Text

Technical Specifications
	ML040990713
Person / Time
Site:	Robinson
Issue date:	04/19/2004
From:	; NRC/NRR/DRIP/RLEP
To:	;
	Auluck R, NRR/DRIP/RLEP, 415-1025
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ML041000034	List: ML040990713; ML041000036; ML041040188;
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APPENDIX A TO THE FACILITY OPERATING LICENSE DPR-23 TECHNICAL SPECIFICATIONS FOR H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 CAROLINA POWER & LIGHT COMPANY DARLINGTON COUNTY, S.C.

DOCKET NO. 50-261 HBRSEP Unit No. 2 i Amendment No. 176

TABLE OF CONTENTS 1.0 USE AND APPLICATION .................... 1.1-1 1.1 Definitions . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.2 Logical Connectors ..................... 1.2-1 1.3 Completion Times ...................... 1.3-1 1.4 Frequency . . . . . . . . . . . . . . . . . . . . . . . . . 1.4-1 2.0 SAFETY LIMITS (SLs) .................... 2.0-1 2.1 SLs 2.0-1 2.2 SL Violations . . . . . . . . . . . . . . . . . . . . . 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY . 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY . . . . . . . . 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS . . . . . . . . . . . . . . 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM) . . . . . . . . . . . . . . 3.1-1 3.1.2 Core Reactivity . . . . . . . . . . . . . . . . . 3.1-2 3.1.3 Moderator Temperature Coefficient (MTC) . . . . . 3.1-4 3.1.4 Rod Group Alignment Limits . . . . . . . . . . . . 3.1-6 3.1.5 Shutdown Bank Insertion Limits . . . . . . . . . . 3.1-10 3.1.6 Control Bank Insertion Limits . . . . . . . . . . 3.1-12 3.1.7 Rod Position Indication . . . . . . . . . . . . . 3.1-15 3.1.8 PHYSICS TESTS Exceptions- MODE 2 . . . . . . . . . 3.1-20 3.2 POWER DISTRIBUTION LIMITS . . . . . . . . . . . . . . . 3.2-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) . ....... 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FZH) . . . 3.2-4 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (PDC-3 Axial Offset Control Methodology) . 3.2-7 3.2.4 QUADRANT POWER TILT RATIO (QPTR). 3.2-12 3.3 INSTRUMENTATION . . . . . . . . 3.3-1 3.3.1 Reactor Protection System (RPS) Instrumentation. 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation ... . . . . . . . . . . . . . 3.3-20 3.3.3 Post Accident Monitoring (PAM) Instrumentation . . . 3.3-29 3.3.4 Remote Shutdown System . . . . . . . . . . . . . . . 3.3-33 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation .. .. .. .. .. ... .. . 3.3-35 3.3.6 Containment Ventilation Isolation Instrumentation .. .. .. .. ... .. .. . 3.3-37 3.3.7 Control Room Emergency Filtration System (CREFS)

Actuation Instrumentation . .. .. ... .. . 3.3-40 3.3.8 Auxiliary Feedwater (AFW) System Instrumentation .. .. .. .. ... .. .. . 3.3-44 (continued)

HBRSEP Unit No. 2 ii Amendment No. 176

TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . 3.4-1 3.4.1 RCS Pressure. Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ... .. .. . . 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . . . . 3.4-3 3.4.3 RCS Pressure and Temperature (PIT) Limits . . . . . 3.4-5 3.4.4 RCS Loops-MODES 1 and 2 . . . . . . . . . . . . . . 3.4-9 3.4.5 RCS Loops-MODE 3 ................. 3.4-10 3.4.6 RCS Loops -MODE 4 .... 3.4-14 3.4.7 RCS Loops-MODE 5. Loops Filled . . . . . . . . . . 3.4-16 3.4.8 RCS Loops-MODE 5. Loops Not Filled ........ 3.4-19 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . . . 3.4-21 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . . . 3.4-23 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) . . 3.4-25 3.4.12 Low Temperature Overpressure Protection (LTOP) System 3.4-29 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . . . 3.4-35 3.4.14 RCS Pressure Isolation Valves (PIVs) . . ... .. 3.4-37 3.4.15 RCS Leakage Detection Instrumentation . . . . . . . 3.4-41 3.4.16 RCS Specific Activity . . . . . . . . . . . . . . . 3.4-45 3.4.17 Chemical and Volume Control System (CVCS) . . . . . 3.4-49 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . . . 3.5-1 3.5.1 Accumulators . . . . . . . . . . . . . . . 3.5-1 3.5.2 ECCS-O0 rating . . . . . . . . . . . . . 3.5-4 3.5.3 ECCS -Shutdown . . . . . . . . . . . . . . 3.5-8 3.5.4 Refueling Water Storage Tank (RWST) . . . 3.5-10 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . 3.6-1 3.6.2 Containment Air Lock ... .. . ... . 3.6-3 3.6.3 Containment Isolation Valves . . .. . . 3.6-7 3.6.4 Containment Pressure . .. .. .. .. . 3.6-13 3.6.5 Containment Air Temperature . . . . . . . 3.6-14 3.6.6 Containment Spray and Cooling Systems . . 3.6-15 3.6.7 Spray Additive System . . . . . . . . . . 3.6-18 3.6.8 Isolation Valve Seal Water (IVSW) System 3.6-20 3.7 PLANT SYSTEMS ..................... 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . . 3.7-6 3.7.3 Main Feedwater Isolation Valves (MFIVs),

Main Feedwater Regulation Valves (MFRVs),

and Bypass Valves . .. .. .. .. .. . . . . 3.7-8 3.7.4 Auxiliary Feedwater (AFW) System . . . . . . . . . . 3.7-10 3.7.5 Condensate Storage Tank (CST) . . . . . . . . . . . 3.7.14 3.7.6 Component Cooling Water (CCW) System . . . . . . . . 3.7-16 3.7.7 Service Water System (SWS) . . . . . . . . . . . . . 3.7-18 3.7.8 Ultimate Heat Sink (UHS) . . . . . . . . . . . . . . 3.7-21 (continued)

HBRSEP Unit No. 2 iii Amendment No. 176

TABLE OF CONTENTS 3.7 PLANT SYSTEMS (continued) 3.7.9 Control Room Emergency Filtration System (CREFS) 3.7-22 3.7.10 Control Room Emergency Air Temperature Control (CREATC) . . . . . . . . . . . . . . . . . . 3.7-25 3.7.11 Fuel Building Air Cleanup System (FBACS) . . . . 3.7-28 3.7.12 Fuel Storage Pool Water Level . . . . . . . . . 3.7-30 3.7.13 Fuel Storage Pool Boron Concentration . . . . . 3.7.31 3.7.14 New and Spent Fuel Assembly Storage . . . . . . 3.7-32 3.7.15 Secondary Specific Activity . . . . . . . . . . 3.7-33 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . 3.8-1 3.8.1 AC Sources -Operating .. .. .. ... 3.8-1 3.8.2 AC Sources -Shutdown and During Movement of Irradiated Fuel Assemblies . .. . . . . . 3.8-13 3.8.3 Diesel Fuel Oil, and Starting Air . . . . . . . . 3.8-16 3.8.4 DC Sources -Operating . . . . . . . . . . . . . . 3.8-19 3.8.5 DC Sources- Shutdown and During Movement of Irradiated Fuel Assemblies . .. . . . . . 3.8-22 3.8.6 Battery Cell Parameters . . . . . . . . . . . . . 3.8-24 3.8.7 AC Instrument Bus Sources- Operating . . . . . 3.8-28 3.8.8 AC Instrument Bus Sources- Shutdown and During Movement of Irradiated Fuel Assemblies .. .. .. .... 3.8-30 3.8.9 Distribution Systems- Operating . . . . ... . . . .. .M 3.8-32 3.8.10 Distribution Systems- Shutdown and During bgMovement of Irradiated Fuel Assemblies 3.8-35 3.9 REFUELING OPERATIONS .................. 3.9-1 3.9.1 Boron Concentration . . . . . . . . . . . . . . . . 3.9-1 3.9.2 Nuclear Instrumentation . . . . . . . . . . . . . . 3.9-2 3.9.3 Containment Penetrations . . . . . 3.9-4 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation- High Water Level . . . . . . . . . . 3.9-6 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation -Low Water Level . . . . . . . . . . 3.9-8 3.9.6 Refueling Cavity Water Level . . . . . . . . . . . . 3.9-10 3.9.7 Containment Purge Filter System . . . . . . . . . . 3.9-11 4.0 DESIGN FEATURES . . . . . . . .. .. .. ... .. .. .. 4.0-1 4.1 Site Location . . . . . . .. .. ... ... . ... . 4.0-1 4.2 Reactor Core . . . . . . . . .. ...

.. .. .. 4.0-1 4.3 Fuel Storage . . . . . . . .. . . 4.0-1 5.0 ADMINISTRATIVE CONTROLS . . . .. .. .. ... .. .. .. 5.0-1 5.1 Responsibility . . . . . . .. .. .. ... .. ... . 5.0-1 5.2 Organization . . . . . . . .. .. .. ... .. ... . 5.0-2 5.3 Unit Staff Qualifications . .. .. .. .. ... .. . 5.0-5 5.4 Procedures . . . . . . . . ... .. .. .. ... .. . 5.0-6 (continued)

HBRSEP Unit No. 2 iv Amendment No. 176

TABLE OF CONTENTS 5.0 ADMINISTRATIVE CONTROLS (continued) 5.5 Programs and Manuals . . . . . . . . . . . . . . . . . . 5.0-7 5.6 Reporting Requirements . . . . . . . . . . . . . . . . . 5.0-26 5.7 High Radiation Area ......... .. .. ... . . 5.0-33 HBRSEP Unit No. 2 v Amendment No. 176

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions 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 the application of various simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic out put. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux (AFD) signals between the top and bottom halves of a two section excore neutron detector.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known input. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions.

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.

Whenever a sensing element is replaced, the next required CHANNEL CALIBRATION shall include an inplace cross calibration that compares the other sensing elements with the recently installed sensing element. The CHANNEL CALIBRATION may be performed by means of any series of sequential.

overlapping calibrations or total channel steps so that the entire channel is calibrated.

(continued)

HBRSEP Unit No. 2 1.1-1 Amendment No. 176

Definitions 1.1 1.1 Definitions (continued)

CHANNEL CHECK 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 OPERATIONAL A COT shall be the injection of a simulated or TEST (COT) actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides 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 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, I-132, I-133, I-134.

and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Regulatory Guide 1.109, Rev. 1.

NRC. 1977.

E- AVERAGE E shall be the average (weighted in proportion to DISINTEGRATION ENERGY the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than (continued)

HBRSEP Unit No. 2 1.1-2 Amendment No. 176

Definitions 1.1 1.1 Definitions E-AVERAGE iodines, with half lives > 15 minutes, making up DISINTEGRATION ENERGY at least 95% of the total noniodine activity in (continued) the coolant.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or return),

that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment 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; or

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System;

b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or return) that is not identified LEAKAGE;

c. Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing each master relay and verifying the OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition. power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning (continued)

HBRSEP Unit No. 2 1.1-3 Amendment No. 176

Definitions 1.1 1.1 Definitions MODE specified in Table 1.1-1 with fuel in the reactor (continued) vessel.

OPERABLE - OPERABILITY A system, subsystem, 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, normal or emergency electrical power, cooling and seal 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).

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 of the Updated Final Safety Analysis Report (UFSAR);

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper RATIO (QPTR) excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 2339 MWt.

I 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:

(continued)

HBRSEP Unit No. 2 1.1-4 Amendment No. 196

Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN a. All rod cluster control assemblies (RCCAs) are (continued) fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and

b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the 547rF.

SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing each slave relay and verifying the OPERABILITY of each slave relay. The SLAVE RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of 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.

TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip OPERATIONAL TEST actuating device and verifying the OPERABILITY of (TADOT) required alarm, interlock, display, and trip functions. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the required accuracy.

HBRSEP Unit No. 2 1.1-5 Amendment No. 176

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

MODES REACTIVITY % RATED AVERAGE CONDITION THERMAL REACTOR COOLANT MODE TITLE (keff) POWER(a) TEMPERATURE (OF) 1 Power Operation 2 0.99 > 5 NA 2 Startup 20.99 s 5 NA 3 Hot Standby < 0.99 NA 2 350 4 Hot Shutdown(b) < 0.99 NA 350 > Tavg > 200 5 Cold Shutdown(b) < 0.99 NA s 200 6 Refueling(C) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

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

HBRSEP Unit No. 2 1.1-6 Amendment No. 176

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 (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

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 by 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 indentations 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.

(continued)

HBRSEP Unit No. 2 1.2-1 Amendment No. 176

Logical Connectors 1.2 1.2 Logical Connectors (continued)

EXAMPLES The following examples illustrate the use of logical connectors.

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.

(continued)

HBRSEP Unit No. 2 1.2-2 Amendment No. 176

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

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.

HBRSEP Unit No. 2 1.2-3 Amendment No. 176

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 time of 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. 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 time of discovery of the situation that required entry into the Condition.

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.

(continued)

HBRSEP Unit No. 2 1 .3-1 Amendment No. 176

Completion Times 1.3 1.3 Completion Times DESCRIPTION However, when a subsequent train, subsystem, component, or (continued) 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ." 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 . . ." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and B in Example 1.3-3 may not be extended.

(continued)

HBRSEP Unit No. 2 1.3-2 Amendment No. 176

Completion Times 1.3 1.3 Completion Times (continued)

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 B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

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 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3. the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

HBRSEP Unit No. 2 1.3-3 Amendment No. 176

Completion Times 1.3 I- 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS CONDITION I REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

When a pump is declared inoperable, Condition A is entered.

If the pump 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 pump 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 pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump. LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump.

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 pumps 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 pumps is restored to OPERABLE status and the Completion Time for (continued)

HBRSEP Unit No. 2 1.3-4 Amendment No. 176

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

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.

On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for

> 7 days.

(continued)

HBRSEP Unit No. 2 1.3-5 Amendment No. 176

Completion Times 1.3 I- 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X train train to OPERABLE AND inoperable. status.

10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y Function Y train train to OPERABLE AND inoperable. status.

10 days from discovery of failure to meet the LCO C. One C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X Function X train train to OPERABLE inoperable. status.

AND OR One C.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y Function Y train train to OPERABLE inoperable. status.

(continued)

HBRSEP Unit No. 2 1.3-6 Amendment No. 176

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (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).

The Completion Times of Conditions A and B are modified by a logical connector with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time.

it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.

The separate Completion Time modified by the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO.

This Completion Time allows for an exception to the normal

'time zero" for beginning the Completion Time 'clock'. In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.

(continued)

HBRSEP Unit No. 2 1.3-7 Amendment No. 176

Completion Times 1.3 I- 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves to OPERABLE inoperable. status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months met.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (including the extension) expires while one or more valves are still inoperable, Condition B is entered.

(continued)

HBRSEP Unit No. 2 1.3-8 Amendment No. 176

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

ACTIONS

NOTE ----------------------------

Separate Condition entry is allowed for each inoperable va1ye.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months met.

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 applicable only 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.

(continued)

HBRSEP Unit No. 2 1.3-9 Amendment No. 176

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

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 that 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.

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per inoperable. SR 3.x.x.x. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to s 50X RTP.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated Completion Time not met.

(continued)

HBRSEP Unit No. 2 1.3-10 Amendment No. 176

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)

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 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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.

(continued)

HBRSEP Unit No. 2 1.3-11 Amendment No. 176

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem inoperable. isolated. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each 'Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter' interval begins upon performance of Required Action A.1.

If after Condition A is entered. Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 (continued)

HBRSEP Unit No. 2 1.3-12 Amendment No. 176

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

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 COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.

HBRSEP Unit No. 2 1.3-13 Amendment No. 176

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.

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.

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. 2, and 3.

(continued)

HBRSEP Unit No. 2 1.4-1 Amendment No. 176

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , 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 is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside 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.

If the interval as 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, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.

(continued)

HBRSEP Unit No. 2 1.4-2 Amendment No. 176

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 2 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 reactor power is increased from a power level < 251 RTP to t 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 25X RTP.

(continued)

HBRSEP Unit No. 2 1.4-3 Amendment No. 176

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 2 25% RTP.

Perform channel adjustment. 7 days The interval continues, whether or not the unit operation is

< 25X 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches t 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power a 25% RTP.

Once the unit reaches 25X RTP. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

HBRSEP Unit No. 2 1.4-4 Amendment No. 176

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2. the combination of THERMAL POWER. Reactor Coolant System (RCS) highest cold leg temperature, and pressurizer pressure shall not exceed the SLs specified in Figure 2.1.1-1.

2.1.2 RCS Pressure SL In MODES 1. 2. 3, 4. and 5. the RCS pressure shall be maintained 5 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2. restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.2 In MODE 3, 4. or 5, restore compliance within 5 minutes.

HBRSEP Unit No. 2 2.0-1 Amendment No. 176

SLs 2.0 of:"-9 UJ 040

. . , I1

= z oAACCEPTABLE OPERATION is 10HIGH FLUX TRIP I 520 AT I'll IL OFl RATED POWER -

0 20 40 60 so 100 12 a PERCENT OF RATED THERMAL POWER NOTE: BASED ON A MINIMUM RCS FLOW OF 97.3 x 106 lbm/hr Figure 2.1.1-1 (page 1 of 1)

Reactor Core Safety Limits HBRSEP Unit No. 2 2.0-2 Amendment No. 196

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 3.0.7.

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 LCO 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

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, 2, 3, and 4.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except 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. This (continued)

HBRSEP Unit No. 2 3.0-1 Amendment No. 176

LCO Applicability 3.0 1 3.0 LCO APPLICABILITY LCO 3.0.4 Specification shall not prevent changes in MODES or other (continued) specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

Exceptions to this Specification are stated in the individual Specifications. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time.

LCO 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2. 3.

and 4.

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, additional evaluations and limitations may be required in accordance with Specification 5.5.15, 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 system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the (continued)

HBRSEP Unit No. 2 3.0-2 Amendment No. 176

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.6 applicable Conditions and Required Actions shall be entered (continued) in accordance with [CO 3.0.2.

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.

HBRSEP Unit No. 2 3.0-3 Amendment No. 176

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for 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 failure to meet the LCO. Failure to Derform a Surveillance within the specified Frequency shall 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance.

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 (continued)

HBRSEP Unit No. 2 3.0-4 Amendment No. 176

SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.3 declared not met, and the applicable Condition(s) must be (continued) entered.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall not be made unless the LCO's Surveillances have been met within their specified Frequency. 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.

SR 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1. 2. 3, and 4.

HBRSEP Unit No. 2 3.0-5 Amendment No. 176

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 provided in the COLR.

APPLICABILITY: MODE 2 with keff < 1.0.

MODES 3. 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to 15 minutes restore SDM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is within the limits provided in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the COLR HBRSEP Unit No. 2 3.1-1 Amendment No. 176

Core Reactivity 3.1.2 I- 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity LCO 3.1.2 The measured core reactivity shall be within +/- 1% Ak/k of predicted values.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core A.1 Re-evaluate core 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months reactivity not within design and safety limit. analysis, and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months operating restrictions and SRs.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

HBRSEP Unit No. 2 3.1-2 Amendment No. 176

Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS .

SURVEILLANCE FREQUENCY SR 3.1.2.1 NOTE-----------------..

The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 effective full power days (EFPD) after each fuel loading.

Verify measured core reactivity is within Once prior to

+/- 1X Ak/k of predicted values. entering MODE 1 after each refueling AND

---NOTE ----- -

Only required after 60 EFPD 31 EFPD thereafter HBRSEP Unit No. 2 3.1-3 Amendment No. 176

MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR. The maximum upper limit shall be s +5.0 pcm/0 F at less than 50% RTP or 0.0 pcm/0 F at 50% RTP and above.

APPLICABILITY: MODE 1 and MODE 2 with keff a 1.0 for the upper MTC limit, MODES 1, 2. and 3 for the lower MTC limit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper A.1 Establish 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit. administrative withdrawal limits for control banks to maintain MTC within limit.

B. Required Action and B.1 Be in MODE 2 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion keff < 1.0.

Time of Condition A not met.

C. MTC not within lower C.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limit.

HBRSEP Unit No. 2 3.1-4 Amendment No. 176

MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within upper limit. Once prior to entering MODE 1 after each refueling SR 3.1.3.2 ------ NOTES----------------

1. Not required to be performed until 7 effective full power days (EFPD) after reaching the equivalent of an equilibrium RTP all rods out (ARO) boron concentration of 300 ppm.

2. If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR.

SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

3. SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of s 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR.

Verify MTC is within lower limit. Once each cycle HBRSEP Unit No. 2 3.1-5 Amendment No. 176

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 control rods shall be OPERABLE.

AND Individual indicated rod positions shall be as follows:

a. For bank demand positions 2 200 steps, each rod shall be within 15 inches of its bank demand position, and

b. For bank demand positions < 200 steps, each rod shall be within 7.5 inches of the average of the individual rod positions in the bank.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod(s) A.1.1 Verify SDM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. the limits provided in the COLR.

OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months A.1.2 Initiate boration to restore SDM to within limit.

AND A.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (continued)

HBRSEP Unit No. 2 3.1-6 Amendment No. 176

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION R REQUIRED ACTION [COMPLETION TIME B. One rod not within B.1 Restore rod to within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months alignment limits. alignment limits.

OR B.2.1.1 Verify SDM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the limits provided in the COLR.

OR B.2.1.2 Initiate boration to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore SDM to within limit.

AND B.2.2 Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to s 70% RTP.

AND B.2.3 Verify SDM is within Once per the limits provided 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in the COLR.

AND B.2.4 Perform SR 3.2.1.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND B.2.5 Perform SR 3.2.2.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND B.2.6 Re-evaluate safety 5 days analyses and confirm results remain valid for duration of operation under these conditions.

(continued)

HBRSEP Unit No. 2 3.1-7 Amendment No. 176

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B not met.

D. More than one rod not D.1.1 Verify SDM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within alignment the limits provided limit. in the COLR.

OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D.1.2 Initiate boration to restore required SDM to within limit.

AND 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D.2 Be in MODE 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months alignment limit.

AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter when the rod position deviation monitor is inoperable (continued)

HBRSEP Unit No. 2 3.1-8 Amendment No. 176

Rod Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify rod freedom of movement 92 days (trippability) by moving each rod not fully inserted in the core i 10 steps in either direction.

SR 3.1.4.3 Verify rod drop time of each rod, from the Prior to fully withdrawn position, is 5 1.8 seconds reactor from the beginning of decay of stationary criticality gripper coil voltage to dashpot entry. after each with: removal of the reactor head

a. T8,9 2 5400F; and

b. All reactor coolant pumps operating.

HBRSEP Unit No. 2 3.1-9 Amendment No. 176

Shutdown Bank Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be within insertion limits specified in the COLR.

APPLICABILITY: MODE 1, MODE 2 with any control bank not fully inserted.

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

This LCO is not applicable while performing SR 3.1.4.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both shutdown A.1.1 Verify SDM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months banks not within the limits provided limits. in the COLR.

OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months A.1.2 Initiate boration to restore SDM to within limit.

AND 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months A.2 Restore shutdown banks to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

HBRSEP Unit No. 2 3.1-10 Amendment No. 176

Shutdown Bank Insertion Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown bank is within the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits specified in the COLR.

HBRSEP Unit No. 2 3.1-11 Amendment No. 176

Control Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO 3.1.6 Control banks shall be within the insertion. sequence, and overlap limits specified in the COLR.

APPLICABILITY: MODE 1.

MODE 2 with kff 2 1.0.

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

This LCO is not applicable while performing SR 3.1.4.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank insertion A.1.1 Verify SDM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits not met. the limits provided in the COLR.

OR A.1.2 Initiate boration to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore SDM to within limit.

AND A.2 Restore control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months bank(s) to within limits.

(continued)

HBRSEP Unit No. 2 3.1-12 Amendment No. 176

Control Bank Insertion Limits 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank sequence B.1.1 Verify SDM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or overlap limits not the limits provided met. in the COLR.

OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B.1.2 Initiate boration to restore SDM to within limit.

AND 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B.2 Restore control bank sequence and overlap to within limits.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify estimated critical control bank Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months position is within the limits specified in prior to the COLR. achieving criticality (continued)

HBRSEP Unit No. 2 3.1-13 Amendment No. 176

Control Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.6.2 Verify each control bank insertion is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months within the limits specified in the COLR.

AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter when the rod insertion limit monitor is inoperable SR 3.1.6.3 Verify sequence and overlap limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months specified in the COLR are met for control banks not fully withdrawn from the core.

HBRSEP Unit No. 2 3.1-14 Amendment No. 176

Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Analog Rod Position Indication (ARPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each inoperable rod position indicator per group and each demand position indicator per bank.

CONDITION REQUIRED ACTION COMPLETION TIME A. One ARPI per group inoperable for one or A.1 Verify the position Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months more groups. of the rods with inoperable position indicators by using movable incore detectors*. I OR A.2 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to & 50% RTP.

B. One or more rods with B.1 Verify the position 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable position of the rods with indicators have been inoperable position moved in excess of indicators by using 24 steps in one movable incore direction since the detectors.

last determination of the rod's position. OR (continued)

During Cycle 22. the position of Control Rod H-10. Shutdown Bank B. can be determined by verifying gripper coil parameters of the Control Rod Drive Mechanism have not changed state.

until the repair of the indication system for this rod is completed.

HBRSEP Unit No. 2 3.1-15 Amendment No. 197

Rod Position Indication 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to s 50X RTP.

C. One demand position C.1.1 Verify by Once per indicator per bank administrative means 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for one or all ARPIs for the more banks. affected banks are OPERABLE.

AND C.1.2 -------- NOTE .-.-.-

Only required to be met for bank positions < 200 steps.

Verify the position Once per of each rod in the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months affected bank(s) is within 7.5 inches of the average of the individual rod positions in the affected bank(s).

AND (continued)

HBRSEP Unit No. 2 3.1-16 Amendment No. 176

Rod Position Indication 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.1.3 ------. NOTE----

Only required to be met for bank positions 2 200 steps.

Verify the position Once per of each rod in the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months affected bank(s) is within 15 inches of the bank demand position.

OR C.2 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to - 50X RTP.

D. Required Action and 0.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

HBRSEP Unit No. 2 3.1-17 Amendment No. 176

Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 ...................

NOTE ------------

Only required to be met for bank positions a 200 steps.

Perform CHANNEL CHECK by comparing analog 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months rod position indication and bank demand position indication. AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following

> 6 inches of rod motion when rod position deviation monitor is inoperable 4

SR 3.1.7.2 ---------- NOTE-............

Only required to be met for bank positions

< 200 steps.

Verify each ARPI is within 7.5 inches of 31 days the average of the individual ARPIs in the associated bank after moving each full length RCCA bank 2 19 steps and returning the banks to their original positions.

SR 3.1.7.3 -----------.----- NOTE ----------- ----

Only required to be met for bank positions 2 200 steps.

Verify each ARPI is within 15 inches of the 31 days associated bank demand position after moving each full length RCCA bank 2 19 steps and returning the banks to their original positions.

(continued)

HBRSEP Unit No. 2 3.1-18 Amendment No. 176

Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.4 Perform CHANNEL CALIBRATION of the ARPI 18 months System.

HBRSEP Unit No. 2 3.1-19 Amendment No. 176

PHYSICS TESTS Exceptions-MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions-MODE 2 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";

ICO 3.1.5. Shutdown Bank Insertion Limits";

LCO 3.1.6. "Control Bank Insertion Limits"; and LCO 3.4.2. "RCS Minimum Temperature for Criticality" may be suspended. provided:

a. RCS lowest loop average temperature is 2 5300F;

b. SDM is within the limits provided in the COLR; and.

c. THERMAL POWER is s 5% RTP APPLICABILITY: MODE 2 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to 15 minutes restore SDM to within limit.

AND A.2 Suspend PHYSICS TESTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months exceptions.

B. THERMAL POWER not B.1 Open reactor trip Immediately within limit. breakers.

(continued)

HBRSEP Unit No. 2 3.1-20 Amendment No. 176

PHYSICS TESTS Exceptions-MODE 2 3.1.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. RCS lowest loop C.1 Restore RCS lowest 15 minutes average temperature loop average not within limit. temperature to within limit.

D. Required Action and D.1 Be in MODE 3. 15 minutes associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Perform a CHANNEL OPERATIONAL TEST on power Within 7 days range and intermediate range channels per prior to SR 3.3.1.7. SR 3.3.1.8, and Table 3.3.1-1. initiation of PHYSICS TESTS SR 3.1.8.2 Verify the RCS lowest loop average 30 minutes temperature is t 530 0F.

SR 3.1.8.3 Verify THERMAL POWER is s 5% RTP. 30 minutes SR 3.1.8.4 Verify SDM is within the limits provided in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the COLR.

HBRSEP Unit No. 2 3.1-21 Amendment No. 176

F0(Z) 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

LCO 3.2.1 FqWZ, as approximated by Fov(Z), shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fav(Z) not within A.1 Reduce AFD target 15 minutes limit. band limits to restore FQ(Z) to within limit.

OR A.2.1 Reduce THERMAL POWER 30 minutes 2 1X RTP for each 1i Fq(Z) exceeds limit.

AND A.2.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Neutron Flux-High trip setpoint9 2 1X for each 1% F(Z) exceeds limit.

AND A.2.3 Reduce Overpower and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Overtemperature AT trip setpoints 2 1X for each 1X FQ(Z) exceeds limit.

AND (continued)

HBRSEP Unit No. 2 3.2-1 Amendment No. 176

Fo(Z) 3.2.1 ACTIONS CONDITION REQUIRED ACTION COMfPLETION TIME A. (continued) A.2.4 Perform SR 3.2.1.1. Prior to increasing THERMAL POWER above the limit of Required Action A.2.1 B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

HBRSEP Unit No. 2 3.2-2 Amendment No. 176

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS

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

During power escalation at the beginning of each cycle. THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.

SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify FQ(Z) is within limit. Once after each refueling prior to THERMAL POWER exceeding 75X RTP AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by t 10% RTP, the THERMAL POWER at which F8(Z) was last verified AND 31 EFPD thereafter L ___________________________

HBRSEP Unit No. 2 3.2-3 Amendment No. 176

FA.H 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FZN)

LCO 3.2.2 EL shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE-------- A.1.1 Restore F^H to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Actions A.2 limit.

and A.3 must be completed whenever OR Condition A is entered. A.1.2.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

...................... . .to< 50%RTP.

FIN not within limit. AND A.1.2.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Neutron Flux-High trip setpoints to 55XRTP.

AND A.2 Perform SR 3.2.2.1. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

HBRSEP Unit No. 2 3.2-4 Amendment No. 176

3.2.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 .--. -NOTEE.

THERMAL POWER does not have to be reduced to comply with this Required Action.

Perform SR 3.2.2.1. Prior to THERMAL POWER exceeding 50X RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER reaching

> 95X RTP B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

HBRSEP Unit No. 2 3.2-5 Amendment No. 176

3N22 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 ............... TE -----------

-.. -NO IfFz is within limits and measurements indicate thatFA, is increasing with exposure then:

a. Increase Fq(Z) by a factor of 1.02 and reverify Fv(Z) is within limits; or

b. Perform SR 3.2.1.1 and SR 3.2.3.3 once per 7 EFPD until two successive measurements indicate FwH is not increasing.

Verify FAH is within limits specified in the Once after each COLR. refueling prior to THERMAL POWER exceeding 75% RTP AND 31 EFPD thereafter A. ___________________________

HBRSEP Unit No. 2 3.2-6 Amendment No. 176

AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (PDC-3 Axial Offset Control Methodology)

LCO 3.2.3 The AFD:

a. Shall be maintained within the target band about the target flux difference. The allowable values of the target band are specified in the COLR.

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

The AFD shall be considered outside the target band when two or more OPERABLE excore channels indicate AFD to be outside the target band.

b. May deviate outside the target band with THERMAL POWER

< 90% RTP or 0.9 APL, whichever is less, but 2 50% RTP.

provided AFD is within the acceptable operation limits and cumulative penalty deviation time is s 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The acceptable operation limits are specified in the COLR.

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

- 1. Penalty deviation time shall be accumulated on the basis of a 1 minute penalty deviation for each 1 minute of power operation with AFD outside the target band.

2. The Allowable Power Level (APL) is the limitation placed on THERMAL POWER for the purposes of applying the AFD target flux and operational limit curves. The APL is as follows:

APL = minimum over Z of (1O0X)(Fq (Z))(K(Z))/Fv(Z)

c. May deviate outside the target band with THERMAL POWER

< 50% RTP.

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

Penalty deviation time shall be accumulated on the basis of a 0.5 minute penalty deviation for each 1 minute of power operation with AFD outside the target band.

HBRSEP Unit No. 2 3.2-7 Amendment No. 176

AFD

3.2.3 APPLICABILITY

MODE 1 with THERMAL POWER > 15X RTP.

NOTE-------------------------

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months of operation may be accumulated with AFD outside the target band without penalty deviation time during surveillance of power range channels in accordance with SR 3.3.1.6. provided AFD is maintained within acceptable operation limits.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. THERMAL POWER A.1 Restore AFD to within 15 minutes 2 90X RTP or 0.9 APL. target band.

whichever is less.

AND AFD not within the target band.

B. Required Action and B.1 Reduce THERMAL POWER 15 minutes associated Completion to < 90X RTP or 0.9 Time of Condition A APL, whichever is not met. less.

(continued)

HBRSEP Unit No. 2 3.2-8 Amendment No. 176

AFD 3.2.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.- -- NOTE .- C.1

-- Reduce THERMAL POWER 30 minutes Rejuired Action C.1 to c 50% RTP.

an C.2 must be completed whenever AND Condition C is entered. C.2 Restore cumulative Prior to

...................... penalty deviation increasing time to less than 1 THERMAL POWER THERMAL POWER < 90% hour. to 2 50% RTP RTP or 0.9 APL.

whichever is less, and 2 50X RTP with cumulative penalty deviation time > 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

OR THERMAL POWER < 90%

RTP or 0.9 APL.

whichever is less, and 2 50X RTP with AFD not within the acceptable operation limits.

D. --------- NOTE . - D.1

--- Reduce THERMAL POWER 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Required Action D.1 to c 15% RTP.

must be completed whenever Condition D is entered.

Required Action and associated Completion Time for Condition C not met.

HBRSEP Unit No. 2 3.2-9 Amendment No. 176

AFD 3.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD is within limits for each 7 days OPERABLE excore channel.

SR 3.2.3.2 ................... NOTE..-.--.

Assume logged values of AFD exist during the preceding time interval.

Verify AFD is within limits and log AFD for .----NOTE. ---

each OPERABLE excore channel. Only required to be performed if AFD monitor alarm is inoperable Once within 15 minutes and every 15 minutes thereafter when THERMAL POWER 2 90% RTP or 0.9 APL, whichever is less AND Once within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months thereafter when THERMAL POWER

< 90X RTP or 0.9 APL.

whichever is less (continued)

HBRSEP Unit No. 2 3.2 10 Amendment No. 176

AFD 3.2.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.3.3 .................... NOTE..---.-.----.-

1. The initial target flux difference after each refueling may be determined from design predictions.

2. The target flux difference shall be determined in conjunction with the measurement of FQ(Z) in accordance with SR 3.2.1.1.

Determine, by measurement, the target flux Once within difference of each OPERABLE excore channel. 31 EFPD after each refueling AND 31 EFPD thereafter HBRSEP Unit No. 2 3.2-11 Amendment No. 176

QPTR 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

LCO 3.2.4 The QPTR shall be < 1.02.

APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit. A.1 Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 3% from RTP for each 1%of QPTR

> 1.00.

AND A.2 Determine QPTR and Once per reduce THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> 3% from RTP for each 1%of QPTR

> 1.00.

AND A.3 Perform SR 3.2.1.1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and SR 3.2.2.1.

AND Once per 7 days thereafter AND A.4 Reevaluate safety Prior to analyses and confirm increasing results remain valid THERMAL POWER for duration of above the limit operation under this of Required condition. Action A.1 (continued)

I S HBRSEP Unit No. 2 3.2-12 Amendment No. 176

QPTR 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.5 ..----- NOTE.-------

Perform Required Action A.5 only after Required Action A.4 is completed.

Normalize excore Prior to detectors to show increasing zero QPTR. THERMAL POWER above the limit of Required Action A.1 or A.2 A.6 .-------NOTE .-.---.

Perform Required Action A.6 only after Required Action A.5 is completed.

Perform SR 3.2.1.1 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and SR 3.2.2.1. after reaching RTP OR Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of Required Action A.1 or A.2 B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to s 50X RTP.

Time not met.

HBRSEP Unit No. 2 3.2 13 Amendment No. 176

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 ---------------- NOTES- -----------

1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER c 75X RTP. the remaining three power range channels can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this Surveillance.

Verify QPTR is within limit by 7 days calculation.

AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter with the QPTR alarm inoperable.

SR 3.2.4.2 .----..-----.----- NOTE .------.----.--

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER 2 75% RTP.

Verify QPTR is within limit using the Once within movable incore detectors. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter HBRSEP Unit No. 2 3.2-14 Amendment No. 176

RPS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1 The RPS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in required channels Table 3.3.1-1 for the inoperable. channel(s).

B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Trip channel OPERABLE status.

inoperable.

OR 8.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months QAN B.2.2 Open reactor trip 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months breakers (RTBs).

(continued)

HBRSEP Unit No. 2 3.3-1 Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One channel or train C.1 Restore channel or 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. train to OPERABLE status.

OR C.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months D. One Power Range D.1.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Neutron Flux- High trip.

channel inoperable.

AND D.1.2 Reduce THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to s 75X RTP.

OR D.2.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trip.

NOTE.----.-.--

Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable.

D.2.2 Perform SR 3.2.4.2. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR D.3 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

HBRSEP Unit No. 2 3.3-2 Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel E.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable. trip.

E.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. THERMAL POWER > P-6 F.1 Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and < P-10. one to < P-6.

Intermediate Range Neutron Flux channel OR inoperable.

F.2 Increase THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to > P-10.

G. THERMAL POWER > P-6 G.1 ------NOTE . -. --

and < P-10. two Limited boron Intermediate Range concentration changes Neutron Flux channels associated with RCS inoperable. inventory control or limited plant temperature changes are allowed.

Suspend operations Immediately involving positive reactivity additions.

AM G.2 Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to < P-6.

(continued)

HBRSEP Unit No. 2 3.3-3 Amendment No. 176.190

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. THERMAL POWER < P-6. H.1 Restore channel(s) to Prior to one or two OPERABLE status. increasing Intermediate Range THERMAL POWER Neutron Flux channels to > P-6 inoperable.

I. One Source Range .1 ------ NOTE-........

Neutron Flux channel Limited boron inoperable. concentration changes associated with RCS inventory control or limited plant temperature changes are allowed.

Suspend operations Immediately involving positive reactivity additions.

J. Two Source Range J.1 Open RTBs. Immediately Neutron Flux channels inoperable.

K. One Source Range K.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Neutron Flux channel OPERABLE status.

inoperable.

OR K.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months (continued)

HBRSEP Unit No. 2 3.3-4 Amendment No. 176.190

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. Required Source Range NOTE-----------

Neutron Flux Plant temperature changes are channel(s) inoperable. allowed provided the temperature change is accounted for in the calculated SDM.

L.1 Suspend operations Immediately involving positive reactivity additions.

AMn L.2 Close unborated water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months source isolation valves.

L.3 Perform SR 3. 1. 1. 1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued)

HBRSEP Unit No. 2 3.3-4a Amendment No. t76.190 I

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME M. One channel M.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable. trip.

M.2 Reduce THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to < P-7.

N. One Reactor Coolant N.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Flow - Low (Single trip.

Loop) channel inoperable. OR N.2 Reduce THERMAL POWER 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to < P-8.

0. One Reactor Coolant 0.1 Restore channel to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Pump Breaker Position OPERABLE status.

channel inoperable.

0.2 Reduce THERMAL POWER 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to < P-B.

P. One Turbine Trip P.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months channel inoperable. trip.

OR P.2 Reduce THERMAL POWER 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to < P-7.

(continued)

HBRSEP Unit No. 2 3.3-5 Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Q. One train inoperable. ---------- NOTE.........

One train may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months provided the other train is OPERABLE.

Q.1 Restore train to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OPERABLE status.

OR Q.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months R. One RTB train ..----- NOTE----.

inoperable. One train may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , provided the other train is OPERABLE.

R.1 Restore train to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

OR R.2 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months (continued)

HBRSEP Unit No. 2 3.3-6 Amendment No. 176

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME S. One channel S.1 Verify interlock is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. in required state for existing unit conditions.

OR S.2 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months T. One channel T.1 Verify interlock is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. in required state for existing unit conditions.

OR T.2 Be in MODE 2. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months U. One trip mechanism U.1 Restore inoperable 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable for one trip mechanism to RTB. OPERABLE status.

OR U.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND U.2.2 Open RTB. 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months V. Two RPS trains V.1 Enter LCO 3.0.3. Immediately inoperable.

HBRSEP Unit No. 2 3.3-7 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1-1 to determine which SRs apply for each RPS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2 ------. ------- NOTES-------------------

1. Adjust NIS channel if absolute difference is > 2X.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is a 15% RTP.

Compare results of calorimetric heat 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months balance calculation to Nuclear Instrumentation System (NIS) channel output.

SR 3.3.1.3 ------------------ NOTES- --. =.-.--.-

1. Adjust NIS channel if absolute difference is a 3X.

2. Not required to be performed until 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months after THERMAL POWER is 2 15X RTP.

Compare results of the incore detector 31 effective measurements to NIS AFD. full power days (EFPD)

(continued)

HBRSEP Unit No. 2 3.3-8 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.4 ---------. ------ NOTE.------.-----------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

Perform TADOT. 31 days on a STAGGERED TEST BASIS SR 3.3.1.5 ------------------ NOTE ------------------

Not required to be performed for the logic inputs from Source Range Neutron Flux detector prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.1.6 -------------------NOTE.-------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER Is 2 50X RTP.

Calibrate excore channels to agree with 92 EFPD incore detector measurements.

SR 3.3.1.7 ------------.---- NOTE.----------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

Perform COT. 92 days (continued)

HBRSEP Unit No. 2 3.3-9 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.8 NOTE...-----------------

This Surveillance shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.

Perform COT. NOTE-....

Only required when not performed within previous 92 days Prior to reactor startup AND Four hours after reducing power below 10 for power and intermediate instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND Every 92 days thereafter (continued)

HBRSEP Unit No. 2 3.3-10 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.9 .----- ..-..-- NOTE.----------.--- ---

Verification of setpoint is not required.

Perform TADOT. 92 days SR 3.3.1.10 ---------.------- NOTE. --- .---

This Surveillance shall include verification that the time constants are adjusted to the prescribed values where applicable.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.11 ---------. ------- NOTE.-------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.12 - .---------- -- NOTE.------------.-----

This Surveillance shall include verification that the electronic dynamic compensation time constants are set at the required values. and verification of RTD response time constants.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.13 Perform COT. 18 months (continued)

HBRSEP Unit No. 2 3.3-11 Amendment No. 176

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.14 .-..-....-----.- NOTE.--------.----------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.1.15 --------------.---- NOTE.--- ---------- -- ..... NOTE ----.

Verification of setpoint is not required. Only required

........................................... .when not performed within previous 31 days Perform TADOT. Prior to reactor startup HBRSEP Unit No. 2 3.3 12 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 7)

Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

1. Manual Reactor 1.2 2 B SR 3.3.1.14 NA NA Trip 3(a). 4(a). 5(a) 2 C SR 3.3.1.14 NA NA

2. Power Range Neutron Flux

a. High 1.2 4 D SR 3.3.1.1 s 110.93S 108%

SR 3.3.1.2 RTP RTP (2)

SR 3.3.1.7 SR 3.3.1.11

b. Low 1(b). 2 4 E SR 3.3.1.1 s 26.93? 24% RTP SR 3.3.1.8 RTP SR 3.3.1.11

3. Intermediate Range 1(b). 2(c) 2 f.6 SR 3.3.1.1 s 37.02% 25% RTP Neutron Flux SR 3.3.1.8 RTP SR 3.3.1.11 2(d) 2 H SR 3.3.1.1 s 37.02* 25% RTP SR 3.3.1.8 RTP SR 3.3.1.11

4. Source Range 2(d) 2 I.J SR 3.3.1.1 s 1.28 E5 1.0 E5 Neutron Flux SR 3.3.1.8 cps cps SR 3.3.1.11 3(a). 4(a). 5(a) 2 J.K SR 3.3.1.1 s 1.28 E5 1.0 E5 SR 3.3.1.7 cps cps SR 3.3.1.11 3(e). 4(e), 5(e) 1 L SR 3.3.1.1 N/A N/A SR 3.3.1.11 (continued)

(1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(2) The Nominal Trip Setpoint is as stated unless reduced as required by one or more of the following requirements:

LCO 3.2.1 Required Action A.2.2: LCO 3.2.2 Required Action A.1.2.2; or LCO 3.7.1 Required Action B.2.

(a) With Rod Control System capable of rod withdrawal. or one or more rods not fully inserted.

(b) Below the P-10 (Power Range Neutron Flux) interlock.

(c) Above the P-6 (Intermediate Range Neutron Flux) interlock.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlock.

(e) With the RTBs open. In this condition. source range Function does not provide reactor trip but does provide indication and alarm.

HBRSEP Unit No. 2 3.3-13 Amnendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 7)

Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

S. Overtemperature AT 1.2 3 E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 1 Note 1 SR 3.3.1.6 (Page (Page SR 3.3.1.7 3.3-18) 3.3-18)

SR 3.3.1.12 (3)

6. Overpower AT 1.2 3 E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 2 Note 2 SR 3.3.1.6 (Page (Page SR 3.3.1.7 3.3-19) 3.3-19)

SR 3.3.1.12 (3)

7. Pressurizer Pressure

a. Low i(f) 3 H SR 3.3.1.1 a 1832.02 1844 SR 3.3.1.7 psig psig SR 3.3.1.10

b. High 1.2 3 E SR 3.3.1.1 s 2381.11 2376 SR 3.3.1.7 psig psig SR 3.3.1.10

8. Pressurizer Water i(f) 3 H SR 3.3.1.1 s 91.64% 91S Level - High SR 3.3.1.7 SR 3.3.1.10 (continued)

(1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(3) The Nbminal Trip Setpoint is as stated unless reduced as required by LCO 3.2.1 Required Action A.2.3.

(fOAbove the P.7 (Low Power Reactor Trips Block) interlock.

HBRSEP Unit No. 2 3.3-14 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 7)

Reactor Protection System Instrumentation APPLICABLE NODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

9. Reactor Coolant Flow - Low

a. Single Loop 1(g) 3 per N SR 3.3.1.1 k 93.47? 94.26X loop SR 3.3.1.7 SR 3.3.1.10

b. Two Loops l(h) 3 per N SR 3.3.1.1 t 93.47X 94.26?

loop SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant Pump (RCP) Breaker Position

a. Single Loop 1(g) 1 per 0 SR 3.3.1.14 NA NA RCP

b. Two Loops 1(h) 1 r N SR 3.3.1.14 NA NA

11. Undervoltage 1(f) 1 per N SR 3.3.1.9 t 2959 V 3120 V RCPs bus SR 3.3.1.10

12. Underfrequency 1t 1 per N SR 3.3.1.10 t 57.84 58.2 Hz RCPs bus SR 3.3.1.14 Hz

13. Steam 1.2 3 per SG E SR 3.3.1.1 t 15.36? 16?

Generator (SG) SR 3.3.1.7 Water Level - Low SR 3.3.1.10 Low (continued)

(1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

Ci) Above the P.7 (Low Power Reactor Trips Block) interlock.

(g) Above the P-8 (Power Range Neutron Flux) Interlock.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) interlock.

HBRSEP Unit No. 2 3.3 15 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7)

Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

14. SG Water 1.2 2 per SG E SR 3.3.1.1 t 29.36S 30S Level - Low SR 3.3.1.7 SR 3.3.1.10 Coincident with 1.2 2 per SG E SR 3.3.1.1 s 7.06 ES 6.4 E5 Steam Flow/ SR 3.3.1.7 Ibm/hr Ibm/hr Feedwater Flow SR 3.3.1.10 Mismatch

15. Turbine Trip

a. Low Auto Stop (f) 3 p SR 3.3.1.10 t 40.87 45 pspg Oil Pressure OilPrssreSR 3.3.1.15 pslg

b. Turbine Stop l) 2 P SR 3.3.1.15 MA NA Valve Closure

16. Safety 1.2 2 trains Q SR 3.3.1.14 NA NA Injection (SI)

Input from Engineered Safety Feature Actuation System (ESFAS)

(continued)

(1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(f) Above the P-7 (Low Power Reactor Trips Block) interlock.

HBRSEP Unit No. 2 3.3 16 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 7)

Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

17. Reactor Protection System Interlocks

a. Intermediate 2 (d) 2 S SR 3.3.1.11 t 7.29 1 E-10 Range Neutron SR 3.3.1.13 E-11 amp amp Flux. P-6

b. Low Power 1 I per T SR 3.3.1.13 MA NA Reactor Trips train SR 3.3.1.14 Block. P-7

c. Power Range 1 4 T SR 3.3.1.11 s 42.94X 40% RTP Neutron Flux, SR 3.3.1.13 RTP P-B

d. Power Range 1.2 4 S SR 3.3.1.11 t 7.06? 10X RTP Neutron Flux. SR 3.3.1.13 RTP and s P.10 12.94%

RTP

e. Turbine Impulse 1 2 T SR 3.3.1.1 s 10.71? 10%

Pressure. Pv7 SR 3.3.1.10 turbine turbine input SR 3.3.1.13 power power

18. Reactor T)P 1.2 2 trains R.V SR 3.3.1.4 NA NA reaers (a) 4 (a), 5(a) 2 trains C.V SR 3.3.1.4 NA MA

19. Reactor Trip 1.2 1 each U SR 3.3.1.4 NA NA Breaker per RTB Undervoltage and Shunt Trip 3(a), 4(a), 5(a) 1 each C SR 3.3.1.4 KA MA Mechanisms per RTB

20. Automatic Trip 1(J)* 2 2 trains Q.V SR 3.3.1.5 NA NA Logic 3(a), 4(a), 5(a) 2 trains C.V SR 3.3.1.5 NA NA (1) A channel isOPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(a) With Rod Control System capable of rod withdrawal. or one or more rods not fully inserted.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlock.

(i) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

(J) Below the P-6 (Intermediate Range Neutron Flux) interlock for the logic inputs from Source Range Neutron Flux detector channels.

HBRSEP Unit No. 2 3.3-17 Amendment No. 176

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 7)

Reactor Protection System Instrumentation Ntnt 1.- fvertmperatire AT The Overtemperature AT Function Allowable Value shall not exceed the following Nominal Trip Setpoint by more than 2.965 of AT span.

ATsem4s < ATo KiK-2 (I %r S) (T - T) + K3(P - P')-irAI)}

Where: ATo is the indicated AT at RTP, 'F.

s is the Laplace transform operator, sec .

T is the measured RCS average temperature, OF.

T' is the reference Tavg at RTP, s 575.9 0F. I P is the measured pressurizer pressure, psig PI is the nominal RCS operating pressure, s 2235 psig Ki s 1.1265 K2 = 0.01228/°F K3 = 0.00089/psig X1 2 20.08 sec x2 s 3.08 sec f(AI) = 2.4{(qb - qt) - 17} when qt - qb < - 17% RTP 0% of RTP when -17X RTP s qt - qb s 12% RTP 2.4{(qt - qb) - 121 when qt - qb > 12X RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

HBRSEP Unit No. 2 3.3-18 Amendment No. 196

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 7)

Reactor Protection System Instrumentation Note 2-7vPrpnwPr AT The Overpower AT Function Allowable Value shall not exceed the following Nominal Trip Setpoint by more than 3.17X of AT span.

ATse *' AToJ K4- Ks[ T3 T-K 6 (T - T')-ftA I)J WI [I+ r3S])

Where: ATo is the indicated AT at RTP, 0F.

s is the Laplace transform operator, sec'.

T is the measured RCS average temperature, OF.

T' is the reference Taxg at RTP. s 575.90F.

K. 5 1.06 K5 2 0.02/1F for Increasing Tavq K6 2 0.00277/°F when T > T' 0/1F for decreasing Taw 01/F when T s T' 13 2 9 sec f(AI) = as defined in Note 1 for Overtemperature AT HBRSEP Unit No. 2 3.3-19 Amendment No. 196

ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2-1.

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 Immediately with one or more referenced in required channels or Table 3.3.2-1 for the trains inoperable. channel(s) or train(s).

B. One channel or train B.1 Restore channel or 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. train to OPERABLE status.

OR B.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

HBRSEP Unit No. 2 3.3-20 Amendment No. 176

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. C.1 Restore train to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

C.2.1 Be in MODE 3. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months AND C.2.2 Be in MODE 5. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months D. One channel D.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable. trip.

OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months E. One Containment E.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Pressure channel trip.

inoperable. OR E.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND E.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months MD E.2.3 Be in MODE 5. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months (continued)

HBRSEP Unit No. 2 3.3-21 Amendment No. 176

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One channel or train F.1 Restore channel or 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. train to OPERABLE status.

OR F.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND F.2.2 Be in MODE 4. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months G. One train inoperable. G.1 Restore train to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

G.2.1 Be in MODE 3. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months AND G.2.2 Be in MODE 4. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

HBRSEP Unit No. 2 3.3-22 Amendment No. 176

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. One channel H.1 Verify interlock is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. in required state for existing unit condition.

OR H.2.1 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND H.2.2 Be in MODE 4. 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months I. One train inoperable I.1 Restore train to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

OR I.2.1 Be in MODE 3 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months I.2.2 Be in MODE 4 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months AND 1.2.3 Be in MODE 5 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months HBRSEP Unit No. 2 3.3-23 Amendment No. 176

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.

2. When a channel or train is placed in an inoperable status solely for the performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the redundant train is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.2.2 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.2.3 Perform MASTER RELAY TEST. 18 months SR 3.3.2.4 Perform COT. 92 days SR 3.3.2.5 Perform SLAVE RELAY TEST. 18 months SR 3.3.2.6 ------------------NOTE.------------------

Verification of setpoint not required for manual initiation functions.

Perform TADOT. 18 months SR 3.3.2.7 Perform CHANNEL CALIBRATION. 18 months HBRSEP Unit No. 2 3.3-24 Amendment No. 176

ESFAS INSTRUMENTATION 3.3.2 Table 3.3.2-1 (page 1 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE HODES OR NOMINAL OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1) 1.Safety Injection

a. Manual Initiation 1.2.3.4 2 B SR 3.3.2.6 NA NA

b. Automatic 1.2.3.4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

c. Containment 1.2.3.4 3 E SR 3.3.2.1 S 4.45 psig 4 psig Pressure High SR 3.3.2.4 SR 3.3.2.7

d. Pressurizer 1.2.3(a) 3 D SR 3.3.2.1 2 1709.89 1715 psig Pressure - Low SR 3.3.2.4 psig SR 3.3.2.7

e. Steam Line High 1.2.3 3 per D SR 3.3.2.1 93.76 8 100 psig Differential steam SR 3.3.2.4 psig Pressure Between line SR 3.3.2.7 S 116.24 Steam Header and psig Steam Lines

f. High Steam Flow in 1.2 b).3M 2 per D SR 3.3.2.1 (c) (d)

Two Steam Lines steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with 1,2(b) .3 b) 1 per D SR 3.3.2.1 2 541.50 543¶F Twig - Low loop SR 3.3.2.4 OF SR 3.3.2.7

g. High Steam Flow in 1.2 ,3 2 per D SR 3.3.2.1 (c) (d)

Two Steam Lines steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with 1.2 .3 1 per D SR 3.3.2.1 2 605.05 614 psig Steam Line loop SR 3.3.2.4 psig Pressure - Low SR 3.3.2.7 (continued)

(1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(a) Above the Pressurizer Pressure interlock.

(b) Above the Twig-Low interlock.

(c) Less than or equal to a function defined as AP corresponding to 41.58* full steam flow below 20* load, and AP increasing linearly from 41.58* full steam flow at 20* load to 110.5t full steam flow at 100% load, and AP corresponding to 110.5* full steam flow above 100* load.

(d) A function defined as AP corresponding to 37.25* full steam flow between 0* and 20* load and then a AP increasing linearly from 37.25% steam flow at 20* load to 109* full steam flow at 100Z load.

HBRSEP Unit No. 2 3.3-25 Amnendment No. 196

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 4)

Engineered Safety Feature Actuation System Instrunentation APPLICABLE MODES OR NOMINAL OTlHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOIALE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

2. Containment Spray

a. Manual Initiation 1.2.3.4 2 trains I SR 3.3.2.6 NA NA

b. Automatic 1.2.3.4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

c. Containment Pressure High High 1.2.3.4 6 E SR 3.3.2.1 s 10.45 10 psig I (2 sets SR 3.3.2.4 psig of 3) SR 3.3.2.7

3. Containment Isolation

a. Phase A Isolation (1) Manual 1.2.3.4 2 B SR 3.3.2.6 NA NA Initiation SR 3.3.2.2 NA KA (2) Automatic 1.2.3.4 2 trains C SR 3.3.2.3 Actuation SR 3.3.2.5 Logic and Actuation Relays (3) Safety Refer to Function 1 (Safety Injection) for all initiation functions and Injection requirements.

b. Phase B Isolation (1) Manual 1.2.3.4 2 trains I SR 3.3.2.6 NA NA Initiation (2) Automatic 1.2.3.4 2 trains C SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic and SR 3.3.2.5 Actuation Relays (3) Containment Pressure High High 1.2.3.4 6 E SR 3.3.2.1 s 10.45 10 psig I (2 sets SR 3.3.2.4 psig of 3) SR 3.3.2.7 (continued)

(1) A channel is OPERABLE with an actual Trip Setpolnt value found outside its calibration tolerance band provided the Trip Setpoint value Is conservative with respect to its associated Allowable Value and the channel Is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

HBRSEP Unit No. 2 3.3-26 Amendment No. 146 187

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 4)

Engineered Safety Feature A:tuation System Instrumentation APPLICABLE NODES OR NOMINAL OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

4. Steam Line Isolation

a. Manual Initiation 1 . 2 (e).3(e) 1 per F SR 3.3.2.6 NA NA steam 1irF?

b. Automatic Actuation 1 . 2 (e). 3 (e) 2 trains G SR 3.3.2.2 NA NA Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.5

c. Containment 1 .2 (e).3(e) 6 D SR 3.3.2.1 s 10.45 10 psig Pressure - High High (2 sets SR 3.3.2.4 pslg of 3) SR 3.3.2.7

d. High Steam Flow in 1 .2 (e). 3 (e) 2 per D SR 3.3.2.1 Wc) (d)

Two Steam Lines steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with 1 . 2 (e), 1 per D SR 3.3.2.1 2 541.50 543-F T",- LOw (e)(b) loop SR 3.3.2.4 OF 3(e()SR 3.3.2.7

e. High Steam Flow in 1 . 2 (e). 3 (e) 2 per D SR 3.3.2.1 (c) Id)

Two Steam Lines steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with 1 , 2 (e), 3 (e) 1 per D SR 3.3.2.1 2 605.05 614 psig Steam Line steam SR 3.3.2.4 psig Pressure- Low line SR 3.3.2.7 (continued)

(1) A channel is OPERABLE with an actual Trip Setpoint value found outside Its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(b) Above the Tq,- Low interlock.

(c) Less than or equal to a function defined as AP corresponding to 41.58t full steam flow below 20t load. and AP increasing linearly from 41.58S full steam flow at 20S load to 110.5 full steam flow at 100S load. and AP corresponding to 110.5S full steam flow above 100S load.

(d) Less than or equal to a function defined as AP corresponding to 37.25S full steam flow between OS and 20Z load and then a AP increasing linearly from 37.25S steam flow at 20S load to 109S full steam flow at 100S load.

(e) Except when all MSIVs are closed.

HBRSEP Unit No. 2 3.3-27 Amendment No. V6 187

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR NOMINAL OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

6. Feedwater Isolation

a. Automatic 1.2(°).3(O) 2 trains 6 SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

b. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

6. ESfAS Interlocks

a. Pressurizer 1.2.3 3 H SR 3.3.2.1 s 2005.11 2000 Pressure Low SR 3.3.2.4 psig psig SR 3.3.2.7

b. Ta, - Low 1.2.3 1 per H SR 3.3.2.1 '544.50 543-F loop SR 3.3.2.4 OF SR 3.3.2.7 (1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

(f) Except when all MFIVs. MFRVs. and bypass valves are closed or isolated by a closed manual valve.

HBRSEP Unit No. 2 3.3-28 Amendment No. 176

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2. and 3.

ACTIONS

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

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------- NOTE -------- A.1 Restore required 30 days Not applicable to channel to OPERABLE Functions 3, 4. 19. status.

22, 23, and 24.

One or more Functions with one required channel inoperable.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.6 not met.

(continued)

HBRSEP Unit No. 2 3.3-29 Amendment No. 176

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. --- NOTE -.-.--.

. C.1 Restore one channel 7 days Not applicable to to OPERABLE status.

hydrogen monitor channels.

One or more Functions with two required channels inoperable.

D. -------- NOTE--------- D.1 Restore required 7 days Only applicable to channel to OPERABLE Functions 3, 4, 19, status.

22, 23, and 24.

One or more Functions with one required channel inoperable.

E. Two hydrogen monitor E.1 Restore one hydrogen 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channels inoperable. monitor channel to OPERABLE status.

F. Required Action and F.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C. Table 3.3.3-1 for the D. or E not met. channel.

G. As required by G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action F.1 and referenced in AND Table 3.3.3-1.

G.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

HBRSEP Unit No. 2 3.3-30 Amendment No. 176

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. As required by H.1 Initiate action in Immediately Required Action F.1 accordance with and referenced in Specification 5.6.6.

Table 3.3.3-1.

SURVEILLANCE REQUIREMENTS

- --------------------------------NOTE-SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1; except Functions 9, 22. 23, and 24. SR 3.3.3.3 applies only to Functions 9, 22, 23, and 24.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2 ------------------NOTE------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.3.3 ----.------ ----- NOTE ----.--------- ---

Verification of setpoint not required.

Perform TADOT. 18 months HBRSEP Unit No. 2 3.3-31 Amendment No. 176

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page I of 1)

Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION F.1

1. Power Range Neutron Flux 2

2. Source Range Neutron flux 2

3. Reactor Coolant System (RCS) Hot Leg Temperature 1 per loop

4. RCS Cold Leg Temperature 1 per loop

5. RCS Pressure (Wide Range) 2

6. Refueling Water Storage Tank Level 2

7. Containment Sump Water Level (Wide Range) 2

8. Containment Pressure (Wide Range) 2

9. Containment Isolation Valve Position 2 per penetration flow path(a)(b)

10. Containment Area Radiation (High Range) 2

11. Hydrogen Monitors 2

12. Pressurizer Level 2

13. Steam Generator Water Level (Narrow Range) 2 per SG

14. Condensate Storage Tank Level 2

15. Core Exit Temperature -Quadrant 1 2 (c)

16. Core Exit Temperature - Quadrant 2 2 (c)

17. Core Exit Temperature - Quadrant 3 2(c)

18. Core Exit Temperature -Quadrant 4 2(c)

19. Auxiliary Feedwater Flow SD AFW Pump 1 per SG 4D AFW Pump 1 per SG

20. Steam Generator Pressure 2 per SG

21. Containment Spray Additive Tank Level 2

22. PORY Position (Primary) 1

23. PORY Block Valve Position (Primary) 1

24. Safety Valve Position (Primary) 1 (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve. blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed automatic containment isolation valve.

(c) A channel consists of one core exit thermocouple (CET).

HBRSEP Unit No. 2 3.3-32 Amendment No. 176

Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System LCO 3.3.4 The Remote Shutdown System Functions shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable. Function to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months HBRSEP Unit No. 2 3.3-33 Amendment No. 176

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.4.2 Verify each required control circuit and 18 months transfer switch is capable of performing the intended function.

SR 3.3.4.3 T----------------NOTE.-------.-----

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each 18 months required instrumentation channel.

SR 3.3.4.4 Perform TADOT of the reactor trip 18 months breaker open/closed indication.

HBRSEP Unit No. 2 3.3-34 Amendment No. 176

LOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.5 Two channels per bus of the loss of voltage Function and three channels per bus of the degraded voltage Function shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, When associated DG is required to be OPERABLE by LCO 3.8.2,

'AC Sources- Shutdown."

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

Degraded Voltage Function may be blocked while starting RCPs when the unit is not in MODE 1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. Loss of Voltage A.1 Restore channel(s) to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Function with one or OPERABLE status.

more channels per bus inoperable.

B. Degraded Voltage B.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Function with one trip.

channel per bus inoperable.

C. Degraded Voltage C.1 Restore all but one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Function with two or channel to OPERABLE more channels per bus status.

inoperable.

(continued)

HBRSEP Unit No. 2 3.3-35 Amendment No. 176

LOP DG Start Instrumentation 3.3.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter applicable Immediately associated Completion Condition(s) and Time not met. Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 ----------- NOTE.----------.-------

Verification of setpoint not required.

Perform TADOT. 18 months SR 3.3.5.2 Perform CHANNEL CALIBRATION with Trip 18 months Setpoints as follows:

a. Loss of voltage Trip Setpoint of 328 V

10% with a time delay of s 1 second (at zero voltage).

b. Degraded voltage Trip Setpoint of 430 V +/- 4 V with a time delay of 10 +/- 0.5 seconds.

HBRSEP Unit No. 2 3.3-36 Amendment No. 176

Containment Ventilation Isolation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Containment Ventilation Isolation Instrumentation LCO 3.3.6 The Containment Ventilation Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6-1.

ACTIONS

- ----------- ----- NOTE-------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place and maintain Immediately with one or more containment purge manual or automatic supply and exhaust actuation trains valves in closed inoperable. position.

OR AND One or more radiation A.2 Enter applicable Immediately monitoring channels Conditions and inoperable. Required Actions of LCO 3.9.3,

'Containment Penetrations.* for containment ventilation isolation valves made inoperable by isolation instrumentation.

HBRSEP Unit No. 2 3.3-37 Amendment No. 176

Containment Ventilation Isolation Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Ventilation Isolation Function.

SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.2 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.6.3 Perform MASTER RELAY TEST. 18 months SR 3.3.6.4 Perform COT. 92 days SR 3.3.6.5 Perform SLAVE RELAY TEST. 18 months SR 3.3.6.6 ------------------ NOTE.-----------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.6.7 Perform CHANNEL CALIBRATION. 18 months HBRSEP Unit No. 2 3.3-38 Amendment No. 176

Containment Ventilation Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)

Containment Ventilation Isolation Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE TRIP MODES OR OTHER CHANNELS REQUIREMENTS SETPOINT SPECIFIED CONDITIONS

1. Manual Initiation 1.2.3.4.(a) 2 SR 3.3.6.6 NA I

2. Automatic Actuation Logic and 2 trains SR 3.3.6.2 NA Actuation Relays 1,2.3.4.(a) SR 3.3.6.3 SR 3.3.6.5 I

3. Containment Radiation

a. Gaseous 1.2.3.4.(a) 1 SR 3.3.6.1 (b) I SR 3.3.6.4 SR 3.3.6.7

b. Particulate 1.2.3.4.(a) 1 SR 3.3.6.1 (b) I SR 3.3.6.4 SR 3.3.6.7

4. Safety Injection Refer to LCO 3.3.2. 'ESFAS Instrumentation.' Functions 1.a-f. for all initiation functions and requirements.

(a) During movement of recently irradiated fuel assemblies within the containment.

(b) Trip Setpoint shall be in accordance with the methodology in the Offsite Dose Calculation Manual.

HBRSEP Unit No. 2 3.3-39 Amendment No. 476 195

CREFS Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Control Room Emergency Filtration System (CREFS) Actuation Instrumentation LCO 3.3.7 The CREFS actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3. 4 During movement of irradiated fuel assemblies I ACTIONS NOTE----------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One automatic A.1 Place one CREFS train 7 days actuation train in emergency inoperable. pressurization mode.

B. Two automatic B.1 Place one CREFS train Immediately actuation trains in emergency inoperable. pressurization mode.

OR One radiation monitoring channel inoperable.

(continued)

HBRSEP Unit No. 2 3.3-40 Amendment No. 416 195

CREFS Actuation Instrumentation 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A AND or B not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and D.1 Suspend movement of Immediately associated Completion irradiated fuel Time for Condition A assemblies.

or B not met during movement of irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS NOTE.--------------------.------.-----

Refer to Table 3.3.7-1 to determine which SRs apply for each CREFS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.7.2 Perform COT. 92 days SR 3.3.7.3 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS (continued)

HBRSEP Unit No. 2 3.3-41 Amendment No. 1A6 195

CREFS Actuation Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.7.4 Perform MASTER RELAY TEST. 18 months SR 3.3.7.5 Perform SLAVE RELAY TEST. 18 months SR 3.3.7.6 Perform CHANNEL CALIBRATION. 18 months HBRSEP Unit No. 2 3.3-42 Amendment No. 176

CREFS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)

CREFS Actuation Instrumentation

=

SURVEILLANCE FUNCTION REQUIRED CHANNELS REQUIREMENTS TRIP SETPOINT

1. Automatic Actuation Logic and 2 trains SR 3.3.7.3 NA Actuation Relays SR 3.3.7.4 SR 3.3.7.5

2. Control Room Radiation Monitor 1 SR 3.3.7.1 s 2.5 vR/hr SR 3.3.7.2 SR 3.3.7.6

3. Safety Injection Refer to LCO 3.3.2. 'ESFAS Instrumentation.' Function 1. for all initiation functions and requirements.

HBRSEP Unit No. 2 3.3-43 Amendment No. 176

Auxiliary Feedwater (AFW) System Instrumentation 3.3.8 3.3 INSTRUMENTATION 3.3.8 Auxiliary Feedwater (AFW) System Instrumentation LCO 3.3.8 The AFW instrumentation for each Function in Table 3.3.8-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.8-1.

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 Immediately with one or more referenced in required channels Table 3.3.8-1 for the inoperable. channel(s) or train(s).

B. One channel B.1 Place channel in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable. trip.

OR B.2.1 Be in MODE 3. 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months AND B.2.2 Be in MODE 4. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months C. One channel C.1 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable. trip.

OR (continued)

HBRSEP Unit No. 2 3.3-44 Amendment No. 176

Auxiliary Feedwater (AFW) System Instrumentation 3.3.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND C.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months D. One channel D.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. OPERABLE status.

OR D.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months D.2.2 Be in MODE 4.

60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months E. One Main Feedwater E.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Pumps trip channel OPERABLE status.

inoperable.

OR E.2 Be inMODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months HBRSEP Unit No. 2 3.3-45 Amendment No. 176

Auxiliary Feedwater (AFW) System Instrumentation 3.3.8 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8-1 to determine which SRs apply for each AFW Function.

SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.8.2 Perform COT. 92 days SR 3.3.8.3 . --------..-.-- NOTE.------.----------

For Function 5. the TADOT shall include injection of a simulated or actual signal to verify channel OPERABILITY.

Perform TADOT. 18 months SR 3.3.8.4 Perform CHANNEL CALIBRATION. 18 months HBRSEP Unit No. 2 3.3-46 Amendment No. 176

Auxiliary Feedwater (AFW) System Instrumentation 3.3.8 Table 3.3.8-1 (page 1 of 1)

Auxiliary Feedwater System Instrumentation APPLICABLE MODES OR NOMINAL OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)

1. SG Water Level-Low Low 1.2.3 3 per SG C SR 3.3.8.1 a 15.36X 16$

SR 3.3.8.2 SR 3.3.8.4

2. Safety Injection Refer to LCO 3.3.2. 'ESFAS Instrumentation.' Function 1. for all initiation functions and requirements.

3. Loss of Offsite Power 1.2.3 2 per Q SR 3.3.8.3 KA 328 V t bus SR 3.3.8.4 lOX with s 1 sec time delay

4. Undervoltage Reactor 1.2.3 2 per B SR 3.3.8.3 r 2959 V 3120 V Coolant Pump bus SR 3.3.8.4

5. Trip of all Main 1.2 1 per E SR 3.3.8.3 NA NA Feedwater Pumps pump (1) A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.

HBRSEP Unit No. 2 3.3-47 Amendment No. 176

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure 2 2205 psig:

b. RCS average temperature s 579.40F; and

c. RCS total flow rate 2 97.3 x 106 lbm/hr.

APPLICABILITY: MODE 1.

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

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5X RTP per minute; or

b. THERMAL POWER step > 10X RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months parameters not within parameter(s) to imits. within limit.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

HBRSEP Unit No. 2 3.4-1 Amendment No. 176

RCS Pressure. Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is 2 2205 psig. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.2 Verify RCS average temperature is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.3 Verify RCS total flow rate is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2 97.3 x 106 ibm/hr.

SR 3.4.1.4 ---------- NOTE ----------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 2 90% RTP.

Verify by precision heat balance that RCS 18 months total flow rate is 2 97.3 x 106 ibm/hr.

HBRSEP Unit No. 2 3.4-2 Amendment No. 176

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 Each RCS loop average temperature (Tavg) shall be 2 5300 F.

APPLICABILITY: MODE 1, MODE 2 with keff a 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more RCS A.1 Be in MODE 2 with Keff 30 minutes loops not within < 1.0.

limit.

HBRSEP Unit No. 2 3.4-3 Amendment No. 176

RCS Minimum Temperature for Criticality 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tvg in each loop a 530'F. -

Only required if low I g alarm not reset and any RCS loop T

< 543OF' 30 minutes thereafter HBRSEP Unit No. 2 3.4-4 Amendment No. 176

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (PIT) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in Figures 3.4.3-1 and 3.4.3-2.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE--------- A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed whenever this AND Condition is entered.

...................... A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of LCO continued operation.

not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5 with RCS 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months pressure < 400 psig.

(continued)

HBRSEP Unit No. 2 3.4-5 Amendment No. 176

RCS P/T Limits 3.4.3 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME C. - ------ NOTE--------- C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered. AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time in continued operation.

other than MODE 1, 2,

3. or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 - .--------.--- NOTE Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure. RCS temperature, and 30 minutes RCS heatup and cooldown rates are within the limits specified in Figures 3.4.3-1 and 3.4.3-2.

HBRSEP Unit No. 2 3.4-6 Amendment No. 176

RCS P/T Limits 3.4.3 qwbnuhi Mabdw :Lo CkuaiurwU Weld QvwmI for hwhb CpaCodtn :0d L ra P w r/ r for Noe NI"k Contwnt :1.06 .txseve perio up t*23.960WP.

RTDbd:-SOaTdld +10 OW --0 .PM RtT~r~fb 23.96 EFPY: 1/4 T. 2D7.83 f~owance fbr Mwomtaft 3/4 T. 137.1SF Or=

amo 2aW Lo* To*

UUALUUMMU Hwtw RAND To WF1W

~180 11211"KINIt"11111 0 15 IIIIIIIIIJIMIIII ox0o amdWMM"CV08 Lka for M468 up to 23.96 El 000 511iIIIIIIIIIIIIIIII 50 10O 150 200 250 30 350 400 405 00 INDICATED TEMPERATURE CF)

Figure 3.4.3-1 Reactor Coolant System Heatup Limits Applicable Up to 23.96 EFPY HBRSEP Unit No. 2 3.4-7 Amendment No. 196

RCS P/T Limits 3.4.3 Conblin Minl :Lowe ChnierntAl Weld Com Foal co oaldown ACtC0 LZ eritX piod UP tO 23.96EWV.

RTNhiNDld :-00x. +101 aw -h0D PM A 23.96 EFPY r14 T. 207.81 dowmi for hsbmw oid T4

. 137.10? enrM 3000 2500 0

IT 20000 wi 1

Ld iI1 I50 MtU..I... ... . I1 _i CL mmnnn0 I00 5 0 I55 0 5 0 INIAE TBPRT E 1F 1l000 z Fignr 3I4 I3_

Appicbl Up to2L6E HBRSEP Unit No. 2 3.4-8 Amendment No. 196

RCS Loops -MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops -MODES 1 and 2 LCO 3.4.4 Three RCS loops shall be OPERABLE and in operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCO A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months HBRSEP Unit No. 2 3.4-9 Amendment No. 176

RCS Loops-MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops-MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE and two RCS loops shall be in operation.

OR Two RCS loops shall be OPERABLE and one RCS loop shall be in operation provided one of the following requirements is met:

a. The Rod Control System is not capable of rod withdrawal:

or

b. The reactor trip breakers are open; or

c. The lift disconnect switches for all control rods not fully withdrawn are open; or

d. SHUTDOWN MARGIN (SDM) is within the MODE 3 limits for one RCS loop in operation as specified in the COLR.

NOTE-------------------------

All reactor coolant pumps may be de-energized for s 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in any 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS. coolant with boron concentration less than required to meet the SDM of LCO 3.1.1;

b. Core outlet temperature is maintained at least 100F below saturation temperature; and

1. Rod Control System is not capable of rod withdrawal.

OR

2. Reactor Trip Breakers are open.

OR

3. Lift disconnect switches for all control rods not fully withdrawn are open.

OR

4. SDM is within MODE 3 limits for no RCS loops in operation as specified in the COLR.

HBRSEP Unit No. 2 3.4-10 Amendment No. f76.190

RCS Loops-MODE 3

3.4.5 APPLICABILITY

MODE 3.

ACTIONS _ _

CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Restore required RCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. loop to OPERABLE status.

B. Required Action and B.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.

C. Requirements of the C.1 Satisfy the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months LCO not met for conditions of the reasons other than LCO.

Condition A or D.

D. Required Act-ion C.1 D.1 De-energize all Immediately and associated CRDMs.

Completion Time not Met.

AM OR D.2 Suspend operations Immediately that would cause introduction into the Two required RCS loops RCS. coolant with inoperable. boron concentration less than required to meet SDM of LCO 3.1.1.

OR AND No RCS loop in operation.

D.3 Initiate action to Immediately restore one RCS loop to OPERABLE status and operation.

HBRSEP Unit No. 2 3.4-11 Amendment No. t7.190

RCS Loops -MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify steam generator secondary side water 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months levels are 2 161 for required RCS loops.

SR 3.4.5.3 .-....-----.--.- NOTE.------------------

Only required to be met if LCO 3.4.5.a is required to be met.

Verify the Rod Control System is not 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months capable of rod withdrawal.

SR 3.4.5.4 .-..-..--.-.---- NOTE .-.----.--.--.-----

Only required to be met if LCO 3.4.5.b is required to be met.

Verify the reactor trip breakers are open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.5 ---------------. NOTE..-.-. --.

Only required to be met if LCO 3.4.5.c is required to be met.

Verify the lift disconnect switches for all 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months control rods not fully withdrawn are open.

(continued)

HBRSEP Unit No. 2 3.4-12 Amendment No. 176

RCS Loops -MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.5.6 NOTE.------------------

Only required to be met if LCO 3.4.5.d is required to be met.

Verify SDM is within required limits 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months specified in the COLR.

SR 3.4.5.7 Verify correct breaker alignment and 7 days indicated power are available to the required pump that is not in operation.

HBRSEP Unit No. 2 3.4-13 Amendment No. 176

RCS Loops-MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and residual heat removal (RHR) trains shall be OPERABLE. and one loop or train shall be in operation.

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

1. All reactor coolant pumps (RCPs) and RHR pumps may be de-energized for s 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in any 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS. coolant with boron concentration less than required to meet the SDM of LCO 3.1.1;

b. Core outlet temperature is maintained at least 100F below saturation temperature; and

c. Rod Control System is not capable of rod withdrawal.

2. No RCP shall be started unless there is a steam bubble in the pressurizer or the secondary side water temperature of each steam generator (SG) is < 500F above each of the RCS cold leg temperatures.

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required loop or A.1 Initiate action to Immediately train inoperable. restore a second loop or train to OPERABLE ND status.

One required RCS loop OPERABLE.

(continued)

HBRSEP Unit No. 2 3.4 14 Amendment No. t76.190

RCS Loops-MODE 4 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One required loop B.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or train inoperable.

AMII One required RHR train OPERABLE.

C. Two required loops or C.1 Suspend operations Immediately trains inoperable. that would cause introduction into the OR RCS. coolant with boron concentration Required loop or train less than required to not in operation. meet SDM of LCO 3.1.1.

C.2 Initiate action to Immediately restore one loop or train to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS _

SURVEI LLANCE FREQUENCY SR 3.4.6.1 Verify one RHR train or RCS loop is in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operation.

SR 3.4.6.2 Verify SG secondary side water levels are 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2 16X for required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and 7 days indicated power are available to the required pump that is not In operation.

HBRSEP Unit No. 2 3.4-15 Amendment No. t76,190

RCS Loops-MODE 5. Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops-MODE 5. Loops Filled LCO 3.4.7 One residual heat removal (RHR) train shall be OPERABLE and in operation, and either:

a. One additional RHR train shall be OPERABLE; or

b. One OPERABLE steam generator (SG) with a secondary side water level of 2 16%.

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

1. The RHR pump of the train in operation may be de-energized for s 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inany 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS. coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature ismaintained at least 10°F below saturation temperature.

2. One required RHR train may be inoperable and de-energized for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR train isOPERABLE.

3. No reactor coolant pump shall be started unless there is a steam bubble inthe pressurizer or the secondary side water temperature of each SG is:5 50F above each of the RCS cold leg temperatures.

4. All RHR trains may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is inoperation.

APPLICABILITY: MODE 5 with RCS loops filled.

HBRSEP Unit No. 2 3.4-16 Amendment No. t76,190

RCS Loops-MODE 5. Loops Filled 3.4.7 ACTIONS .__ .__

CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR train A.1 Initiate action to Immediately inoperable. restore a second RHR train to OPERABLE AND status.

Required SG secondary OR si dewater level not within limits. A.2 Initiate action to Immediately restore required SG secondary side water level to within limits.

B. Required RHR trains B.1 Suspend operations Immediately inoperable. that would cause introduction into the OR RCS. coolant with boron concentration No RHR train in less than required to operation. meet SDM of LCO 3.1.1.

AND B.2 Initiate action to Immediately restore one RHR train to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS_________

SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR train is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify SG secondary side water level is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2 16% in required SG.

(continued)

HBRSEP Unit No. 2 3.4-17 Amendment No. M76.190

RCS Loops -MODE 5. Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.7.3 Verify correct breaker alignment and 7 days indicated power are available to the required RHR pump that is not in operation.

HBRSEP Unit No. 2 3.4 18 Amendment No. 176

RCS Loops - MODE 5. Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops-MODE 5. Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) trains shall be OPERABLE and one RHR train shall be in operation.

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

1. All RHR pumps may be de-energized for s 15 minutes when switching from one train to another or to perform testing of the RHR loop supply valves provided:

a. The core outlet temperature is maintained > 100F below saturation temperature.

b. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

c. No draining operations to further reduce the RCS water volume are permitted.

2. One RHR train may be inoperable for s 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR train is OPERABLE.

APPLICABILITY: MODE 5 with RCS loops not filled.

ACTONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR train A.1 Initiate action to Immediately inoperable. restore RHR train to OPERABLE status.

(continued)

HBRSEP Unit No. 2 3.4-19 Amendment No. 176.190

RCS Loops-MODE 5. Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required RHR trains B.1 Suspend operations Immediately inoperable. that would cause introduction into the OR RCS. coolant with boron concentration No RHR train in less than required to operation. meet SDM of LCO 3.1.1.

AM B.2 Initiate action to Immediately restore one RHR train to OPERABLE status and operation.

SURVEILLANCE &EOUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR train is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.8.2 Verify correct breaker alignment and 7 days indicated power are available to the required RHR pump that is not in operation.

HBRSEP Unit No. 2 3.4-20 Amendment No. 76.190

Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level s 63.3X in MODE 1;

b. Pressurizer water level s 92X in MODES 2 and 3; and

c. Pressurizer heaters OPERABLE with a capacity of t 125 kW and capable of being powered from an emergency power supply.

APPLICABILITY: MODES 1, 2. and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water A.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months level not within reactor trip breakers limit. open.

A.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B. Capacity of required B.1 Restore required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressurizer heaters pressurizer heaters s 125 kW. to OPERABLE status.

C. Required pressurizer C.1 Restore capability to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

heaters not capable of power the required being powered from an pressurizer heaters emergency power from an emergency supply. power supply.

(continued)

HBRSEP Unit No. 2 3.4-21 Amendment No. 176

Pressurizer 3.4.9 CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B or AND C not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits.

SR 3.4.9.2 Verify capacity of required pressurizer 18 months heaters is z 125 kW.

SR 3.4.9.3 Verify required pressurizer heaters are 18 months capable of being powered from an emergency power supply.

HBRSEP Unit No. 2 3.4-22 Amendment No. 176

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings 2 2410 psig and s 2560 psig.

APPLICABILITY: MODES 1. 2. and 3.

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

The lift settings are not required to be within the LCO limits during MODE 3 for the purpose of setting the ressurizer safety valves under ambient (hot) conditions.

his exception is allowed for 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Two or more pressurizer safety valves inoperable.

HBRSEP Unit No. 2 3.4-23 Amendment No. 176

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is In accordance OPERABLE in accordance with the Inservice with the Testing Program. Following testing, lift Inservice settings shall be within +/- 1X. Testing Program HBRSEP Unit No. 2 3.4-24 Amendment No. 176

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4. 11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

1. Separate Condition entry is allowed for each PORV.

2. ICO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and capable power to associated of being manually block valve.

cycled.

B. One PORV inoperable B.1 Close associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of block valve.

being manually cycled.

AND B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

HBRSEP Unit No. 2 3.4-25 Amendment No. 176

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve C.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. in manual control.

AND C.2 Restore block valve 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, D B. or C not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two PORVs inoperable E.1 Close associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of block valves.

being manually cycled.

AND E.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valves.

AND E.3 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND E.4 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. Two block valves F.1 Place associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. PORVs in manual control.

AND (continued)

HBRSEP Unit No. 2 3.4-26 Amendment No. 176

Pressurizer PORVs 3.4.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. (continued) F.2 Restore one block 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months valve to OPERABLE status.

AND F.3 Restore remaining 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months block valve to OPERABLE status.

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition F AND not met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 .-....--- .----- NOTE.-------------------

Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.

Perform a complete cycle of each block 92 days valve.

(continued)

HBRSEP Unit No. 2 3.4-27 Amendment No. 176

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.11.2 - .--.-.-.-.-.-.---- NOTE.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entry into MODE 3.

..................................... 18 Perform a complete cycle of each PORV. 18 months SR 3.4.11.3 Perform a complete cycle of each solenoid 18 months air control valve and check valve on the nitrogen accumulators in PORV control systems.

SR 3.4.11.4 Verify accumulators are capable of 18 months operating PORV's through a complete cycle.

I_

HBRSEP Unit No. 2 3.4-28 Amendment No. 176

LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with the accumulator isolation valves closed and deenergized and either a or b below:

a. 1. Two power operated relief valves (PORVs) with nominal lift settings of 400 psig and allowable values of s 418 psig (PORVs with lift settings, found between CHANNEL CALIBRATIONS, greater than the nominal lift setting but less than the allowable value are OPERABLE);

2. A maximum of one Safety Injection (SI) pump capable of injecting into the RCS when all cold leg temperatures are t 1750F; and

3. No SI pumps capable of injecting into the RCS when any cold leg temperature is < 1750F.

OR

b. The RCS depressurized and an RCS vent of t 4.4 square inches.

APPLICABILITY: MODES 4 and 5.

MODE 6 when the reactor vessel head is on.

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

Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed y the P/T limit curves provided in Figures 3.4.3-1 and 3.4.3-2.

HBRSEP Unit No. 2 3.4-29 Amendment No. 176

LTOP System 3.4.12 ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. Two or more SI pumps A.1 Initiate action to Immediately capable of injecting verify a maximum of into the RCS with all one SI pump is RCS cold leg capable of injecting temperatures t 175 0F. into the RCS.

AND Requirements of LCO 3.4.12.b not met.

B. One or more SI pumps B.1 Initiate action to Immediately capable of injecting verify no SI pumps into the RCS with any capable of injecting RCS cold leg into the RCS.

temperature < 1750F.

AND Requirements of LCO 3.4.12.b not met.

C. An accumulator C.1 Close and deenergize 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolation valve not affected accumulator closed and deenergized isolation valve.

when the accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in Figures 3.4.3-1 and 3.4.3-2.

(continued)

HBRSEP Unit No. 2 3.4-30 Amendment No. 176

LTOP System 3.4.12 ACTIONS .

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Increase RCS cold leg 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion temperature to Time of Condition C > 3500F.

not met.

OR D.2 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in Figures 3.4.3-1 and 3.4.3-2.

E. One required PORV E.1 Restore required PORV 7 days inoperable in MODE 4. to OPERABLE status.

F. One required PORV F.1 Restore required PORV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable in MODE 5 to OPERABLE status.

or 6.

(continued)

HBRSEP Unit No. 2 3.4-31 Amendment No. 176

LTOP System 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. Two required PORVs G.1 Depressurize RCS and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. establish RCS vent of 2 4.4 square inches.

OR Required Action and associated Completion Time of Condition A.

B. D, E, or F not met.

OR LTOP System inoperable for any reason other than Condition A, B, C. D, E, or F.

SURVEILLANCE REQUIREMENTS .

SURVEILLANCE FREQUENCY SR 3.4.12.1 ----------------- NOTE------------------

Only required to be met when all RCS cold leg temperatures k 1750 F and requirements of LCO 3.4.12.b not met.

Verify a maximum of one SI pump is capable 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of injecting into the RCS.

(continued)

HBRSEP Unit No. 2 3.4-32 Amendment No. 176

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.2 .-..------ .-.--- NOTE.-------.---------

Only required to be met when any RCS cold leg temperature < 1750 F and requirements of LCO 3.4.12.b not met.

Verify no SI pumps capable of injecting 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months into the RCS.

SR 3.4.12.3 Verify each accumulator isolation valve is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months closed and deenergized.

SR 3.4.12.4 ................... NOTE.------------------

Only required to be met when complying with LCO 3.4.12.b.

Verify RCS vent 2 4.4 square inches open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for unlocked open vent valve(s)

AND 31 days for locked open vent valve(s)

SR 3.4.12.5 Verify PORV block valve is open for each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months required PORV.

(continued)

HBRSEP Unit No. 2 3.4-33 Amendment No. 176

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.6 Perform a COT on each required PORV, Once within 31 excluding actuation. days prior to entering MODE

4. 5. or 6 when reactor vessel head is on AND 31 days thereafter SR 3.4.12.7 Perform CHANNEL CALIBRATION for each 18 months required PORV actuation channel.

HBRSEP Unit No. 2 3.4-34 Amendment No. 176

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE:

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE;

d. 1 gpm total primary to secondary LEAKAGE through all steam generators (SGs); and

e. 500 gallons per day primary to secondary LEAKAGE through any one SG.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS LEAKAGE not within A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits for reasons within limits.

other than pressure boundary LEAKAGE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

HBRSEP Unit No. 2 3.4-35 Amendment No. 176

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 Verify RCS operational LEAKAGE is within Once within 12 limits by performance of RCS water hours after inventory balance. reaching steady state operation conditions AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereafter during steady state operation SR 3.4.13.2 Verify steam generator tube integrity is in In accordance accordance with the Steam Generator Tube with the Steam Surveillance Program. Generator Tube Surveillance Program HBRSEP Unit No. 2 3.4-36 Amendment No. 176

RCS PIVs 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valves (PIVs)

LCO 3.4.14 Each RCS PIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

MODE 4, except valves in the residual heat removal (RHR) flow path when in,or during the transition to or from, the RHR mode of operation.

ACTIONS

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

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths ----.----- NOTE------------

with leakage from one Each valve used to satisfy or more RCS PIVs not Required Action A.1 and within limit. Required Action A.2 must have been verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary or the high pressure portion of the system.

(continued)

HBRSEP Unit No. 2 3.4-37 Amendment No. 176

RCS PIVs 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1 Isolate the high 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pressure portion of the affected system from the low pressure portion by use of one closed manual.

deactivated automatic, or check valve.

AND A.2 Isolate the high 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressure portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic, or check valve.

B. RHR System interlock B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months function inoperable. penetration by use of one closed manual or deactivated automatic valve.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Times for Condition A AND or B not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HBRSEP Unit No. 2 3.4-38 Amendment No. 176

RCS PIVs 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 ------- NOTES -------.--------

1. Not required to be performed in MODES 3 and 4.

2. Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

3. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is less In accordance than or equal to an equivalent of 5 gpm at with the an RCS pressure 2 2235 psig, and verify the Inservice margin between the results of the previous Testing Program leak rate test and the 5 gpm limit has not and 18 months been reduced by 2 50% for valves with leakage rates > 1.0 gpm. AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months AND (continued)

HBRSEP Unit No. 2 3.4-39 Amendment No. 176

RCS PIVs 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 (continued) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve SR 3.4.14.2 Verify RHR System interlock prevents the 18 months valves from being opened with a simulated or actual RCS pressure signal > 474 psig. I HBRSEP Unit No. 2 3.4-40 Amendment No. A4d , 182

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. One containment sump level monitor;

b. One containment atmosphere radioactivity monitor (gaseous or particulate); and

c. One containment fan cooler condensate flow rate monitor.

APPLICABILITY: MODES 1. 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment ........-.-. NOTE . -.----

sump monitor LCO 3.0.4 is not applicable.

inoperable. .............................

A.1 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore required 30 days containment sump monitor to OPERABLE status.

(continued)

HBRSEP Unit No. 2 3.4-41 Amendment No. 176

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required containment ..........-- NOTE-------

atmosphere LCO 3.0.4 is not applicable.

radioactivity monitor .................

inoperable.

B.1.1 Analyze grab samples Once per of the containment 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months atmosphere.

OR B.1.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2.1 Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.

OR B.2.2 Verify required 30 days containment fan cooler condensate flow rate monitor is OPERABLE.

C. Required containment C.1 Perform SR 3.4.15.1. Once per fan cooler condensate 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow rate monitor OR inoperable.

C.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

HBRSEP Unit No. 2 3.4-42 Amendment No. 176

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required containment D.1 Restore required 30 days atmosphere containment radioactivity monitor atmosphere inoperable. radioactivity monitor to OPERABLE status.

AND OR Required containment fan cooler condensate D.2 Restore required 30 days flow rate monitor containment fan inoperable. cooler condensate flow rate monitor to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. All required monitors F.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere radioactivity monitor.

(continued)

HBRSEP Unit No. 2 3.4-43 Amendment No. 176

RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.15.2 Perform COT of the required containment 92 days atmosphere radioactivity monitor.

SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required 18 months containment sump monitor.

SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required 18 months containment atmosphere radioactivity monitor.

SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required 18 months containment fan cooler condensate flow rate monitor.

HBRSEP Unit No. 2 3.4-44 Amendment No. 176

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (T.,g) a 500 0F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT I-131 . .----- Note .--------.

> 1.0 pCi/gm. LCO 3.0.4 is not applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B. Gross specific B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months activity of the Tog < 5000F.

reactor coolant not within limit.

(continued)

HBRSEP Unit No. 2 3.4-45 Amendment No. 176

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tavg < 500 0F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131 in the unacceptable region of Figure 3.4.16-1.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific 7 days activity S 100/E pCi/gm.

SR 3.4.16.2 ------------------NOTE .----.-.

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days I-131 specific activity s 1.0 pCi/gm.

AND Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of 2 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period (continued)

HBRSEP Unit No. 2 3.4-46 Amendment No. 176

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.16.3 ------------NOTE--------------------

Not required to be performed until 31 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 2 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine E from a sample taken in MODE 1 184 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 2 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

HBRSEP Unit No. 2 3.4-47 Amendment No. 176

RCS Specific Activity 3.4.16 7 = 0 I

E I.-

0 OPERATION 2w I a-W-

I I-z C,,

w

-J I-o 100 w

w 0

0 zLU a l) ACCEPaLE Mu 0 50 I-. OPERATION 0

C) 0 W.-

0 . .

20 30 40 so SO 70 80 90 I

100 PERCENT OF RATED THERMAL POWER Figure 3.4.16-1 Reactor Coolant DOSE EQUIVALENT 1-131 Specific Activity Limit Versus Percent of RATED THERAL POWER HBRSEP Unit No. 2 3.4-48 Amendment No. 176

CVCS 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Chemical and Volume Control System (CVCS)

LCO 3.4.17 Reactor Coolant Pump (RCP) seal injection shall be OPERABLE, with:

a. Two charging pumps shall be OPERABLE: and

b. Two Makeup Water Pathways from the Refueling Water Storage Tank (RWST) shall be OPERABLE.

APPLICABILITY: MODES 1. 2, 3, and 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required A.1 Restore required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months charging pump charging pump to inoperable. OPERABLE status.

B. One Makeup Water B.1 Restore Makeup Water 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Pathway from the Pathway from the RWST RWST inoperable. to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of AND Condition A or B not met. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HBRSEP Unit No. 2 3.4-49 Amendment No. 176

CvCS 3.4.17 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Seal injection to D.1 Initiate action to Immediately any RCP not within restore seal injection limit. to affected RCP(s).

AND AND Both required D.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months charging pumps inoperable. AND D.3 Cool down and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months depressurize the RCS to a pressure of

< 1400 psig.

E. Seal injection to E.1 Initiate action to Immediately any RCP not within restore seal injection limit. to affected RCP(s)

AND AND At least one E.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months charging pump OPERABLE. AND E.3 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Both Makeup Water F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Pathways from the RWST inoperable. AND F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HBRSEP Unit No. 2 3.4-50 Amendment No. 176

cVcS 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify seal injection flow of 2 6 gpm to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months each RCP.

SR 3.4.17.2 Verify seal injection flow of t 6 gpm to 18 months each RCP from each Makeup Water Pathway from the RWST.

SR 3.4.17.3 For Makeup Water Pathways from the RWST to In accordance be OPERABLE, SR 3.5.4.2 is applicable. with SR 3.5.4.2 HBRSEP Unit No. 2 3.4 51 Amendment No. 176

Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 Three ECCS accumulators shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with pressurizer pressure > 1000 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable due to concentration to within boron concentration limits.

not within limits.

B. One valve identified B.1 Verify control power or Immediately in SR 3.5.1.5 with air is removed to all control power valves identified in SR restored. 3.5.2.1 and SR 3.5.2.7.

AND B.2 Remove control power to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valve.

C. One accumulator C.1 Restore accumulator to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable for OPERABLE status.

reasons other than Condition A.

(continued)

HBRSEP Unit No. 2 3.5-1 Amendment No. 176

Accumulators 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of QLD Condition A or B not met. D.2 Reduce pressurizer 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months pressure to S 1000 psig.

E. Two or more E.1 Enter LCO 3.0.3. Immediately accumulators inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is Once prior to fully open. removing power from the valve operator SR 3.5.1.2 Verify borated water volume in each 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator is 2 825 ft3 and s 841 ft3.

SR 3.5.1.3 Verify nitrogen cover pressure in each 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator is 2 600 psig and s 660 psig.

(continued)

HBRSEP Unit No. 2 3.5-2 Amendment No. 176

Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.4 Verify boron concentration in each 31 days accumulator is t 1950 ppm and s 2400 ppm. MD

.- --NOTE------

Only required to be performed for affected accumulators Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of 2 70 gallons that is not the result of addition from the refueling water storage tank SR 3.5.1.5 Verify control power is removed from each 31 days accumulator iso ation valve operator.

HBRSEP Unit No. 2 3.5-3 Amendment No. 176

ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS -Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

APPLICABILITY: MODES 1. 2, and 3

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

1. In MODE 3, one cold leg safety injection (SI) pump flow path may be isolated by closing the isolation valves for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform pressure isolation valve testing per SR 3.4.14.1.

2. Operation in MODE 3 with one required SI pump declared inoperable pursuant to LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)

System," is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or until the temperature of all RCS cold legs exceeds 375°F, whichever comes first.

ACTIONS_

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more trains A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

AND At least 100X of the ECCS flow equivalent to a single OPERABLE ECCS train available.

B. One valve identified B.1 Verify control power is Immediately in SR 3.5.2.1 or SR removed to all valves 3.5.2.7 with control identified in SR power or air 3.5.1.5.

restored.

AND (continued)

HBRSEP Unit No. 2 3.5-4 Amendment No. 176

ECCS - Operating 3.5.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Remove control power or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months air to valve.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months listed position with control power to the valve operator removed.

Number Position Function SI-862 A&B Open Low Head Safety Injection (LHSI)

SI-863 A&B Closed LHSI SI-864 A&B Open LHSI, High Head Safety Injection (HHSI)

SI-866 AMB Closed HHSI SI-878 AMB Open HHSI SR 3.5.2.2 Verify each ECCS manual, power operated, 31 days and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued)

HBRSEP Unit No. 2 3.5-5 Amendment No. 176

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify each ECCS pump's developed head at In accordance the test flow point is greater than or with the equal to the required developed head. Inservice Testing Program SR 3.5.2.4 Verify each ECCS automatic valve in the 18 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.2.5 Verify each ECCS pump starts automatically 18 months on an actual or simulated actuation signal.

SR 3.5.2.6 Verify, by visual inspection, the ECCS 18 months train containment sump suction inlet is not restricted by debris and the suction inlet trash racks and screens show no evidence of structural distress or abnormal corrosion.

(continued)

HBRSEP Unit No. 2 3.5-6 Amendment No. 176

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.7 Verify the following valves in the listed position: 31 days Number Position Function FCV-605 Closed/Motive RHR Air Isolated HCV-758 Closed/Motive RHR Air Isolated SR 3.5.2.8 Verify the following manual valve is locked 92 days in the listed position Number Position Function RHR-764 Locked Open LHSI HBRSEP Unit No. 2 3.5-7 Amendment No. 176

ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS -Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.1 Initiate action to Immediately heat removal (RHR) restore required ECCS subsystem inoperable. RHR subsystem to OPERABLE status.

B. Required ECCS high B.1 Restore required ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months head injection high head injection subsystem inoperable. subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition B not met.

HBRSEP Unit No. 2 3.5-8 Amendment No. 176

ECCS -Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I.

SR 3.5.3.1 NOTE.--------------.

An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.

The following SRs are applicable for all In accordance equipment required to be OPERABLE: with applicable SRs SR 3.5.2.3 SR 3.5.2.6 HBRSEP Unit No. 2 3.5-9 Amendment No. 176

RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST)

LCO 3.5.4 The RWST shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron A.1 Restore RWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not OPERABLE status.

within limits.

QR RWST borated water temperature not within limits.

B. RWST inoperable for B.1 Restore RWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HBRSEP Unit No. 2 3.5-10 Amendment No. 176

RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 -----------------NOTE---------.---------

Only required to be performed when ambient air temperature is < 450F or > 100 0F.

Verify RWST borated water temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2 45OF and s 100 0F.

SR 3.5.4.2 Verify RWST borated water volume is 7 days 2 300,000 gallons.

SR 3.5.4.3 Verify RWST boron concentration is 7 days 2 1950 ppm and s 2400 ppm.

HBRSEP Unit No. 2 3.5-11 Amendment No. 176

Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2. 3. and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. MD B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HBRSEP Unit No. 2 3.6-1 Amendment No. 176

Containment 3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

1 SR 3.6.1.1 Perform required Type B and C leakage rate .---- NOTE-----

testing except for containment air lock SR 3.0.2 is not testing, in accordance with 10 CFR 50, applicable Appendix J. Option A, as modified by ..............

approved exemptions.

The leakage rate acceptance criterion is In accordance s 1.0 L.. However, during the first unit with 10 CFR 50, startup following testing performed in Appendix J.

accordance with 10 CFR 50, Appendix J. Option A, as Option A, as modified by approved modified by exemptions, the leakage rate acceptance approved criterion is < 0.6 L. for the Type B and exemptions Type C tests.

SR 3.6.1.2 Verify containment structural integrity In accordance in accordance with the Containment Tendon with the Surveillance Program. Containment Tendon Surveillance Program SR 3.6.1.3 Perform required visual examinations and In accordance Type A leakage rate testing, in accordance with the with the Containment Leakage Rate Testing Containment Program. Leakage Rate Testing Program HBRSEP Unit No. 2 3.6-2 Amendment No. 176

Containment Air Lock 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Lock LCO 3.6.2 The containment air lock shall be OPERABLE.

APPLICABILITY: MODES 1. 2, 3, and 4.

ACTIONS

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

1. Entry and exit is permissible to perform repairs on the affected air lock components.

2. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when air lock leakage results in exceeding the overall containment leakage rate.

CONDITION REQUIRED ACTION COMPLETION TIME A. One containment air . ........... NOTES -.----- .

lock door inoperable. 1. Required Actions A.1, A.2, and A.3 are not applicable if both doors are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls.

A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

AND A.2 Lock the OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed.

AND (continued)

HBRSEP Unit No. 2 3.6-3 Amendment No. 176

Containment Air Lock 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 .NOTE-- . ---

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify the OPERABLE Once per 31 days door is locked closed.

B. Containment air lock . ---.------ NOTES ----- .

interlock mechanism 1. Required Actions B.1, inoperable. B.2, and B.3 are not applicable if both doors are inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

AND B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed.

(n u (continued)

HBRSEP Unit No. 2 3.6-4 Amendment No. 176

Containment Air Lock 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3- - NOTE.--

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify an OPERABLE Once per 31 days door is locked closed.

C. Containment air lock C.1 Initiate action to Immediately inoperable for reasons evaluate overall other than Condition A containment leakage or B. rate per LCO 3.6.1.

AND C.2 Verify a door is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months closed in the air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HBRSEP Unit No. 2 3.6-5 Amendment No. 176

Containment Air Lock 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 ------------------NOTES.------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria of SR 3.6.1.1, in accordance with 10 CFR 50, Appendix J. .-- NOTE-.--

Option A. as modified by approved SR 3.0.2 is not exemptions. applicable Perform required air lock leakage rate In accordance testing in accordance with 10 CFR 50, with 10 CFR 50, Appendix J, Option A, as modified by Appendix J.

approved exemptions. Option A. as modified by approved exemptions.

SR 3.6.2.2 Verify only one door in the air lock can be 24 months opened at a time.

HBRSEP Unit No. 2 3.6-6 Amendment No. 176

Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1. 2. 3. and 4.

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.

5. Enter applicable Conditions and Required Actions of LCO 3.6.8. "Isolation Valve Seal Water (IVSW) System," when required IVSW supply to a penetration flowpath is isolated.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE--------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path penetration flow paths by use of at least with two containment one closed and isolation valves. de-activated

.. .. automatic valve, closed manual valve, One or more blind flange, or penetration flow paths check valve with flow with one containment through the valve isolation valve secured.

inoperable.

AND (continued)

HBRSEP Unit No. 2 3.6-7 Amendment No. 176

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 . ....... NOTE ........

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path for isolation is isolated. devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment B. --------- NOTE.-------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path penetration flow paths by use of at least with two containment one closed and isolation valves. de-activated

...................... . automatic valve.

closed manual valve, One or more or blind flange.

penetration flow paths with two containment isolation valves inoperable.

(continued)

HBRSEP Unit No. 2 3.6-8 Amendment No. 176

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. .--- NOTE ------ C.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable to penetration flow path penetration flow paths y use of at least with only one one closed and containment isolation de-activated valve and a closed automatic valve, system. closed manual valve, or blind flange.

One or more AND Penetration flow paths with one containment C.2 --------NOTE-........

isolation valve Isolation devices in inoperable. high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path for isolation is isolated. devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment I. L (continued)

HBRSEP Unit No. 2 3.6-9 Amendment No. 176

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 42 inch penetration (Supply or Exhaust) purge valves open and 6 inch penetration (pressure or vacuum relief) valves open simultaneously.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 ---.----- ------ NOTE.------------------

The 42 inch and 6 inch valves may not be open simultaneously.

Verify each 42 inch purge supply and 31 days exhaust valve and each 6 inch pressure and vacuum relief valve is closed, except when the valves are open for safety related reasons, or for tests or Surveillances that require the valves to be open.

(continued)

HBRSEP Unit No. 2 3.6 10 Amendment No. 176

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.2 . ' ----- ----- NOTE-............

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual 31 days for valve and blind flange that is located containment outside containment and not locked, sealed isolation or otherwise secured and required to be manual valves closed during accident conditions is (except closed, except for containment isolation Penetration valves that are open under administrative Pressurization controls. System valves with a diameter

3/8 inch) and blind flanges AND 18 months for Penetration Pressurization System valves with a diameter z 3/8 inch SR 3.6.3.3 . - ---- NOTE..----

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each containment isolation manual Prior to valve and blind flange that is located entering MODE 4 inside containment and not locked, sealed from MODE 5 if or otherwise secured and required to be not performed closed during accident conditions is within the closed, except for containment isolation previous valves that are open under administrative 92 days controls.

(continued)

HBRSEP Unit No. 2 3.6-11 Amendment No. 176

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.4 Verify the isolation time of each automatic In power operated containment isolation valve accordance is within limits. with the Inservice Testing Program SR 3.6.3.5 Verify each automatic containment isolation 18 months valve that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

SR 3.6.3.6 Verify each 42 inch inboard containment 18 months purge valve is blocked to restrict the valve from opening > 700.

HBRSEP Unit No. 2 3.6-12 Amendment No. 176

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be 2 -0.8 psig and s +1.0 psig.

APPLICABILITY: MODES 1. 2. 3. and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limits. pressure to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits.

HBRSEP Unit No. 2 3.6-13 Amendment No. 176

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be s 1200F.

APPLICABILITY: MODES 1, 2. 3; and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average A.1 Restore containment 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months air temperature not average air within limit. temperature to within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is within limit.

HBRSEP Unit No. 2 3.6 14 Amendment No. 176

Containment Spray and Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1. 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train inoperable. spray train to OPERABLE status. AND 10 days from discovery of failure to meet the LCO B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months C. One containment C.1 Restore containment 7 days cooling train cooling train to inoperable. OPERABLE status. AND 10 days from discovery of failure to meet the LCO (continued)

HBRSEP Unit No. 2 3.6 15 Amendment No. 176

Containment Spray and Cooling Systems 3.6.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two containment D.1 Restore one 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months cooling trains containment cooling inoperable. train to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C AND or D not met.

E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Two containment spray F.1 Enter LCO 3.0.3. Immediately trains inoperable.

OR Any combination of three or more trains inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual. power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

(continued)

HBRSEP Unit No. 2 3.6-16 Amendment No. 176

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.2 Operate each containment cooling train fan 31 days unit for 2 15 minutes.

SR 3.6.6.3 Verify cooling water flow rate to each 31 days cooling unit is > 750 gpm.

SR 3.6.6.4 Verify each containment spray pump's In accordance developed head at the flow test point is with the greater than or equal to the required Inservice developed head. Testing Program SR 3.6.6.5 Verify each automatic containment spray 18 months valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.6.6 Verify each containment spray pump starts 18 months automatically on an actual or simulated actuation signal.

SR 3.6.6.7 Verify each containment cooling train 18 months starts automatically on an actual or simulated actuation signal.

SR 3.6.6.8 Verify each spray nozzle is unobstructed. Following activities which could result in nozzle blockage HBRSEP Unit No. 2 3.6 17 Amendment No. P6f 194

Spray Additive System 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Spray Additive System LCO 3.6.7 The Spray Additive System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spray Additive System A.1 Restore Spray 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. Additive System train to OPERABLE status.

AND At least 100X of the Spray Additive System flow equivalent to a single OPERABLE Spray Additive System train available to an OPERABLE Containment Spray Train.

B. Spray Additive System B.1 Restore Spray 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable for reasons Additive System to other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months HBRSEP Unit No. 2 3.6-18 Amendment No. 176

Spray Additive System 3.6.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Verify each spray additive manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.7.2 Verify spray additive tank solution volume 184 days is 2 2505 gal.

SR 3.6.7.3 Verify spray additive tank NaOH solution 184 days concentration is 2 30X by weight.

SR 3.6.7.4 Verify each spray additive automatic valve 18 months in the flow path that is not locked, sealed, or otherwise secured in position.

actuates to the correct position on an actual or simulated actuation signal.

HBRSEP Unit No. 2 3.6-19 Amendment No. 176

Isolation Valve Seal Water System 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Isolation Valve Seal Water (IVSW) System LCO 3.6.8 The IVSW System shall be OPERABLE.

APPLICABILITY: MODES 1. 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. IVSW system A.1 Restore IVSW system 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. to OPERABLE status.

B. Required Action B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Completion Time AND not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify IVSW tank pressure is 2 44.6 psig. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I

SR 3.6.8.2 Verify the IVSW tank volume is 31 days 2 85 gallons.

(continued)

HBRSEP Unit No. 2 3.6-20 Amendment No. 1476 187

Isolation Valve Seal Water System 3.6.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.8.3 Verify the opening time of each air In accordance operated header injection valve is within with the limits. Inservice Testing Program SR 3.6.8.4 Verify each automatic valve in the IVSW 18 months System actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.8.5 Verify the IVSW dedicated nitrogen 18 months bottles will pressurize the IVSW tank to 2 44.6 psig.

I SR 3.6.8.6 Verify IVSW seal header flow rate is: 18 months

a. s 52.00 cc/minute for Header A.

b. & 16.50 cc/minute for Header B,

c. s 32.50 cc/minute for Header C, and

d. s 23.00 cc/minute for Header D.

HBRSEP Unit No. 2 3.6-21 Amendment No. 1-A6 187

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and Table 3.7.1-2.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONs

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

Separate Condition entry is allowed for each MSSV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more steam A.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months generators with one < 50 X RTP.

MSSV inoperable and the Moderator Temperature Coefficient (MWC) zero or negative at all power levels.

(continued)

HBRSEP Unit No. 2 3.7-1 Amendment No. 196

MSSVs 3.7.1 CONDITION REQUIRED ACTION COMPLETION TIME B. One or more steam B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months generators with two or to less than or equal more MSSVs inoperable. to the Maximum Allowable X RTP OR specified in Table 3.7.1-1 for the One or more steam number of OPERABLE generators with one MSSVs.

MSSV inoperable and MTC positive at any AND power level.

B.2 . ........ NOTE .......

Only required in MODE 1 Reduce the Power 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Range Neutron Flux -

High reactor trip setpoint to less than or equal to the Maximum Allowable X RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months One or more steam generators with 2 3 MSSVs inoperable.

HBRSEP Unit No. 2 3.7-2 Amendment No. 176

MSSVs 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4

SR 3.7.1.1 NOTE---..............

Only required to be performed in MODES 1 and 2.

Verify each required MSSV lift setpoint per In accordance Table 3.7.1-2 in accordance with the with the Inservice Testing Program. Following Inservice testing, lift setting shall be within +1X. Testing Program HBRSEP Unit No. 2 3.7-3 Amendment No. 176

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs MAXIMUM ALLOWABLE POWER PER STEAM GENERATOR (X RTP) 3 s 46 2 s 24 HBRSEP Unit No. 2 3 .7-4 Amendment No. 176

MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)

Main Steam Safety Valve Lift Settings VALVE NUMBER STEAM GENERATOR LIFT SETTING STEAMGENEATOR(psig +/- 3%)

A B C SV1-1A SV1-1B SV1-1C 1085 SV1-2A SV1-2B SV1-2C 1110 SV1-3A SV1-3B SV1-3C 1125 SV1-4A SV1-4B SV1-4C 1140 HBRSEP Unit No. 2 3.7-5 Amendment No. 176

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Three MSIVs shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 except when all MSIVs are closed.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months MODE 1. OPERABLE status.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met.

C. --------- NOTE--------- C.1 Close MSIV. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Separate Condition entry is allowed for AND each MSIV.

...................... C.2 Verify MSIV is Once per closed. 7 days One or more MSIVs inoperable in MODE 2 or 3.

(continued)

HBRSEP Unit No. 2 3.7-6 Amendment No. 176

MSIVs 3.7.2 ACTIONS (continued) 3 REQUIRED ACTION COMPLETION TIME CONDITION D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C AND not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 ------------------NOTE----- ----------

Only required to be performed in MODES 1 and 2.

Verify closure time of each MSIV is In accordance 5 5 seconds on an actual or simulated with the actuation signal. Inservice Testing Program HBRSEP Unit No. 2 3.7-7 Amendment No. 176

MFIVs, MFRVs. and Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation Valves (MFRVs), and Bypass Valves LCO 3.7.3 Three MFIVs. three MFRVs, and three bypass valves shall be OPERABLE.

APPLICABILITY: MODES 1. 2, and 3 except when MFIV. MFRV. or bypass valve is closed or isolated by a closed manual valve.

ACTIONS

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

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MFIVs A.1 Close or isolate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. MFIV.

A.2 Verify MFIV is closed Once per or isolated. 7 days B. One or more MFRVs B.1 Close or isolate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. MFRV.

AND B.2 Verify MFRV is closed Once per or isolated. 7 days (continued)

HBRSEP Unit No. 2 3.7-8 Amendment No. 176

MFIVs, MFRVs, and Bypass Valves 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more bypass C.1 Close or isolate bypass 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months valves inoperable. valve.

AM C.2 Verify bypass valve is Once per 7 days closed or isolated.

D Two valves in the D.1 Isolate affected flow 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months same flow path path.

inoperable.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AMN E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each MFRV and In accordance bypass valve is s 20 seconds on an actual or with the simulated actuation signal. Inservice I Testing Program SR 3.7.3.2 Verify the closure time of each MFIV is In accordance g 50 seconds on an actual or simulated with the actuation signal. Inservice

_Testing Program HBRSEP Unit No. 2 3.7-9 Amendment No. 196

AFW System 3.7.4 I 3.7 PLANT SYSTEMS f

3.7.4 Auxiliary Feedwater (AFW) System LCO 3.7.4 Four AFW flow paths and three AFW pumps shall be OPERABLE.

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

Only one AFW flow path with one motor driven pump is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2. and 3, MODE 4 when steam generator is being used for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AFW pump A.1 Restore AFW pump or 7 days inoperable in MODE 1, flow path(s) to

2. or 3. OPERABLE status. AND OR 8 days from discovery of One or two AFW flow failure to paths inoperable in meet the LCO MODE 1, 2. or 3.

B. Two motor driven AFW B.1 Restore one motor 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months pumps inoperable in driven AFW pump or MODE 1. 2. or 3. one flow path to AND OPERABLE status.

OR 8 days from discovery of Three motor driven AFW failure to flow paths inoperable meet the LCO in MODE 1, 2, or 3.

(continued)

HBRSEP Unit No. 2 3 .7-10 Amendment No. 176

AFW System 3.7.4 CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A AND or B not met.

C.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months D. Steam driven AFW pump D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or flow path inoperable in MODE 1. AND 2, or 3.

D.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months AND One motor driven AFW pump or flow path inoperable in MODE 1,

2. or 3.

E. Four AFW flow paths E.1 ---------NOTE ------

inoperable in MODE 1, LCO 3.0.3 and all

2. or 3. other LCO Required Actions requiring OR MODE changes are suspended until Three AFW pumps one AFW pump and flow inoperable in MODE 1. path are restored to

2. or 3. OPERABLE status.

Initiate action to Immediately restore one AFW pump and flow path to OPERABLE status.

F. Required AFW pump and F.1 Initiate action to Immediately flow path inoperable restore AFW pump and in MODE 4. flow path to OPERABLE status.

HBRSEP Unit No. 2 3.7-11 Amendment No. 176

AFW System 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path, and in the steam supply flow path to the steam driven AFW pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.4.2 ----------- NOTE-------------------

Not required to be performed for the steam driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after x 1000 psig in the steam generator.

Verify the developed head of each AFW pump 31 days on a at the flow test point is greater than or STAGGERED TEST equal to the required developed head. BASIS SR 3.7.4.3 -------------------NOTE--------------------

Not applicable in MODE 4 when steam generator is being used for heat removal.

Verify each AFW automatic valve that is 18 months not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

(continued)

HBRSEP Unit No. 2 3-7-12 Amendment No. 176

AFW System 3.7.4 SURVEILLANCE REQUIREMENTS (continued) T SURVEILLANCE FREQUENCY t

SR 3.7.4.4 -------------------NOTES- ---------------

1. Not required to be performed for the steam driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a 1000 psig in the steam generator.

2. Not applicable in MODE 4 when steam generator is being used for heat removal.

Verify each AFW pump starts automatically 18 months on an actual or simulated actuation signal.

SR 3.7.4.5 ------- NOTE.----------------

Not required to be performed for the steam driven AFW pump until prior to entering MODE 1.

Verify proper alignment of the required Prior to AFW flow paths by verifying flow from the entering condensate storage tank to each steam MODE 2.

generator. whenever unit has been in MODE 5 or 6 for > 30 days SR 3.7.4.6 Verify the AFW automatic bus transfer 18 months switch associated with discharge valve V2-16A operates automatically on an actual or simulated actuation signal.

HBRSEP Unit No. 2 3.7-13 Amendment No. 176

CST 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Condensate Storage Tank (CST)

LCO 3.7.5 The CST level shall be 2 35,000 gal and the backup Service Water System (SWS) supply to the AFW system shall be OPERABLE.

APPLICABILITY: MODES 1. 2, and 3.

MODE 4 when a steam generator is being used for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CST level not within A.1 Verify by 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limit. administrative means OPERABILITY of backup AND water supply.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND A.2 Restore CST level to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4, without 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months reliance on steam generator for heat removal.

(continued)

HBRSEP Unit No. 2 3.7-14 Amendment No. 176

CST 3.7.5 ACTIONS (Continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. SWS supply to AFW C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months system inoperable.

AND C.2 Be in MODE 4, without 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months reliance on steam generator for heat removal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify the CST level is t 35,000 gal. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.7.5.2 Verify by administrative means OPERABILITY 31 days of backup SWS supply to the AFW System.

HBRSEP Unit No. 2 3.7-15 Amendment No. 176

CCW System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Component Cooling Water (CCW) System LCO 3.7.6 Two CCW trains powered from emergency power supplies shall be OPERABLE.

APPLICABILITY: MODES 1, 2. 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required CCW train A.1 . ....... NOTE---------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, ARCS Loops - MODE 4," for residual heat removal loops made inoperable by CCW.

Restore required CCW 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HBRSEP Unit No. 2 3.7-16 Amendment No. 176

CCW System 3.7.6 SURVEILLANCE REQUIREMENTS Y

SURVEILLANCE FREQUENCY 4

SR 3.7.6.1 -------------------NOTE--------------------

Isolation of CCW flow to individual components does not render the CCW System inoperable.

Verify each required CCW manual, power 31 days operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.6.2 Verify each required CCW pump starts 18 months automatically on an actual or simulated LOP DG Start undervoltage signal.

HBRSEP Unit No. 2 3.7-17 Amendment No. 146 186 l

SWS 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Service Water System (SWS)

LCO 3.7.7 Two SWS trains and the Turbine Building loop isolation valves shall be OPERABLE.

APPLICABILITY: MODES 1. 2. 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SWS train A.1 ---.-.-- NOTES-......

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.1, 'AC Sources-Operating."

for emergency diesel generator made inoperable by SWS.

Restore SWS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. One Turbine Building B.1 Close and deactivate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months loop isolation valve inoperable Turbine inoperable. Building loop isolation valve.

AND B.2 Verify the inoperable 31 days Turbine Building loop isolation valve is closed and deactivated.

(continued)

HBRSEP Unit No. 2 3.7-18 Amendment No. 176

sWs 3.7.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two Turbine Building C.1 Close and deactivate 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loop isolation valves one inoperable Turbine inoperable. Building loop isolation valve.

D. Required Actions and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Times of Conditions A, ANQ B. or C not met.

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 --------------- NOTE------------

Isolation of SWS flow to individual components does not render the SWS inoperable.

Verify each SWS manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.7.2 Verify each SWS automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

(continued)

HBRSEP Unit No. 2 3.7-19 Amendment No. 176

sWS 3.7.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.7.3 Verify each SWS pump and SWS booster pump 18 months starts automatically on an actual or simulated actuation signal.

SR 3.7.7.4 Verify the SWS automatic bus transfer 18 months switch associated with Turbine Building loop isolation valve V6-16C operates automatically on an actual or simulated actuation signal.

HBRSEP Unit No. 2 3.7-20 Amendment No. 176

UHS 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Ultimate Heat Sink (UHS)

LCO 3.7.8 The UHS shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Service water A.1 Verify required cooling 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months temperature not capacity maintained.

within limit. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND A.2 Verify service water Once per hour temperature is

990F.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months UHS inoperable for reasons other than Condition A.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify water level of UHS is 2 218 ft mean 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sea level.

HBRSEP Unit No. 2 3.7-21 Amendment No. 191

UHS 3.7.8 Surveillance Requirements (continued)

SURVEILLANCE FREQUENCY SR 3.7.8.2 Verify service water temperature is

970F. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months HBRSEP Unit No. 2 3.7-21a Amendment No. 191

CREFS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Control Room Emergency Filtration System (CREFS)

LCO 3.7.9 Two CREFS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4 During movement of ii rradiated fuel assemblies.

I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREFS train A.1 Restore CREFS train 7 days inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2,

3. or 4. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Required Action and C.1 Place OPERABLE CREFS Immediately associated Completion train in emergency Time of Condition A pressurization mode.

not met during movement of irradiated OR fuel assemblies.

C.2 Suspend movement of Immediately irradiated fuel assemblies.

(continued)

HBRSEP Unit 2 3.7-22 Amendment No. 4-76 195

CREFS 3.7.9 ACTIONS (continued)

D. Two CREFS trains D.1 Suspend movement of Immediately inoperable during irradiated fuel movement of irradiated assemblies.

fuel assemblies.

E. Two CREFS trains E.1 Restore at least one 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable in MODE 1, CREFS train to

2. 3, or 4. OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition E AND not met in MODE 1, 2, 3, or 4. F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Operate each CREFS train for 2 15 minutes. 31 days SR 3.7.9.2 Perform required CREFS filter testing in In accordance accordance with the Ventilation Filter with VFTP Testing Program (VFTP).

SR 3.7.9.3 Verify each CREFS train actuates on an 18 months actual or simulated actuation signal.

SR 3.7.9.4 Verify one CREFS train can maintain a 18 months on a positive pressure of 2 0.125 inches water STAGGERED TEST gauge, relative to the outside atmosphere BASIS and a positive pressure relative to adjacent building areas during the emergency pressurization mode of operation at a makeup flow rate of

400 cfm.

HBRSEP Unit 2 3.7-23 Amendment No. 176 195

CREFS 3.7.9 Page is intentionally blank HBRSEP Unit 2 3.7-24 Amendment No. 176 195

CREATC 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Air Temperature Control (CREATC)

LCO 3.7.10 Two CREATC Water Cooled Condensing Unit (WCCU) trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4 During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREATC WCCU train A.1 Restore CREATC WCCU 30 days inoperable. train to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2,

3. or 4. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HBRSEP Unit No. 2 3.7-25 Amendment No. ;6 195

CREATC 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Place OPERABLE CREATC Immediately associated Completion WCCU train in Time of Condition A operation.

not met during movement of irradiated OR fuel assemblies.

C.2 Suspend movement of Immediately irradiated fuel assemblies.

D. Two CREATC WCCU trains D.1 Suspend movement of Immediately inoperable during irradiated fuel movement of irradiated assemblies.

fuel assemblies.

E. Two CREATC WCCU trains E.1 Restore at least one 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable in MODE 1. CREATC WCCU train to 2, 3, or 4. OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition E AND not met in MODE 1, 2, 3, or 4. F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HBRSEP Unit No. 2 3.7-26 Amendment No. -6 195

CREATC 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Verify each CREATC WCCU train has the 18 months capability to remove the assumed heat load.

HBRSEP Unit No. 2 3.7-27 Amendment No. 176

FBACS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Fuel Building Air Cleanup System (FBACS)

LCO 3.7.11 The FBACS shall be OPERABLE and operating.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel building.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The FBACS inoperable A.1 Suspend movement of Immediately during movement of irradiated fuel irradiated fuel assemblies in the assemblies in the fuel fuel building.

building.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Operate the FBACS for 2 10 continuous hours 31 days with the heaters operating automatically.

SR 3.7.11.2 Perform required FBACS filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

(continued)

HBRSEP Unit No. 2 3.7-28 Amendment No. 176

FBACS 3.7.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.11.3 ----- NOTE---------

Not required to be met when the only movement of irradiated fuel is movement of the spent fuel shipping cask containing irradiated fuel.

Verify the FBACS can maintain a negative 18 months pressure with respect to atmospheric pressure.

HBRSEP Unit No. 2 3.7-29 Amendment No. 176

Fuel Storage Pool Water Level 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Fuel Storage Pool Water Level LCO 3.7.12 The fuel storage pool water level shall be 2 21 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool A.1 --------NOTE ........

water level not within LCO 3.0.3 is not limit. applicable.

Suspend movement of Immediately irradiated fuel assemblies in the fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Verify the fuel storage pool water level is 7 days 2 21 ft above the top of the irradiated fuel assemblies seated in the storage racks.

HNRSEP Unit No. 2 3.7-30 Amendment No. 176

Fuel Storage Pool Boron Concentration 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Fuel Storage Pool Boron Concentration LCO 3.7.13 The fuel storage pool boron concentration shall be 2 1500 ppm.

APPLICABILITY: At all times. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool ----.------. NOTE- ---.---

boron concentration LCO 3.0.3 is not applicable.

not within limit. ...........................

A.1 Suspend movement of fuel assemblies in Immediately the fuel storage pool.

AND A.2 Initiate action to restore fuel storage pool boron Immediately concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify the fuel storage pool boron concentration is within limit. 7 days HBRSEP Unit No. 2 3.7-31 Amendment No. 198

New and Spent Fuel Assembly Storage 3.7.14 3.7 PLANT SYSTEMS 3.7.14 New and Spent Fuel Assembly Storage LCO 3.7.14 New and spent fuel shall be stored in approved locations.

APPLICABILITY: Whenever any fuel assembly is stored in the new or spent fuel storage racks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 --.----NOTE---------

LCO not met. LCO 3.0.3 is not applicable.

Initiate action to Immediately restore fuel storage to within requirements.

SURVEILLANCE REQUIREMENTS SURVEI LANCE FREQUENCY SR 3.7.14.1 Verify by administrative means that fuel Prior to assemblies are stored in approved storing the locations. fuel assembly HBRSEP Unit No. 2 3.7-32 Amendment No. 176

Secondary Specific Activity 3.7.15 3.7 PLANT SYSTEMS

,-,S 3.7.15 Secondary Specific Activity LCO 3.7.15 The specific activity of the secondary coolant shall be s 0.10 pCi/gm DOSE EQUIVALENT I-131.

APPLICABILITY: MODES 1. 2. 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit.

AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the specific activity of the 31 days secondary coolant is s 0.10 pCi/gm DOSE EQUIVALENT I-131.

HBRSEP Unit No. 2 3.7-33 Amendment No. 176

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources- Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. The qualified circuit between the offsite transmission network and the onsite emergency AC Electrical Power Distribution System: and

b. Two diesel generators (DGs) capable of supplying the onsite emergency power distribution subsystem(s)

APPLICABILITY: MODES 1. 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The qualified offsite A.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from circuit inoperable. feature(s) with no discovery of no offsite power offsite power to available inoperable one train when its redundant concurrent with required feature(s) inoperability of is inoperable. redundant required feature(s).

AND A.2 Restore offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months circuit to OPERABLE status. AND 8 days from discovery of failure to meet LCO (continued)

HBRSEP Unit No. 2 3.8-1 Amendment No. 176

AC Sources- Operating 3.8.1 ACTIONS (continued)

CONDITION I REQUIRED ACTION [ COMPLETION TIME B. One DG inoperable. B.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for the offsite circuit. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s) supported discovery of by the inoperable DG Condition B inoperable when its concurrent with required redundant inoperability of feature(s) is redundant inoperable. required feature(s)

AND B.3.1 Perform SR 3.8.1.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for OPERABLE DG OR B.3.2.1 Determine OPERABLE DG 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is not inoperable due to common cause failure.

AND B.3.2.2 Perform SR 3.8.1.2 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months for OPERABLE DG.

AND (continued)

HBRSEP Unit No. 2 3.8-2 Amendment No. 176

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 Restore DG to 7 days OPERABLE status.

AND 8 days from discovery of failure to meet LCO C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or AND B not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Two or more AC sources --------NOTE------------

inoperable. Entry into this Required Action may be delayed for no greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months during performance of Required Action B.3.1 and Required Action B.3.2.2.

D.1 Enter LCO 3.0.3. Immediately HBRSEP Unit No. 2 3.8-3 Amendment No. 176

AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days indicated power availability for the offsite circuit.

SR 3.8.1.2 -------------------NOTES------------------

1. Performance of SR 3.8.1.7 satisfies this SR.

2. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

3. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

Verify each DG starts from standby 31 days conditions and achieves steady state voltage 2 467 V and s 493 V. and frequency 2 58.8 Hz and i 61.2 Hz.

(continued)

HBRSEP Unit No. 2 3.8-4 Amendment No. 176

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) 7 SURVEILLANCE FREQUENCY t

SR 3.8.1.3 . -- - -- ------- NOTES-............

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

5. During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.

Verify each DG is synchronized and loaded 31 days and operates for 2 60 minutes at a load 2 2350 kW and s 2500 kW.

SR 3.8.1.4 Verify each day tank contains 2 140 gallons 31 days of fuel oil.

SR 3.8.1.5 Check for and remove accumulated water from 31 days each day tank.

(continued)

HBRSEP Unit No. 2 3.8-5 Amendment No. 176

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify the fuel oil transfer system 31 days operates to automatically transfer fuel oil from storage tank to the day tank.

SR 3.8.1.7 ---------------- NOTES.--------.--------

All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby 184 days condition and achieves in s 10 seconds, voltage 2 467 V and frequency 2 58.8 Hz, and after steady state conditions are reached, maintains voltage 2 467 V and s 493 V and frequency x 58.8 Hz and s 61.2 Hz.

SR 3.8.1.8 ------------.------ NOTES.-----------------

1. This Surveillance shall not be performed in MODE 1 or 2.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor s 0.9.

Verify each DG rejects a load greater than 18 months or equal to its associated single largest post-accident load and does not trip on overspeed.

(continued)

HBRSEP Unit No. 2 3.8-6 Amendment No. 176

AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 ------- -----NOTES.------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1. 2, 3, or 4.

3. During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.

Verify on an actual or simulated loss of 18 months offsite power signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses;

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in s 10 seconds.

2. energizes auto-connected shutdown loads through automatic load sequencer,

3. maintains steady state voltage 2 467 V and s 493 V.

4. maintains steady state frequency a 58.8 Hz and s 61.2 Hz. and

5. supplies permanently connected and auto-connected shutdown loads for 2 5 minutes.

(continued)

HBRSEP Unit No. 2 3.8-7 Amendment No. 176

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

.9 SR 3.8.1.10 ... * *------*-*NOTES -.--.- ..

1. All DG starts may be preceded by prelube period.

2. This Surveillance shall not be performed in MODE 1 or 2.

3. During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.

Verify on an actual or simulated Engineered 18 months Safety Feature (ESF) actuation signal each DG auto-starts from standby condition and:

a. In s 10 seconds after auto-start achieves voltage 2 467 V, and after steady state conditions are reached.

maintains voltage 2 467 V and s 493 V;

b. In s 10 seconds after auto-start achieves frequency 2 58.8 Hz. and after steady state conditions are reached, maintains frequency 2 58.8 Hz and s 61.2 Hz:

c. Operates for 2 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are energized through the automatic load sequencer from the offsite power system.

(continued)

HBRSEP Unit No. 2 3.8-8 Amendment No. 176

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 Verify each DG's automatic trips are 18 months bypassed except engine overspeed.

SR 3.8.1.12 ------------------ NOTES. ---- .---------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not be performed in MODE 1 or 2.

3. During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.

Verify each DG operating at a power factor 18 months s 0.9 operates for 2 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For a 1.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months loaded 2 2650 kW and s 2750 kW; and

b. For the remaining hours of the test loaded 2 2400 kW and s 2500 kW.

(continued)

HBRSEP Unit No. 2 3.8-9 Amendment No. 176

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 4

SR 3.8.1.13 ---- NOTES.---------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated a 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded a 2400 kW and s 2500 kW.

Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

Verify each DG starts and achieves, in 18 months s 10 seconds, voltage 2 467 V, and frequency 2 58.8 Hz, and after steady state conditions are reached, maintains voltage 2 467 V and s 493 V and frequency 2 58.8 Hz and s 61.2 Hz.

SR 3.8.1.14 .-...........-- NOTE.----------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify actuation of each sequenced load 18 months block is within i 0.5 seconds of design setpoint for each emergency load sequencer.

(continued)

HBRSEP Unit No. 2 3.8-10 Amendment No. 176

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 ---------------- NOTES------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1. 2. 3. or 4.

3. During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.

Verify on an actual or simulated loss of 18 months offsite power signal in conjunction with an actual or simulated ESF actuation signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in s 10 seconds,

2. energizes auto-connected emergency loads through load sequencer,

3. achieves steady state voltage 2 467 V and s 493 V,

4. achieves steady state frequency 2 58.8 Hz and s 61.2 Hz, and (continued)

HBRSEP Unit No. 2 3.8-11 Amendment No. 176

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.15 (continued)

5. supplies permanently connected and auto connected emergency loads for 2 5 minutes.

SR 3.8.1.16 ---------------- NOTE ------------------ ;

1. This Surveillance shall not be perfomed in MODE 1 or 2.

2. SR 3.8.1.16 is not required to be met if 4.160 kV bus 2 and 480 V Emergency Bus 1 power supply is from the start up transformer.

Verify automatic transfer capability of the 18 months 4.160 kV bus 2 and the 480 V Emergency bus 1 loads from the Unit auxiliary transformer to the start up transformer.

SR 3.8.1.17 ------------------ NOTE.-------------------

All DG starts may be preceded by an engine prelube period.

Verify when started simultaneously from 10 years standby condition, each DG achieves. in s 10 seconds, voltage a 467 V and frequency 2 58.8 Hz, and after steady state conditions are reached, maintains voltage 2 467 V and z 493 V and frequency 2 58.8 Hz and s 61.2 Hz.

HBRSEP Unit No. 2 3.8-12 Amendment No. 176

AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite AC electrical power distribution subsystem(s) required by LCO 3.8.10, Distribution Systems - Shutdown"; and

b. One diesel generator (DG) capable of supplying one train of the onsite AC electrical power distribution subsystemts) required by LCO 3.8.10.

APPLICABILITY: MODES 5 and 6 and During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The required offsite .......... NOTE.------------

circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.10. with one required train de-energized as a result of Condition A.

A.1 Declare affected Immediately required feature(s) with no offsite power available inoperable.

OR (continued)

HBRSEP Unit No. 2 3.8-13 Amendment No. 176

AC Sources -Shutdown 3.8.2 ACTIONS ----

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Suspend CORE Immediately ALTERATIONS.

A.2.2 Suspend movement of Inmediately irradiated fuel assemblies.

A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AMD A.2.4 Initiate action to Immediately restore required offsite power circuit to OPERABLE status.

B. The required DG B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

8.2 Suspend movement of Immediately irradiated fuel assemblies.

(continued)

HBRSEP Unit No. 2 3.8-14 Amendment No. t76.190

AC Sources - Shutdown 3.8.2 ACTIONS__

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.4 Initiate action to Immediately restore required DG to OPERABLE status.

SURVEILLANCE REOUIREMENTS_

SURVEILLANCE FREQUENCY SR 3.8.2.1 --- . NOTE.-------------------

The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.8. SR 3.8.1.9. SR 3.8.1.11 through SR 3.8.1.15.

For AC sources required to be OPERABLE. the In accordance SRs of Specification 3.8.1, "AC Sources- with applicable Operating," except SR 3.8.1.16. and SRs SR 3.8.1.17. are applicable.

HBRSEP Unit No. 2 3.8-15 Amendment No. t76.190

Diesel Fuel Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil and Starting Air LCO 3.8.3 The common stored diesel fuel oil and starting air subsystem for each diesel generator (DG) shall be within limits.

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with A.1 Restore fuel oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months DG fuel oil level level to within

< 19,000 gal and limits.

> 14,145 gal in the Unit 2 DG fuel oil storage tank.

B. One or more DGs with B.1 Restore fuel oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months DG Fuel oil level level to within

< 34,000 gal and limits.

> 29.145 gal in the combination of the Unit 1 IC turbine fuel oil storage tanks and the Unit 2 DG fuel oil storage tank.

(continued)

HBRSEP Unit No. 2 3.8-16 Amendment No. 176

Diesel Fuel Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more DGs with C.1 Restore stored fuel 30 days new fuel oil oil properties to properties not within within limits.

imits.

D. One or more DGs with D.1 Restore starting air 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months starting air receiver receiver pressure to pressure < 210 psig 210 psig.

and 2 100 psig.

E. Required Action and E.1 Declare associated Immediately associated Completion DG(s) inoperable.

Time not met.

OR Common stored DGs diesel fuel oil or starting air subsystem for each DG not within limits for reasons other than Condition A. B. C. or D.

HBRSEP Unit No. 2 3.8-17 Amendment No. 176

Diesel Fuel Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4.

SR 3.8.3.1 Verify a 19,000 gallons of diesel fuel oil 7 days available to the DGs from the Unit 2 DG fuel oil storage tank AND 2 34,000 gallons available to the DGs from the combination of the Unit 1 IC turbine fuel oil storage tanks and the Unit 2 DG fuel oil storage tank.

SR 3.8.3.2 Verify fuel oil properties of stored fuel In accordance oil are tested in accordance with, and with the Diesel maintained within the limits of, the Diesel Fuel Oil Fuel Oil Testing Program. Testing Program SR 3.8.3.3 Verify each DG air start receiver pressure 31 days is z 210 psig.

SR 3.8.3.4 Check for and remove accumulated water from 31 days each fuel oil storage tank.

HBRSEP Unit No. 2 3.8-18 Amendment No. 176

DC Sources- Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources- Operating LCO 3.8.4 The Train A and Train B DC electrical power subsystems shall be OPERABLE.

APPLICABILITY: MODES 1. 2, 3. and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One DC electrical A.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power subsystem power subsystem to inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 7 days t 125.7 V on float charge.

(continued)

HBRSEP Unit No. 2 3.8-19 Amendment No. 176

DC Sources- Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.2 Verify battery cells, cell plates, and 18 months racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.

SR 3.8.4.3 Remove visible terminal corrosion, verify 18 months battery cell to cell and terminal connections are clean and tight, and are coated with anti-corrosion material.

SR 3.8.4.4 Verify each battery charger supplies 18 months 2 300 amps at a 125 V for a 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SR 3.8.4.5 -------------------NOTES-------------------

1. The performance discharge test in SR 3.8.4.6 may be performed in lieu of the service test in SR 3.8.4.5 once per 75 months.

2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads for the design 18 months duty cycle when subjected to a battery service test.

(continued)

HBRSEP Unit No. 2 3.8-20 Amendment No. 176

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.6 ................... E---------

-NOT ----

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is 2 80% for the "A"Battery and 91X for the "B"battery of the manufacturer's rating when subjected to 60 months a performance discharge test.

AND 18 months when battery shows degradation or has reached 85%

for battery "A" and 95% for battery OB" of expected life.

HBRSEP Unit No. 2 3.8-21 Amendment No. 176

DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources- Shutdown LCO 3.8.5 DC electrical power subsystem shall be OPERABLE to support the DC electrical power distribution subsystemts) required by LCO 3.8.10, "Distribution Systems-Shutdown."

APPLICABILITY: MODES 5 and 6, and During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1.1 Declare affected Immediately DC electrical power required feature(s) subsystems inoperable. inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND (continued)

HBRSEP Unit No. 2 3.8-22 Amendment No. 176

DC Sources -Shutdown 3.8.5 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

Amn A.2.4 Initiate action to Immediately restore required DC electrical power subsystems to OPERABLE status.

SURVE LLANCE REOUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 ---------------- NOTE-----------------

The following SRs are not required to be performed: SR 3.8.4.4. SR 3.8.4.5. and SR 3.8.4.6.

For DC sources required to be OPERABLE, the In accordance following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.3 SR 3.8.4.5 SR 3.8.4.2 SR 3.8.4.4 SR 3.8.4.6 HBRSEP Unit No. 2 3.8-23 Amendment No. 1J6.190

Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for Train A and Train B batteries shall be within the limits of Table 3.8.6-1 and average electrolyte temperature of representative cells shall be within limit.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verify pilot cell 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one or more electrolyte level and battery cell float voltage meet parameters not within Table 3.8.6-1 Category A or B Category C limits.

limits.

AD A.2 Verify battery cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters meet Table 3.8.6-1 AND Category C limits.

Once per 7 days thereafter AND A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.

(continued)

HBRSEP Unit No. 2 3.8-24 Amendment No. 176

Battery Cell Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A not met.

OR One or more batteries with average electrolyte temperature of the representative cells

< 670F.

OR One or more batteries with one or more battery cell parameters not within Category C values.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days Table 3.8.6-1 Category A limits.

(continued)

HBRSEP Unit No. 2 3.8-25 Amendment No. 176

Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued) Y.

SURVEILLANCE FREQUENCY 4.

SR 3.8.6.2 Verify battery cell parameters meet 92 days Table 3.8.6-1 Category B limits.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a battery discharge

' 110 V Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a battery overcharge

> 150 V SR 3.8.6.3 Verify average electrolyte temperature 92 days of representative cells is 2 670F.

HBRSEP Unit No. 2 3.8-26 Amendment No. 176

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Cell Parameters Requirements CATEGORY A: CATEGORY C:

LIMITS FOR EACH CATEGORY B: ALLOWABLE LIMITS DESIGNATED PILOT LIMITS FOR EACH FOR EACH PARAMETER CELL CONNECTED CELL CONNECTED CELL Electrolyte Level > Minimum level > Minimum level Above top of indication mark, indication mark, plates, and not and s V/ inch and s % inch overflowing above maximum above maximum level indication level indication markta) markta)

Float Voltage t 2.13 V 2 2.13 V > 2.07 V Specifi z 1.200 2 1.195 Not more than Gravity b)(c) 0.020 below AND average of all connected cells Average of all connected cells AND

> 1.205 Average of all connected cells 2 1.195 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overfl owing.

(b) Corrected for electrolyte temperature and level. Level correction is not required, however, when battery charging current is < 2 amps while on float charge.

(c) A battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits following a battery recharge. for a maximum of 7 days. When charging current is used to satisfy specific gravity requirements, specific gravity of each connected cell shall be measured prior to expiration of the 7 day allowance.

HBRSEP Unit No. 2 3.8-27 Amendment No. 176

AC Instrument Bus Sources -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 AC Instrument Bus Sources- Operating LCO 3.8.7 The following AC Instrument Bus Power Sources shall be OPERABLE:

a. Inverters A and B. and

b. Constant Voltage Transformers (CVT) 1 and 2.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC Instrument Bus A.1 --------NOTE--------

power source Enter applicable inoperable. Conditions and Required Actions of LCO 3.8.9.

'Distribution Systems - Operating*

with any instrument bus de-energized.

Restore AC Instrument 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Bus Power Source to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HBRSEP Unit No. 2 3.8-28 Amendment No. 176

AC Instrument Bus Sources -Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, 7 days and alignment to required AC instrument buses.

SR 3.8.7.2 Verify voltage availability and correct CVT 7 days alignment to required AC instrument buses.

HBRSEP Unit No. 2 3.8-29 Amendment No. 176

AC Instrument Buses-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 AC Instrument Bus Sources -Shutdown LCO 3.8.8 AC instrument bus source shall be OPERABLE to support the onsite AC instrument bus electrical power distribution subsystem~s) required by LCO 3.8.10, "Distribution Systems- Shutdown."

APPLICABILITY: MODES 5 and 6. and During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC A.1 Declare affected Immediately instrument bus sources required feature(s) inoperable. inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND (continued)

HBRSEP Unit No. 2 3.8-30 Amendment No. 176

AC Instrument Buses-Shutdown 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

A.2.4 Initiate action to Immediately restore AC instrument bus sources to OPERABLE status.

SURVEILLANCE REOVIREMENTS SURVEILLANCE FRECUENCY SR 3.8.8.1 ------ NOTE-------------------

Actual voltage and frequency measurement is not required for AC instrument buses supplied from CVTs.

Verify correct Inverter voltage, frequency. 7 days and alignments to required AC instrument buses.

HBRSEP Unit No. 2 3.8-31 Amendment No. 176.190

Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems -Operating LCO 3.8.9 Train A and Train B AC, DC, and AC instrument bus electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2. 3. and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC electrical A.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution power distribution subsystem inoperable. subsystem to OPERABLE AND status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO B. One AC instrument bus B.1 Restore AC instrument 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months subsystem inoperable. bus subsystem to OPERABLE status. AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO C. One DC electrical C.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power distribution power distribution subsystem inoperable. subsystem to OPERABLE AND status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO (continued)

HBRSEP Unit No. 2 3.8-32 Amendment No. 176

Distribution Systems -Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Trip elements D.1 . - NOTE-.......

inoperable for both of Enter applicable the molded case Conditions and circuit breakers Required Actions for associated with the Systems made AFW Header Discharge inoperable by to S/G "A"valve, inoperable valves.

V2-16A. .....................

Open one of the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months circuit breaker(s) with the inoperable trip element.

E. Trip elements E.1 --------- NOTE -------

inoperable for both of Enter applicable the molded case Conditions and circuit breakers Required Actions for associated with the Systems made Service Water System inoperable by Turbine Building inoperable valves.

Supply Valve .....................

(emergency supply)

V6-16C. Open one of the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months circuit breaker(s) with the inoperable trip element.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HBRSEP Unit No. 2 3.8-33 Amendment No. 176

Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Two trains with G.1 Enter LCO 3.0.3. Immediately inoperable distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 N------------------NOTE... . .

Actual voltage measurement is not required for the AC vital buses supplied from the constant voltage transformers.

Verify correct breaker alignments and 7 days voltage to AC. DC, and AC instrument bus electrical power distribution subsystems.

SR 3.8.9.2 Verify capability of the two molded case 18 months circuit breakers for AFW Header Discharge Valve to S/G 'A', V2-16A to trip on overcurrent.

SR 3.8.9.3 Verify capability of the two molded case 18 months circuit breakers for Service Water System Turbine Building Supply Valve (emergency supply), V6-16C to trip on overcurrent.

HBRSEP Unit No. 2 3.8-34 Amendment No. 176

Distribution Systems- Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems- Shutdown LCO 3.8.10 The necessary portion of AC, DC, and AC instrument bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 5 and 6, and During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC, or AC supported required instrument bus feature(s) electrical power inoperable.

distribution subsystems inoperable. _

A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND (continued)

HBRSEP Unit No. 2 3.8-35 Amendment No. 176

Distribution Systems -Shutdown 3.8.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

A.2.4 Initiate actions to Immediately restore required AC, DC. and AC instrument bus electrical power distribution subsystems to OPERABLE status.

AM A.2.5 Declare associated Immediately required residual heat removal subsystem(s) inoperable and not in operation.

SURVEIL[LNE QUIREMENTS ________

SURVEILLANCE FREQUENCY SR 3.8.10.1 ---------------- NOTE------------.-------

Actual voltage measurement is not required for the AC vital buses supplied from constant voltage transformers.

Verify correct breaker alignments and 7 days voltage to required AC. DC. and AC instrument bus electrical power distribution subsystems.

HBRSEP Unit No. 2 3.8-36 Amendment No. -7.190

_-be

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Suspend CORE Immediately not within limit. ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to Immediately restore boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limit specified in COLR.

HBRSEP Unit No. 2 3.9-1 Amendment No. 176

Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range neutron flux monitors shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source A.1 Verify one Post 15 minutes range neutron flux Accident Monitor monitor inoperable (PAM) source range neutron flux monitor provides indication in the Control Room.

A.2 Log indicated PAM 30 minutes source range neutron monitor count rate. AMD Once per 30 minutes thereafter (continued)

HBRSEP Unit No. 2 3.9-2 Amendment No. iJ6,t8M .190 I

Nuclear Instrumentation 3.9.2 AIONS- cntinued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Actions and B.1 Suspend CORE Immediately Completion Times of ALTERATIONS.

Condition A not met.

8.2 Suspend operations Immediately that would cause introduction into the RCS. coolant with boron concentration less than required to meet boron concentration of LCO 3.9.1.

C. Two required source C.1 Initiate action to Immediately range neutron flux restore one source monitors inoperable. range neutron flux monitor to OPERABLE status.

C.2 Suspend CORE Immediately ALTERATIONS.

C.3 Suspend positive Immediately reactivity additions.

AMI CA Perform SR 3.9.1.1. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AM Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter HBRSEP Unit No. 2 3.9-3 Amendment No. tMA.I80.190

Nuclear Instrumentation 3.9.2 SURVEILLANCE REQtJTREMENT ________

SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.2.2 ----------- NOTE------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months HBRSEP Unit No. 2 3.9-3a Amendment No. M76.A80O190 I

Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations LCO 3.9.3 The containment penetrations shall be in the following status:

a. The equipment hatch closed and held in place by four bolts;

b. One door in the air lock closed; and

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:

1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or

2. capable of being closed by an OPERABLE Containment Ventilation Isolation System.

APPLICABILITY: During movement of recently irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Suspend movement of Immediately penetrations not in recently irradiated required status. fuel assemblies within containment.

HBRSEP Unit No. 2 3.9-4 Amendment No. 4-6 195

Containment Penetrations 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify each required containment 7 days penetration is in the required status.

SR 3.9.3.2 Verify each required containment 18 months ventilation valve actuates to the isolation position on an actual or simulated actuation signal.

HBRSEP Unit No. 2 3.9-5 Amendment No. 176

RHR and Coolant Circulation-High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level LCO 3.9.4 One RHR train shall be OPERABLE and in operation.

NOTE----------------------

The required RHR train may be removed from operation for s 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months In any 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause introduction into the Reactor Coolant System, coolant with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1.

APPLICABILITY: MODE 6 with the water level 2 23 ft above the top of reactor vessel flange.

ACTIONS - .

CONDITION REQUIRED ACTION COMPLETION TIME A. RHR train requirements A.1 Suspend operations Immediately not met. that would cause introduction into the RCS, coolant with boron concentration less than required to meet boron concentration of LCO 3.9.1.

A.2 Suspend loading Immediately irradiated fuel assemblies in the core.

(continued)

HBRSEP Unit No. 2 3.9-6 Amendment No. t76.190

RHR and Coolant Circulation-High Water Level 3.9.4 CIONS (ontiued)_ .

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Initiate action to Immediately satisfy RHR train requirements.

AND A.4 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SRVEILLANCREIREHENTS_

SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one RHR train isinoperation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months HBRSEP Unit No. 2 3.9-7 Amendment No. tf7,190

RHR and Coolant Circulation-Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level LCO 3.9.5 Two RHR trains shall be OPERABLE, and one RHR train shall be in operation.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

TONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to Immediately number of RHR trains restore required RHR OPERABLE. trains to OPERABLE status.

OR A.2 Initiate action to Immediately establish 2 23 ft of water above the top of reactor vessel flange.

B. No RHR train in B.1 Suspend operations Immediately operation. that would cause introduction into the RCS. coolant with boron concentration less than required to meet boron concentration of LCO 3.9.1.

AM (continued)

HBRSEP Unit No. 2 3.9-8 Amendment No. t76.190

RHR and Coolant Circulation -Low Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Initiate action to Immediately restore one RHR train to operation.

AND B.3 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR train is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.5.2 Verify correct breaker alignment and 7 days indicated power available to the required RHR pump that is not in operation.

HBRSEP Unit No. 2 3.9-9 Amendment No. 176

Refueling Cavity Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Cavity Water Level LCO 3.9.6 Refueling cavity water level shall be maintained 2 23 ft above the top of reactor vessel flange.

APPLICABILITY: During movement of irradiated fuel assemblies within containment. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.1 Suspend movement of Immediately level not within irradiated fuel limit. assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling cavity water level is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2 23 ft above the top of reactor vessel flange.

HBRSEP Unit No. 2 3.9-10 Amendment No. 4-6 195

Containment Purge Filter System 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Containment Purge Filter System LCO 3.9.7 The Containment Purge Filter System shall be OPERABLE and operating.

APPLICABILITY: During movement of recently irradiated fuel assemblies in containment. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment Purge A.1 Close each Immediately Filter System penetration providing inoperable. direct access from the containment OR atmosphere to the outside atmosphere by Containment Purge a manual or automatic Filter System not in valve, blind flange, operation. or equivalent method.

OR A.2 Suspend movement of Immediately recently irradiated fuel assemblies within containment.

HBRSEP Unit No. 2 3 .9-11 Amendment No. 176 195

Containment Purge Filter System 3.9.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify relative humidity of containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months atmosphere to be processed by the Containment Purge Filter System is s 70%.

SR 3.9.7.2 Verify the Containment Purge Filter System 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is in operation and maintaining containment pressure negative relative to the adjacent auxiliary building areas.

SR 3.9.7.3 Perform required Containment Purge Filter In accordance System filter testing in accordance with with the VFTP the Ventilation Filter Testing Program (VFTP).

HBRSEP Unit No. 2 3.9-12 Amendment No. 176

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The H. B. Robinson Steam Electric Plant, Unit No. 2 is located on the southwest shore of Lake Robinson, in northwest Darlington County, South Carolina. The site location is approximately 25 miles NW of Florence, 35 miles NNE of Sumter, and 56 miles ENE of Columbia. South Carolina.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 157 fuel assemblies. Each assembly shall consist of a matrix of Zircaloy-4 fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO 2) as fuel material. Limited substitutions of zirconium 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 all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Rod Cluster Control (RCC) Assemblies The reactor core shall contain 45 full length RCC assemblies. The control material shall be silver-indium-cadmium, as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 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:

(continued)

HBRSEP Unit No. 2 4.0-1 Amendment No. 176

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

b. keff

0.95 in the low density storage racks if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

c. ketf

0.95 in the high density storage racks if fully flooded with water borated to 1500 ppm, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

d. keft less than 1.0 in the high density storage racks if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

e. A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the high density fuel storage racks;

f. A nominal 21 inch center-to-center distance between fuel assemblies placed in low density fuel storage racks.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;

b. keff s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

c. kerf

0.98 in an optimum moderation event, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and

d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

HBRSEP Unit No. 2 4.0-2 Amendment No. 198

Design Features 4.0 4.0 DESIGN FEATURES 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below 18 feet above the fuel.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 544 assemblies.

HBRSEP Unit No. 2 4.0-3 Amendment No. 198 l

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Plant Manager shall be responsible for overall unit operation 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 and modification to systems or equipment that affect nuclear safety.

5.1.2 The Superintendent-Shift Operations (SSO) shall be responsible for the control room command function. During any absence of the SSO from the control room while the unit is in MODE 1, 2. 3. or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function.

During any absence of the SSO from the control room while the unit is in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

HBRSEP Unit No. 2 5.0-1 Amendment No. 176

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 unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. 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, inorganization charts. These lines of authority, responsibility, and communication shall be documented inthe UFSAR;

b. 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:

c. 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 inoperating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d. The individuals who train the operating staff, carry out radiation control, 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 Unit Staff The unit staff organization shall include the following:

a. An auxiliary operator shall be assigned to the shift crew when fuel is in the reactor. An additional auxiliary (continued)

HBRSEP Unit No. 2 5.0-2 Amendment No. 176

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued) operator shall be assigned to the shift crew while the unit isoperating inMODES 1,2. 3. or 4.

b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is inMODE 1,2, 3. or 4, at least one licensed Senior Reactor Operator (SRO) shall be present inthe control room.

c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specification 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action istaken to restore the shift crew composition to within the minimum requirements.

d. An individual qualified as a radiation control technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action istaken to fill the required position.

e. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (e.g., licensed SROs, licensed ROs, radiation control personnel, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day, nominal 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week while the unit isoperating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time; (continued)

HBRSEP Unit No. 2 5.0-3 Amendment No. 176

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months inany 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inany 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period. nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inany 7 day period, all excluding shift turnover time:

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time;

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized inadvance by the Plant Manager or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included inthe procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines isnot authorized.

f. The Operations Manager or Superintendent incharge of the operations shift crews shall hold an SRO license.

g. During MODES 1,2, 3, and 4, the shift technical advisor (STA) shall provide advisory technical support to the SSO with regard to the safe operation of the unit. If an individual that holds an SRO license also meets the STA requirements, that individual may act in both capacities.

HBRSEP Unit No. 2 5.0-4 Amendment No. 176

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the manager of the radiation control function, who shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1981, and the STA, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

HBRSEP Unit No. 2 5.0-5 Amendment No. 176

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 rocedures required to implement the commitments to NUREG-0737 and of NUREG-0737, Supplement 1, as stated in Generic Letter 82-33:

c. Quality assurance for effluent and environmental monitoring;

d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.5.

HBRSEP Unit No. 2 5.0-6 Amendment No. 176

Programs and Manuals 5.5-5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs and manuals 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: and

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 5.6.2 and Specification 5.6.3.

c. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

(a) sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and (b) 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 do not adversely impact the accuracy or reliability of effluent, dose, or setpoint 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 entire ODCH as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the 00CM was made. Each change shall be identified by (continued)

HBRSEP Unit No. 2 5.0-7 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (O1CM) (continued) 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.

5.5.2 Primary Coolant Sources Outside Containment This program provides controls to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Residual Heat Removal, Safety Injection, Containment Spray, Post Accident Containment Ventilation; and portions of Chemical and Volume Control, Liquid Waste Disposal, Gaseous Waste Disposal, and Sampling. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at refueling cycle intervals or less.

5.5.3 DFlIFTFE 5.5.4 Radioactive Fffluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of (continued)

HBRSEP Unit No. 2 5.0-8 Amendment No. 192

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls ProQram (continued) the public from radioactive effluents as low as 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:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentration values in Appendix B. Table 2, Column 2 to 10 CFR 20.1001-20.2401;

c. 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;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative and projected 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;

f. 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 dose commitments due to the release of effluents to unrestricted areas exceed specified limits conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary as follows:

1. For noble gases: < 500 mrem/yr to the whole body, c 3000 mrem/yr to the skin; and (continued)

HBRSEP Unit No. 2 5.0-9 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

2. For 1-131, 1-133, tritium, and all radionuclides in particulate form (inhalation pathway only) with half lives > 8 days: < 1500 mrem/yr to any organ.:

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50.

Appendix I;

i. 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 to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Table 3.9.1-1, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Procram This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments. including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include inspection frequencies, and acceptance criteria.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

(continued)

HBRSEP Unit No. 2 5.0-10 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program provides controls for the inspection of each reactor coolant pump flywheel in accordance with the Inservice Inspection Program.

5.5.8 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1. 2. and 3 pumps and valves. The program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for pxWrforming inservice testing activities:

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

(continued)

HBRSEP Unit No. 2 5.0-11 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.9 Steam Generator (SG) Tube Surveillance Program This program provides controls for the inservice inspection of SG tubes to assure the continued integrity of the Reactor Coolant System pressure boundary and shall include the following:

a. Tube Inspection Entry from either the hot-leg side or cold-leg side with examination encompassing the area from the hot-leg tube end completely around the U-bend to the top support of the cold leg is considered a tube inspection.

b. Sample Selection and Testing Selection and testing of steam generator tubes shall be made on the following basis:

1. One steam generator shall be inspected during inservice inspection in accordance with the following requirements:

(a) The inservice inspection may be limited to one steam generator on a rotating sequence basis.

This examination shall include at least 9X of the tubes if the results of the first or a prior inspection indicate that all three generators are performing in a comparable manner.

(b) When other steam generators are required to be examined by Table 5.5-1 and if the condition of the tubes in one or more generators is found to be more severe than in the other steam generators.

the steam generator sampling sequence at the subsequent inservice inspection shall be modified to examine the steam generator or generators with the more severe condition.

2. The minimum sample size, inspection result classification and the associated required action shall be in conformance with the requirements specified in Table 5.5-1. The results of each sampling examination of a steam generator shall be classified into the following three categories:

(continued)

HBRSEP Unit No. 2 5.0-12 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Program (continued)

Cate-gorv C-1: less than 5X of the total number of tubes examined are degraded but none are defective.

Categorv C-2: Between 5% and 10% of the total number of tubes examined are degraded, but none are defective or one tube to not more than 1% of the sample is defective.

Categorv C-3: More than 10X or the total number of tubes examined are degraded. but none are defective or more than 1X of the sample is defective.

In the first saniple of a given steam generator during any inservice irispection. degraded tubes not beyond the plugging limit cletected by the prior examinations in that steam gener ator shall be included in the above percentage calcLalations, only if these tubes are demonstrated to have a further wall penetration of greater than 101 of the nominal tube wall thickness.

3. Tubes shall be !selected for examination primarily from those areas of t;he tube bundle where service experience has shown the mc )st severe tube degradation.

4. The tubes examir ied in a given steam generator during the first examir nation of any inservice inspection shall include all non- pplugged tubes in that steam generator that from prior examination were degraded, plus additional tubes are required to satisfy the minimum sample size spec :ified inTable 5.5-1. If any selected tube does not pEirmit passage of the eddy current probe for a tube inspeaction. this shall be recorded and an adjacent tube stiall be selected and subjected to a tube inspection. Thi isinformation shall be included in the report required by Specification 5.6.8.b.

5. During the secoridand third sample examinations of any inservice inspec:tion, the tube inspection may be limited to those sections of the tube lengths where (continued)

HBRSEP Unit No. 2 5.0-13 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Program (continued) imperfections were detected during the prior examination.

6. During subsequent inservice inspections, the tube inspection may be limited to certain areas of the tube sheet array and those sections of the tube lengths where imperfections were detected during previous inservice inspections.

c. Examination Method and Requirements Steam generator tubes shall be examined in accordance with the method prescribed in Appendix IV, 'Eddy Current Examination of Non-Ferromagnetic Steam Generator Heat Exchanger Tubes," as contained in ASME Boiler and Pressure Vessel Code,Section XI, aInservice Inspection of Nuclear Power Plant Components."

d. Inspection Intervals

1. Inservice inspections shall not be more than 24 calendar months apart, except that reduced or tightened inspection intervals shall be governed as specified in 5.5.9.d.3 and d.4.

2. The inservice inspections may be scheduled to be coincident with refueling outages or any plant shutdown, provided the inspection intervals of 5.5.9.d.1, d.3, or d.4, as applicable, are not exceeded.

3. If two consecutive inservice inspections covering a time span of at least 12 months yield results that fall in C-1 category, the inspection frequency may be extended to 40 month intervals between inspections.

4. If the results of the inservice inspection of steam generator tubing conducted in accordance with Table 5.5-1 at 40 month intervals fall in category C-3, the inspection frequency shall be reduced to at least once per 20 months. The increase in inspection frequency shall apply until a subsequent inspection meets the (continued)

HBRSEP Unit No. 2 5.0-14 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Program (continued) conditions specified in 5.5.9.d.3 and the interval can be extended to a 40 month period.

5. Unscheduled inspections shall be conducted in accordance with Specification 5.5.9.b on any steam generator with primary-to-secondary tube leakage (not including leaks originating from tube-to-tube sheet welds) exceeding Specification 3.4.13.

All steam generators shall be inspected before returning to power in the event of a seismic occurrence greater than an operating basis earthquake, a LOCA requiring actuation of engineering safeguards, or a main steam line or feedwater line break.

e. Acceptance Limits Definitions:

Imperfection is an exception to the dimension, finish, or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

Degradation means a service induced cracking, wastage, wear.

or general corrosion occurring on either inside or outside of a tube.

Decraded Tube is a tube that contains imperfections caused by degradation equal to or greater than 20% of the nominal tube wall thickness.

Defect is an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.

Plugqing Limit is the imperfection depth beyond which a degraded tube must be removed from service by plugging, because the tube may become defective prior to the next scheduled inspection of that tube. The plugging limit is 47% of the nominal tube wall thickness if the next inspection interval of that tube is 12 months, and a 2X (continued)

HBRSEP Unit No. 2 5.0-15 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Tube Surveillance Program (continued) reduction in the plugging limit for each 12 month period until the next inspection of the inspected steam generator.

f. Corrective Measures All tubes that leak or are determined to have degradation exceeding the plugging limit shall be plugged prior to return to power.

5.5.10 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation. The program shall include:

a. Identification of critical parameters. their sampling frequency, sampling points, and control band limits:

b. Procedures used to measure the critical parameters;

c. Requirements for the documentation and review of sample results;

d. Procedures which identify the administrative events and corrective actions required to return the secondary chemistry to its normal control band following an out of control band condition; and

e. Identification of the authority responsible for the interpretation of the sample results.

(continued)

HBRSEP Unit No. 2 5.0-16 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.11 Ventilation Filter Testing Program (VFTP)

This program provides controls for implementation of the following required testing of Engineered Safety Feature (ESF) ventilation filter systems at the frequencies specified in Positions C.5 and C.6 of Regulatory Guide 1.52, Revision 2, March 1978, and conducted in general conformance with ANSI N510-1975 or N510-1980.

a. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows the specified penetration and system bypass leakage when tested in accordance with the referenced standard at the system flowrate specified below.

ESF Ventilation Penetration System /Bypass Flowrate Reference Std Control Room <0.05% 3300 - 4150 ACFM Regulatory Guide Emergency 1.52, Revision 2, March 1978, C.5.a, C.5.c, C.5.d (using ANSI N510-1980)

Spent Fuel <1X 11070- 13530 CFM ANSI N510-1975 Building Containment 31500- 38500 CFM ANSI N510-1975 Purge (continued)

HBRSEP Unit No. 2 5.0-17 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows the specified penetration and system bypass leakage when tested in accordance with the referenced standard at the system flowrate specified below.

ESF Ventilation Penetration System /Bypass Flowrate Reference Std Control <0.05X 3300 4150 ACFM Regulatory Guide Room 1.52. Revision 2.

Emergency March 1978, C.5.a. C.5.c.

C.5.d (using ANSI N510-1980)

Spent Fuel <1% 11070- 13530 CFM ANSI N510-1975 Building Containment 31500- 38500 CFM ANSI N510-1975 Purge (continued)

HBRSEP Unit No. 2 5.0-18 Amendment No. 176

Programs and Manual s 5.5 5.5 Programs and Manuals 5.5.11 Vpntilatinn Filtpr Tasting Prngram (VFTP) (continued)

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber. when obtained as described in Regulatory Guide 1.52. Revision 2. shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 300C (86°) and the relative humidity specified below.

FSF Filtir Syctpm PenetratiMn RH Control Room *2.5% 70X Emergency Spent Fuel 10% 70%

Building Containment Purge o10X 95X (continued)

HBRSEP Unit No. 2 5.0-19 Amendment No. 189

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below.

ESF Filter System Delta P Flowrate Control Room 53.4 inches 3300 - 4150 ACFM Emergency water gauge Spent Fuel <6 inches 12300 CFM +10X Building water gauge Containment <6 inches 35000 CFM +1OX Purge water gauge

e. Demonstrate that the heaters for the Spent Fuel Building ventilation filter system maintains the filter inlet air at s 70% relative humidity when tested in accordance with ASME N510-1975.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas Decay Tanks, the quantity of radioactivity contained in The Waste Gas Decay Tanks and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Waste Gas Decay Tanks and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate (continued)

HBRSEP Unit No. 2 5.0-20 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued) 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 Waste Gas Decay Tank is less than the amount that would result in a whole body exposure of 2 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 each outdoor liquid radwaste tank that is not surrounded by liners, dikes, or walls, capable of holding the tank's contents and that does not have tank overflows and surrounding area drains connected to the Liquid Waste Disposal System is less than or equal to ten (10) Curies, excluding tritium and dissolved or entrained noble gases.

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.

5.5.13 Diesel Fuel Oil Testing Program A diesel fuel oil testing program shall be established requiring testing of both new fuel oil and stored fuel oil. The program shall include sampling and testing requirements, and acceptance criteria. The testing methods shall be in accordance with applicable ASTM Standards. The acceptance criteria shall be in accordance with the diesel engine manufacturer specifications.

The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has not become contaminated with other products during transit, thus altering the quality of the fuel oil.

(continued)

HBRSEP Unit No. 2 5.0-21 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Diesel Fuel Oil Testing Proaram (continued)

b. Acceptability of fuel oil for use by testing the following parameters at a 31 day frequency:

API or specific gravity, viscosity, water and sediment, and cloud point.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program surveillance frequencies.

5.5.14 Technical Specifications (TS) Bases Control Program This program provides controls 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 involve 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 involves an unreviewed safety question as defined in 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d. Proposed changes that meet the criteria of Specification 5.5.14b 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).

5.5.15 Safety Function Determination Program (SFDP)

This program provides controls to ensure loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be (continued)

HBRSEP Unit No. 2 5.0-22 Amendment No. 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination ProQram (SFDP) (continued) taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.

a. The SFDP shall contain the following:

1. Provisions for cross train 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 plant is maintained in a safe condition if a loss of function condition exists:

3. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system 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 described in b.1 and b.2 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.

(continued)

HBRSEP Unit No. 2 5.0-23 Amendment No. 176

Programs and'Manuals 5.5 Programs and Manuals . . a .

5.5.16 C6ntalriment Leakage Rate Testing Program' This program provides controls for Implementation of the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B.as modified by approved exemptions for Type A testing. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, Performance-Based Containment Leak-Test Program," dated September 1995. as modified by the following exception:

a. NEI 94 1995. Section 9.2.3: The first Type A test performed after the April 9.1992, Type A test shall be performed no later than April 9. 2007. l Type B and C testing shall be implemented in the program in accordance with the requirements of 10 CFR 50, Appendix J, Option A.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa. is40.5 psig.

The maximum allowable containment leakage rate, La, at P.. shall be 0.1X of the containment air weight per day.

Leakage rate acceptance criteria are:

a. Containment leakage rate acceptance criteria is s 1.0 L.

During the first unit startup following testing inaccordance with this program, the leakage rate acceptance criteria are s 0.60 LA for the Type B and Type C tests, and s 0.75 La for Type A tests.

The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

(continued)

HBRSEP Unit No. 2 5.0-24 Amendment No. 199

Programs and Manuals 5.5 5.5 Programs and Manuals (continued)

TABLE 5.5-1 STEAM GENERATOR TUBE INSPECTION 1st SAMPLE EXAMINATION 2nd SAMPLE EXAMINATION 3rd SAMPLE EXAMINATION Sample Size Result Action Required Result Action Required Result Action Required A minimum of S C-l Acceptable for N/A N/A N/A N/A tubes per Steam Continued Service 6enerator (SG)

C-2 Plug tubes C-I Acceptable for N/A N/A exceeding the Continued S-3(N/n)S plugging limit and Service proceed with 2nd sample examination C-2 Plug tubes C-I Acceptable for where: of 2S tubes in exceeding the Continued Service same steam plugging limit generator and proceed with C-2 Plug tubes exc.

N is the number 3rd sample plug limit.

of steam examination of 9Acceptable for generators in 4S tubes In same continued service the plant - 3 steam generator C-3 Perform action n is the number ~ ~ ~required he .... C-3 of Istunder sample of steam exam1nation generators inspected during an C-3 Perform action N/A N/A examination required under C-3 of 1st sample examination C-3 Inspect all tubes All other Acceptable for N/A N/A in this SG. plug S~s are C-I Continued tubes exceeding Service the plugging limit and proceed with 2nd sample Some SGs are Perform Action N/A N/A examination of 2 C-2 but no required under tubes In each additional C-Zof 2nd other steam S~s are sample generator not C-3 examination included in the above inservice inspection Additional Inspect all N/A N/A program. Report SO isC-3 tubes inthis SG results to C1C. and plug tubes exceeding the plugging limit.

teport results to NRC HBRSEP Unit No. 2 5.0-25 Amendment No. 176

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 Occupational Radiation Exposure Report A tabulation on an annual basis of the number of station, utility.

and other personnel (including contractors) receiving an annual deep dose equivalent > 100 mrem/yr and their associated collective deep dose equivalent (reported in person-rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, maintenance, waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD). or film badge measurements. Small exposures totalling < 20X of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total deep dose equivalent received from external sources should be assigned to specific major work functions. The report shall be submitted by April 30 of each year.

5.6.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit 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 inthe Offsite Dose Calculation Manual (ODCM), and in10 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 inthe table and figures inthe ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of Table 3 inthe Radiological Assessment Branch Technical Position, Revision 1,November 1979.

(continued)

HBRSEP Unit No. 2 5.0-26 Amendment No. 176

Reporting Requirements Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)

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.

5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit shall be submitted 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 unit. 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.

5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the pressurizer power operated relief valves or pressurizer safety valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 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:

1. Shutdown Margin (SDM) for Specification 3.1.1:

2. Moderator Temperature Coefficient limits for Specification 3.1.3;

3. Shutdown Bank Insertion Limits for Specification 3.1.5; (continued)

HBRSEP Unit No. 2 5.0-27 Amendment No. 176

Reporting Requirements Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORF OPFRATTNG ITMTTS RFPrNI MOI.R) (continued)

4. Control Bank Insertion Limits for Specification 3.1.6;

5. Heat Flux Hot Channel Factor (Fo(Z)) limit for Specification 3.2.1;

6. Nuclear Enthalpy Rise Hot Channel Factor(F) limit for Specification 3.2.2;

7. Axial Flux Difference (AFD) limits for Specification 3.2.3; and

8. Boron Concentration limit for Specification 3.9.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. The approved version shall be identified in the COLR.

These methods are those specifically described in the following documents:

1. XN-75-27(A). "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors." approved version as l specified in the COLR.

2. XN-NF-84-73(P). "Exxon Nuclear Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," approved version as specified in the COLR.

3. XN-NF-82-21(A). "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations." approved version as specified in the COLR.

4. Steam Line Break Methodology as defined by:

ANF-84-093(P)(A), "'Steamline Break Methodology for PWRs," approved version as specified in the COLR.

EMF-84-093(P)(A). "Steam Line Break Methodology for PWRs." approved version as specified in the COLR.

(continued)

HBRSEP Unit No. 2 5.0-28 Amendment No. th . 188

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CARF APFRATTNG ITMTTS RFPORT (COIR' (continued)

5. XN-75-32(A), "Computational Procedure for Evaluating Rod Bow," approved version as specified in the COLR.

6. XN-NF-82-49(A), "Exxon Nuclear Corporation Evaluation Model EXEM PWR Small Break Model," approved version as specified in the COLR.

7. EMF-2087 (P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," approved version as specified in the COLR.

8. XN-NF-78-44(A). "Generic Control Rod Ejection Analysis," approved version as specified in the COLR. l

9. XN-NF-621(A), "XNB Critical Heat Flux Correlation,"

approved version as specified in the COLR.

10. ANF-1224(A), "Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel."

approved version as specified in the COLR.

11. XN-NF-82-06(A), "Qualification of Exxon Nuclear Fuel for Extended Burnup." approved version as specified in the

12. WCAP-10080-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," approved version as specified in the COLR.

13. WCAP-10081-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP code," approved version as specified in the COLR.

14. WCAP-8301 (Proprietary) and WCAP-8305 (Nonproprietary).

"LOCTA-IV Program: Loss of Coolant Transient Analysis,"

approved version as specified in the COrR.

(continued)

HBRSEP Unit No. 2 5.0-29 Amendment No. IM6. 188

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 MfRF nPFPATTN. ItTMTTS RFPORT (CMIR' (continued)

15. "Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 87 to Facility Operating License No. DPR-23. Carolina Power & Light Co..

H. B. Robinson Steam Electric Plant, Unit No. 2, Docket No. 50-261." USNRC. Washington. DC 20555. 7 Nov. 84.

16. ANF-88-054(P). "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B.

Robinson Unit 2." approved version as specified in the COLR.

17. ANF-88-133 (P)(A). "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 Gwd/MTU." approved version as specified in the COLR.

18. ANF-89-151(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events." approved version as specified in the COLR.

19. EMF-92 081(A). "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors." approved version as specified in the COLR.

20. EMF-92-153(P)(A). "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel."

approved version as specified in the COLR.

21. XN-NF-85-92(P)(A). "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results." approved version as specified in the COLR.

22. EMF-96-029(P)(A), "Reactor Analysis System for PWRs,"

approved version as specified in the COLR.

23 EMF-92-116. "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.

(continued)

HBRSEP Unit No. 2 5.0-30 Amendment No. 76. 188

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 MARF nPFRATTN(: I IMTTS RFP(ORT (Crfl R) (continued)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM. transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR. including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Pnst Arcident Mnnitnring PAM) Tnctrtimentation RPeprt When a report is required by Condition B or H of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability. and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

(continued)

HBRSEP Unit No. 2 5.0-31 Amendment No. 16,. M78 M85. 188 '

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.7 Tendon Surveillance Report

a. Notification of a pending sample tendon test, along with detailed acceptance criteria. shall be submitted to the NRC at least two months prior to the actual test.

b. A report containing the sample tendon test evaluation shall be submitted to the NRC within six months of conducting the test.

5.6.8 Steam Generator Tube Inspection Report

a. A report of the number of tubes plugged in each steam generator shall be submitted to the NRC within 14 days after completion of the tube plugging.

b. A report of the results of the steam generator tube inspection shall be included in the Monthly Operating Report for the period beginning after the final inspection is completed.

Reports shall include:

1. Number and extent of tubes inspected

2. Location and percent of wall thickness penetration for each eddy current indication and any leaks.

3. Identification of tubes plugged.

c. A report of examination results falling in Category C-3 of Table 5.5-1 shall be submitted to the NRC within 30 days.

and prior to resumption of plant operation.

A report of investigations conducted to determine cause(s) of the tube degradation and corrective measures taken to prevent recurrence shall be submitted within 90 days following completion of the startup test program.

HBRSEP Unit No. 2 5.0-32 Amendment No. 4;6 , 185 l

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each High Radiation Area in which the intensity of radiation is 1000 mRem/hour or less shall be barricaded and conspicuously posted by requiring issuance of a Radiation Work Permit (RWP).

Radiation control personnel or personnel escorted by radiation control personnel shall be exempt from the RWP issuance requirements during the performance of their assigned duties within the RCA, provided they comply with approved radiation protection procedures for entry into High Radiation Areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device provided for each individual that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c. An individual qualified as a radiation control technician with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the radiation control supervisor in the RWP.

(continued)

HBRSEP Unit No. 2 5.0-33 Amendment No. 176

High Radiation Area 5.7 5.7 High Radiation Area (continued) 5.7.2 The requirements of 5.7.1 shall apply to each High Radiation Area in which the intensity of radiation is greater than 1000 mRem/hour at 30 centimeters (12 inches) 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. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the SS on duty and/or the radiation control supervisor.

Entrance thereto shall also be controlled by requiring issuance of an RWP. The exemption from RWP issuance requirements discussed in 5.7.1 is not applicable for any High Radiation Area in which the intensity of radiation is greater than 1000 mRem/hour.

HBRSEP Unit No. 2 5.0-34 Amendment No. 176

APPENDIX B ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-23 Carolina Power & Ught Company (the term licensee in Appendix B refers to Carolina Power &

Light Company) shall comply with the following conditions on the schedules noted below:

Amendment Number Additional Conditions Implementation Date 176 The licensee Is authorized to relocate This amendment Is certain requirements included in effective immediately Appendix A and the former Appendix B to and shall be Implemented licensee-controlled documents. within 90 days of the date Implementation of this amendment shall of this amendment.

Include the relocation of these requirements to the appropriate documents, as described In the licensee's letters dated September 10, 1997, and October 13, 1997, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment.

Amendment No. -96, 200

NRC FORM 8C:

(794 RnCMD:3.

COVER SHEET FOR CORRESPONDENCE USE THIS COVER SHEET TO PROTECT ORIGINALS OF MULTI-PAGE CORRESPONDENCE

ML040990713

Text

3.2.3 APPLICABILITY

3.4.5 APPLICABILITY

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