 psia and 2100 psia as shown below: PROGRAM Valve 1 Setpoint: 2055 psia and 2095 psia. | |||
Valve 2 Setpoint: 2079 psia and 2121 psia. | |||
NuScale 3.4.4-2 Revision 1.0 | |||
RCS Operational LEAKAGE 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Operational LEAKAGE LCO 3.4.5 RCS operational LEAKAGE shall be limited to: | |||
: a. No pressure boundary LEAKAGE, | |||
: b. 0.5 gpm unidentified LEAKAGE, | |||
: c. 2 gpm identified LEAKAGE from the RCS, and | |||
: d. 150 gallons per day primary to secondary LEAKAGE. | |||
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS hot temperature 200°F. | |||
-------------------------------------------NOTE---------------------------------------------- | |||
This LCO is not applicable if one or more ECCS valves is open. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A.1 Reduce LEAKAGE to within 4 hours LEAKAGE not within limits. | |||
limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE. | |||
NuScale 3.4.5-1 Revision 1.0 | |||
RCS Operational LEAKAGE 3.4.5 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time of Condition A not AND met. | |||
B.2 Be in MODE 3 with RCS hot 48 hours OR temperature < 200°F. | |||
Pressure boundary LEAKAGE exists. | |||
OR Primary to secondary LEAKAGE not within limit. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 --------------------------------NOTES----------------------------- | |||
: 1. Not required to be performed until 12 hours after establishment of steady state operation. | |||
: 2. Not applicable to primary to secondary LEAKAGE. | |||
Verify RCS Operational LEAKAGE is within limits by In accordance with performance of RCS water inventory balance. the Surveillance Frequency Control Program NuScale 3.4.5-2 Revision 1.0 | |||
RCS Operational LEAKAGE 3.4.5 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.4.5.2 --------------------------------NOTE------------------------------ | |||
Not required to be performed until 12 hours after establishment of steady state operation. | |||
Verify primary to secondary LEAKAGE is In accordance with 150 gallons per day through the Steam Generator the Surveillance System. Frequency Control Program NuScale 3.4.5-3 Revision 1.0 | |||
Chemical and Volume Control System Isolation Valves 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 Chemical and Volume Control System (CVCS) Isolation Valves LCO 3.4.6 Each of the following CVCS line flow path isolation valves shall be OPERABLE: | |||
: a. RCS Injection Isolation Valves, | |||
: b. RCS Discharge Isolation Valves, | |||
: c. Pressurizer Spray Isolation Valves, and | |||
: d. RPV High Point Degasification Isolation Valves. | |||
APPLICABILITY: MODES 1, 2, and 3. | |||
ACTIONS | |||
---------------------------------------------------------NOTES------------------------------------------------------------ | |||
: 1. CVCS flow path(s) may be unisolated intermittently under administrative controls. | |||
: 2. Separate Condition entry is allowed for each flow path. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more CVCS flow A.1 Isolate the affected CVCS 72 hours paths with one CVCS flow path by use of at least valve inoperable. one closed and de-activated automatic valve, closed manual valve, or blind flange. | |||
AND NuScale 3.4.6-1 Revision 1.0 | |||
Chemical and Volume Control System Isolation Valves 3.4.6 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ---------------NOTES------------- | |||
: 1. Isolation devices in high radiation areas may be verified by use of administrative means. | |||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | |||
Verify the affected CVCS Once per 31 days flow path is isolated. | |||
B. One or more CVCS flow B.1 Isolate the affected CVCS 1 hour paths with two CVCS flow path by use of at least valves inoperable. one closed and de-activated automatic valve, closed manual valve, or blind flange. | |||
C. Required Action and C.1 Be in MODE 2. 6 hours associated Completion Time not met. AND C.2 Be in MODE 3 with RCS hot 48 hours temperature < 200°F. | |||
NuScale 3.4.6-2 Revision 1.0 | |||
Chemical and Volume Control System Isolation Valves 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required valves accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program. | |||
SR 3.4.6.2 ---------------------------------NOTE------------------------------ | |||
Not required to be met for valves that are closed or open under administrative controls. | |||
Verify the isolation time of each automatic power In accordance with operated CVCS valve is within limits. the INSERVICE TESTING PROGRAM SR 3.4.6.3 Verify each automatic CVCS valve that is not locked, In accordance with sealed, or otherwise secured in position, actuates to the Surveillance the isolation position on an actual or simulated Frequency Control actuation signal except for valves that are open under Program administrative controls. | |||
NuScale 3.4.6-3 Revision 1.0 | |||
RCS Leakage Detection Instrumentation 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Leakage Detection Instrumentation LCO 3.4.7 Two of the following RCS leakage detection instrumentation methods shall be OPERABLE: | |||
: a. Two Containment Evacuation System (CES) condensate channels, | |||
: b. Two CES inlet pressure channels, and | |||
: c. One CES gaseous radioactivity monitor channel. | |||
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS hot temperature 200°F. | |||
------------------------------------------NOTES--------------------------------------------- | |||
: 1. Not required when one or more ECCS valves open. | |||
: 2. Not required in MODE 3 during containment flood operations. | |||
ACTIONS | |||
------------------------------------------------------------NOTE----------------------------------------------------------- | |||
Separate Condition entry is allowed for each condensate channel and each pressure channel. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 ---------------NOTE--------------- | |||
leakage detection Not required until 12 hours instrumentation methods after establishment of steady with one required state operation. | |||
channel inoperable. --------------------------------------- | |||
Perform SR 3.4.5.1. Once per 24 hours AND A.2 Restore required leakage 14 days detection channel(s) to OPERABLE status. | |||
NuScale 3.4.7-1 Revision 1.0 | |||
RCS Leakage Detection Instrumentation 3.4.7 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. One required leakage B.1 Restore one channel of 72 hours detection instrumentation affected required leakage method with all required detection instrumentation channels inoperable. method to OPERABLE status. | |||
C. Required Action and C.1 Be in MODE 2. 6 hours associated Completion Time not met. AND OR C.2 Be in MODE 3 with 48 hours RCS hot temperature Two required leakage < 200°F. | |||
detection instrumentation methods with all required channels inoperable. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Perform a CHANNEL CHECK of each required CES In accordance with condensate channel. the Surveillance Frequency Control Program SR 3.4.7.2 Perform a CHANNEL CHECK of each required CES In accordance with inlet pressure channel. the Surveillance Frequency Control Program NuScale 3.4.7-2 Revision 1.0 | |||
RCS Leakage Detection Instrumentation 3.4.7 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.4.7.3 Perform a CHANNEL CHECK of required CES In accordance with gaseous radioactivity monitor channel. the Surveillance Frequency Control Program SR 3.4.7.4 Perform a COT of required CES gaseous radioactivity In accordance with monitor channel. the Surveillance Frequency Control Program SR 3.4.7.5 Perform a COT of each required CES condensate In accordance with channel. the Surveillance Frequency Control Program SR 3.4.7.6 Perform a CHANNEL CALIBRATION of each In accordance with required CES condensate channel. the Surveillance Frequency Control Program SR 3.4.7.7 Perform a CHANNEL CALIBRATION of each In accordance with required CES inlet pressure channel. the Surveillance Frequency Control Program SR 3.4.7.8 Perform a CHANNEL CALIBRATION of required CES In accordance with gaseous radioactivity monitor channel. the Surveillance Frequency Control Program NuScale 3.4.7-3 Revision 1.0 | |||
RCS Specific Activity 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Specific Activity LCO 3.4.8 The specific activity of the reactor coolant shall be within limits. | |||
APPLICABILITY: MODES 1 and 2. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT ---------------------NOTE------------------- | |||
I-131 > 0.2 µCi/gm. LCO 3.0.4.c is applicable. | |||
A.1 Verify DOSE EQUIVALENT Once per 4 hours I-131 12 µCi/gm. | |||
AND A.2 Restore DOSE 48 hours EQUIVALENT I-131 to within limit. | |||
B. DOSE EQUIVALENT ---------------------NOTE------------------- | |||
XE-133 > 60 Ci/gm. LCO 3.0.4.c is applicable. | |||
B.1 Restore DOSE 48 hours EQUIVALENT XE-133 to within limit. | |||
C. Required Action and C.1 Be in MODE 2. 6 hours associated Completion Time of Condition A or B AND not met. | |||
C.2 Be in MODE 3. 36 hours OR DOSE EQUIVALENT I-131 > 12 Ci/gm. | |||
NuScale 3.4.8-1 Revision 1.0 | |||
RCS Specific Activity 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify reactor coolant DOSE EQUIVALENT XE-133 In accordance with specific activity 60 µCi/gm. the Surveillance Frequency Control Program SR 3.4.8.2 Verify reactor coolant DOSE EQUIVALENT I-131 In accordance with specific activity 0.2 µCi/gm. the Surveillance Frequency Control Program AND Between 2 and 6 hours after a THERMAL POWER change of 15% of RTP within a 1 hour period NuScale 3.4.8-2 Revision 1.0 | |||
SG Tube Integrity 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Steam Generator (SG) Tube Integrity LCO 3.4.9 SG tube integrity shall be maintained. | |||
AND All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with the Steam Generator Program. | |||
APPLICABILITY: MODES 1 and 2, MODE 3 and not PASSIVELY COOLED. | |||
ACTIONS | |||
----------------------------------------------------------NOTE------------------------------------------------------------- | |||
Separate Condition entry is allowed for each SG tube. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes A.1 Verify tube integrity of the 7 days satisfying the tube affected tube(s) is plugging criteria and not maintained until the next plugged in accordance refueling outage or SG tube with the Steam Generator inspection. | |||
Program. | |||
AND A.2 Plug the affected tube(s) in Prior to entering accordance with the Steam MODE 3 following the Generator Program. next refueling outage or SG tube inspection B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time of Condition A not AND met. | |||
B.2 Be in MODE 3 and 36 hours OR PASSIVELY COOLED. | |||
SG tube integrity not maintained. | |||
NuScale 3.4.9-1 Revision 1.0 | |||
SG Tube Integrity 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify SG tube integrity in accordance with the Steam In accordance with Generator Program. the Steam Generator Program SR 3.4.9.2 Verify that each inspected SG tube that satisfies the Prior to entering tube plugging criteria is plugged in accordance with MODE 3 following the Steam Generator Program. a SG tube inspection NuScale 3.4.9-2 Revision 1.0 | |||
LTOP Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Low Temperature Overpressure Protection (LTOP) Valves LCO 3.4.10 Each closed reactor vent valve (RVV) shall be OPERABLE. | |||
APPLICABILITY: MODE 3 with wide range RCS cold temperature below T-1 interlock. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------- | |||
Not applicable with two RVVs open. | |||
One closed RVV A.1 Restore RVV to 72 hours inoperable. OPERABLE status. | |||
OR A.2 Open inoperable RVV. 72 hours B. Two closed RVVs B.1 Restore two closed RVVs 4 hours inoperable. to OPERABLE status. | |||
OR B.2 Open two RVVs. 4 hours C. Three closed RVVs C.1 Initiate action to 2 hours inoperable. depressurize RCS. | |||
AND C.2 Initiate action to open two 2 hours RVVs. | |||
NuScale 3.4.10-1 Revision 1.0 | |||
LTOP Valves 3.4.10 SURVEILLANCE REQUIREMENTS | |||
----------------------------------------------------------NOTE------------------------------------------------------------- | |||
Not required to be met for valves that are open. | |||
SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each RVV actuates to the open position on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program SR 3.4.10.2 Verify the open actuation time of each RVV is within In accordance with limits. the INSERVICE TESTING PROGRAM SR 3.4.10.3 Verify the inadvertent actuation block function for In accordance with each RVV. the Surveillance Frequency Control Program SR 3.4.10.4 Verify the inadvertent block setpoint is within limits for In accordance with each RVV. the INSERVICE TESTING PROGRAM NuScale 3.4.10-2 Revision 1.0 | |||
ECCS 3.5.1 3.5 PASSIVE CORE COOLING SYSTEM (PCCS) 3.5.1 Emergency Core Cooling System (ECCS) | |||
LCO 3.5.1 Three reactor vent valves (RVV) and two reactor recirculation valves (RRV) shall be OPERABLE. | |||
APPLICABILITY: MODES 1 and 2, MODE 3 and not PASSIVELY COOLED. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RVV inoperable. A.1 Restore RVV to OPERABLE 72 hours status. | |||
B. One RRV inoperable. B.1 Restore RRV to OPERABLE 72 hours status. | |||
C. Required Action and C.1 Be in MODE 2. 6 hours associated Completion Time of Condition A or B AND not met. | |||
C.2 Be in MODE 3 and 36 hours OR PASSIVELY COOLED. | |||
Two or more RVVs inoperable. | |||
OR Two RRVs inoperable. | |||
NuScale 3.5.1-1 Revision 1.0 | |||
ECCS 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 -------------------------------NOTE-------------------------------- | |||
Not required to be met for valves that are open. | |||
Verify each RVV and RRV actuates to the open In accordance with position on an actual or simulated actuation signal. the Surveillance Frequency Control Program SR 3.5.1.2 -------------------------------NOTE-------------------------------- | |||
Not required to be met for valves that are open. | |||
Verify the open actuation time of each RVV and RRV In accordance with is within limits. the INSERVICE TESTING PROGRAM SR 3.5.1.3 Verify the inadvertent actuation block function of each In accordance with RVV and RRV. the Surveillance Frequency Control Program SR 3.5.1.4 Verify the inadvertent block setpoint is within limits for In accordance with each RVV and RRV. the INSERVICE TESTING PROGRAM NuScale 3.5.1-2 Revision 1.0 | |||
DHRS 3.5.2 3.5 PASSIVE CORE COOLING SYSTEMS (PCCS) 3.5.2 Decay Heat Removal System (DHRS) | |||
LCO 3.5.2 Two DHRS trains shall be OPERABLE. | |||
APPLICABILITY: MODES 1 and 2, MODE 3 and not PASSIVELY COOLED. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One DHRS train A.1 Restore DHRS train to 72 hours inoperable. OPERABLE status. | |||
B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time not met. AND B.2 Be in MODE 3 and 36 hours OR PASSIVELY COOLED. | |||
Both DHRS trains inoperable. | |||
NuScale 3.5.2-1 Revision 1.0 | |||
DHRS 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify required valves accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program SR 3.5.2.2 Verify DHRS loops are filled. In accordance with the Surveillance Frequency Control Program SR 3.5.2.3 Verify that each DHRS actuation valve actuates to In accordance with the open position on an actual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.5.2.4 Verify the open actuation time of each DHRS In accordance with actuation valve is within limits. the INSERVICE TESTING PROGRAM NuScale 3.5.2-2 Revision 1.0 | |||
Ultimate Heat Sink 3.5.3 3.5 PASSIVE CORE COOLING SYSTEMS (PCCS) 3.5.3 Ultimate Heat Sink LCO 3.5.3 Ultimate Heat Sink shall be maintained within the limits specified below: | |||
: a. Level 68 ft, | |||
: b. Bulk average temperature 140 ºF, and | |||
: c. Bulk average boron concentration shall be maintained within the limit specified in the COLR. | |||
APPLICABILITY: At all times. | |||
ACTIONS | |||
------------------------------------------------------------NOTE----------------------------------------------------------- | |||
LCO 3.0.3 is not applicable. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. Ultimate Heat Sink Level A.1 Suspend module Immediately | |||
< 68 ft and > 55 ft. movements. | |||
AND A.2 Suspend movement of Immediately irradiated fuel assemblies in the refueling area. | |||
AND A.3 Restore Ultimate Heat Sink 30 Days Level to within limits. | |||
NuScale 3.5.3-1 Revision 1.0 | |||
Ultimate Heat Sink 3.5.3 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. Ultimate Heat Sink Level B.1 Initiate action to restore Immediately 55 ft. Ultimate Heat Sink Level to | |||
> 55 ft. | |||
AND B.2 Restore Ultimate Heat Sink 24 Hours Level to > 55 ft. | |||
C. Ultimate Heat Sink bulk C.1 Suspend module Immediately average temperature not movements. | |||
within limits. | |||
AND C.2 Initiate action to restore Immediately Ultimate Heat Sink bulk average temperature to within limits. | |||
AND C.3 Restore Ultimate Heat Sink 14 Days bulk average temperature to within limits. | |||
D. Required Action and D.1 Be in MODE 2. 6 hours associated Completion Time of Condition A, B or AND C not met. | |||
D.2 Be in MODE 3. 36 hours NuScale 3.5.3-2 Revision 1.0 | |||
Ultimate Heat Sink 3.5.3 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME E. Ultimate Heat Sink bulk E.1 Initiate action to restore Immediately average boron Ultimate Heat Sink bulk concentration not within average boron concentration limits. to within limits. | |||
AND E.2 Terminate flow into Immediately containment vessel from Ultimate Heat Sink via the Containment Flood and Drain System. | |||
AND E.3 Suspend containment vessel Immediately disassembly activities at containment tool. | |||
AND E.4 Suspend module Immediately movements. | |||
AND E.5 Suspend movement of Immediately irradiated fuel assemblies in the refueling area. | |||
NuScale 3.5.3-3 Revision 1.0 | |||
Ultimate Heat Sink 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the Ultimate Heat Sink level is within limits. In accordance with the Surveillance Frequency Control Program SR 3.5.3.2 Verify the Ultimate Heat Sink bulk average In accordance with temperature is within limits. the Surveillance Frequency Control Program SR 3.5.3.3 Verify Ultimate Heat Sink bulk average boron In accordance with concentration is within limits. the Surveillance Frequency Control Program NuScale 3.5.3-4 Revision 1.0 | |||
Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE. | |||
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS hot temperature 200ºF. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment inoperable. A.1 Restore containment to 1 hour OPERABLE status. | |||
B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time not met. AND B.2 Be in MODE 3 with RCS hot 48 hours temperature < 200ºF. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and leakage In accordance with rate testing in accordance with the Containment the Containment Leakage Rate Testing Program. Leakage Rate Testing Program NuScale 3.6.1-1 Revision 1.0 | |||
Containment Isolation Valves 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Isolation Valves LCO 3.6.2 Each containment isolation valve shall be OPERABLE. | |||
APPLICABILTY: MODES 1 and 2, MODE 3 with RCS hot temperature 200ºF. | |||
ACTIONS | |||
----------------------------------------------------------NOTES----------------------------------------------------------- | |||
: 1. Penetration flow path(s) may be unisolated intermittently under administrative controls. | |||
: 2. Separate Condition entry is allowed for each penetration flow path. | |||
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves. | |||
: 4. Enter applicable Conditions and Required Actions of LCO 3.6.1, Containment, when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. -----------NOTE------------ A.1 Isolate the affected 72 hours Only applicable to penetration flow path by use penetration flow paths of at least one closed and with two containment de-activated automatic isolation valves. valve, closed manual valve, | |||
-------------------------------- blind flange, or check valve with flow through the valve One or more penetration secured. | |||
flow paths with one containment isolation AND valve inoperable. | |||
NuScale 3.6.2-1 Revision 1.0 | |||
Containment Isolation Valves 3.6.2 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ---------------NOTES------------- | |||
: 1. Isolation devices in high radiation areas may be verified by use of administrative means. | |||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | |||
Verify the affected Once per 31 days penetration flow path is isolated. | |||
B. ---------NOTES------------ B.1 Isolate the affected 1 hour Only applicable to penetration flow path by use penetration flow paths of at least one closed and with two containment de-activated automatic isolation valves. valve, closed manual valve, | |||
------------------------------- or blind flange. | |||
One or more penetration flow paths with two containment isolation valves inoperable. | |||
C. Required Action and C.1 Be in MODE 2. 6 hours associated Completion Time not met. AND C.2 Be in MODE 3 with RCS hot 48 hours temperature < 200ºF. | |||
NuScale 3.6.2-2 Revision 1.0 | |||
Containment Isolation Valves 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 Verify required valves accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program SR 3.6.2.2 ---------------------------------NOTE------------------------------ | |||
Valves and blind flanges in high radiation areas may be verified by use of administrative means. | |||
Verify each containment isolation manual valve and In accordance with blind flange that is located outside containment and the Surveillance not locked, sealed, or otherwise secured and is Frequency Control required to be closed during accident conditions is Program closed, except for containment isolation valves that are open under administrative controls. | |||
SR 3.6.2.3 Verify the isolation time of each automatic In accordance with containment isolation valve is within limits except for the INSERVICE valves that are open under administrative controls. TESTING PROGRAM SR 3.6.2.4 Verify each automatic containment isolation valve In accordance with that is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the isolation position on an Frequency Control actual or simulated actuation signal except for valves Program that are open under administrative controls. | |||
SR 3.6.2.5 Verify the combined leakage rate for all containment In accordance with bypass leakage paths is 0.6 La when pressurized the Containment to 951 psia. Leakage Rate Testing Program NuScale 3.6.2-3 Revision 1.0 | |||
MSIVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Isolation Valves (MSIVs) | |||
LCO 3.7.1 Two MSIVs and two MSIV bypass valves per steam line shall be OPERABLE. | |||
APPLICABILITY: MODE 1 and 2, MODES 3 and not PASSIVELY COOLED. | |||
ACTIONS | |||
----------------------------------------------------------NOTES----------------------------------------------------------- | |||
: 1. Separate Condition entry is allowed for each inoperable valve. | |||
: 2. Main steam line flow path(s) may be unisolated intermittently under administrative controls. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Isolate the affected main 72 hours MSIV valves inoperable. steam line flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. | |||
AND A.2 --------------NOTES-------------- | |||
: 1. Isolation in high radiation areas may be verified by use of administrative means. | |||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | |||
Verify the affected main Once per 7 days steam line flow path is isolated. | |||
NuScale 3.7.1-1 Revision 1.0 | |||
MSIVs 3.7.1 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Isolate the affected main 72 hours MSIV bypass valves steam line bypass flow path inoperable. by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. | |||
AND B.2 ---------------NOTES------------- | |||
: 1. Isolation in high radiation areas may be verified by use of administrative means. | |||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | |||
Verify the affected main Once per 7 days steam line bypass flow path is isolated. | |||
C. One flow path with an C.1 Isolate the affected main 8 hours inner and outer required steam line flow path by use valve inoperable. of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. | |||
D. Required Action and D.1 Be in Mode 2. 6 hours associated Completion Time not met. AND D.2 Be in Mode 3 and 36 hours PASSIVELY COOLED. | |||
NuScale 3.7.1-2 Revision 1.0 | |||
MSIVs 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify required valves accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program SR 3.7.1.2 Verify isolation time of each MSIV and MSIV In accordance with bypass valve is within limits on an actual or the INSERVICE simulated actuation signal. TESTING PROGRAM SR 3.7.1.3 Verify each MSIV and MSIV bypass valve leakage In accordance with is within limits. the INSERVICE TESTING PROGRAM NuScale 3.7.1-3 Revision 1.0 | |||
Feedwater Isolation 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Feedwater Isolation LCO 3.7.2 One Feedwater Isolation Valve (FWIV) and one Feedwater Regulation Valve (FWRV) for each steam generator shall be OPERABLE. | |||
APPLICABILITY: MODE 1 and 2, MODES 3 and not PASSIVELY COOLED. | |||
ACTIONS | |||
---------------------------------------------------------NOTES------------------------------------------------------------ | |||
: 1. Separate Condition entry is allowed for each inoperable valve. | |||
: 2. Feedwater flow path(s) may be unisolated intermittently under administrative controls. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two FWIVs A.1 Isolate the affected FWIV 72 hours inoperable. flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. | |||
AND A.2 --------------NOTES-------------- | |||
: 1. Isolation in high radiation areas may be verified by use of administrative means. | |||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | |||
Verify FWIV path isolated. Once per 7 days NuScale 3.7.2-1 Revision 1.0 | |||
Feedwater Isolation 3.7.2 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. One or two FWRVs B.1 Isolate the affected FWRV 72 hours inoperable. flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. | |||
AND B.2 --------------NOTES-------------- | |||
: 1. Isolation in high radiation areas may be verified by use of administrative means. | |||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | |||
Verify FWRV path Once per 7 days isolated. | |||
C. Two valves in the same C.1 Isolate the affected flow path 8 hours flow path inoperable. by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. | |||
D. Required Action and D.1 Be in MODE 2. 6 hours associated Completion Time not met. AND D.2 Be in MODE 3 and 36 hours PASSIVELY COOLED. | |||
NuScale 3.7.2-2 Revision 1.0 | |||
Feedwater Isolation 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify required FWIV accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program. | |||
SR 3.7.2.2 Verify the closure time of each FWIV and FWRV is In accordance with within limits on an actual or simulated actuation the INSERVICE signal. TESTING PROGRAM SR 3.7.2.3 Verify each FWIV and FWRV leakage is within In accordance with limits. the INSERVICE TESTING PROGRAM NuScale 3.7.2-3 Revision 1.0 | |||
Nuclear Instrumentation 3.8.1 3.8 REFUELING OPERATIONS 3.8.1 Nuclear Instrumentation LCO 3.8.1 Two refueling neutron flux channels and one refueling neutron flux audible count rate channel shall be OPERABLE. | |||
APPLICABILITY: MODE 5, except when reactor vessel upper assembly is seated on reactor vessel flange. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required refueling A.1 Suspend positive reactivity Immediately neutron flux channel changes. | |||
inoperable. | |||
AND OR A.2 Suspend operations that Immediately Required refueling would cause introduction of neutron flux audible water into reactor pool with count rate channel boron concentration less inoperable. than specified in the COLR. | |||
B. Two required refueling B.1 Initiate actions to restore Immediately neutron flux channels one refueling neutron flux inoperable. channel to OPERABLE status. | |||
AND B.2 Perform SR 3.5.3.3. Once per 12 hours NuScale 3.8.1-1 Revision 1.0 | |||
Nuclear Instrumentation 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Perform a CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.8.1.2 --------------------------------NOTE------------------------------ | |||
Neutron detectors are excluded from CHANNEL CALIBRATION. | |||
Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program NuScale 3.8.1-2 Revision 1.0 | |||
Decay Time 3.8.2 3.8 REFUELING OPERATIONS 3.8.2 Decay Time LCO 3.8.2 Reactor shall be subcritical for 48 hours. | |||
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor subcritical for A.1 Suspend movement of Immediately | |||
< 48 hours. irradiated fuel in the reactor pressure vessel. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 Verify reactor has been subcritical for 48 hours. Once prior to movement of irradiated fuel assemblies in the reactor pressure vessel NuScale 3.8.2-1 Revision 1.0 | |||
Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location | |||
[Site specific information to be provided by the combined license applicant.] | |||
4.1.1 Site and Exclusion Boundaries | |||
[Site specific information to be provided by the combined license applicant.] | |||
4.1.2 Low Population Zone (LPZ) | |||
[Site specific information to be provided by the combined license applicant.] | |||
4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 37 fuel assemblies. Each assembly shall consist of a matrix of fuel rods clad with a zirconium based alloy and containing an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. | |||
Limited substitutions of zirconium based alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions. | |||
4.2.2 Control Rod Assemblies The reactor core shall contain 16 control rod assemblies. The control material shall be silver indium cadmium or boron carbide as approved by the NRC. | |||
4.3 Fuel Storage 4.3.1 Criticality The spent fuel storage racks are designed and shall be maintained with: | |||
: a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; NuScale 4.0-1 Revision 1.0 | |||
Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) | |||
: b. keff 0.95 if fully flooded with borated water at a minimum soluble boron concentration of 800 ppm, which includes an allowance for uncertainties to assure a 95 percent probability and 95 percent confidence level; | |||
: c. keff < 1.00 if fully flooded with unborated water, which includes an allowance for uncertainties to assure a 95 percent probability and 95 percent confidence level; | |||
: d. A nominal 11.22 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks. | |||
4.3.2 Drainage The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below 20 ft above the spent fuel pool floor. | |||
4.3.3 Capacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 1404 fuel assemblies. | |||
NuScale 4.0-2 Revision 1.0 | |||
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The [Plant Manager] shall be responsible for overall facility operations and shall delegate in writing the succession to this responsibility during his absence. | |||
The [Plant Manager] or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety. | |||
5.1.2 The [Shift Manager (SM)] shall be responsible for the control room command function. During any absence of the SM from the control room while any unit is in MODE 1, 2, 3, 4, or 5, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. | |||
NuScale 5.1-1 Revision 1.0 | |||
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for facility operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. | |||
Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the [FSAR/QA Plan]; | |||
The [Plant Manager] shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant; A [specified corporate officer] shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures. | |||
5.2.2 Facility Staff The facility staff organization shall include the following: | |||
: a. The minimum licensed operator staffing shall be: | |||
Number of units Reactor Senior Reactor Operating(1) Operator Operator None 2 1 One to twelve 3 3 (1) | |||
For the purpose of this table, a unit is considered to be operating when it is in MODE 1, 2, or 3. | |||
NuScale 5.2-1 Revision 1.0 | |||
Organization 5.2 5.2 Organization 5.2.2 Facility Staff (continued) | |||
: b. A person holding a senior reactor operator license for all fueled units at the site who is assigned responsibility for overall plant operation shall be onsite at all times when there is fuel in any unit. | |||
: c. A senior reactor operator license shall be in the control room at all times. | |||
In addition to this senior reactor operator, a licensed reactor operator or senior reactor operator shall be present at the controls at all times. | |||
: d. Shift crew composition may be less than the minimum requirement for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements. | |||
: e. A radiation protection technician shall be on site when fuel is in any unit. | |||
The position may be vacant for not more than 2 hours, in order to provide for unexpected absence, provided immediate action is taken to fill the required position. | |||
: f. The operations manager or assistant operations manager shall hold an SRO license. | |||
: g. An individual shall provide advisory technical support to the facility operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the facility. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. | |||
NuScale 5.2-2 Revision 1.0 | |||
Facility Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 3, 2000, or more recent revisions, or ANSI Standards acceptable to the NRC staff. The staff not covered by Regulatory Guide 1.8 shall meet or exceed the minimum qualifications of Regulations, Regulatory Guides, or ANSI Standards acceptable to NRC staff. | |||
5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, meet the requirements of TS 5.3.1 and TS 5.2.2. | |||
NuScale 5.3-1 Revision 1.0 | |||
Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities: | |||
: a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978; | |||
: b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1; | |||
: c. Quality assurance for effluent and environmental monitoring; | |||
: d. Fire Protection Program implementation; and | |||
: e. All programs specified in Specification 5.5. | |||
NuScale 5.4-1 Revision 1.0 | |||
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained. | |||
5.5.1 Offsite Dose Calculation Manual (ODCM) | |||
: a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program. | |||
: b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.1 and Specification 5.6.2. | |||
: c. Licensee initiated changes to the ODCM: | |||
: 1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain: | |||
: i. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and ii. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent or dose calculations; | |||
: 2. Shall become effective after the approval of the [plant manager]; | |||
and | |||
: 3. Shall be submitted to the NRC in the form of a complete, legible copy of the changed portion of the ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. | |||
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented. | |||
NuScale 5.5-1 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Radioactive Effluent Control Program | |||
: a. This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as is reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements: | |||
: 1. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoints determination in accordance with the methodology in the ODCM; | |||
: 2. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20; | |||
: 3. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; | |||
: 4. Limitations on the annual and quarterly doses or dose commitment to a member of the public for radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I; | |||
: 5. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days; | |||
: 6. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; NuScale 5.5-2 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Radioactive Effluent Control Program (continued) | |||
: 7. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary shall be in accordance with the following: | |||
: i. For noble gases: a dose rate 500 mrem/yr to the whole body and a dose rate 3000 mrem/yr to the skin and ii. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate 1500 mrem/yr to any organ; | |||
: 8. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; | |||
: 9. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and | |||
: 10. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190. | |||
: b. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency. | |||
5.5.3 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Section 3.9, cyclic and transient occurrences to ensure that components are maintained within the design limits. | |||
5.5.4 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following: | |||
NuScale 5.5-3 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Steam Generator (SG) Program (continued) | |||
: a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the as found condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met. | |||
: b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE. | |||
: 1. Structural integrity performance criterion: All inservice steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, and cool down and all anticipated transients included in the design specification) and design basis accidents. | |||
This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads. | |||
: 2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube failure, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. | |||
Leakage is not to exceed 150 gallons per day. | |||
: 3. The operational LEAKAGE performance criterion is specified in LCO 3.4.5, "RCS Operational LEAKAGE. | |||
NuScale 5.5-4 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Steam Generator (SG) Program (continued) | |||
: c. Provisions for SG tube plugging criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding [40%] of the nominal tube wall thickness shall be plugged. | |||
: d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube plugging criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations. | |||
: 1. Inspect 100% of the tubes in each SG during the first refueling outage following initial startup and SG replacement. | |||
: 2. After the first refueling outage following SG installation, inspect each SG at least every 72 effective full power months or at least every third refueling outage (whichever results in more frequent inspections). In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b, c and d below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated. The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up NuScale 5.5-5 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Steam Generator (SG) Program (continued) to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage. | |||
a) After the first refueling outage following SG installation, inspect 100% of the tubes during the next 144 effective full power months. This constitutes the first inspection period; b) During the next 120 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; c) During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the third inspection period; and d) During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the fourth and subsequent inspection periods. | |||
: 3. If crack indications are found in any SG tube, then the next inspection for each affected or potentially affected unit SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack. | |||
: e. Provisions for monitoring operational primary to secondary LEAKAGE. | |||
5.5.5 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include: | |||
: a. Identification of a sampling schedule for the critical variables and control points for these variables; | |||
: b. Identification of the procedures used to measure the values of the critical variables; NuScale 5.5-6 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Secondary Water Chemistry Program (continued) | |||
: c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage; | |||
: d. Procedures for the recording and management of data; | |||
: e. Procedures defining corrective actions for all off control point chemistry conditions; and | |||
: f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action. | |||
5.5.6 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Gaseous Rad-Waste Management System, the quantity of radioactivity contained in gas storage tanks or fed into the offgas treatment system, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. | |||
The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Liquid-Containing Tank Failures. | |||
The program shall include: | |||
: a. The limits for concentrations of hydrogen and oxygen in the Gaseous Rad-Waste Management System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion), | |||
: b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank and fed into the offgas treatment system is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents, and | |||
: c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radioactive Waste System is less than the amount that would NuScale 5.5-7 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued) result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents. | |||
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies. | |||
5.5.7 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications. | |||
: a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews. | |||
: b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following: | |||
: 1. A change in the TS incorporated in the license; or | |||
: 2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59. | |||
: c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR. | |||
: d. Proposed changes that meet the criteria of 5.5.7(b) above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e). | |||
5.5.8 Safety Function Determination Program (SFDP) | |||
: a. This program ensures that loss of safety function is detected and appropriate action taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the supported system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirement of LCO 3.0.6. The SFDP shall contain the following: | |||
NuScale 5.5-8 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Safety Function Determination Program (SFDP) (continued) | |||
: 1. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected; | |||
: 2. Provisions for ensuring the unit is maintained in a safe condition if a loss of function condition exists; | |||
: 3. Provisions to ensure that an inoperable supported systems Completion Time is not inappropriately extended as a result of multiple support systems inoperabilities; and | |||
: 4. Other appropriate limitations and remedial or compensatory actions. | |||
: b. A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and: | |||
: 1. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or | |||
: 2. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or | |||
: 3. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable. | |||
: c. The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system. | |||
5.5.9 Containment Leakage Rate Testing Program | |||
: a. A program shall implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option A, as modified by approved exemptions. | |||
: b. The maximum allowable containment leakage rate, La, at Pa, shall be 0.20% of containment air weight per day. | |||
NuScale 5.5-9 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Containment Leakage Rate Testing Program (continued) | |||
: c. Containment leakage rate acceptance criterion is < 0.60 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests. | |||
: d. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program. | |||
: e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J. | |||
5.5.10 Setpoint Program (SP) | |||
: a. The Setpoint Program (SP) implements the regulatory requirement of 10 CFR 50.36(c)(1)(ii)(A) that technical specifications will include items in the category of limiting safety system settings (LSSS), which are settings for automatic protective devices related to those variables having significant safety functions. | |||
: b. The Nominal Trip Setpoint (NTSP), As-Found Tolerance (AFT), and As-Left Tolerance (ALT) for each Technical Specification required automatic protection instrumentation function shall be calculated in conformance with TR-0616-49121-P, "NuScale Instrument Setpoint Methodology." | |||
: c. For each Technical Specification required automatic protection instrumentation function, performance of a CHANNEL CALIBRATION surveillance in accordance with the Setpoint Program (SP) shall include the following: | |||
: 1. The as-found value of the instrument channel trip setting shall be compared with the previously recorded as-left value. | |||
: i. If all as-found measured trip setpoint values during calibration and surveillance testing are inside the two-sided limits of Nominal Trip Setpoint (NTSP) plus or minus the Performance and Test Acceptance Criteria Band (PTAC), | |||
then the channel is fully OPERABLE, no additional actions are required. | |||
NuScale 5.5-10 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Setpoint Program (SP) (continued) ii. If during channel OPERABILITY or calibration testing, the measured trip setpoint values are within the As-Found Tolerance band but outside the As-Left Tolerance Band, then the instrumentation channel is fully OPERABLE, however, calibration is required to restore the channel within the as-left tolerance band. | |||
iii. If any as-found calibration setting value is outside the as-found Tolerance band, then the channel is inoperable, and corrective action is required. Calibration is required to restore the channel to within as-left tolerance band. | |||
: 2. The instrument channel trip setting shall be set to a value within the specified ALT around the specified NTSP at the completion of the surveillance; otherwise, the surveillance requirement is not met and the instrument channel shall be immediately declared inoperable. | |||
: d. The difference between the instrument channel trip setting as-found value and the previously recorded as-left value for each Technical Specification required automatic protection instrumentation function shall be trended and evaluated to verify that the instrument channel is functioning in accordance with its design basis. | |||
: e. The SP shall establish a document containing the current value of the specified NTSP, AFT, and ALT for each Technical Specification required automatic protection instrumentation function and references to the calculation documentation. Changes to this document shall be governed by the regulatory requirement of 10 CFR 50.59. In addition, changes to the specified NTSP, AFT, and ALT values shall be governed by the approved setpoint methodology. This document, including any revisions or supplements, shall be provided upon issuance to the NRC. | |||
5.5.11 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met. | |||
: a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program. | |||
NuScale 5.5-11 Revision 1.0 | |||
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Surveillance Frequency Control Program (continued) | |||
: b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1. | |||
: c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program. | |||
5.5.12 Spent Fuel Storage Rack Neutron Absorber Monitoring Program This Program provides controls for monitoring the condition of the neutron absorber used in the spent fuel pool storage racks to verify the neutron absorber density is consistent with the assumptions in the spent fuel pool criticality analysis. The program shall be in accordance with NEI 16-03-A, "Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools," Revision 0, May 2017. | |||
NuScale 5.5-12 Revision 1.0 | |||
Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4. | |||
5.6.1 Annual Radiological Environmental Operating Report | |||
-----------------------------------------------NOTE---------------------------------------------------- | |||
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station. | |||
The Annual Radiological Environmental Operating Report covering the operation of the facility during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. | |||
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. | |||
5.6.2 Radioactive Effluent Release Report | |||
-----------------------------------------------NOTE---------------------------------------------------- | |||
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station. | |||
The Radioactive Effluent Release Report covering the operation of the facility in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. | |||
The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1. | |||
NuScale 5.6-1 Revision 1.0 | |||
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Core Operating Limits Report (COLR) | |||
: a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following: | |||
2.1.1, "Reactor Core Safety Limits"; | |||
3.1.1, SHUTDOWN MARGIN (SDM); | |||
3.1.3, Moderator Temperature Coefficient (MTC); | |||
3.1.4, Rod Group Alignment Limits; 3.1.5, Shutdown Group Insertion Limits; 3.1.6, Regulating Group Insertion Limits; 3.1.8, PHYSICS TESTS Exceptions; 3.1.9, Boron Dilution Control; 3.2.1, Enthalpy Rise Hot Channel Factor ( F H); | |||
3.2.2, AXIAL OFFSET (AO); | |||
3.4.1, RCS Pressure, Temperature, and Flow Resistance Critical Heat Flux (CHF) Limits; and 3.5.3, Ultimate Heat Sink. | |||
: b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: | |||
: 1. [List of NRC-approved Topical Reports that are used to determine the core operating limits listed in 5.6.3.a above.] | |||
: c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Passive Core Cooling Systems limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met. | |||
NuScale 5.6-2 Revision 1.0 | |||
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Core Operating Limits Report (COLR) (continued) | |||
: d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC. | |||
5.6.4 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) | |||
: a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following: | |||
3.3.1, Module Protection System (MPS) Instrumentation; 3.3.3, Engineered Safety Features Actuation System (ESFAS) | |||
Logic and Actuation; 3.3.4, Manual Actuation Functions; 3.4.3, RCS Pressure and Temperature (P/T) Limits; and 3.4.4, Reactor Safety Valves (RSVs). | |||
: b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document: | |||
TR-1015-18177, "Pressure and Temperature Limits Methodology." | |||
: c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for any revision or supplement thereto. | |||
NuScale 5.6-3 Revision 1.0 | |||
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 3 following completion of an inspection performed in accordance with the Specification 5.5.4, "Steam Generator (SG) Program." The report shall include: | |||
: a. The scope of inspections performed on each SG. | |||
: b. Degradation mechanisms found. | |||
: c. Nondestructive examination techniques utilized for each degradation mechanism. | |||
: d. Location orientation (if linear), and measured sizes (if available) of service induced indications. | |||
: e. Number of tubes plugged during the inspection outage for each degradation mechanism. | |||
: f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator. | |||
: g. The results of condition monitoring, including the results of tube pulls and in-situ testing. | |||
NuScale 5.6-4 Revision 1.0 | |||
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20: | |||
5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation | |||
: a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment. | |||
: b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures. | |||
: c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas. | |||
: d. Each individual or group entering such an area shall possess: | |||
: 1. A radiation monitoring device that continuously displays radiation dose rates in the area; or | |||
: 2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the devices dose alarm setpoint is reached, with an appropriate alarm setpoint; or | |||
: 3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area; or | |||
: 4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter); and NuScale 5.7-1 Revision 1.0 | |||
High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued) | |||
(i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area; or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance. | |||
: e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry. | |||
5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation | |||
: a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition: | |||
: 1. All such door and gate keys shall be maintained under the administrative control of the [shift manager], radiation protection manager, or his or her designees; and | |||
: 2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit. | |||
NuScale 5.7-2 Revision 1.0 | |||
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued) | |||
: b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures. | |||
: c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas. | |||
: d. Each individual group entering such an area shall possess: | |||
: 1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the devices dose alarm setpoint is reached, with an appropriate alarm setpoint; or | |||
: 2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area; or | |||
: 3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter); and (i) Be under surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, or personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area. | |||
NuScale 5.7-3 Revision 1.0 | |||
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued) | |||
: 4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the As Low As is Reasonably Achievable principle, a radiation monitoring device that continuously displaces radiation dose rates in the area. | |||
: e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing do not require documentation prior to initial entry. | |||
: f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device. | |||
NuScale 5.7-4 Revision 1.0}} | |||
Latest revision as of 18:08, 17 March 2020
| ML18086A198 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 03/15/2018 |
| From: | Bergman T NuScale |
| To: | Office of New Reactors |
| Cranston G | |
| References | |
| NUSCALESMRDC, NUSCALESMRDC.SUBMISSION.4, NUSCALEPART04.NP, NUSCALEPART04.NP.1 | |
| Download: ML18086A198 (154) | |
Text
DCA Part 4 Volume 1 Revision 1.0 Generic Technical Specifications NuScale Nuclear Power Plants Volume 1: Specifications
TABLE OF CONTENTS Revision 1.0 USE AND APPLICATION 1.1 Definitions................................................................................................................. 1.0 1.2 Logical Connectors................................................................................................... 1.0 1.3 Completion Times .................................................................................................... 1.0 1.4 Frequency ................................................................................................................ 1.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs ........................................................................................................................... 1.0 2.1 SL Violations ............................................................................................................ 1.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .............................. 1.0 3.0 SURVEILLANCE REQUIREMENTS (SR) APPLICABILITY .......................................... 1.0 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)............................................................................ 1.0 3.1.2 Core Reactivity ................................................................................................... 1.0 3.1.3 Moderator Temperature Coefficient (MTC) ........................................................ 1.0 3.1.4 Rod Group Alignment Limits .............................................................................. 1.0 3.1.5 Shutdown Group Insertion Limits ....................................................................... 1.0 3.1.6 Regulating Group Insertion Limits ...................................................................... 1.0 3.1.7 Rod Position Indication (RPI) ............................................................................. 1.0 3.1.8 PHYSICS TESTS Exceptions............................................................................. 1.0 3.1.9 Boron Dilution Control ........................................................................................ 1.0 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Enthalpy Rise Hot Channel Factor ..................................................................... 1.0 3.2.2 AXIAL OFFSET (AO).......................................................................................... 1.0 3.3 INSTRUMENTATION 3.3.1 Module Protection System (MPS) Instrumentation............................................. 1.0 3.3.2 Reactor Trip System (RTS) Logic and Actuation................................................ 1.0 3.3.3 Engineered Safety Features Actuation System (ESFAS) Logic and Actuation ..................................................................................................... 1.0 3.3.4 Manual Actuation Functions ............................................................................... 1.0 3.3.5 Remote Shutdown Station (RSS) ....................................................................... 1.0 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Resistance Critical Heat Flux (CHF)
Limits .................................................................................................................. 1.0 3.4.2 RCS Minimum Temperature for Criticality .......................................................... 1.0 3.4.3 RCS Pressure and Temperature (P/T) Limits..................................................... 1.0 3.4.4 Reactor Safety Valves (RSVs) ........................................................................... 1.0 3.4.5 RCS Operational LEAKAGE............................................................................... 1.0 3.4.6 Chemical and Volume Control System (CVCS) Isolation Valves ....................... 1.0 3.4.7 RCS Leakage Detection Instrumentation ........................................................... 1.0 3.4.8 RCS Specific Activity .......................................................................................... 1.0 3.4.9 Steam Generator (SG) Tube Integrity ................................................................ 1.0 3.4.10 Low Temperature Overpressure Protection (LTOP) Valves ............................... 1.0 NuScale i Revision 1.0
TABLE OF CONTENTS Revision 3.0 LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS (continued) 3.5 PASSIVE CORE COOLING SYSTEMS (PCCS) 3.5.1 Emergency Core Cooling System (ECCS) ......................................................... 1.0 3.5.2 Decay Heat Removal System (DHRS) ............................................................... 1.0 3.5.3 Ultimate Heat Sink .............................................................................................. 1.0 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment ....................................................................................................... 1.0 3.6.2 Containment Isolation Valves ............................................................................. 1.0 3.7 PLANT SYSTEMS 3.7.1 Main Steam Isolation Valves (MSIVs) ................................................................ 1.0 3.7.2 Feedwater Isolation ............................................................................................ 1.0 3.8 REFUELING OPERATIONS 3.8.1 Nuclear Instrumentation ..................................................................................... 1.0 3.8.2 Decay Time ........................................................................................................ 1.0 4.0 DESIGN FEATURES 4.1 Site Location............................................................................................................. 1.0 4.2 Reactor Core ............................................................................................................ 1.0 4.3 Fuel Storage ............................................................................................................. 1.0 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility ........................................................................................................... 1.0 5.2 Organization ............................................................................................................. 1.0 5.3 Facility Staff Qualifications ....................................................................................... 1.0 5.4 Procedures ............................................................................................................... 1.0 5.5 Programs and Manuals ............................................................................................ 1.0 5.6 Reporting Requirements .......................................................................................... 1.0 5.7 High Radiation Area ................................................................................................. 1.0 NuScale ii Revision 1.0
Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions
NOTE--------------------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be:
- a. The use of diagnostic programs, or application of simulated or actual input combinations, to test digital computer hardware; and
- b. Verification of the required logic output.
An ACTUATION LOGIC TEST shall include each possible interlock logic state required for OPERABILITY of a logic circuit. The ACTUATION LOGIC TEST shall verify the OPERABILITY of each manual logic input device required for channel OPERABILITY. The ACTUATION LOGIC TEST shall be conducted such that it provides component overlap with the actuated device. The ACTUATION LOGIC TEST may be performed by means of any series of sequential, overlapping, or total steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
AXIAL OFFSET (AO) AO shall be the difference in power generated in the top half of the core (Ptop) and the bottom half of the core (Pbottom), divided by the sum of the power generated in the core (Ptotal).
AO = (Ptop - Pbottom) / Ptotal NuScale 1.1-1 Revision 1.0
Definitions 1.1 1.1 Definitions CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY.
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
CHANNEL CHECK A CHANNEL CHECK shall be the verification through the absence of alarms from the automatic analog and binary process signal monitoring features used to monitor channel behavior during operation. Deviation beyond the established acceptance criteria is alarmed to allow appropriate action to be taken. This determination shall include, where possible, comparison of channel indication and status to other indications or status derived from the independent channels measuring the same parameter.
This determination can be made using computer software or be performed manually.
CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal TEST (COT) into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
NuScale 1.1-2 Revision 1.0
Definitions 1.1 1.1 Definitions CORE OPERATING LIMITS The COLR is the unit-specific document that provides REPORT (COLR) cycle specific parameter limits for the current reload cycle.
These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Module operation within these parameter limits is addressed in individual Specifications.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same committed effective dose equivalent as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Table 2.1 of EPA Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, EPA-520/1-88-020, September 1988.
DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same effective dose equivalent as the quantity and isotopic mixture of noble gases (Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138) actually present. The dose conversion factors used for this calculation shall be those listed in Table III.1 of EPA Federal Guidance Report No. 12, External Exposure to Radionuclides in Air, Water, and Soil, EPA 402-R-93-081, September 1993.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions). The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).
NuScale 1.1-3 Revision 1.0
Definitions 1.1 1.1 Definitions LEAKAGE LEAKAGE shall be:
- a. Identified LEAKAGE
- 1. LEAKAGE from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE, or
- 2. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System (primary to secondary LEAKAGE),
- b. Unidentified LEAKAGE All LEAKAGE that is not identified LEAKAGE, and
- c. Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in a RCS component body, pipe wall, or vessel wall. A fault in an RCS component body, pipe wall, or vessel wall is isolated if LEAKAGE through the isolation device is 0.5 gpm per nominal inch of valve size up to a maximum limit of 5 gpm.
MODE A MODE shall correspond to any one inclusive combination of Reactivity Condition, Reactor Coolant Temperature, control rod assembly (CRA) capability, Chemical and Volume Control System (CVCS) and Containment Flood and Drain System (CFDS) configuration, and reactor vessel flange bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
OPERABLE-OPERABILITY A system, subsystem, separation group, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, electrical power, cooling water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
NuScale 1.1-4 Revision 1.0
Definitions 1.1 1.1 Definitions PASSIVELY COOLED - A module is in PASSIVE COOLING or is being PASSIVE COOLING PASSIVELY COOLED when:
- a. Two or more reactor vent valves are open and one or more reactor recirculation valves is open, or
- b. One or more trains of DHRS is in operation, or
- c. Water level in the containment vessel is > 45 ft.
PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:
- a. Described in Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, of the FSAR;
- b. Authorized under the provisions of 10 CFR 50.59; or
- c. Otherwise approved by the Nuclear Regulatory Commission.
PRESSURE AND The PTLR is the unit-specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.4.
RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 160 MWt.
NuScale 1.1-5 Revision 1.0
Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:
- a. Moderator temperature is 420°F; and
- b. All CRAs are fully inserted except for the single assembly of highest reactivity worth, which is assumed to be fully withdrawn. However, with all CRAs verified fully inserted by two independent means, it is not necessary to account for a stuck CRA in the SDM calculation. With any CRA(s) not capable of being fully inserted, the reactivity worth of these assemblies must be accounted for in the determination of SDM.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
NuScale 1.1-6 Revision 1.0
Definitions 1.1 Table 1.1-1 (page 1 of 1)
MODES INDICATED REACTOR REACTIVITY COOLANT MODE TITLE CONDITION (keff) TEMPERATURES (°F) 1 Operations 0.99 All 420 2 Hot Shutdown < 0.99 Any 420 3 Safe Shutdown (a) < 0.99 All < 420 4 Transition (b)(c) < 0.95 N/A 5 Refueling (d) N/A N/A (a) Any CRA capable of withdrawal, any CVCS or CFDS connection to the module not isolated.
(b) All CRAs incapable of withdrawal, CVCS and CFDS connections to the module isolated, and all reactor vent valves electrically isolated.
(c) All reactor vessel flange bolts fully tensioned.
(d) One or more reactor vessel flange bolts less than fully tensioned.
NuScale 1.1-7 Revision 1.0
Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.
Logical connectors are used in Technical Specifications to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in Technical Specifications are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meaning.
BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).
The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.
EXAMPLES The following examples illustrate the use of logical connectors.
NuScale 1.2-1 Revision 1.0
Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)
EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify AND A.2 Restore In this example, the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.
NuScale 1.2-2 Revision 1.0
Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)
EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip OR A.2.1 Verify AND A.2.2.1 Reduce OR A.2.2.2 Perform OR A.3 Align This example represents a more complicated use of logical connectors.
Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.
NuScale 1.2-3 Revision 1.0
Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.
BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).
DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the discovery of a situation (e.g.,
inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO.
Unless otherwise specified, the Completion Time begins when a senior licensed operator on the operating shift crew with responsibility for plant operations makes the determination that an LCO is not met and an ACTIONS Condition is entered. The "otherwise specified" exceptions are varied, such as a Required Action Note or Surveillance Requirement Note that provides an alternative time to perform specific tasks, such as testing, without starting the Completion Time. While utilizing the Note, should a Condition be applicable for any reason not addressed by the Note, the Completion Time begins. Should the time allowance in the Note be exceeded, the Completion Time begins at that point.
Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.
If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified.
NuScale 1.3-1 Revision 1.0
Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)
Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition, unless otherwise specified.
However, when a subsequent train, subsystem, component, or variable, expressed in the Condition, is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:
- a. Must exist concurrent with the first inoperability; and
- b. Must remain inoperable or not within limits after the first inoperability is resolved.
The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:
- a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; or
- b. The stated Completion Time as measured from discovery of the subsequent inoperability.
The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.
The above Completion Time extension does not apply to a Completion Time with a modified time zero. This modified time zero may be expressed as a repetitive time (i.e., once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase from discovery ....
NuScale 1.3-2 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion AND Time not met.
B.2 Be in MODE 3. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.
The Required Actions of Condition B are to be in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND in MODE 3 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A total of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is allowed for reaching MODE 2 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />) is allowed for reaching MODE 3 from the time that Condition B was entered. If MODE 2 is reached within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the time allowed for reaching MODE 3 is the next 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> because the total time allowed for reaching MODE 3 is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
If Condition B is entered while in MODE 2, the time allowed for reaching MODE 3 is the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
NuScale 1.3-3 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One valve A.1 Restore valve to 7 days inoperable. OPERABLE status.
B. Required Action B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion AND Time not met.
B.2 Be in MODE 3. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> When a valve is declared inoperable, Condition A is entered. If the valve is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion time clocks for Required Actions B.1 and B.2 start. If the inoperable valve is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.
When a second valve is declared inoperable while the first valve is still inoperable, Condition A is not re-entered for the second valve. LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable valve. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.
While in LCO 3.0.3, if one of the inoperable valves is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A.
While in LCO 3.0.3, if one of the inoperable valves is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.
NuScale 1.3-4 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
On restoring one of the valves to OPERABLE status the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. This Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve.
A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> extension to the stated 7 days is allowed, provided this does not result in the second valve being inoperable for > 7 days.
EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X A.1 Restore Function 7 days train X train to inoperable. OPERABLE status.
B. One Function Y B.1 Restore Function Y 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> train train to inoperable. OPERABLE status.
C. One Function X C.1 Restore Function 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> train X train to inoperable. OPERABLE status.
AND OR One Function Y train C.2 Restore Function Y 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. train to OPERABLE status.
NuScale 1.3-5 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).
If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).
It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.
NuScale 1.3-6 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> valves OPERABLE status.
B. Required B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not met. B.2 Be in MODE 3. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.
Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
If the Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (including the extension) expires while one or more valves are still inoperable, Condition B is entered.
NuScale 1.3-7 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
EXAMPLE 1.3-5 ACTIONS
NOTE----------------------------------------------
Separate Condition entry is allowed for each inoperable valve.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> valves OPERABLE inoperable. status.
B. Required B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not met. B.2 Be in MODE 3. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was only applicable to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.
The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.
If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve which caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve. Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.
NuScale 1.3-8 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable. SR 3.x.x.x.
OR A.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to 50%
RTP.
B. Required Action B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion Time not met.
Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a once per Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval. If Required Action A.1 is followed, and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2),
Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is not met, Condition B is entered.
If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.
NuScale 1.3-9 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem A.1 Verify affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. subsystem isolated. AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to OPERABLE status.
B. Required Action B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion AND Time not met.
B.2 Be in MODE 3. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time begins at the time the Condition is entered and each Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter interval begins upon performance of Required Action A.1.
NuScale 1.3-10 Revision 1.0
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or any subsequent 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.
IMMEDIATE When Immediately is used as a Completion Time, the Required Action COMPLETION should be pursued without delay and in a controlled manner.
TIME NuScale 1.3-11 Revision 1.0
Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.
DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.
The specified Frequency is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)
Applicability. The specified Frequency consists of the requirements of the Frequency column of each SR as well as certain Notes in the Surveillance column that modify performance requirements.
Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are otherwise stated conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillances, or both.
Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only required when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.
The use of met or performed in these instances conveys specific meanings. A Surveillance is met only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not met. Performance refers only to the requirement to specifically determine the ability to meet the acceptance criteria.
Some Surveillances contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:
NuScale 1.4-1 Revision 1.0
Frequency 1.4 1.4 Frequency DESCRIPTION (continued)
- a. The Surveillance is not required to be met in the MODE or other specified condition to be entered; or
- b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to be failed; or
- c. The Surveillance is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed.
Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations.
EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1 and 2.
EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR in not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside the specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.
NuScale 1.4-2 Revision 1.0
Frequency 1.4 1.4 Frequency EXAMPLES (continued)
If the interval specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.
EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after 25% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector AND indicates that both Frequency requirements must be met. Each time the reactor power is increased from a power level
< 25% RTP to 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The use of once indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by AND).
This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2. Thereafter indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the once performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.
NuScale 1.4-3 Revision 1.0
Frequency 1.4 1.4 Frequency EXAMPLES (continued)
EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
NOTE-------------------------
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 25% RTP.
Perform channel adjustment. 7 days The interval continues, whether or not the unit operation is < 25% RTP between performances.
As the Note modifies the required performance of the Surveillance, it is construed to be part of the specified Frequency. Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after power reaches 25% RTP to perform the Surveillance.
The Surveillance is still considered to be performed within the specified Frequency. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was
< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (plus the extension allowed by SR 3.0.2) with power 25% RTP.
Once the unit reaches 25% RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.
NuScale 1.4-4 Revision 1.0
Frequency 1.4 1.4 Frequency EXAMPLES (continued)
EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
NOTE-------------------------
Only required to be met in MODE 1.
Verify leakage rates are within limits. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an otherwise stated exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval (plus the extension allowed by SR 3.0.2), but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency were not met), SR 3.0.4 would require satisfying the SR.
NuScale 1.4-5 Revision 1.0
Frequency 1.4 1.4 Frequency EXAMPLES (continued)
EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
NOTE-------------------------
Only required to be performed in MODE 1.
Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1 or 2 (the assumed Applicability of the associated LCO) between performances.
As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the specified Frequency. Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODE 2 to perform the Surveillance.
The Surveillance is still considered to be performed within the specified Frequency if completed prior to entering MODE 1. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1.
Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance were not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.
NuScale 1.4-6 Revision 1.0
Frequency 1.4 1.4 Frequency EXAMPLES (continued)
EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
NOTE-------------------------
Not required to be met in MODE 2.
Verify parameter is within limits. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 2 (the assumed Applicability of the associated LCO is MODES 1 and 2). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an otherwise stated exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 2, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 2, even with the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency exceeded, provided the MODE change does not result in entry into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency were not met), SR 3.0.4 would require satisfying the SR.
NuScale 1.4-7 Revision 1.0
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODE 1 the critical heat flux ratio shall be maintained the 95/95 critical heat flux ratio criterion for the critical heat flux correlation(s) specified in Section 5.6.3.
2.1.1.2 In MODE 1 the peak fuel centerline temperature shall be maintained 4901 - (1.37E-3 x Burnup, MWD/MTU) °F.
2.1.2 RCS Pressure SL In MODES 1, 2, and 3 pressurizer pressure shall be maintained 2285 psia.
2.2 Safety Limit Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 2 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1, restore compliance and be in MODE 2 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 2 or 3, restore compliance within 5 minutes.
NuScale 2.0-1 Revision 1.0
LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, [and] LCO 3.0.7[,
and LCO 3.0.8].
LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and 3.0.6.
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.
LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:
- a. MODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />; and
- b. MODE 3 and PASSIVELY COOLED within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Exceptions to this Specification are stated in the individual Specifications.
Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.
LCO 3.0.3 is only applicable in MODES 1 and 2, and in MODE 3 when not PASSIVELY COOLED.
LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:
- a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; NuScale 3.0-1 Revision 1.0
LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 (continued)
- b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate (exceptions to this Specification are stated in the individual Specifications); or
- c. When an allowance is stated in the individual value, parameter, or other Specification.
This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered.
Only the support system LCO ACTIONS are required to be entered.
This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.8, Safety Function Determination Program (SFDP). If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
When a support systems Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.
NuScale 3.0-2 Revision 1.0
LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.7 Test Exception LCO 3.1.8 allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional.
When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.
[ ------------------------------ REVIEWERS NOTE ------------------------------------
A COL applicant who wants to adopt LCO 3.0.8 must perform or reference a risk assessment for the NuScale design that has been submitted to the NRC, and that was prepared consistent with the bounding generic risk assessment provided in TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System OPERABILITY, Revision 2-A.
]
[LCO 3.0.8 When one or more required barriers are unable to perform their related support function(s), any supported system LCO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support function(s), and risk is assessed and managed. This Specification may be concurrently applied to more than one train or subsystem of a multiple train or subsystem supported system provided at least one train or subsystem of the supported system is OPERABLE and the barriers supporting each of these trains or subsystems provide their related support function(s) for different categories of initiating events.
If the required OPERABLE train or subsystem becomes inoperable while this Specification is in use, it must be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the provisions of this Specification cannot be applied to the trains or subsystems supported by the barriers that cannot perform their related support function(s).
At the end of the specified period, the required barriers must be able to perform their related support function(s) or the supported system LCO(s) shall be declared not met.]
NuScale 3.0-3 Revision 1.0
SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENTS (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified Conditions in the applicability of individual LCOs, unless otherwise stated in the SR.
Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be a failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as once, the above interval extension does not apply.
If a Completion Time requires periodic performance on a once per...
basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this Specification are stated in the individual Specifications.
SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. The delay period is only applicable when there is a reasonable expectation the Surveillance will be met when performed.
A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
When the Surveillance is performed within the delay period, and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
NuScale 3.0-4 Revision 1.0
SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of a LCO shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
NuScale 3.0-5 Revision 1.0
SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)
LCO 3.1.1 SDM shall be within the limits specified in the COLR.
APPLICABILITY: MODE 1 with keff < 1.0, MODES 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits. A.1 Initiate boration to restore 15 minutes SDM to within limits.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 ------------------------------NOTE--------------------------------
Not required to be performed in MODE 4.
Verify SDM to be within limits specified in the COLR. In accordance with the Surveillance Frequency Control Program NuScale 3.1.1-1 Revision 1.0
Core Reactivity 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity LCO 3.1.2 The core reactivity balance shall be within +/-1% k/k of the normalized predicted values.
APPLICABILITY: MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity balance A.1 Re-evaluate core design and 7 days not within limit. safety analysis and determine that the reactor core is acceptable for continued operation.
AND A.2 Establish appropriate 7 days operating restrictions.
B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
NuScale 3.1.2-1 Revision 1.0
Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ------------------------------NOTE--------------------------------
Predicted reactivity values may be adjusted to correspond to measured core reactivity prior to exceeding a fuel burnup of 60 effective full power days (EFPD) after each fuel loading.
Verify overall core reactivity balance is within Once prior to
+/-1% k/k of predicted values. exceeding 5%
RTP after each refueling AND
NOTE--------
Only required after 60 EFPD In accordance with the Surveillance Frequency Control Program NuScale 3.1.2-2 Revision 1.0
MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)
LCO 3.1.3 MTC shall be within limits specified in the COLR.
APPLICABILITY: MODE 1 for upper MTC limit, MODES 1 and 2 for lower MTC limit, MODE 3 with any RCS temperature 200°F for lower MTC limit.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within limits. A.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B. MTC not within lower B.1 Be in MODE 3 with all 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit. RCS temperatures
< 200°F.
NuScale 3.1.3-1 Revision 1.0
MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within the upper limit. Once prior to exceeding 5%
RTP after each fuel loading SR 3.1.3.2 Verify MTC is within the lower limit. Once within 7 effective full power days (EFPDs) after reaching 40 EFPDs fuel burnup from beginning of cycle (BOC)
AND Once within 7 EFPDs after reaching 2/3 fuel burnup from BOC AND
NOTE------
Only required when projected end of cycle MTC is not within limit 7 EFPDs thereafter NuScale 3.1.3-2 Revision 1.0
Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and regulating control rod assemblies (CRAs) shall be OPERABLE.
AND Individual CRA positions shall be within 6 steps of their group position.
APPLICABILITY: MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more CRAs A.1.1 Verify SDM to be within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. limits specified in the COLR.
OR OR One or more CRAs not within alignment limits. A.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.
AND A.2 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> NuScale 3.1.4-1 Revision 1.0
Rod Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 -----------------------------NOTE-------------------------------
Not required to be performed for rods associated with an inoperable rod position indicator.
Verify position of individual CRAs within alignment In accordance limit. with the Surveillance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement (trippability) by In accordance moving each rod not fully inserted in the with the core 4 steps in either direction. Surveillance Frequency Control Program SR 3.1.4.3 Verify each CRA drop time 2.2 seconds. Prior to reactor criticality after each removal of the upper reactor pressure vessel section NuScale 3.1.4-2 Revision 1.0
Shutdown Group Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Group Insertion Limits LCO 3.1.5 Each shutdown group shall be within insertion limits specified in the COLR.
NOTE-------------------------------------------------
Not applicable to shutdown groups inserted while performing SR 3.1.4.2.
APPLICABILITY: MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Shutdown group not A.1.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> within limits. limits specified in the COLR.
OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.
AND A.2 Restore shutdown group 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to within limits.
B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
NuScale 3.1.5-1 Revision 1.0
Shutdown Group Insertion Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown group is within the insertion In accordance limits specified in the COLR. with the Surveillance Frequency Control Program NuScale 3.1.5-2 Revision 1.0
Regulating Group Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Regulating Group Insertion Limits LCO 3.1.6 Each regulating group shall be within the insertion limits specified in the COLR.
NOTE---------------------------------------------
Not applicable to regulating groups inserted while performing SR 3.1.4.2.
APPLICABILITY: MODE 1 with keff 1.0.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Regulating group A.1.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> insertion limits not met. limits specified in the COLR.
OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limits.
AND A.2 Restore regulating group 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to within limits.
B. Required Action and B.1 Be in MODE 1 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion keff < 1.0.
Time not met.
NuScale 3.1.6-1 Revision 1.0
Regulating Group Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify each regulating group is within the insertion In accordance with limits specified in the COLR. the Surveillance Frequency Control Program NuScale 3.1.6-2 Revision 1.0
Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication (RPI)
LCO 3.1.7 The Control Rod Drive System (CRDS) Rod Position Indication (RPI)
System and the Control Rod Assembly (CRA) Counter Position Indication (CPI) System shall be OPERABLE.
APPLICABILITY: MODE 1.
ACTIONS
NOTE-------------------------------------------------------------
Separate Condition entry is allowed for each inoperable CRDS rod position indicator and each CRA counter position indicator.
CONDITION REQUIRED ACTION COMPLETION TIME A. One RPI per CRDM A.1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for one or CRA with inoperable more CRDMs. position indicators with the Module Control System (MCS).
B. More than one RPI per B.1 Place the CRA under Immediately CRDM inoperable. manual control.
AND B.2 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CRA with inoperable CRDS position indicators indirectly by using the incore detectors.
AND NuScale 3.1.7-1 Revision 1.0
Rod Position Indication 3.1.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Restore inoperable rod 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> position indicators to OPERABLE status such that a maximum of one RPI per CRDM is inoperable.
C. One or more control C.1 Verify the position of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> rod drive mechanisms CRA with inoperable (CRDMs) with position indicators by inoperable position using the MCS.
indicators have been moved in excess of 6 steps in one direction since the last determination of the CRAs position.
D. CRA CPI position D.1 Verify by administrative Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indicator inoperable for means all RPIs for the one or more CRAs. affected groups are OPERABLE.
AND D.2 Verify the most withdrawn Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CRA and the least withdrawn CRA of the affected groups are 6 steps apart.
E. Required Action and E.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
NuScale 3.1.7-2 Revision 1.0
Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each RPI agrees within 6 steps of the group Prior to criticality demand position for the full indicated range of CRA after coupling of travel. one or more CRA to the associated CRDM NuScale 3.1.7-3 Revision 1.0
PHYSICS TESTS Exceptions 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of:
LCO 3.1.3, Moderator Temperature Coefficient (MTC),
LCO 3.1.4, Rod Group Alignment Limits, LCO 3.1.5, Shutdown Group Insertion Limits, and LCO 3.1.6, Regulating Group Insertion Limits may be suspended provided:
- b. THERMAL POWER is 5% RTP.
APPLICABILITY: During PHYSICS TESTS initiated in MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.
AND A.2 Suspend PHYSICS TESTS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> exceptions.
B. THERMAL POWER not B.1 Open reactor trip breakers. Immediately within limit.
NuScale 3.1.8-1 Revision 1.0
PHYSICS TESTS Exceptions 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Verify THERMAL POWER is 5% RTP. In accordance with the Surveillance Frequency Control Program SR 3.1.8.2 Verify SDM is within the limits specified in the In accordance COLR. with the Surveillance Frequency Control Program NuScale 3.1.8-2 Revision 1.0
Boron Dilution Control 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 Boron Dilution Control LCO 3.1.9 Two CVCS demineralized water isolation valves shall be OPERABLE.
AND Boric Acid Storage Tank boron concentration shall be within the limits specified in the COLR.
AND Maximum CVCS makeup pump demineralized water flow path flowrate is within the limits specified in the COLR.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CVCS A.1 Restore CVCS 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> demineralized water demineralized water isolation valve isolation valves to inoperable. OPERABLE status.
NuScale 3.1.9-1 Revision 1.0
Boron Dilution Control 3.1.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 --------------NOTE------------
associated Completion Flow path(s) may be Time not met. unisolated intermittently under administrative OR controls.
Two CVCS demineralized water Isolate dilution source flow 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolation valves paths in the CVCS inoperable. makeup line by use of at least one closed manual or OR one closed and de-activated automatic valve.
Boric Acid Storage Tank not within limits.
OR CVCS makeup pump demineralized water flow path not configured to ensure maximum flowrate is within limits.
NuScale 3.1.9-2 Revision 1.0
Boron Dilution Control 3.1.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify that CVCS makeup pump demineralized In accordance water flow path is configured to ensure that it with the remains within the limits specified in the COLR. Surveillance Frequency Control Program SR 3.1.9.2 Verify each automatic CVCS demineralized water In accordance isolation valve that is not locked, sealed, or with the otherwise secured in the isolated position, actuates Surveillance to the isolated position on an actual or simulated Frequency signal except for valves that are open under Control Program administrative controls.
SR 3.1.9.3 Verify Boric Acid Storage Tank boron concentration In accordance to be within the limits specified in the COLR. with the Surveillance Frequency Control Program SR 3.1.9.4 Verify each CVCS makeup pump maximum In accordance flowrate is 25 gpm. with the Surveillance Frequency Control Program NuScale 3.1.9-3 Revision 1.0
FH 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Enthalpy Rise Hot Channel Factor ( F H )
LCO 3.2.1 FH shall be within the limits specified in the COLR.
APPLICABILITY: MODE 1 with THERMAL POWER 25% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. FH not within limit. A.1 Reduce THERMAL POWER 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to < 25% RTP.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify FH within limits specified in the COLR. Once after each refueling prior to THERMAL POWER exceeding 25% RTP AND In accordance with the Surveillance Frequency Control Program NuScale 3.2.1-1 Revision 1.0
AO 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 AXIAL OFFSET (AO)
LCO 3.2.2 The AO shall be maintained within the limits specified in the COLR.
APPLICABILITY: MODE 1 with THERMAL POWER 25% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AO not within limits. A.1 Reduce THERMAL POWER 6 Hours to < 25% RTP.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify AO within limits using all OPERABLE in-core In accordance instrumentation channels. with the Surveillance Frequency Control Program NuScale 3.2.2-1 Revision 1.0
MPS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Module Protection System (MPS) Instrumentation LCO 3.3.1 MPS instrumentation channels required for each Function in Table 3.3.1-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.1-1.
ACTIONS
NOTE--------------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place inoperable channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with one channel bypass or trip.
B. One or more Functions B.1 Place one inoperable 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with two channels channel in bypass.
AND B.2 Place one inoperable 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> channel in trip.
C. Required Action and C.1 Enter Condition referenced Immediately associated Completion in Table 3.3.1-1 for the Time of Condition A or B channel(s).
not met.
OR One or more Functions with three or more channels inoperable.
NuScale 3.3.1-1 Revision 1.0
MPS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Open reactor trip breakers. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action C.1 and referenced in Table 3.3.1-1.
E. As required by Required E.1 Reduce THERMAL POWER 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action C.1 and to below the N-2L interlock.
referenced in Table 3.3.1-1.
F. As required by Required F.1 --------------NOTE----------------
Action C.1 and CVCS flow path(s) may be referenced in unisolated intermittently Table 3.3.1-1. under administrative controls.
Isolate the CVCS flow to the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Reactor Coolant System (RCS).
G. As required by Required G.1 Open pressurizer heater 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action C.1 and breakers.
referenced in Table 3.3.1-1.
H. As required by Required H.1 Isolate demineralized water 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action C.1 and flow path to RCS.
referenced in Table 3.3.1-1.
I. As required by Required I.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action C.1 and referenced in AND Table 3.3.1-1.
I.2 Be in MODE 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> PASSIVELY COOLED.
NuScale 3.3.1-2 Revision 1.0
MPS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required J.1 Open two reactor vent 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action C.1 and valves.
referenced in Table 3.3.1-1.
K. As required by Required K.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action C.1 and referenced in AND Table 3.3.1-1.
K.2 Be in MODE 3. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> L. As required by Required L.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action C.1 and referenced in AND Table 3.3.1-1.
L.2 Be in MODE 3 with RCS 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> temperature below the T-2 interlock.
M. As required by Required M.1 Be in MODE 2. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Action C.1 and referenced in AND Table 3.3.1-1.
M.2 Be in MODE 3 and 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> PASSIVELY COOLED.
AND M.3 Be in MODE 3 with RCS 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> temperaturebelow the T-2 interlock.
AND NuScale 3.3.1-3 Revision 1.0
MPS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME M. (continued) M.4 Isolate demineralized water 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> flow to the reactor coolant system.
AND M.5 Open pressurizer heater 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> breakers.
N. As required by Required N.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action C.1 and referenced in AND Table 3.3.1-1.
N.2.1 Be in MODE 3 with RCS 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> temperature below the T-2 interlock.
OR N.2.2 Be in MODE 3 with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Containment Water Level above the L-1 interlock.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK on each required In accordance with channel listed in Table 3.3.1-1. the Surveillance Frequency Control Program NuScale 3.3.1-4 Revision 1.0
MPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.2 -------------------------------NOTES---------------------------
- 1. Adjust Neutron Monitoring System (NMS) nuclear instrument channel when absolute difference is
> 1% RTP.
- 2. 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 reaching 15% RTP.
- 3. If the calorimetric heat balance is < 15% RTP, and if NMS nuclear instrumentation channel indicated power is:
- a. lower than the calorimetric measurement by
> 1%, then adjust the NMS nuclear instrumentation channel upward to match the calorimetric measurement.
- b. higher than the calorimetric measurement, then no adjustment is required.
Compare results of calorimetric heat balance to NMS In accordance with nuclear instrument channel output. the Surveillance Frequency Control Program SR 3.3.1.3 -------------------------------NOTE-----------------------------
Neutron detectors are excluded from response time testing.
Verify channel RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program NuScale 3.3.1-5 Revision 1.0
MPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.4 -------------------------------NOTE-----------------------------
Neutron detectors are excluded from the CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION on each In accordance with required channel listed in Table 3.3.1-1. the Surveillance Frequency Control Program SR 3.3.1.5 Verify associated Class 1E isolation devices are In accordance with OPERABLE. the Surveillance Frequency Control Program.
NuScale 3.3.1-6 Revision 1.0
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 7)
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS
- 1. High Power Range Linear Power (a) (a)
- a. RTS 1, 2 , 3 4 D (a) (a)
- b. DWSI 1, 2 , 3 4 H
- 2. High Power Range Positive and Negative Rate (b)
- a. RTS 1 4 E (b)
- b. DWSI 1 4 H
- 3. High Intermediate Range Log Power Rate (c) (a) (a)
- a. RTS 1 ,2 ,3 4 D (c) (a) (a)
- b. DWSI 1 ,2 ,3 4 H
- 4. High Source Range Count Rate (d) (a) (a)
- a. RTS 1 ,2 ,3 4 D (d) (a) (a)
- b. DWSI 1 ,2 ,3 4 H
- 5. High Source Range Log Power Rate (d) (a) (a)
- a. RTS 1 ,2 ,3 4 D (d) (a) (a)
- b. DWSI 1 ,2 ,3 4 H
- 6. High Subcritical Multiplication (d) (a) (a)
- a. DWSI 1 ,2 ,3 4 H (a) When capable of CRA withdrawal.
(b) Above the N-2H Interlock.
(c) Below the N-2L Interlock.
(d) When Intermediate Range Log Power less than N-1 interlock.
NuScale 3.3.1-7 Revision 1.0
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 7)
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS
- 7. High Pressurizer Pressure (a) (a)
- a. RTS 1, 2 , 3 4 D (e)
- b. DHRS 1, 2, 3 4 I (f) (f)
- c. Pressurizer Heater Trip 1, 2 , 3 4 G (a) (a)
- d. DWSI 1, 2 , 3 4 H
- 8. Low Pressurizer Pressure (g)
- a. RTS 1 4 D (g)
- b. DHRS 1 4 D (g)
- c. CVCSI 1 4 F (g)
- d. Pressurizer Heater Trip 1 4 G (g)
- e. DWSI 1 4 H
- 9. Low Low Pressurizer Pressure (a)
- a. RTS 1, 2 4 D
- b. DHRS 1, 2 4 I
- c. CVCSI 1, 2 4 F
- d. Pressurizer Heater Trip 1, 2 4 G (a)
- e. DWSI 1, 2 4 H (a) When capable of CRA withdrawal.
(e) When not PASSIVELY COOLED.
(f) With pressurizer heater trip breakers closed.
(g) With narrow range RCS hot temperature above the T-4 interlock.
NuScale 3.3.1-8 Revision 1.0
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 7)
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS
- 10. High Pressurizer Level (a) (a)
- a. RTS 1, 2 , 3 4 D
- b. CVCSI 1, 2, 3 4 F (a) (a)
- c. DWSI 1, 2 , 3 4 H
- 11. Low Pressurizer Level (a) (a)
- a. RTS 1, 2 , 3 4 D (f) (f)
- b. Pressurizer Heater Trip 1, 2 , 3 4 G (a) (a)
- c. DWSI 1, 2 , 3 4 H
- 12. Low Low Pressurizer Level (h)
- a. DHRS 1, 2, 3 4 N (h)
- b. CIS 1, 2, 3 4 L (h)
- c. CVCSI 1, 2, 3 4 F (f) (f)
- d. Pressurizer Heater Trip 1, 2 , 3 4 G
- 13. High Narrow Range RCS Hot Temperature
- a. RTS 1 4 D (e)
- b. DHRS 1, 2, 3 4 I (f) (f)
- c. Pressurizer Heater Trip 1, 2 , 3 4 G
- d. DWSI 1 4 H
- 14. Low RCS Flow
- a. DWSI 1, 2, 3 4 H (a) When capable of CRA withdrawal.
(e) When not PASSIVELY COOLED.
(f) With pressurizer heater trip breakers closed.
(h) With RCS temperature above the T-2 interlock and containment water level below the L-1 interlock.
NuScale 3.3.1-9 Revision 1.0
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7)
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS
- 15. Low Low RCS Flow (a) (a)
- a. RTS 1, 2 , 3 4 D
- b. CVCSI 1, 2, 3 4 F (a) (a)
- c. DWSI 1, 2 , 3 4 H
- 16. Low RPV Riser Level
- a. ECCS 1, 2, 3 4 I
- 17. High Main Steam Pressure (a)
- b. DHRS 1, 2, 3 4 per SG I (f) (f)
- c. Pressurizer Heater Trip 1, 2 , 3 4 per SG G (a)
- d. DWSI 1, 2 4 per SG H
- 18. Low Main Steam Pressure (b)
- b. DHRS 1 4 per SG E (b)
- c. Pressurizer Heater Trip 1 4 per SG E (b)
- d. DWSI 1 4 per SG H (a) When capable of CRA withdrawal.
(b) With power above the N-2H interlock.
(e) When not PASSIVELY COOLED.
(f) With pressurizer heater trip breakers closed.
NuScale 3.3.1-10 Revision 1.0
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 7)
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS
- 19. Low Low Main Steam Pressure (a)
- b. DHRS 1, 2 4 per SG K (f)
- c. Pressurizer Heater Trip 1, 2 4 per SG G (a)
- d. DWSI 1, 2 4 per SG H
- 20. High Steam Superheat
- b. DHRS 1 4 per SG D
- c. Pressurizer Heater Trip 1 4 per SG G
- d. DWSI 1 4 per SG H
- 21. Low Steam Superheat
- b. DHRS 1 4 per SG D
- c. Pressurizer Heater Trip 1 4 per SG G
- d. DWSI 1 4 per SG H (a) When capable of CRA withdrawal.
(f) With pressurizer heater trip breakers closed.
NuScale 3.3.1-11 Revision 1.0
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 7)
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS
- 22. High Narrow Range Containment Pressure (a) (a)
- a. RTS 1, 2 , 3 4 D (e)
- b. DHRS 1, 2, 3 4 I (i)
- c. CIS 1, 2, 3 4 L (i)
- d. CVCSI 1, 2, 3 4 F (f) (f)
- e. Pressurizer Heater Trip 1, 2 , 3 4 G (a) (a)
- f. DWSI 1, 2 , 3 4 H
- 23. High Containment Water Level (e)
- a. ECCS 1, 2, 3 4 I
- 24. High RCS Pressure - Low Temperature Overpressure Protection (k)
- a. LTOP 3 4 J
- 25. Low AC Voltage to ELVS Battery Chargers (a) (a)
- a. RTS 1, 2 , 3 4 per bus M (e)
- b. DHRS 1, 2, 3 4 per bus M
- c. CIS 1, 2, 3 4 per bus M (a) (a)
- d. DWSI 1, 2 , 3 4 per bus M (f)
- e. Pressurizer Heater Trip 1, 2 4 per bus M (a) When capable of CRA withdrawal.
(e) When not PASSIVELY COOLED.
(f) With pressurizer heater trip breakers closed.
(i) With RCS temperature above the T-3 interlock.
(k) With wide range RCS cold temperature below the LTOP enable temperature specified in the PTLR (T-1 interlock) and more than one reactor vent valve closed.
NuScale 3.3.1-12 Revision 1.0
MPS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7)
Module Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS
- 26. High Under-the-Bioshield Temperature (a) (a)
- a. RTS 1, 2 , 3 4 M
- b. DHRS 1, 2, 3 4 M
- c. CIS 1, 2, 3 4 M (a) (a)
- d. DWSI 1, 2 , 3 4 M (f) (f)
- e. Pressurizer Heater Trip 1, 2 , 3 4 M (a) When capable of CRA withdrawal.
(f) With pressurizer heater trip breakers closed.
NuScale 3.3.1-13 Revision 1.0
Reactor Trip System Logic and Actuation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Reactor Trip System (RTS) Logic and Actuation LCO 3.3.2 Reactor Trip System (RTS) Logic and Actuation shall be OPERABLE.
APPLICABILITY: MODE 1, MODES 2 and 3 when capable of CRA withdrawal.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One reactor trip breaker A.1 Open the inoperable RTB. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (RTB) inoperable.
B. One division of RTS logic B.1 Restore division of RTS 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and actuation inoperable. logic and actuation to OPERABLE status.
C. Required Action and C.1 Open all RTBs. Immediately associated Completion Time not met.
OR Both divisions of RTS logic and actuation inoperable.
OR More than one RTB inoperable.
NuScale 3.3.2-1 Revision 1.0
Reactor Trip System Logic and Actuation 3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1 ------------------------------NOTE------------------------------
Not required to be met for reactor trip breakers that are open.
Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2 ------------------------------NOTES------------------------------
- 1. Neutron detectors are excluded from response time testing.
- 2. Not required to be met for reactor trip breakers that are open.
Verify RTS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.2.3 ------------------------------NOTE------------------------------
Not required to be met for Class 1E isolation devices that have isolated 1E circuits from non-1E power.
Verify associated Class 1E isolation devices are In accordance with OPERABLE. the Surveillance Frequency Control Program SR 3.3.2.4 ------------------------------NOTE------------------------------
Not required to be met for reactor trip breakers that are open.
Verify each RTB actuates to the open position on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program NuScale 3.3.2-2 Revision 1.0
ESFAS Logic and Actuation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Engineered Safety Features Actuation System (ESFAS) Logic and Actuation LCO 3.3.3 Engineered Safety Features Actuation System (ESFAS) Logic and Actuation divisions required for each Function in Table 3.3.3-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.3-1.
ACTIONS
NOTE------------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more divisions of A.1 Open two reactor vent 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the LTOP Logic and valves (RVVs).
Actuation Function inoperable.
B. One division of required B.1 Enter the Condition 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ESFAS function in Referenced in Table 3.3.3-1 inoperable Table 3.3.3-1 for the other than LTOP function(s).
function.
NuScale 3.3.3-1 Revision 1.0
ESFAS Logic and Actuation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action B.1 and referenced in AND Table 3.3.3-1.
C.2 Be in MODE 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR PASSIVELY COOLED.
Both divisions of ECCS actuation function inoperable.
OR Both divisions of DHRS actuation function inoperable.
D. As required by Required D.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action B.1 and referenced in AND Table 3.3.3-1.
D.2 Be in MODE 3 with RCS 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> OR temperature below the T-2 interlock.
Both divisions of Containment Isolation actuation function inoperable.
NuScale 3.3.3-2 Revision 1.0
ESFAS Logic and Actuation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 ---------------NOTE---------------
Action B.1 and Flow path(s) may be referenced in unisolated intermittently Table 3.3.3-1. under administrative controls.
OR --------------------------------------
Both divisions of Isolate the flow path from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Demineralized Water the demineralized water Supply Isolation storage tank to the reactor actuation function coolant system by use of at inoperable. least one closed manual or one closed and de-activated automatic valve.
F. As required by Required F.1 ----------------NOTE--------------
Action B.1 and Flow path(s) may be referenced in unisolated intermittently Table 3.3.3-1. under administrative controls.
OR --------------------------------------
Both divisions of CVCS Isolate CVCS charging and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Isolation actuation letdown flow paths to the function inoperable. Reactor Coolant System by use of at least one closed manual or one closed and de-activated automatic valve.
G. As required by Required G.1 ----------------NOTE--------------
Action B.1 and Heater(s) may be energized referenced in intermittently under manual Table 3.3.3-1. controls.
OR De-energize Pressurizer 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Both divisions of Heaters.
Pressurizer Heater de-energization function inoperable.
NuScale 3.3.3-3 Revision 1.0
ESFAS Logic and Actuation 3.3.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.3.2 ---------------------------------NOTES----------------------------
- 1. Neutron detectors are excluded from response time testing.
- 2. Not required to be met for components that are in their actuated position or under administrative controls.
Verify required RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.3.3 ---------------------------------NOTE------------------------------
Not required to be met for Class 1E isolation devices that have isolated 1E circuits from non-1E power.
Verify associated Class 1E isolation devices are In accordance with OPERABLE. the Surveillance Frequency Control Program SR 3.3.3.4 ---------------------------------NOTE------------------------------
Not required to be met for pressurizer heater trip breakers that are open or breakers closed under administrative controls.
Verify each pressurizer heater trip breaker (PHTB) In accordance with actuates to the open position on an actual or the Surveillance simulated actuation signal. Frequency Control Program NuScale 3.3.3-4 Revision 1.0
ESFAS Logic and Actuation 3.3.3 Table 3.3.3-1 (page 1 of 1)
ESFAS Logic and Actuation Functions APPLICABLE MODES OR OTHER ACTUATION SPECIFIED REQUIRED FUNCTION CONDITIONS DIVISIONS CONDITIONS (a)
- 1. Emergency Core 1, 2, 3 2 C Cooling System (ECCS)
(a)
- 2. Decay Heat 1, 2, 3 2 C Removal System (DHRS)
(b)
- 3. Containment 1, 2, 3 2 D Isolation System (CIS)
- 4. Demineralized 1, 2, 3 2 E Water Supply Isolation (DWSI)
- 5. CVCS Isolation 1, 2, 3 2 F (CVCSI)
(c) (c)
- 6. Pressurizer Heater 1, 2 , 3 2 G Trip (d)
- 7. Low Temperature 3 2 A Overpressure Protection (LTOP)
(a) Not PASSIVELY COOLED.
(b) With any RCS temperature above the T-2 interlock.
(c) Not required when Pressurizer Heater trip breakers are open and deactivated.
(d) With wide range RCS cold temperature below the LTOP enable temperature specified in the PTLR (T-1 interlock) and more than one reactor vent valve closed.
NuScale 3.3.3-5 Revision 1.0
Manual Actuation Functions 3.3.4 3.3 INSTRUMENTATION 3.3.4 Manual Actuation Functions LCO 3.3.4 Each manual actuation division for each Function in Table 3.3.4-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.4-1.
ACTIONS
NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with one manual referenced in Table 3.3.4-1 actuation division for the function(s).
B. One or more Functions B.1 Enter the Condition 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with two manual referenced in Table 3.3.4-1 actuation divisions for the function(s).
C. As required by Required C.1 Open reactor trip breakers. Immediately Action A.1 or B.1 and referenced in Table 3.3.4-1.
D. As required by Required D.1 Be in MODE 2. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action A.1 or B.1 and referenced in AND Table 3.3.4-1.
D.2 Be in MODE 3 and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> PASSIVELY COOLED.
NuScale 3.3.4-1 Revision 1.0
Manual Actuation Functions 3.3.4 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 ----------------NOTE--------------
Action A.1 or B.1 and Flow path(s) may be referenced in unisolated intermittently Table 3.3.4-1. under administrative controls.
Isolate the flow path from the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> demineralized water storage tank to the Reactor Coolant System by use of at least one closed manual or one closed and de-activated automatic valve.
F. As required by Required F.1 ---------------NOTE------------
Action A.1 or B.1 and Flow path(s) may be referenced in unisolated intermittently Table 3.3.4-1. under administrative controls.
Isolate the flow paths from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the CVCS to the Reactor Coolant System by use of at least one closed manual or one closed and de-activated automatic valve.
G. As required by Required G.1 -------------NOTE-------------
Action A.1 or B.1 and Heater(s) may be energized referenced in intermittently under Table 3.3.4-1. administrative controls.
De-energize affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pressurizer heaters.
NuScale 3.3.4-2 Revision 1.0
Manual Actuation Functions 3.3.4 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required H.1 Open two reactor vent Immediately Action A.1 or B.1 and valves.
referenced in Table 3.3.4-1.
I. As required by Required I.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action A.1 or B.1 and Referenced in AND Table 3.3.4 1.
I.2 Be in MODE 3 with RCS 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> temperature below the T-2 interlock.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform actuation device operational test. In accordance with the Surveillance Frequency Control Program NuScale 3.3.4-3 Revision 1.0
Manual Actuation Functions 3.3.4 Table 3.3.4-1 (page 1 of 1)
Manual Actuation Functions APPLICABLE MODES MANUALLY OR OTHER ACTUATED SPECIFIED REQUIRED FUNCTION CONDITIONS DIVISIONS CONDITIONS (a) (a)
- 1. Reactor Trip 1, 2 , 3 2 C System (b)
- 2. Emergency Core 1, 2, 3 2 D Cooling System (b)
- 3. Decay Heat 1, 2, 3 2 D Removal System (c)
- 4. Containment 1, 2, 3 2 I Isolation System
- 5. Demineralized 1, 2, 3 2 E Water Supply Isolation
- 6. CVCS Isolation 1, 2, 3 2 F System (d) (d)
- 7. Pressurizer Heater 1, 2 , 3 2 G Trip (e)
- 8. Low Temperature 3 2 H Overpressure Protection (a) When capable of CRA withdrawal.
(b) When not PASSIVELY COOLED.
(c) With any RCS temperature above the T-2 interlock.
(d) Not required when pressurizer heater trip breakers are open and deactivated.
(e) With wide range RCS cold temperature below the LTOP enable temperature specified in the PTLR (T-1 interlock) and more than one reactor vent valve closed.
NuScale 3.3.4-4 Revision 1.0
RSS 3.3.5 3.3 INSTRUMENTATION 3.3.5 Remote Shutdown Station (RSS)
LCO 3.3.5 Instrumentation in the RSS shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 and not PASSIVELY COOLED.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Instrumentation in the A.1 Restore to OPERABLE 30 days RSS inoperable. status.
B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> PASSIVELY COOLED.
NuScale 3.3.5-1 Revision 1.0
RSS 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform transfer protocol of required functions. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2 Verify that the RSS communicates indication with In accordance with each required function of the Module Control the Surveillance System and Plant Control System. Frequency Control Program SR 3.3.5.3 Verify the OPERABILITY of the RSS hardware and In accordance with software. the Surveillance Frequency Control Program NuScale 3.3.5-2 Revision 1.0
RCS Pressure, Temperature, and Flow Resistance CHF Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Resistance Critical Heat Flux (CHF) Limits LCO 3.4.1 Each RCS CHF parameter shall be within the limits specified in the COLR:
- a. Pressurizer pressure,
- b. RCS cold temperature, and
- c. RCS flow resistance.
APPLICABILITY: MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS pressurizer A.1 Restore RCS CHF 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pressure or RCS cold parameter(s) to within limit.
temperature CHF parameters not within limits.
B. RCS flow resistance not B.1 Evaluate flow resistance 7 days within limits effect on safety analysis and verify that the reactor coolant system flow rate is acceptable for continued operation.
C. Required Action and C.1 Be in Mode 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
NuScale 3.4.1-1 Revision 1.0
RCS Pressure, Temperature, and Flow Resistance CHF Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to In accordance with the limit specified in the COLR. the Surveillance Frequency Control Program SR 3.4.1.2 Verify RCS cold temperature is less than or equal to In accordance with the limit specified in the COLR. the Surveillance Frequency Control Program SR 3.4.1.3 --------------------------------NOTE-----------------------------
Not required to be performed until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after exceeding 50% RTP.
Verify RCS flow resistance is within the limits Once prior to specified in the COLR. exceeding 75%
RTP after each refueling NuScale 3.4.1-2 Revision 1.0
RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 All RCS temperatures shall be 420°F.
APPLICABILITY: MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS A.1 Be in MODE 2. 30 minutes temperatures not within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify all RCS temperatures 420°F. In accordance with the Surveillance Frequency Control Program NuScale 3.4.2-1 Revision 1.0
RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE------------- A.1 Restore parameters to 30 minutes Required Action A.2 shall within limits.
be completed whenever this Condition is entered. AND A.2 Determine RCS is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Requirements of LCO not acceptable for continued met in MODE 1, 2, or 3. operation.
B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in MODE 3 with RCS 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> pressure < 500 psia.
C. --------------NOTE ------------ C.1 Initiate action to restore Immediately Required Action C.2 shall parameter(s) to within limits.
be completed whenever this Condition is entered. AND C.2 Determine RCS is Prior to entering Requirements of LCO not acceptable for continued MODE 3 met any time in other than operation.
MODE 1, 2, or 3.
NuScale 3.4.3-1 Revision 1.0
RCS P/T Limits 3.4.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Containment flooding D.1 Be in MODE 2. Immediately initiated while RCS temperature greater than AND allowed by PTLR.
D.2 Be in MODE 3 with RCS 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> temperature less than or equal to the containment flooding RCS temperature limit allowed by the PTLR.
AND D.3 Determine RCS is Prior to entering acceptable for continued MODE 2 from operation. MODE 3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 --------------------------------NOTE-----------------------------
Only required to be performed during RCS heatup and cooldown operations and inservice leak and hydrostatic testing.
Verify RCS pressure, RCS temperature, and RCS In accordance with heatup and cooldown rates are within limits specified the Surveillance in the PTLR. Frequency Control Program NuScale 3.4.3-2 Revision 1.0
RSVs 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 Reactor Safety Valves (RSVs)
LCO 3.4.4 Two RSVs shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS cold temperature above the low temperature overpressure protection (LTOP) interlock T-1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RSV inoperable. A.1 Restore valve to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.
B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND OR B.2 Be in MODE 3 with RCS 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> cold temperature below Two RSVs inoperable. LTOP enable interlock T-1 temperature.
NuScale 3.4.4-1 Revision 1.0
RSVs 3.4.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RSV is OPERABLE in accordance with In accordance with the INSERVICE TESTING PROGRAM. Following the INSERVICE testing, lift settings shall be within 1% of the nominal TESTING setpoints of 2075 psia and 2100 psia as shown below: PROGRAM Valve 1 Setpoint: 2055 psia and 2095 psia.
Valve 2 Setpoint: 2079 psia and 2121 psia.
NuScale 3.4.4-2 Revision 1.0
RCS Operational LEAKAGE 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Operational LEAKAGE LCO 3.4.5 RCS operational LEAKAGE shall be limited to:
- a. No pressure boundary LEAKAGE,
- b. 0.5 gpm unidentified LEAKAGE,
- c. 2 gpm identified LEAKAGE from the RCS, and
- d. 150 gallons per day primary to secondary LEAKAGE.
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS hot temperature 200°F.
NOTE----------------------------------------------
This LCO is not applicable if one or more ECCS valves is open.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A.1 Reduce LEAKAGE to within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LEAKAGE not within limits.
limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.
NuScale 3.4.5-1 Revision 1.0
RCS Operational LEAKAGE 3.4.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in MODE 3 with RCS hot 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> OR temperature < 200°F.
Pressure boundary LEAKAGE exists.
OR Primary to secondary LEAKAGE not within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 --------------------------------NOTES-----------------------------
- 1. 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.
- 2. Not applicable to primary to secondary LEAKAGE.
Verify RCS Operational LEAKAGE is within limits by In accordance with performance of RCS water inventory balance. the Surveillance Frequency Control Program NuScale 3.4.5-2 Revision 1.0
RCS Operational LEAKAGE 3.4.5 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.5.2 --------------------------------NOTE------------------------------
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.
Verify primary to secondary LEAKAGE is In accordance with 150 gallons per day through the Steam Generator the Surveillance System. Frequency Control Program NuScale 3.4.5-3 Revision 1.0
Chemical and Volume Control System Isolation Valves 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 Chemical and Volume Control System (CVCS) Isolation Valves LCO 3.4.6 Each of the following CVCS line flow path isolation valves shall be OPERABLE:
- a. RCS Injection Isolation Valves,
- b. RCS Discharge Isolation Valves,
- c. Pressurizer Spray Isolation Valves, and
- d. RPV High Point Degasification Isolation Valves.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS
NOTES------------------------------------------------------------
- 1. CVCS flow path(s) may be unisolated intermittently under administrative controls.
- 2. Separate Condition entry is allowed for each flow path.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more CVCS flow A.1 Isolate the affected CVCS 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> paths with one CVCS flow path by use of at least valve inoperable. one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND NuScale 3.4.6-1 Revision 1.0
Chemical and Volume Control System Isolation Valves 3.4.6 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ---------------NOTES-------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected CVCS Once per 31 days flow path is isolated.
B. One or more CVCS flow B.1 Isolate the affected CVCS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> paths with two CVCS flow path by use of at least valves inoperable. one closed and de-activated automatic valve, closed manual valve, or blind flange.
C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 3 with RCS hot 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> temperature < 200°F.
NuScale 3.4.6-2 Revision 1.0
Chemical and Volume Control System Isolation Valves 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required valves accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program.
SR 3.4.6.2 ---------------------------------NOTE------------------------------
Not required to be met for valves that are closed or open under administrative controls.
Verify the isolation time of each automatic power In accordance with operated CVCS valve is within limits. the INSERVICE TESTING PROGRAM SR 3.4.6.3 Verify each automatic CVCS valve that is not locked, In accordance with sealed, or otherwise secured in position, actuates to the Surveillance the isolation position on an actual or simulated Frequency Control actuation signal except for valves that are open under Program administrative controls.
NuScale 3.4.6-3 Revision 1.0
RCS Leakage Detection Instrumentation 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Leakage Detection Instrumentation LCO 3.4.7 Two of the following RCS leakage detection instrumentation methods shall be OPERABLE:
- a. Two Containment Evacuation System (CES) condensate channels,
- b. Two CES inlet pressure channels, and
- c. One CES gaseous radioactivity monitor channel.
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS hot temperature 200°F.
NOTES---------------------------------------------
- 1. Not required when one or more ECCS valves open.
- 2. Not required in MODE 3 during containment flood operations.
ACTIONS
NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each condensate channel and each pressure channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 ---------------NOTE---------------
leakage detection Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> instrumentation methods after establishment of steady with one required state operation.
channel inoperable. ---------------------------------------
Perform SR 3.4.5.1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND A.2 Restore required leakage 14 days detection channel(s) to OPERABLE status.
NuScale 3.4.7-1 Revision 1.0
RCS Leakage Detection Instrumentation 3.4.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One required leakage B.1 Restore one channel of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> detection instrumentation affected required leakage method with all required detection instrumentation channels inoperable. method to OPERABLE status.
C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND OR C.2 Be in MODE 3 with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> RCS hot temperature Two required leakage < 200°F.
detection instrumentation methods with all required channels inoperable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Perform a CHANNEL CHECK of each required CES In accordance with condensate channel. the Surveillance Frequency Control Program SR 3.4.7.2 Perform a CHANNEL CHECK of each required CES In accordance with inlet pressure channel. the Surveillance Frequency Control Program NuScale 3.4.7-2 Revision 1.0
RCS Leakage Detection Instrumentation 3.4.7 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.7.3 Perform a CHANNEL CHECK of required CES In accordance with gaseous radioactivity monitor channel. the Surveillance Frequency Control Program SR 3.4.7.4 Perform a COT of required CES gaseous radioactivity In accordance with monitor channel. the Surveillance Frequency Control Program SR 3.4.7.5 Perform a COT of each required CES condensate In accordance with channel. the Surveillance Frequency Control Program SR 3.4.7.6 Perform a CHANNEL CALIBRATION of each In accordance with required CES condensate channel. the Surveillance Frequency Control Program SR 3.4.7.7 Perform a CHANNEL CALIBRATION of each In accordance with required CES inlet pressure channel. the Surveillance Frequency Control Program SR 3.4.7.8 Perform a CHANNEL CALIBRATION of required CES In accordance with gaseous radioactivity monitor channel. the Surveillance Frequency Control Program NuScale 3.4.7-3 Revision 1.0
RCS Specific Activity 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Specific Activity LCO 3.4.8 The specific activity of the reactor coolant shall be within limits.
APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT ---------------------NOTE-------------------
I-131 > 0.2 µCi/gm. LCO 3.0.4.c is applicable.
A.1 Verify DOSE EQUIVALENT Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> I-131 12 µCi/gm.
AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT I-131 to within limit.
B. DOSE EQUIVALENT ---------------------NOTE-------------------
XE-133 > 60 Ci/gm. LCO 3.0.4.c is applicable.
B.1 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to within limit.
C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met.
C.2 Be in MODE 3. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR DOSE EQUIVALENT I-131 > 12 Ci/gm.
NuScale 3.4.8-1 Revision 1.0
RCS Specific Activity 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify reactor coolant DOSE EQUIVALENT XE-133 In accordance with specific activity 60 µCi/gm. the Surveillance Frequency Control Program SR 3.4.8.2 Verify reactor coolant DOSE EQUIVALENT I-131 In accordance with specific activity 0.2 µCi/gm. the Surveillance Frequency Control Program AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of 15% of RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period NuScale 3.4.8-2 Revision 1.0
SG Tube Integrity 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Steam Generator (SG) Tube Integrity LCO 3.4.9 SG tube integrity shall be maintained.
AND All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with the Steam Generator Program.
APPLICABILITY: MODES 1 and 2, MODE 3 and not PASSIVELY COOLED.
ACTIONS
NOTE-------------------------------------------------------------
Separate Condition entry is allowed for each SG tube.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes A.1 Verify tube integrity of the 7 days satisfying the tube affected tube(s) is plugging criteria and not maintained until the next plugged in accordance refueling outage or SG tube with the Steam Generator inspection.
Program.
AND A.2 Plug the affected tube(s) in Prior to entering accordance with the Steam MODE 3 following the Generator Program. next refueling outage or SG tube inspection B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in MODE 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR PASSIVELY COOLED.
SG tube integrity not maintained.
NuScale 3.4.9-1 Revision 1.0
SG Tube Integrity 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify SG tube integrity in accordance with the Steam In accordance with Generator Program. the Steam Generator Program SR 3.4.9.2 Verify that each inspected SG tube that satisfies the Prior to entering tube plugging criteria is plugged in accordance with MODE 3 following the Steam Generator Program. a SG tube inspection NuScale 3.4.9-2 Revision 1.0
LTOP Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Low Temperature Overpressure Protection (LTOP) Valves LCO 3.4.10 Each closed reactor vent valve (RVV) shall be OPERABLE.
APPLICABILITY: MODE 3 with wide range RCS cold temperature below T-1 interlock.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE-------------
Not applicable with two RVVs open.
One closed RVV A.1 Restore RVV to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.
OR A.2 Open inoperable RVV. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Two closed RVVs B.1 Restore two closed RVVs 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable. to OPERABLE status.
OR B.2 Open two RVVs. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. Three closed RVVs C.1 Initiate action to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> inoperable. depressurize RCS.
AND C.2 Initiate action to open two 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> RVVs.
NuScale 3.4.10-1 Revision 1.0
LTOP Valves 3.4.10 SURVEILLANCE REQUIREMENTS
NOTE-------------------------------------------------------------
Not required to be met for valves that are open.
SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each RVV actuates to the open position on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program SR 3.4.10.2 Verify the open actuation time of each RVV is within In accordance with limits. the INSERVICE TESTING PROGRAM SR 3.4.10.3 Verify the inadvertent actuation block function for In accordance with each RVV. the Surveillance Frequency Control Program SR 3.4.10.4 Verify the inadvertent block setpoint is within limits for In accordance with each RVV. the INSERVICE TESTING PROGRAM NuScale 3.4.10-2 Revision 1.0
ECCS 3.5.1 3.5 PASSIVE CORE COOLING SYSTEM (PCCS) 3.5.1 Emergency Core Cooling System (ECCS)
LCO 3.5.1 Three reactor vent valves (RVV) and two reactor recirculation valves (RRV) shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 and not PASSIVELY COOLED.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RVV inoperable. A.1 Restore RVV to OPERABLE 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> status.
B. One RRV inoperable. B.1 Restore RRV to OPERABLE 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> status.
C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met.
C.2 Be in MODE 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR PASSIVELY COOLED.
Two or more RVVs inoperable.
OR Two RRVs inoperable.
NuScale 3.5.1-1 Revision 1.0
ECCS 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 -------------------------------NOTE--------------------------------
Not required to be met for valves that are open.
Verify each RVV and RRV actuates to the open In accordance with position on an actual or simulated actuation signal. the Surveillance Frequency Control Program SR 3.5.1.2 -------------------------------NOTE--------------------------------
Not required to be met for valves that are open.
Verify the open actuation time of each RVV and RRV In accordance with is within limits. the INSERVICE TESTING PROGRAM SR 3.5.1.3 Verify the inadvertent actuation block function of each In accordance with RVV and RRV. the Surveillance Frequency Control Program SR 3.5.1.4 Verify the inadvertent block setpoint is within limits for In accordance with each RVV and RRV. the INSERVICE TESTING PROGRAM NuScale 3.5.1-2 Revision 1.0
DHRS 3.5.2 3.5 PASSIVE CORE COOLING SYSTEMS (PCCS) 3.5.2 Decay Heat Removal System (DHRS)
LCO 3.5.2 Two DHRS trains shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 and not PASSIVELY COOLED.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One DHRS train A.1 Restore DHRS train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.
B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR PASSIVELY COOLED.
Both DHRS trains inoperable.
NuScale 3.5.2-1 Revision 1.0
DHRS 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify required valves accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program SR 3.5.2.2 Verify DHRS loops are filled. In accordance with the Surveillance Frequency Control Program SR 3.5.2.3 Verify that each DHRS actuation valve actuates to In accordance with the open position on an actual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.5.2.4 Verify the open actuation time of each DHRS In accordance with actuation valve is within limits. the INSERVICE TESTING PROGRAM NuScale 3.5.2-2 Revision 1.0
Ultimate Heat Sink 3.5.3 3.5 PASSIVE CORE COOLING SYSTEMS (PCCS) 3.5.3 Ultimate Heat Sink LCO 3.5.3 Ultimate Heat Sink shall be maintained within the limits specified below:
- a. Level 68 ft,
- b. Bulk average temperature 140 ºF, and
APPLICABILITY: At all times.
ACTIONS
NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Ultimate Heat Sink Level A.1 Suspend module Immediately
< 68 ft and > 55 ft. movements.
AND A.2 Suspend movement of Immediately irradiated fuel assemblies in the refueling area.
AND A.3 Restore Ultimate Heat Sink 30 Days Level to within limits.
NuScale 3.5.3-1 Revision 1.0
Ultimate Heat Sink 3.5.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Ultimate Heat Sink Level B.1 Initiate action to restore Immediately 55 ft. Ultimate Heat Sink Level to
> 55 ft.
AND B.2 Restore Ultimate Heat Sink 24 Hours Level to > 55 ft.
C. Ultimate Heat Sink bulk C.1 Suspend module Immediately average temperature not movements.
within limits.
AND C.2 Initiate action to restore Immediately Ultimate Heat Sink bulk average temperature to within limits.
AND C.3 Restore Ultimate Heat Sink 14 Days bulk average temperature to within limits.
D. Required Action and D.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A, B or AND C not met.
D.2 Be in MODE 3. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> NuScale 3.5.3-2 Revision 1.0
Ultimate Heat Sink 3.5.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. Ultimate Heat Sink bulk E.1 Initiate action to restore Immediately average boron Ultimate Heat Sink bulk concentration not within average boron concentration limits. to within limits.
AND E.2 Terminate flow into Immediately containment vessel from Ultimate Heat Sink via the Containment Flood and Drain System.
AND E.3 Suspend containment vessel Immediately disassembly activities at containment tool.
AND E.4 Suspend module Immediately movements.
AND E.5 Suspend movement of Immediately irradiated fuel assemblies in the refueling area.
NuScale 3.5.3-3 Revision 1.0
Ultimate Heat Sink 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the Ultimate Heat Sink level is within limits. In accordance with the Surveillance Frequency Control Program SR 3.5.3.2 Verify the Ultimate Heat Sink bulk average In accordance with temperature is within limits. the Surveillance Frequency Control Program SR 3.5.3.3 Verify Ultimate Heat Sink bulk average boron In accordance with concentration is within limits. the Surveillance Frequency Control Program NuScale 3.5.3-4 Revision 1.0
Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS hot temperature 200ºF.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment inoperable. A.1 Restore containment to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OPERABLE status.
B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 3 with RCS hot 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> temperature < 200ºF.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and leakage In accordance with rate testing in accordance with the Containment the Containment Leakage Rate Testing Program. Leakage Rate Testing Program NuScale 3.6.1-1 Revision 1.0
Containment Isolation Valves 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Isolation Valves LCO 3.6.2 Each containment isolation valve shall be OPERABLE.
APPLICABILTY: MODES 1 and 2, MODE 3 with RCS hot temperature 200ºF.
ACTIONS
NOTES-----------------------------------------------------------
- 1. Penetration flow path(s) may be unisolated intermittently under administrative controls.
- 2. Separate Condition entry is allowed for each penetration flow path.
- 3. Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves.
- 4. Enter applicable Conditions and Required Actions of LCO 3.6.1, Containment, when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.
CONDITION REQUIRED ACTION COMPLETION TIME A. -----------NOTE------------ A.1 Isolate the affected 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Only applicable to penetration flow path by use penetration flow paths of at least one closed and with two containment de-activated automatic isolation valves. valve, closed manual valve,
blind flange, or check valve with flow through the valve One or more penetration secured.
flow paths with one containment isolation AND valve inoperable.
NuScale 3.6.2-1 Revision 1.0
Containment Isolation Valves 3.6.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ---------------NOTES-------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days penetration flow path is isolated.
B. ---------NOTES------------ B.1 Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Only applicable to penetration flow path by use penetration flow paths of at least one closed and with two containment de-activated automatic isolation valves. valve, closed manual valve,
or blind flange.
One or more penetration flow paths with two containment isolation valves inoperable.
C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 3 with RCS hot 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> temperature < 200ºF.
NuScale 3.6.2-2 Revision 1.0
Containment Isolation Valves 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 Verify required valves accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program SR 3.6.2.2 ---------------------------------NOTE------------------------------
Valves and blind flanges in high radiation areas may be verified by use of administrative means.
Verify each containment isolation manual valve and In accordance with blind flange that is located outside containment and the Surveillance not locked, sealed, or otherwise secured and is Frequency Control required to be closed during accident conditions is Program closed, except for containment isolation valves that are open under administrative controls.
SR 3.6.2.3 Verify the isolation time of each automatic In accordance with containment isolation valve is within limits except for the INSERVICE valves that are open under administrative controls. TESTING PROGRAM SR 3.6.2.4 Verify each automatic containment isolation valve In accordance with that is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the isolation position on an Frequency Control actual or simulated actuation signal except for valves Program that are open under administrative controls.
SR 3.6.2.5 Verify the combined leakage rate for all containment In accordance with bypass leakage paths is 0.6 La when pressurized the Containment to 951 psia. Leakage Rate Testing Program NuScale 3.6.2-3 Revision 1.0
MSIVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Isolation Valves (MSIVs)
LCO 3.7.1 Two MSIVs and two MSIV bypass valves per steam line shall be OPERABLE.
APPLICABILITY: MODE 1 and 2, MODES 3 and not PASSIVELY COOLED.
ACTIONS
NOTES-----------------------------------------------------------
- 1. Separate Condition entry is allowed for each inoperable valve.
- 2. Main steam line flow path(s) may be unisolated intermittently under administrative controls.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Isolate the affected main 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> MSIV valves inoperable. steam line flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND A.2 --------------NOTES--------------
- 1. Isolation in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected main Once per 7 days steam line flow path is isolated.
NuScale 3.7.1-1 Revision 1.0
MSIVs 3.7.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Isolate the affected main 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> MSIV bypass valves steam line bypass flow path inoperable. by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND B.2 ---------------NOTES-------------
- 1. Isolation in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected main Once per 7 days steam line bypass flow path is isolated.
C. One flow path with an C.1 Isolate the affected main 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inner and outer required steam line flow path by use valve inoperable. of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
D. Required Action and D.1 Be in Mode 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND D.2 Be in Mode 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> PASSIVELY COOLED.
NuScale 3.7.1-2 Revision 1.0
MSIVs 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify required valves accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program SR 3.7.1.2 Verify isolation time of each MSIV and MSIV In accordance with bypass valve is within limits on an actual or the INSERVICE simulated actuation signal. TESTING PROGRAM SR 3.7.1.3 Verify each MSIV and MSIV bypass valve leakage In accordance with is within limits. the INSERVICE TESTING PROGRAM NuScale 3.7.1-3 Revision 1.0
Feedwater Isolation 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Feedwater Isolation LCO 3.7.2 One Feedwater Isolation Valve (FWIV) and one Feedwater Regulation Valve (FWRV) for each steam generator shall be OPERABLE.
APPLICABILITY: MODE 1 and 2, MODES 3 and not PASSIVELY COOLED.
ACTIONS
NOTES------------------------------------------------------------
- 1. Separate Condition entry is allowed for each inoperable valve.
- 2. Feedwater flow path(s) may be unisolated intermittently under administrative controls.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two FWIVs A.1 Isolate the affected FWIV 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND A.2 --------------NOTES--------------
- 1. Isolation in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify FWIV path isolated. Once per 7 days NuScale 3.7.2-1 Revision 1.0
Feedwater Isolation 3.7.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One or two FWRVs B.1 Isolate the affected FWRV 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND B.2 --------------NOTES--------------
- 1. Isolation in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify FWRV path Once per 7 days isolated.
C. Two valves in the same C.1 Isolate the affected flow path 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> flow path inoperable. by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
D. Required Action and D.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND D.2 Be in MODE 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> PASSIVELY COOLED.
NuScale 3.7.2-2 Revision 1.0
Feedwater Isolation 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify required FWIV accumulator pressures are In accordance with within limits. the Surveillance Frequency Control Program.
SR 3.7.2.2 Verify the closure time of each FWIV and FWRV is In accordance with within limits on an actual or simulated actuation the INSERVICE signal. TESTING PROGRAM SR 3.7.2.3 Verify each FWIV and FWRV leakage is within In accordance with limits. the INSERVICE TESTING PROGRAM NuScale 3.7.2-3 Revision 1.0
Nuclear Instrumentation 3.8.1 3.8 REFUELING OPERATIONS 3.8.1 Nuclear Instrumentation LCO 3.8.1 Two refueling neutron flux channels and one refueling neutron flux audible count rate channel shall be OPERABLE.
APPLICABILITY: MODE 5, except when reactor vessel upper assembly is seated on reactor vessel flange.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required refueling A.1 Suspend positive reactivity Immediately neutron flux channel changes.
AND OR A.2 Suspend operations that Immediately Required refueling would cause introduction of neutron flux audible water into reactor pool with count rate channel boron concentration less inoperable. than specified in the COLR.
B. Two required refueling B.1 Initiate actions to restore Immediately neutron flux channels one refueling neutron flux inoperable. channel to OPERABLE status.
AND B.2 Perform SR 3.5.3.3. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> NuScale 3.8.1-1 Revision 1.0
Nuclear Instrumentation 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Perform a CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.8.1.2 --------------------------------NOTE------------------------------
Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program NuScale 3.8.1-2 Revision 1.0
Decay Time 3.8.2 3.8 REFUELING OPERATIONS 3.8.2 Decay Time LCO 3.8.2 Reactor shall be subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor subcritical for A.1 Suspend movement of Immediately
< 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. irradiated fuel in the reactor pressure vessel.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 Verify reactor has been subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Once prior to movement of irradiated fuel assemblies in the reactor pressure vessel NuScale 3.8.2-1 Revision 1.0
Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location
[Site specific information to be provided by the combined license applicant.]
4.1.1 Site and Exclusion Boundaries
[Site specific information to be provided by the combined license applicant.]
4.1.2 Low Population Zone (LPZ)
[Site specific information to be provided by the combined license applicant.]
4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 37 fuel assemblies. Each assembly shall consist of a matrix of fuel rods clad with a zirconium based alloy and containing an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material.
Limited substitutions of zirconium based alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
4.2.2 Control Rod Assemblies The reactor core shall contain 16 control rod assemblies. The control material shall be silver indium cadmium or boron carbide as approved by the NRC.
4.3 Fuel Storage 4.3.1 Criticality The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; NuScale 4.0-1 Revision 1.0
Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)
- b. keff 0.95 if fully flooded with borated water at a minimum soluble boron concentration of 800 ppm, which includes an allowance for uncertainties to assure a 95 percent probability and 95 percent confidence level;
- c. keff < 1.00 if fully flooded with unborated water, which includes an allowance for uncertainties to assure a 95 percent probability and 95 percent confidence level;
- d. A nominal 11.22 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks.
4.3.2 Drainage The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below 20 ft above the spent fuel pool floor.
4.3.3 Capacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 1404 fuel assemblies.
NuScale 4.0-2 Revision 1.0
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The [Plant Manager] shall be responsible for overall facility operations and shall delegate in writing the succession to this responsibility during his absence.
The [Plant Manager] or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.
5.1.2 The [Shift Manager (SM)] shall be responsible for the control room command function. During any absence of the SM from the control room while any unit is in MODE 1, 2, 3, 4, or 5, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function.
NuScale 5.1-1 Revision 1.0
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for facility operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the [FSAR/QA Plan];
The [Plant Manager] shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant; A [specified corporate officer] shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Facility Staff The facility staff organization shall include the following:
- a. The minimum licensed operator staffing shall be:
Number of units Reactor Senior Reactor Operating(1) Operator Operator None 2 1 One to twelve 3 3 (1)
For the purpose of this table, a unit is considered to be operating when it is in MODE 1, 2, or 3.
NuScale 5.2-1 Revision 1.0
Organization 5.2 5.2 Organization 5.2.2 Facility Staff (continued)
- b. A person holding a senior reactor operator license for all fueled units at the site who is assigned responsibility for overall plant operation shall be onsite at all times when there is fuel in any unit.
- c. A senior reactor operator license shall be in the control room at all times.
In addition to this senior reactor operator, a licensed reactor operator or senior reactor operator shall be present at the controls at all times.
- d. Shift crew composition may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- e. A radiation protection technician shall be on site when fuel is in any unit.
The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- f. The operations manager or assistant operations manager shall hold an SRO license.
- g. An individual shall provide advisory technical support to the facility operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the facility. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
NuScale 5.2-2 Revision 1.0
Facility Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 3, 2000, or more recent revisions, or ANSI Standards acceptable to the NRC staff. The staff not covered by Regulatory Guide 1.8 shall meet or exceed the minimum qualifications of Regulations, Regulatory Guides, or ANSI Standards acceptable to NRC staff.
5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, meet the requirements of TS 5.3.1 and TS 5.2.2.
NuScale 5.3-1 Revision 1.0
Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:
- a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;
- b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1;
- c. Quality assurance for effluent and environmental monitoring;
- d. Fire Protection Program implementation; and
- e. All programs specified in Specification 5.5.
NuScale 5.4-1 Revision 1.0
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.
5.5.1 Offsite Dose Calculation Manual (ODCM)
- a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program.
- b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.1 and Specification 5.6.2.
- c. Licensee initiated changes to the ODCM:
- 1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
- i. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and ii. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent or dose calculations;
- 2. Shall become effective after the approval of the [plant manager];
and
- 3. Shall be submitted to the NRC in the form of a complete, legible copy of the changed portion of the ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
NuScale 5.5-1 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Radioactive Effluent Control Program
- a. This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as is reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
- 1. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoints determination in accordance with the methodology in the ODCM;
- 2. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20;
- 3. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;
- 4. Limitations on the annual and quarterly doses or dose commitment to a member of the public for radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;
- 5. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days;
- 6. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; NuScale 5.5-2 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Radioactive Effluent Control Program (continued)
- 7. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary shall be in accordance with the following:
- i. For noble gases: a dose rate 500 mrem/yr to the whole body and a dose rate 3000 mrem/yr to the skin and ii. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate 1500 mrem/yr to any organ;
- 8. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;
- 9. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and
- 10. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
- b. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
5.5.3 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Section 3.9, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.4 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following:
NuScale 5.5-3 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Steam Generator (SG) Program (continued)
- a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the as found condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.
- b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.
- 1. Structural integrity performance criterion: All inservice steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, and cool down and all anticipated transients included in the design specification) and design basis accidents.
This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.
- 2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube failure, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG.
Leakage is not to exceed 150 gallons per day.
- 3. The operational LEAKAGE performance criterion is specified in LCO 3.4.5, "RCS Operational LEAKAGE.
NuScale 5.5-4 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Steam Generator (SG) Program (continued)
- c. Provisions for SG tube plugging criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding [40%] of the nominal tube wall thickness shall be plugged.
- d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube plugging criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.
- 1. Inspect 100% of the tubes in each SG during the first refueling outage following initial startup and SG replacement.
- 2. After the first refueling outage following SG installation, inspect each SG at least every 72 effective full power months or at least every third refueling outage (whichever results in more frequent inspections). In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b, c and d below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated. The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up NuScale 5.5-5 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Steam Generator (SG) Program (continued) to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage.
a) After the first refueling outage following SG installation, inspect 100% of the tubes during the next 144 effective full power months. This constitutes the first inspection period; b) During the next 120 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; c) During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the third inspection period; and d) During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the fourth and subsequent inspection periods.
- 3. If crack indications are found in any SG tube, then the next inspection for each affected or potentially affected unit SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.
- e. Provisions for monitoring operational primary to secondary LEAKAGE.
5.5.5 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include:
- a. Identification of a sampling schedule for the critical variables and control points for these variables;
- b. Identification of the procedures used to measure the values of the critical variables; NuScale 5.5-6 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Secondary Water Chemistry Program (continued)
- c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage;
- d. Procedures for the recording and management of data;
- e. Procedures defining corrective actions for all off control point chemistry conditions; and
- f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.
5.5.6 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Gaseous Rad-Waste Management System, the quantity of radioactivity contained in gas storage tanks or fed into the offgas treatment system, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.
The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Liquid-Containing Tank Failures.
The program shall include:
- a. The limits for concentrations of hydrogen and oxygen in the Gaseous Rad-Waste Management System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion),
- b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank and fed into the offgas treatment system is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents, and
- c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radioactive Waste System is less than the amount that would NuScale 5.5-7 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued) result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.
5.5.7 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
- a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
- 1. A change in the TS incorporated in the license; or
- 2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
- c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.
- d. Proposed changes that meet the criteria of 5.5.7(b) above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.8 Safety Function Determination Program (SFDP)
- a. This program ensures that loss of safety function is detected and appropriate action taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the supported system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirement of LCO 3.0.6. The SFDP shall contain the following:
NuScale 5.5-8 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Safety Function Determination Program (SFDP) (continued)
- 1. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;
- 2. Provisions for ensuring the unit is maintained in a safe condition if a loss of function condition exists;
- 3. Provisions to ensure that an inoperable supported systems Completion Time is not inappropriately extended as a result of multiple support systems inoperabilities; and
- 4. Other appropriate limitations and remedial or compensatory actions.
- b. A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:
- 1. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or
- 2. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or
- 3. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.
- c. The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.
5.5.9 Containment Leakage Rate Testing Program
- a. A program shall implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option A, as modified by approved exemptions.
- b. The maximum allowable containment leakage rate, La, at Pa, shall be 0.20% of containment air weight per day.
NuScale 5.5-9 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Containment Leakage Rate Testing Program (continued)
- c. Containment leakage rate acceptance criterion is < 0.60 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests.
- d. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
- e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.
5.5.10 Setpoint Program (SP)
- a. The Setpoint Program (SP) implements the regulatory requirement of 10 CFR 50.36(c)(1)(ii)(A) that technical specifications will include items in the category of limiting safety system settings (LSSS), which are settings for automatic protective devices related to those variables having significant safety functions.
- b. The Nominal Trip Setpoint (NTSP), As-Found Tolerance (AFT), and As-Left Tolerance (ALT) for each Technical Specification required automatic protection instrumentation function shall be calculated in conformance with TR-0616-49121-P, "NuScale Instrument Setpoint Methodology."
- c. For each Technical Specification required automatic protection instrumentation function, performance of a CHANNEL CALIBRATION surveillance in accordance with the Setpoint Program (SP) shall include the following:
- 1. The as-found value of the instrument channel trip setting shall be compared with the previously recorded as-left value.
- i. If all as-found measured trip setpoint values during calibration and surveillance testing are inside the two-sided limits of Nominal Trip Setpoint (NTSP) plus or minus the Performance and Test Acceptance Criteria Band (PTAC),
then the channel is fully OPERABLE, no additional actions are required.
NuScale 5.5-10 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Setpoint Program (SP) (continued) ii. If during channel OPERABILITY or calibration testing, the measured trip setpoint values are within the As-Found Tolerance band but outside the As-Left Tolerance Band, then the instrumentation channel is fully OPERABLE, however, calibration is required to restore the channel within the as-left tolerance band.
iii. If any as-found calibration setting value is outside the as-found Tolerance band, then the channel is inoperable, and corrective action is required. Calibration is required to restore the channel to within as-left tolerance band.
- 2. The instrument channel trip setting shall be set to a value within the specified ALT around the specified NTSP at the completion of the surveillance; otherwise, the surveillance requirement is not met and the instrument channel shall be immediately declared inoperable.
- d. The difference between the instrument channel trip setting as-found value and the previously recorded as-left value for each Technical Specification required automatic protection instrumentation function shall be trended and evaluated to verify that the instrument channel is functioning in accordance with its design basis.
- e. The SP shall establish a document containing the current value of the specified NTSP, AFT, and ALT for each Technical Specification required automatic protection instrumentation function and references to the calculation documentation. Changes to this document shall be governed by the regulatory requirement of 10 CFR 50.59. In addition, changes to the specified NTSP, AFT, and ALT values shall be governed by the approved setpoint methodology. This document, including any revisions or supplements, shall be provided upon issuance to the NRC.
5.5.11 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.
- a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
NuScale 5.5-11 Revision 1.0
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Surveillance Frequency Control Program (continued)
- b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
- c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
5.5.12 Spent Fuel Storage Rack Neutron Absorber Monitoring Program This Program provides controls for monitoring the condition of the neutron absorber used in the spent fuel pool storage racks to verify the neutron absorber density is consistent with the assumptions in the spent fuel pool criticality analysis. The program shall be in accordance with NEI 16-03-A, "Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools," Revision 0, May 2017.
NuScale 5.5-12 Revision 1.0
Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 Annual Radiological Environmental Operating Report
NOTE----------------------------------------------------
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
The Annual Radiological Environmental Operating Report covering the operation of the facility during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.
5.6.2 Radioactive Effluent Release Report
NOTE----------------------------------------------------
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
The Radioactive Effluent Release Report covering the operation of the facility in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility.
The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
NuScale 5.6-1 Revision 1.0
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Core Operating Limits Report (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
2.1.1, "Reactor Core Safety Limits";
3.1.1, SHUTDOWN MARGIN (SDM);
3.1.3, Moderator Temperature Coefficient (MTC);
3.1.4, Rod Group Alignment Limits; 3.1.5, Shutdown Group Insertion Limits; 3.1.6, Regulating Group Insertion Limits; 3.1.8, PHYSICS TESTS Exceptions; 3.1.9, Boron Dilution Control; 3.2.1, Enthalpy Rise Hot Channel Factor ( F H);
3.2.2, AXIAL OFFSET (AO);
3.4.1, RCS Pressure, Temperature, and Flow Resistance Critical Heat Flux (CHF) Limits; and 3.5.3, Ultimate Heat Sink.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. [List of NRC-approved Topical Reports that are used to determine the core operating limits listed in 5.6.3.a above.]
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Passive Core Cooling Systems limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
NuScale 5.6-2 Revision 1.0
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Core Operating Limits Report (COLR) (continued)
- d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.4 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
3.3.1, Module Protection System (MPS) Instrumentation; 3.3.3, Engineered Safety Features Actuation System (ESFAS)
Logic and Actuation; 3.3.4, Manual Actuation Functions; 3.4.3, RCS Pressure and Temperature (P/T) Limits; and 3.4.4, Reactor Safety Valves (RSVs).
- b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:
TR-1015-18177, "Pressure and Temperature Limits Methodology."
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for any revision or supplement thereto.
NuScale 5.6-3 Revision 1.0
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 3 following completion of an inspection performed in accordance with the Specification 5.5.4, "Steam Generator (SG) Program." The report shall include:
- a. The scope of inspections performed on each SG.
- b. Degradation mechanisms found.
- c. Nondestructive examination techniques utilized for each degradation mechanism.
- d. Location orientation (if linear), and measured sizes (if available) of service induced indications.
- e. Number of tubes plugged during the inspection outage for each degradation mechanism.
- f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator.
- g. The results of condition monitoring, including the results of tube pulls and in-situ testing.
NuScale 5.6-4 Revision 1.0
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:
5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation
- a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
- b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d. Each individual or group entering such an area shall possess:
- 1. A radiation monitoring device that continuously displays radiation dose rates in the area; or
- 2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the devices dose alarm setpoint is reached, with an appropriate alarm setpoint; or
- 3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area; or
- 4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter); and NuScale 5.7-1 Revision 1.0
High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)
(i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area; or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
- e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation
- a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:
- 1. All such door and gate keys shall be maintained under the administrative control of the [shift manager], radiation protection manager, or his or her designees; and
- 2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.
NuScale 5.7-2 Revision 1.0
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)
- b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d. Each individual group entering such an area shall possess:
- 1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the devices dose alarm setpoint is reached, with an appropriate alarm setpoint; or
- 2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area; or
- 3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter); and (i) Be under surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, or personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.
NuScale 5.7-3 Revision 1.0
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)
- 4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the As Low As is Reasonably Achievable principle, a radiation monitoring device that continuously displaces radiation dose rates in the area.
- e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing do not require documentation prior to initial entry.
- f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.
NuScale 5.7-4 Revision 1.0