ML022700243

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Technical Specification for Amendment 176 Revising the TS to Support Extension of Certain Surveillance Requirements from 92 Days to 92 Days on an Alternate Test Bases.
ML022700243
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 09/26/2002
From:
NRC/NRR/DLPM/LPD2
To:
References
TAC MB2968
Download: ML022700243 (47)
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Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions RkI f'TI !

-................... ................... ...............---- I1! I--------------------- ------------

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.

ALTERNATE An ALTERNATE TEST BASIS shall consist of the testing of systems, TEST BASIS subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during two consecutive Surveillance Frequency intervals according to the partial testing formula that follows, where n is the total number of systems, subsystems, channels, or other designated components in the associated function. If the total number of systems, subsystems, channels, or other designated components is even, then nW2 are tested during each interval specified by the Surveillance Frequency. If the total number of systems, subsystems, channels, or other designated components is odd, then either (n+1)12 or (n-1)/2 are tested during the first test interval at the specified Surveillance Frequency. The systems, subsystems, channels, or other designated components not tested during the first interval are tested during the next interval.

AVERAGE PLANAR The APLHGR shall be applicable to a specific planar height and is LINEAR HEAT equal to the sum of the LHGRs for all the fuel rods in the specified GENERATION bundle at the specified height divided by the number of fuel rods in RATE (APLHGR) the fuel bundle at the height.

CHANNEL A CHANNEL CALIBRATION shall be the adjustment, as necessary, CALIBRATION 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 the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. 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 so that the entire channel is calibrated.

(continued)

HATCH UNIT 2 1.1-1 Amendment No. 176

Definitions 1.1 1.1 Definitions (continued)

CHANNELCHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL A CHANNEL FUNCTIONAL TEST shall be the injection of a FUNCTIONAL simulated or actual signal into the channel as close to the sensor TEST as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

CORE CORE ALTERATION shall be the movement of any fuel, sources, ALTERATION or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING The COLR is the unit specific document that provides cycle specific LIMITS REPORT parameter limits for the current reload cycle. These cycle specific (COLR) limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 EQUIVALENT (microcuries/gram) that alone would produce the same thyroid dose as 1-131 the quantity and isotopic mixture of 1-131, 1-132, 1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites";

Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977; or ICRP 30, Supplement to Part 1, pages 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

(continued)

HATCH UNIT 2 1.1-2 Amendment No. 176 1

Definitions 1.1 1.1 Definitions (continued)

EMERGENCY The ECCS RESPONSE TIME shall be that time interval from when CORE COOLING the monitored parameter exceeds its ECCS initiation setpoint at the SYSTEM (ECCS) channel sensor until the ECCS equipment is capable of performing RESPONSE its safety function (i.e., the valves travel to their required positions, TIME pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. 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.

END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval RECIRCULATION from initial signal generation by the associated turbine stop valve limit PUMP TRIP switch or from when the turbine control valve hydraulic control oil (EOC-RPT) pressure drops below the pressure switch setpoint to complete SYSTEM suppression of the electric arc between the fully open contacts of the RESPONSE TIME recirculation pump circuit breaker. 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.

ISOLATION The ISOLATION SYSTEM RESPONSE TIME shall be that time interval SYSTEM from when the monitored parameter exceeds its isolation initiation RESPONSE TIME setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays, where applicable. 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.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE
1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
2. LEAKAGE into the drywell atmosphere 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;
b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE; (continued) 1.1-3 UNIT 2 Amendment No. 176 1 HATCH UNIT 2 1.1-3

Definitions 1.1 1.1 Definitions LEAKAGE c. Total LEAKAGE (continued)

Sum of the identified and unidentified LEAKAGE;

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

LOGIC SYSTEM A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all FUNCTIONAL required logic components (i.e., all required relays and contacts, trip TEST units, solid state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM The MCPR shall be the smallest critical power ratio (CPR) that CRITICAL POWER exists in the core for each class of fuel. The CPR is that power RATIO (MCPR) in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE A system, subsystem, division, component, or device shall be OPERABILITY OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

(continued)

HATCH UNIT 2 1.1-4 Amendment No. 176 1

Definitions 1.1 1.1 Definitions (continued)

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 Tests and Operation, of the FSAR;
b. " Authorized under the provisions of 10 CFR 50.59; or
c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL RTP shall be a total reactor core heat transfer rate to the reactor POWER (RTP) coolant of 2763 MWt.

REACTOR The RPS RESPONSE TIME shall be that time interval from when the PROTECTION monitored parameter exceeds its RPS trip setpoint at the channel SYSTEM (RPS) sensor until de-energization of the scram pilot valve solenoids. The RESPONSE TIME response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SDM shall be the amount of reactivity by which the reactor is subcritical SHUTDOWN MARGIN (SDM) or would be subcritical assuming that:

a. The reactor is xenon free;
b. The moderator temperature is 68°F; and
c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

STAGGERED A STAGGERED TEST BASIS shall consist of the testing of one of TEST BASIS the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

(continued)

Amendment No. 176 1.1-5 Amendment No. 176 1 HATCH UNIT 22 1.1-5

Definitions Definitions 1.1 1.1 Definitions (continued)

TURBINE BYPASS The TURBINE BYPASS SYSTEM RESPONSE TIME consists of two SYSTEM components:

RESPONSE

TIME a. The time from initial movement of the main turbine stop valve or control valve until 80% of the turbine bypass capacity is established; and

b. The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.

HATCH UNIT 2 1.1 -6 Amendment No. 1761

Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES AVERAGE REACTOR COOLANT REACTOR MODE TEMPERATURE MODE TITLE SWITCH POSITION (OF) 1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot NA Standby 3 Hot Shutdown(a) Shutdown > 212 4 Cold Shutdown(a) Shutdown -<212 5 Refueling (b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

(b) One or more reactor vessel head closure bolts less than fully tensioned.

HATCH UNIT 2 1.1 -7 Amendment No. 176 1

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.3 (Not used.)

SR 3.3.1.1.4 ----------------------------- NOTE ----------------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after entering MODE 2.

Perform CHANNEL---. FUNCT.IONAL................ T....7.....days.

Perform CHANNEL FUNCTIONAL TEST. 7 days S R 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. 7 days SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels withdrawing SRMs overlap, from the fully inserted position SR 3.3.1.1.7 ----------------------------- NOTE ----------------------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap. 7 days SR 3.3.1.1.8 Calibrate the local power range monitors. 1000 effective full power hours SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.1.1.10 ----------------------------- NOTE ----------------------------

For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 184 days (continued)

Amendment No. 176 HATCH UNIT 2 3.3-4

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

NOTES ----------------------------------------------------------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.
2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.2.1.2 ------------------------------ NOTE-- -----------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at < 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.2.1.3 ----------------------------- NOTE -------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS (continued)

HATCH UNIT 2 3.3-17 Amendment No. 176

Feedwater and Main Turbine Trip High Water Level Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS

...----------------------------- NOTE -----------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided feedwater and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.2.2.2 Perform CHANNEL CALIBRATION. The 24 months Allowable Value shall be < 55.5 inches.

SR 3.3.2.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including valve actuation.

HATCH UNIT 2 3.3-21 Amendment No. 176

EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with B.1 Restore EOC-RPT trip 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> EOC-RPT trip capability not capability.

maintained.

OR AND B.2 Apply the MCPR limit 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> MCPR limit for inoperable for inoperable EOC-RPT not made EOC-RPT as specified applicable, in the COLR.

C. Required Action and C.1 Remove the associated 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> associated Completion recirculation pump from Time not met. service.

OR C.2 Reduce THERMAL 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> POWER to < 28% RTP.

SURVEILLANCE REQUIREMENTS

...---------------------------- NOTE ---------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.4.1.2 Verify TSV - Closure and TCV Fast Closure, Trip 24 months Oil Pressure - Low Functions are not bypassed when THERMAL POWER is Z 28% RTP.

(continued)

HATCH UNIT 2 3.3-28 Amendment No. 176

ATWS-RPT Instrumentation 3.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ATWS-RPT trip capability capability for one not maintained. Function.

D. Required Action and D.1 Remove the associated 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion recirculation pump from Time not met. service.

OR D.2 Be in MODE 2. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> SURVEILLANCE REQUIREMENTS

-.-.--.----------.--...........---------------------------- NOTE ---------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS (continued)

HATCH UNIT 2 3.3-31 Amendment No. 176

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

..---------..........---------------------...... NOTES ----------------------------------------------------------

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.5.1.3 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months HATCH UNIT 2 3.3-37 Amendment No. 176

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

.....------------------------- N r7 --------------------------------------------------------------

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> for Function 2; and (b) for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.5.2.3 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.5.2.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months HATCH UNIT 2 3.3-45 Amendment No. 176

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

1. As required by Required 1.1 Initiate action to restore Immediately Action C.1 and referenced channel to OPERABLE in Table 3.3.6.1-1. status.

OR 1.2 Initiate action to isolate Immediately

- the Residual Heat Removal (RHR)

Shutdown Cooling System.

SURVEILLANCE REQUIREMENTS

.....-------..........---------------------...... NOTES ----------------------------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. 92 days on an ALTERNATE TEST BASIS (continued)

HATCH UNIT 2 3.3-49 Amendment No. 176

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.6.1.7 - - ------------------------- NOTE ------------------------------

Channel sensors are excluded.

Verify the ISOLATION SYSTEM RESPONSE 24 months on a TIME is within limits. STAGGERED TEST BASIS HATCH UNIT 2 3.3-50 Amendment No. 176 I

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Place the associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> standby gas treatment (SGT) subsystem(s) in operation.

OR C.2.2 Declare associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SGT subsystem(s) inoperable.

SURVEILLANCE REQUIREMENTS

.......---------------------------- NOTES ----------------------------------------------------------

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. 92 days on an ALTERNATE TEST BASIS SR 3.3.6.2.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months HATCH UNIT 2 3.3-56 Amendment No. 176

LLS Instrumentation 3.3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare the associated Immediately associated Completion LLS valve(s)

Time of Condition A, B, inoperable.

or C not met.

OR Two or more LLS valves with initiation capability not maintained.

SURVEILLANCE REQUIREMENTS

.....----------------------------- NO TES ------------------------------------------------------------

1. Refer to Table 3.3.6.3-1 to determine which SRs apply for each Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided LLS initiation capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.6.3.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.6.3.2 Perform CHANNEL FUNCTIONAL TEST for 92 days on an portion of the channel outside primary ALTERNATE TEST containment. BASIS (continued)

HATCH UNIT 2 3.3-59 Amendment No. 176

LLS Instrumentation 3.3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.3.3 ------------------------------ NOTE ----------------------------

Only required to be performed prior to entering MODE 2 during each scheduled outage > 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> when entry is made into primary containment.

Perform CHANNEL FUNCTIONAL TEST for 92 days on an portions of the channel inside primary ALTERNATE TEST containment. BASIS SR 3.3.6.3.4 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.6.3.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.3.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months HATCH UNIT 2 3.3-60 Amendment No. 176

MCREC System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS NOT E

--------- OTE--------------------------------

When a Control Room Air Inlet Radiation - High channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the other channel is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. The 92 days on an Allowable Value shall be < 1 mr/hour. ALTERNATE TEST BASIS SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months HATCH UNIT 2 3.3-63 Amendment No. 176

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.9 and SR 3.3.1.1.12 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The 92 day on an ALTERNATE TEST BASIS Frequency of SR 3.3.1.1.9 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 21.

The 24 month Frequency of SR 3.3.1.1.12 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency of SR 3.3.1.1.12 is based on a review of the surveillance test history and Reference 20.

SR 3.3.1.1.10 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. For the APRM Functions, this test supplements the automatic self-test functions that operate continuously in the APRM and voter channels. The APRM CHANNEL FUNCTIONAL TEST covers the APRM channels (including recirculation flow processing applicable to Function 2.b only), the two-out-of-four voter channels, and the interface connections to the RPS trip systems from the voter channels. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. The 184 day Frequency of SR 3.1.1.1.10 is based on the reliability analysis of References 13 and 17. (NOTE: The actual voting logic of the two-out-of-four voter channels is tested as part of SR 3.3.1.1.15.)

For Function 2.a, a Note that requires this SR to be performed within 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> of entering MODE 2 from MODE 1 is provided. Testing of the MODE 2 APRM Function cannot be performed in MODE 1 without utilizing jumpers or lifted leads. This Note allows entry into MODE 2 from MODE 1 if the associated Frequency is not met per SR 3.0.2.

SR 3.3.1.1.11 This SR ensures that scrams initiated from the Turbine Stop Valve Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure Low Functions will not be inadvertently bypassed when THERMAL (continued)

HATCH UNIT 2 B 3.3-27 Revision No. 38

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.11 (continued)

REQUIREMENTS POWER is ;t 28% RTP. This involves calibration of the bypass channels. Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint. Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from turbine first stage pressure), the main turbine bypass valves must remain closed during the calibration at THERMAL POWER ; 28% RTP to ensure that the calibration is valid.

If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at 2 28% RTP, either due to open main turbine bypass valve(s) or other reasons), then the affected Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are considered inoperable. Alternatively, the bypass channel can be placed in the conservative condition (nonbypass). If placed in the nonbypass condition (Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are enabled), this SR is met and the channel is considered OPERABLE.

The 24 month Frequency is based on a review of the surveillance test history, drift of the associated instrumentation, and Reference 20.

SR 3.3.1.1.13 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies that the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology. For MSIV - Closure, SDV Water Level - High (Float Switch), and TSV - Closure Functions, this SR also includes a physical inspection and actuation of the switches. For the APRM Simulated Thermal Power - High Function, this SR also includes calibrating the associated recirculation loop flow channel.

Note 1 states that neutron detectors are excluded from CHANNEL CALIBRATION because they are passive devices, with minimal drift, and because of the difficulty of simulating a meaningful signal.

Changes in neutron detector sensitivity are compensated for by performing the 7 day calorimetric calibration (SR 3.3.1.1.2) and the 1000 effective full power hours LPRM calibration against the TIPs (SR 3.3.1.1.8). A second Note is provided that requires the IRM SRs (continued)

HATCH UNIT 2 B 3.3-28 Revision No. 38 1

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.13 (continued)

REQUIREMENTS to be performed within 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> of entering MODE 2 from MODE 1.

Testing of the MODE 2 IRM Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads or movable links. This Note allows entry into MODE 2 from MODE 1 if the associated Frequency is not met per SR 3.0.2.

Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR.

The 24 month Frequency is based on a review of the surveillance test history, drift analysis of the associated instrumentation (ifapplicable),

and Reference 20.

SR 3.3.1.1.14 (Not used.)

SR 3.3.1.1.15 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The functional testing of control rods (LCO 3.1.3), and SDV vent and drain valves (LCO 3.1.8), overlaps this Surveillance to provide complete testing of the assumed safety function.

The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on a review of the surveillance test history and Reference 20.

The LOGIC SYSTEM FUNCTIONAL TEST for APRM Function 2.e simulates APRM and OPRM trip conditions at the two-out-of-four voter channel inputs to check all combinations of two tripped inputs to the two-out-of-four logic in the voter channels and APRM related redundant RPS relays.

SR 3.3.1.1.16 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident (continued)

HATCH UNIT 2 B 3.3-29 Revision No. 38 1

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.16 (continued)

REQUIREMENTS analysis. This test may be performed in one measurement or in overlapping segments, with verification that all components are tested. The RPS RESPONSE TIME acceptance criteria are included in Reference 10.

RPS RESPONSE TIME for APRM two-out-of-four Voter Function 2.e includes the output relays of the voter and the associated RPS relays and contactors. (The digital portions of the APRM and two-out-of-four voter channels are excluded from RPS RESPONSE TIME testing because self-testing and calibration check the time base of the digital electronics.) Confirmation of the time base is adequate to assure required response times are met. Neutron detectors are excluded from RPS RESPONSE TIME testing because the principles of detector operation virtually ensure an instantaneous response time.

Note 1 allows neutron detectors to be excluded from RPS RESPONSE TIME testing because the principles of detector operation virtually ensure an instantaneous response time.

RPS RESPONSE TIME tests are conducted on an 24 month STAGGERED TEST BASIS. Note 3 requires STAGGERED TEST BASIS Frequency to be determined based on four channels per trip system, in lieu of the eight channels specified in Table 3.3.1.1-1 for the Main Steam Line Isolation Valve - Closure Function. This Frequency is based on the logic interrelationships of the various channels required to produce an RPS scram signal. This Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences. The 24 month Frequency, on a STAGGERED TEST BASIS, is also based on a review of the surveillance test history and Reference 20.

Note: SR 3.3.1.1.16 for Function 2.e confirms the response time of that function, and also confirms the response time of loop components common to APRM - Two Out of Four Voter logic and other RPS loops.

SR 3.3.1.1.17 This SR ensures that scrams initiated from OPRM Upscale Function 2.f will not be inadvertently bypassed when THERMAL POWER, as indicated by APRM Simulated Thermal Power, is

25% RTP and core flow, as indicated by recirculation drive flow, is

< 60% rated core flow. This normally involves confirming the bypass (continued)

B 3.3-30 Revision No. 38 1 HATCH UNIT 2

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.17 (continued)

REQUIREMENTS setpoints. Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint. The actual Surveillance ensures that the OPRM Upscale Function is enabled (not bypassed) for the correct values of APRM Simulated Thermal Power and recirculation drive flow. Other Surveillances ensure that the APRM Simulated Thermal Power and recirculation flow properly correlate with THERMAL POWER and core flow, respectively.

If any bypass setpoint is nonconservative (i.e., the OPRM Upscale Function is bypassed when APRM Simulated Thermal Power is ý: 25%

and recirculation drive flow is < 60% rated), then the affected channel is considered inoperable for the OPRM Upscale Function.

Alternatively, the bypass setpoint may be adjusted to place the channel in a conservative condition (unbypass). If placed in the unbypass condition, this SR is met and the channel is considered OPERABLE.

The 24 month Frequency is based on a review of the surveillance test history and Reference 20.

REFERENCES 1. FSAR, Section 7.2.

2. FSAR, Chapter 15.
3. FSAR, Section 6.3.3.
4. FSAR, Supplement 5A.
5. FSAR, Section 15.1.12.
6. NEDO-23842, "Continuous Control Rod Withdrawal in the Startup Range," April 18, 1978.
7. FSAR, Section 15.1.38.
8. P. Check (NRC) letter to G. Lainas (NRC), "BWR Scram Discharge System Safety Evaluation," December 1, 1980.
9. NEDO-30851-P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System," March 1988.
10. Technical Requirements Manual.

(continued)

HATCH UNIT 2 B 3.3-31 Revision No. 38 1

RPS Instrumentation B 3.3.1.1 BASES REFERENCES 11. NRC No.93-102, "Final Policy Statement on Technical (continued) Specification Improvements," July 23, 1993.

12. NEDO-32291, "System Analyses for Elimination of Selected Response Time Testing Requirements," January 1994.
13. NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function," October 1995.
14. NEDO-31960-A, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology," November 1995.
15. NEDO-31960-A, Supplement 1, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology,"

November 1995.

16. NEDO-32465-A, "BWR Owners' Group Long-Term Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," March 1996.
17. NEDO-3241OP-A, Supplement 1, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function,"

November 1997.

18. Letter, L.A. England (BWROG) to M.J. Virgilio, "BWR Owners' Group Guidelines for Stability Interim Corrective Action,"

June 6, 1994.

19. NEDO-32291-A, Supplement 1, "System Analyses for the Elimination of Selected Response Time Testing Requirements," October 1999.
20. NRC Safety Evaluation Report for Amendment 174.
21. NRC Safety Evaluation Report for Amendment 176 , Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-32 Revision No. 38

Control Rod Block Instrumentation B 3.3.2.1 BASES SURVEILLANCE SR 3.3.2.1.2 and SR 3.3.2.1.3 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed for the RWM to ensure that the entire system will perform the intended function. The CHANNEL FUNCTIONAL TEST for the RWM is performed by attempting to withdraw a control rod not in compliance with the prescribed sequence and verifying a control rod block occurs. This test is performed as soon as possible after the applicable conditions are entered. As noted in the SRs, SR 3.3.2.1.2 is not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at

< 10% RTP in MODE 2, and SR 3.3.2.1.3 is not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1. This allows entry into MODE 2 (and if entered during a shutdown, concurrent power reduction to < 10% RTP) for SR 3.3.2.1.2 and THERMAL POWER reduction to < 10% RTP in MODE 1 for SR 3.3.2.1.3 to perform the required Surveillances if the 92 day on an ALTERNATE TEST BASIS Frequency is not met per SR 3.0.2. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> allowance is based on operating experience I

and in consideration of providing a reasonable time in which to complete the SRs. The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history and Reference 13.

SR 3.3.2.1.4 The RBM setpoints are automatically varied as a function of power.

Three Allowable Values are specified in Table 3.3.2.1-1, each within a specific power range. The power at which the control rod block Allowable Values automatically change are based on the APRM signal's input to each RBM channel. Below the minimum power setpoint, the RBM is automatically bypassed. These power Allowable Values must be verified periodically to be less than or equal to the specified values. If any power range setpoint is nonconservative, then the affected RBM channel is considered inoperable. Alternatively, the power range channel can be placed in the conservative condition (i.e.,

enabling the proper RBM setpoint). If placed in this condition, the SR is met and the RBM channel is not considered inoperable. As noted, neutron detectors are excluded from the Surveillance because they are passive devices, with minimal drift, and because of the difficulty of simulating a meaningful signal. Neutron detectors are adequately tested in SR 3.3.1.1.2 and SR 3.3.1.1.8. The 24 month Frequency is based on a review of the surveillance test history and Reference 12.

(continued)

B 3.3-49 Revision No. 38 HATCH UNIT 2

31 Control Rod Block Instrumentation B 3.3.2.1 BASES REFERENCES 7. NRC SER, "Acceptance of Referencing of Licensing Topical (continued) Report NEDE-2401 1-P-A," "General Electric Standard Application for Reactor Fuel, Revision 8, Amendment 17,"

December 27, 1987.

8. NEDC-30851-P-A, "Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation,"

October 1988.

9. GENE-770-06-1, "Bases for Changes To Surveillance Test Intervals And Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications," February 1991.
10. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
11. NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM)

Retrofit Plus Option III Stability Trip Function," October 1995.

12. NRC Safety Evaluation Report for Amendment 174.
13. NRC Safety Evaluation Report for Amendment 176, Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-52 Revision No. 38

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not significantly REQUIREMENTS reduce the probability that the feedwater pump turbines and main (continued) turbine will trip when necessary.

SR 3.3.2.2.1 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

Due to the high turbine trip and reactor scram potential incurred when valving reactor water level differential pressure transmitters into and out of service, it is acceptable to perform the CHANNEL FUNCTIONAL TEST for this logic from the input of the alarm unit.

This is consistent with the CHANNEL FUNCTIONAL TEST definition requiring the signal to be injected "as close to the sensor as practicable." Additionally, due to the physical location of the turbine trip relays and their close proximity to other sensitive equipment, accessibility is extremely limited. Verification of relay actuation and associated relay contact status by accessing the relay introduces a high potential for turbine trip and reactor scram. One contact from each turbine trip relay energizes an amber light indicating relay actuation. Therefore, it is acceptable to terminate the test at the turbine trip relay, utilizing light indication for relay status. These allowances are only acceptable if the CHANNEL CALIBRATION and the LOGIC SYSTEM FUNCTIONAL TEST overlap both the initiation and termination point of this CHANNEL FUNCTIONAL TEST such that the entire trip logic is tested.

The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 5.

SR 3.3.2.2.2 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

(continued)

HATCH UNIT 2 B 3.3-57 Revision Nlo. 38

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE SR 3.3.2.2.2 (continued)

REQUIREMENTS The 24 month Frequency is based on a review of the surveillance test history, drift analysis of the associated instrumentation, and Reference 4.

SR 3.3.2.2.3 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The system functional test of the feedwater and main turbine valves is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide complete testing of the assumed safety function. Therefore, if a valve is incapable of operating, the associated instrumentation channels would also be inoperable. The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on a review of the surveillance test history and Reference 4.

REFERENCES 1. FSAR, Section 15.1.7.

2. GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications," February 1991.
3. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
4. NRC Safety Evaluation Report for Amendment 174.
5. NRC Safety Evaluation Report for Amendment 176 , Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-58 Revision No. 38

EOC-RPT Instrumentation B 3.3.4.1 BASES SUREVILLANCE SR 3.3.4.1.1 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history and Reference 8.

SR 3.3.4.1.2 This SR ensures that an EOC-RPT initiated from the TSV - Closure and TCV Fast Closure, Trip Oil Pressure - Low Functions will not be inadvertently bypassed when THERMAL POWER is a 28% RTP.

This involves calibration of the bypass channels. Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint. Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from first stage pressure) the main turbine bypass valves must remain closed during the calibration at THERMAL POWER ? 28% RTP to ensure that the calibration is valid. If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at Ž 28% RTP, either due to open main turbine bypass valves or other reasons), the affected TSV - Closure and TCV Fast Closure, Trip Oil Pressure - Low Functions are considered inoperable. Alternatively, the bypass channel can be placed in the conservative condition (nonbypass). If placed in the nonbypass condition (Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are enabled), this SR is met with the channel considered OPERABLE.

The 24 month Frequency is based on a review of the surveillance test history, drift of the associated instrumentation, and Reference 7.

SR 3.3.4.1.3 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology. For the TSV - Closure Function, this SR also includes a physical inspection and actuation of the switches.

(continued)

HATCH UNIT 2 B 3.3-81 Revision No. 38

EOC-RPT Instrumentation B 3.3.4.1 BASES SURVEILLANCE SR 3.3.4.1.5 (continued)

REQUIREMENTS STAGGERED TEST BASIS, is also based on a review of the surveillance test history and Reference 7.

SR 3.3.4.1.6 This SR ensures that the RPT breaker interruption time is provided to the EOC-RPT SYSTEM RESPONSE TIME test. Breaker interruption (i.e., trip) time is defined as breaker response time plus arc suppression time. Breaker response time is the time from application of voltage to the trip coil until the main contacts separate. Arc suppression time is the time from main contact separation until the complete suppression of the electrical arc across the open contacts.

Breaker response shall be verified by testing and added to the manufacturer's design arc suppression time to determine breaker interruption time. The breaker arc suppression time shall be validated by the performance of periodic contact gap measurements in accordance with plant procedures. The 60 month Frequency of the testing is based on the difficulty of performing the test and the reliability of the circuit breakers.

REFERENCES 1. FSAR, Section 7.6.10.

2. FSAR, Sections 15.1.1, 15.1.2, and 15.1.3.
3. FSAR, Sections 5.5.16.1 and 7.6.10.
4. GENE-770-06-1, "Bases For Changes To Surveillance Test Intervals And Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications," February 1991.
5. Technical Requirements Manual.
6. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
7. NRC Safety Evaluation Report for Amendment 174.
8. NRC Safety Evaluation Report for Amendment 176, Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-83 Revision No. 38

ATWS-RPT Instrumentation "B3.3.4.2 BASES SURVEILLANCE SR 3.3.4.2.1 (continued)

REQUIREMENTS CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.4.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trips units, and Reference 5.

SR 3.3.4.2.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

(continued)

HATCH UNIT 2 B 3.3-90 Revision No. 38

ATWS-RPT Instrumentation B 3.3.4.2 BASES SURVEILLANCE SR 3.3.4.2.3 (continued)

REQUIREMENTS The 24 month Frequency is based on a review of the surveillance test history, drift analysis of the associated instrumentation, and Reference 4.

SR 3.3.4.2.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The system functional test of the pump breakers is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide complete testing of the assumed safety function.

Therefore, if a breaker is incapable of operating, the associated instrument channel(s) would be inoperable.

The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on a review of the surveillance test history and Reference 4.

REFERENCES 1. FSAR, Section 7.6.10.7.

2. GENE-770-06-1, "Bases for Changes To Surveillance Test Intervals and Allowed Out-of-Service Times For Selected Instrumentation Technical Specifications," February 1991.
3. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
4. NRC Safety Evaluation Report for Amendment 174.
5. NRC Safety Evaluation Report for Amendment 176 Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-91 Revision No. 38

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE SR 3.3.5.1.2 and SR 3.3.5.1.3 (continued)

REQUIREMENTS The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 8.

SR 3.3.5.1.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 24 month Frequency is based on a review of the surveillance test history, drift analysis of the associated instrumentation, and Reference 7.

SR 3.3.5.1.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.1, LCO 3.5.2, LCO 3.7.2, LCO 3.8.1, and LCO 3.8.2 overlaps this Surveillance to complete testing of the assumed safety function.

The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on a review of the surveillance test history and Reference 7.

REFERENCES 1. FSAR, Section 5.2.

2. FSAR, Section 6.3.
3. FSAR, Chapter 15.

(continued)

HATCH UNIT 2 B 3.3-123 Revision No. 38

I ECCS Instrumentation B 3.3.5.1 BASES REFERENCES 4. NEDC-31376-P, "Edwin I. Hatch Nuclear Power Plant, (continued) SAFER/GESTR-LOCA, Loss-of-Coolant Accident Analysis," December 1986.

5. NEDC-30936-P-A, "BWR Owners' Group Technical Specification Improvement Analyses for ECCS Actuation Instrumentation, Part 2," December 1988.
6. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
7. NRC Safety Evaluation Report for Amendment 174.
8. NRC Safety Evaluation Report for Amendment 176 , Quarterly Surveillance Extension. I B 3.3-124 Revision No. 38 HATCH UNIT 2

,* - RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE SR 3.3.5.2.1 (continued)

REQUIREMENTS assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.5.2.2 and SR 3.3.5.2.3 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

SR 3.3.5.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

(continued)

HATCH UNIT 2 B 3.3-133 Revision No. 38

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE SR 3.3.5.2.3 and SR 3.3.5.2.4 (continued)

"REQUIREMENTS The 92 day on an ALTERNATE TEST BASIS Frequency of SR 3.3.5.2.3 is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

The 24 month Frequency of SR 3.3.5.2.4 is based on a review of the surveillance test history, drift analysis of the associated instrumentation, and Reference 3.

SR 3.3.5.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.3 overlaps this Surveillance to provide complete testing of the safety function.

The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on a review of the surveillance test history and Reference 3.

REFERENCES 1. GENE-770-06-2, "Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

2. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
3. NRC Safety Evaluation Report for Amendment 174.
4. NRC Safety Evaluation Report for Amendment 176 , Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-134 Revision No. 38

"PrimaryContainment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.2 (continued)

REQUIREMENTS function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 10.

SR 3.3.6.1.3, SR 3.3.6.1.4, and SR 3.3.6.1.5 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency of SR 3.3.6.1.3 is based on a review of the surveillance test history, drift analysis of the associated pressure (or vacuum) switches (if applicable), and Reference 10. The 184 day Frequency of SR 3.3.6.1.4 and the 24 month Frequency of SR 3.3.6.1.5 are based on a review of the surveillance test history, drift analysis of the associated instrumentation (if applicable), and Reference 9.

SR 3.3.6.1.6 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this Surveillance to provide complete testing of the assumed safety function. The 24 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on a review of the surveillance test history and Reference 9.

SR 3.3.6.1.7 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident (continued)

HATCH UNIT 2 B 3.3-159 Revision No. 38

"PrimaryContainment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6 1.7 (continued)

REQUIREMENTS analysis. The instrument response times must be added to the PCIV closure times to obtain the ISOLATION SYSTEM RESPONSE TIME.ISOLATION SYSTEM RESPONSE TIME acceptance criteria are included in Reference 6. This test may be performed in one measurement, or in overlapping segments, with verification that all components are tested.

A Note to the Surveillance states that channel sensors are excluded from ISOLATION SYSTEM RESPONSE TIME testing. The exclusion of the channel sensors is supported by Reference 8 which indicates that the sensors' response times are a small fraction of the total response time. Even if the sensors experienced response time degradation, they would be expected to respond in the microsecond to millisecond range until complete failure.

ISOLATION SYSTEM RESPONSE TIME tests are conducted on a 24 month STAGGERED TEST BASIS. This Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience that shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.

The 24 month Frequency, on a STAGGERED TEST BASIS, is also based on a review of the surveillance test history and Reference 9.

REFERENCES 1. FSAR, Section 6.3.

2. FSAR, Chapter 15.
3. FSAR, Section 4.2.3.4.2.
4. NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

5. NEDC-30851 P-A Supplement 2, "Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.
6. Technical Requirements Manual.
7. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

(continued)

HATCH UNIT 2 B 3.3-160 Revision No. 38 1

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES REFERENCES 8. NEDO-32291, "System Analyses for Elimination of Selected (continued) Response Time Testing Requirements," January 1994.

9. NRC Safety Evaluation Report for Amendment 174.
10. NRC Safety Evaluation Report for Amendment 176, Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-161 Revision No. 38

-- * - Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE be returned to OPERABLE status or the applicable Condition entered REQUIREMENTS and Required Actions taken. This Note is based on the reliability (continued) analysis (Refs. 5 and 6) assumption of the average time required to perform channel surveillance. That analysis demonstrated the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not significantly reduce the probability that the SCIVs will isolate the associated penetration flow paths and that the SGT System will initiate when necessary.

SR 3.3.6.2.1 Performance of the CHANNEL CHECK once every 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based on operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 9.

(continued)

HATCH UNIT 2 B 3.3-168 Revision No. 38

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE SR 3.3.6.2.3 and SR 3.3.6.2.4 REQUIREMENTS (continued) A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency of SR 3.3.6.2.3 is based on a review of the surveillance test history and Reference 9. The 24 month Frequency of SR 3.3.6.2.4 is based on a review of the surveillance test history, drift analysis of the associated instrumentation, and Reference 8.

SR 3.3.6.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on SCIVs and the SGT System in LCO 3.6.4.2 and LCO 3.6.4.3, respectively, overlaps this Surveillance to provide complete testing of the assumed safety function.

This Surveillance can be performed with the reactor at power for some of the Functions. The 24 month Frequency is based on a review of the surveillance test history and Reference 8.

REFERENCES 1. FSAR, Section 6.3.

2. FSAR, Section 15.
3. FSAR, Section 15.1.40.
4. FSAR, Sections 15.1.39 and 15.1.41.
5. NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

(continued)

Revision No. 38 HATCH UNIT 2 B 3.3-169

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES REFERENCES 6. NEDC-30851 P-A Supplement 2, "Technical Specifications (continued) Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

7. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
8. NRC Safety Evaluation Report for Amendment 174.
9. NRC Safety Evaluation Report for Amendment 17_6_., Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-170 Revision No. 38

LLS Instrumentation B 3.3.6.3 BASES SURVEILLANCE SR 3.3.6.3.2. SR 3.3.6.3.3, and SR 3.3.6.3.4 (continued)

REQUIREMENTS function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units (ifapplicable), and Reference 6.

A portion of the S/RV tailpipe pressure switch instrument channels are located inside the primary containment. The Note for SR 3.3.6.3.3, "Only required to be performed prior to entering MODE 2 during each scheduled outage > 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> when entry is made into primary containment," is based on the location of these instruments, ALARA considerations, and compatibility with the Completion Time of the associated Required Action (Required Action B.1).

SR 3.3.6.3.5 CHANNEL CALIBRATION is a complete check of the instrument loop and sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 24 month Frequency is based on a review of the surveillance test history, drift analysis of the associated instrumentation (if applicable),

and Reference 5.

SR 3.3.6.3.6 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specified channel.

The system functional testing performed in LCO 3.4.3, "Safety/Relief Valves(S/RVs) and LCO 3.6.1.8, "Low-Low Set (LLS) Safety/Relief Valves (S/RVs)," for S/RVs overlaps this test to provide complete testing of the assumed safety function.

The Frequency of once every 24 months for SR 3.3.6.3.6 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 24 month Frequency is based on a review of the surveillance test history and Reference 5.

(continued)

HATCH UNIT 2 B 3.3-177 Revision No. 38

LLS Instrumentation B 3.3.6.3 BASES (continued)

REFERENCES 1. FSAR, Section 7.4.4.

2. FSAR, Section 5.5.17.
3. GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.
4. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
5. NRC Safety Evaluation Report for Amendment 174.
6. NRC Safety Evaluation Report for Amendment 176 , Quarterly Surveillance Extension. I HATCH UNIT 2 B 3.3-178 Revision No. 38

MCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE SR 3.3.7.1.3 REQUIREMENTS (continued) A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on an ALTERNATE TEST BASIS Frequency is based on a review of the surveillance test history and Reference 9.

SR 3.3.7.1.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.7.4, "Main Control Room Environmental Control (MCREC) System," overlaps this Surveillance to provide complete testing of the assumed safety function.

This Surveillance can be performed with the reactor at power. The 24 month Frequency is based on a review of the surveillance test history and Reference 8.

REFERENCES 1. FSAR, Section 7.3.5

2. FSAR, Chapter 6.
3. FSAR, Section 6.4.1.2.2.
4. FSAR, Chapter 15.
5. FSAR, Table 15.1-28.
6. GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.
7. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
8. NRC Safety Evaluation Report for Amendment 174.
9. NRC Safety Evaluation Report for Amendment 16.., Quarterly Surveillance Extension.

HATCH UNIT 2 B 3.3-184 Revision No. 38

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