Text

Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 2
	ML061140209
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Site:	Browns Ferry
Issue date:	05/04/2006
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	DIAZ-SANABRIA, Y /NRR/DLR/RLRA, 415-1594
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50-2601 IMPWROVED TECHNICAL SPECIFICATIONS Browns [erry :Nuclear Plant, Unit No. 2 (Volume l)

TECHNICAL SPECIFICATION REQUIREMENTS FOR BROWNS FERRY NUCLEAR PLANT UNIT 2

-ABLE OF CONTENTS section . Page No.

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) .................. ,.0-1

'2.1 SLs ........ ;.0o-1 2.2 SL Violations ......... ; 2.0-1 s3.0 LIMITING CONDITION FOR OPERATION (LCO)

APPLICABILITY............................................................-............ i...

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 Reactivity Anomalies .3.1-5 3.1.3 Control Rod OPERABILITY .3.1-7 3.1.4 Control Rod Scram Times. 3.1-12 3.1.5 Control Rod Scram Accumulators. 31-16 3.1.6 Rod Pattern Control. 3.1-20 3.1.7 Standby Liquid Control (SLC) System.3.1-23.

3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ..... 3.1-28 3 .2 POWER DISTRIBUTION LIMITS ......................................... 3.2-1 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ..................................... 3.2-1 3.2;2 MINIMUM CRITICAL POWER RATIO (MCPR) ...................... 3.2-3 1.2.3 LINEAR HEAT GENERATION RATE (LHGR) ..................... 3.:2-5 3.3 INSTRUMENTATION ..................................... 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation .............. 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation .................... 3.3-10 3.3.2.1 Control Rod Block Instrumentation ..................................... 3.3-16 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation ................................. 3.3;-22 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ................. 3.3-24 3.3.3.2 Backup Control System ............... 3.X-28

. 13FN-UNIT 2 i Amendment No. 253

Section Page No.

3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation............................................................... :3.3-30 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ........................ 3.3-33 3.3.5.1 Emergency Core Cooling System (ECCS)

Instrumentation............................................................... .3.3-36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation .3-49 3.3.6.1 Primary Containment Isolation Instrumentation .-. 353 3.3.6.2 Secondary Containment Isolation Instrumentation . .3-62 3.3.7.1 Control Room Emergency Ventilation (CREV)

System Instrumentation .3.3-66 3.3.8.1 Loss of Power (LOP) Instrumentation .3.3-71 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring....................................................................... 3.3-76 3.4 REACTOR COOLANT SYSTEM (RCS). 3.4-1 3.4.1 Recirculation Loops Operating .3.4-1 3.4.2 Jet Pumps .3.4-5 3.4.3 Safety/Relief Valves (SIRVs) .3.4-7 3.4.4 RCS Operational LEAKAGE .3.4-9 3.4.5. RCS Leakage Detection Instrumentation .3.4-12 3.4.6 RCS Specific Activity.................. 3.4-15 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown .3.4-18 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown .3.4-21 3.4.9 RCS Pressure and Temperature (PIT) Limits. 3.-24

.4.10 Reactor Steam Dome Pressure .3.4-30 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM ....................................................................... 3.5-1 3.5.1 ECCS - Operating.3.5-1 3.5.2 ECCS - Shutdown. ;. 3.5-8 3.5.3 RCIC System .3.5-12 EIFN-UNIT 2 ii Amendment No. 253

'Section Paae No.

_.6 CONTAINMENT SYSTEMS ................................... :3.6-1 3.6.1.1 Primary Containment ................................ .3.6-1 3.6.1.2 Primary Containment Air Lock ................................ 3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs) .......................3.6-9 3.6.1.4 Drywell Air Temperature ................. '.6-17 3.6.1.5 Reactor Building-to-Suppression Chamber Vacuum Breakers ............. 3.6-19 3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ........... 2. .6-22 3.6.2.1 Suppression Pool Average Temperature ............................. 3.6-24 3.6.2.2 Suppression Pool Water Level ...................................... 3.6-29 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ...................................... 3.6-31 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ...................................... 3.6-34 3.6.2.5 Residual Heat Removal (RHR) Drywell Spray ..................... 3.6-36 3.6.2.6 Drywell-to-Suppression Chamber Differential Pressure ....... 3.6-38 3.6.3.1 Containment Atmosphere Dilution (CAD) System ................ 3.6-40 3.6.3.2 Primary Containment Oxygen Concentration ....................... 3.6-42 3.6.4.1 Secondary Containment ............... . 3.6-44 3.6.4.2 Secondary Containment Isolation Valves ?SCIVs) ............... 3.1-47 3.6.4.3 Standby Gas Treatment (SGT) System ................................. 3.6-51 3.7 PLANT SYSTEMS ..................................... 3. 7-1 3.7.1 Residual Heat Removal Service Water (RHRSW)

System and Ultimate Heat Sink (mls). .. ;,,,, 3.7-1 3.7.2 Emergency Equipment Cooling Water (EECW)

System and Ultimate Heat Sink (UHS) ........................... 3.7-7 3.7.3 Control Room Emergency Ventilation (CREV) System ........ 3.7-9 3.7.4 Control Room Air Conditioning (AC) System ........... ............. 3.7-13 3.7.5 Main Turbine Bypass System ........................................ 3.7-17 3.7.6 Spent Fuel Storage Pool Water Level ................................... 3.7-19 3.1B ELECTRICAL POWER SYSTEMS ........................................ 3.8-1 3.B.1 AC Sources - Operating ........................................ 3.8-1 3.B.2 AC Sources - Shutdown ........................................ 3.8-14 3.B.3 Diesel Fuel Oil, Lube Oil, and Starting Air ........................... 3.8-19 3.B.4 DC Sources - Operating ........................................ 3.8-22 3.B.5 DC Sources - Shutdown ........................................ 3.8-26 3.B.6 Battery Cell Parameters ........................................ 3.8-29 3.B.7 Distribution Systems - Operating ........................................ 3.8.33 3.B.8 Distribution Systems - Shutdown ........................................ 3.8-39 Bl:N-UNIT 2 iii Amendment No.-26a 263 MAR 1 4 20'0

"-;ection Page N o.

3.9 REFUELING REFELNGOPERATIONS.39-1 PEATINS........................................3.9-1. . .. .

3.9.1 Refueling Equipment Interlocks ........................................ 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock................................ 9-3 3.9.3 Control Rod Position ........................................ 3.9-5 3.9.4 Control Rod Position Indication ........................................ 3.9-7 3.9.5 Control Rod OPERABILITY - Refueling ................................ 3.9-10 3.9.6 Reactor Pressure Vessel (RPV) Water Level ......... ............. 3.9-12 3.9.7 Residual Heat Removal (RHR) -'High Water Level ....... ...... 3.9-14 3.9.8 Residual Heat Removal (RHR) - Low Water Level ....... ....... 3.9-18 3.10 SPECIAL OPERATIONS.....3.10-1 SPEIALOPEATINS......................................:3.10-1.. .. .

3.10.1 Inservice Leak and Hydrostatic Testing Operation ....... ....... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ................................ 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown ......... ......... 3.10-7 3.10.4 Single Control Rod Withdrawal - Cold Shutdown ................. 3.10-10 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ......... 3.10-14 3.10.6 Multiple Control Rod Withdrawal - Refueling ....................... 3.10-17 3.10.7 Control Rod Testing - Operating ...................................... 3.10-20 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling ......... .......... 3.10-22 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 ...................................... 4.0-2 5.0 ADMINISTRATIVE CONTROLS ....................... -1

.5.1' Responsibility ................................................................. t.. 511A1........

5.2 Organization..............................................I............................... 5.CI-2 5.3 Unit Staff Qualifications ...................................... 5.0-8 5.4 Procedures ................................................ ................................ 5.0-7 5.5 Programs and Manuals ...................................... 5.0-8 5.6. Reporting Requirements ...................................... 5.0-22 5.7 High Radiation Area ...................................... 5.0-26 E FN-U NIT 2 iv Amendment No. 253

BROWNS FERRY NUCLEAR PLANT TECHNICAL SPECIFICATIONS (REQUIREMENTS)

LIST OF FIGURES Figure Page No.

Figure 3.1.7-1 ....... ;3.1-27 Figure 3.4.1-1 ........ .3.4-4 Figure 3.4.9-1 ............ 3.4-29 Figure 3.7.1-1 ....... 7-6 BFN-UNIT 2 v Amendment No. 253, 263 l1' 2ala

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

- ~NOTE The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

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

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shadl include the CHANNEL FUNCTIONAL TEST.

Non-calibratable devices are excluded from this requirement, but will be included in CHANNEL FUNCTIONAL TESTS and source checks. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

(continued)

EFN-UNIT 2 1 .1-1 Amendment ND. 253

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

CORE 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. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);

and

b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

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

(continued)

[3FN-UNIT 2 1.1-2 Amendment No. 253

Definitions 1.1 1.1 Definitions (continued) 0ORE OPERATING LIMITS The COLR is the unit specific document that provides REPORT (COLR) cycle specific parameter limits for the current reload cycle. These cycle specific 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 1-131 DOSE EQUIVALENT 1-131 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, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table Ill of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites."

(conminued) 13FN-UNIT 2 1.1-3 Amendment No. 253

Definitions 1.1 1.1 Definitions (continued)

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;

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

LINEAR HEAT The LHGR shall be the heat generation rate per unit GENERATION RATE length of fuel rod. It is the integral of the heat flux (LHGR) over the heat transfer area associated with the unit length.

(continued)

B3FN-UNIT 2 1.1-4 Amendment No. 253

Definitions 1.1 1;1 Definitions (continued)

LOGIC SYSTEM A LOGIC SYSTEM FUNCTIONAL TEST shall be a FUNCTIONAL TEST test of all required logic components (i.e., all required relays and contacts, trip units, solid state logic:

elements, etc.) of a logic circuit, from as close to the sensor as practicable up to,. but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic syste!mis tested.

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

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

OPERABLE - OPERABILITY, A system, subsystem, division,, 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, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

(continued) 13FN-UNIT 2 1.1-5 Amendment No. 253

Definitions 1.1 1.1 Definitions (continued)

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a. Described in Section 13.10, Refueling Test Program; of the FSAR;

b. Authorized under the provisions of 10 CF:R 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to (RTP) the reactor coolant of 3458 MWt. I SHUTDOWN MARGIN SDM shall be the amount of reactivity by which the (SDM) reactor is subcritical or would be subcritical assuming that:

'a. The reactor is xenon free;

b. The moderator temperature is 681F; and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn. With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDIA.

(continued)

ElFN-UNIT 2 1.1-6 Amendment No. 254

^ . ' :. .-. -:,

Definitions 1.1

1.1 Definitions (continued)

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.

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

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

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

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

BFN-UNIT 2 1.1-7 Amendment No. 253

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

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

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

E;FN-UNIT 2 1.1-8 Amendment No. 253

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 indentions of the logical connectors.

When logical connectors are used to state a C6ndition, 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)

BFN-UNIT 2 1.2-1 Amendment No. 253

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)

EFN-UNIT 2 1.2-2 Amendment No. 253

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 altermative 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 pcsition 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.

.13FN-UNIT 2 1.2-3 Amendment No. 253

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.

13ACKGROUND 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 Times(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 LGO 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.

(continued) 13FN-UNIT 2 1.3-1 Amendment No. 253

Completion Times 1.3 1.3 Completion Times DESCRIPTION Once a Condition has been entered, subsequent divisions, (continued) 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.

However, when a subsequent division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours1 days 0.143 weeks 0.0329 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 division, 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.

(continued) 13FN-UNIT 2 1.3-2 Amendment No. 253

Completion Times 1.3 1.3 Completion Times DESCRIPTION The above Completion Time extension does not apply to a (continued) Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours0.333 days 0.0476 weeks 0.011 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 Condition A and B in Example 1.3-3 may not be extended.

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. 12 hours0.5 days 0.0714 weeks 0.0164 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months 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.

(continued)

.BFN-UNIT 2 1.3-3 Amendment No. 253

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-1 (continued)

The Required Actions of Condition B are to be in MODE 3 within 12 hours0.5 days 0.0714 weeks 0.0164 months AND in MODE 4 within 36 hours1.5 days 0.214 weeks 0.0493 months . A total of 12 hours0.5 days 0.0714 weeks 0.0164 months is allowed for reaching MODE 3 and a total of 36 hours1.5 days 0.214 weeks 0.0493 months (not 48 hours2 days 0.286 weeks 0.0658 months ) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours0.25 days 0.0357 weeks 0.00822 months , the time allowed for reaching MODE 4 is the next 30 hours1.25 days 0.179 weeks 0.0411 months because the total time allowed for reaching MODE 4 is 36 hours1.5 days 0.214 weeks 0.0493 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours1.5 days 0.214 weeks 0.0493 months .

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump 7 days inoperable. to OPERABLE status.

- B. Required B.1 Be in 12 hours0.5 days 0.0714 weeks 0.0164 months Action and MODE 3.

associated Completion AND Time not met.

B.2 Be in 36 hours1.5 days 0.214 weeks 0.0493 months MODE 4.

a a -

(continued)

EIFN-UNIT 2 1.3-4 Amendment No. 253

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

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 pLImp.

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 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.

(conlinued)

EIFN-UNIT 2 1.3-5 Amendment No. 253

Completion Times 1.3 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 subsystem subsystem to AND inoperable. OPERABLE status. 10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours3 days 0.429 weeks 0.0986 months Function Y Function Y subsystem subsystem to AND, inoperable. OPERABLE status. 10 days from discovery of failure to meet the LCO (continued) 13FN-UNIT 2 1.3-6 Amendment No. 253

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One C.1 Restore 12 hours0.5 days 0.0714 weeks 0.0164 months Function X Function X subsystem subsystem to inoperable. OPERABLE status.

AND OR One C.2 Restore 12 hours0.5 days 0.0714 weeks 0.0164 months Function Y Function Y subsystem subsystem to inoperable. OPERABLE status.

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

(continued)

EIFN-UNIT 2 1.3-7 Amendment No. 253

Completion Times 1.3 1.3 Completion Times

[EXAMPLES EXAMPLE 1.3-3 (continued)

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 subsystem 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) 13FN-UNIT 2 1.3-8 Amendment No. 253

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore 4 hours0.167 days 0.0238 weeks 0.00548 months valves valve(s) to inoperable. OPERABLE status.

B. Required B.1 Be in 12 hours0.5 days 0.0714 weeks 0.0164 months Action and MODE 3.

associated Completion AND Time not met.

B.2 Be in 36 hours1.5 days 0.214 weeks 0.0493 months MODE 4.

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 (continued)

EIFN-UNIT 2 1.3-9 Amendment No. 253

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

OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours0.167 days 0.0238 weeks 0.00548 months provided this does not result in any subsequent valve being inoperable for > 4 hours0.167 days 0.0238 weeks 0.00548 months .

If the Completion Time of 4 hours0.167 days 0.0238 weeks 0.00548 months (plus the extensionsl expires while one or more valves are still.inoperable,.Conditiori B is entered.

EXAMPLE 1.3-5 ACTIONS NOTE Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve 4 hours0.167 days 0.0238 weeks 0.00548 months valves to inoperable. OPERABLE status.

B. Required B.1 Be in 12 hours0.5 days 0.0714 weeks 0.0164 months Action and MODE 3.

associated Completion AND Time not met.

B.2 Be in 36 hours1.5 days 0.214 weeks 0.0493 months MODE 4.

(continued) 13FN-UNIT 2 1.3-1 0 Amendment No. 253

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

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.

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.

(continued) 13FN-UNIT 2 1.3-11 Amendment No. 253

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per 8 hours0.333 days 0.0476 weeks 0.011 months inoperable. SR 3.x.x.x.

OR A.2 Place 8 hours0.333 days 0.0476 weeks 0.011 months channel in

- trip.

B. Required - B.1 Be in 12 hours0.5 days 0.0714 weeks 0.0164 months Action and MODE 3.

associated Completion Time not met.

(continued)

ElFN-UNIT 2 1.3-12 Amendment No. 253

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 pear" 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 hours0.333 days 0.0476 weeks 0.011 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) 13FN-UNIT 2 1.3-13 Amendment No. 253

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem affected inoperable. subsystem AND isolated.

Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND A.2 Restore 72 hours3 days 0.429 weeks 0.0986 months subsystem, to OPERABLE status.

B. Required B.1 Be in 12 hours0.5 days 0.0714 weeks 0.0164 months Action and MODE 3.

associated Completion AND Time not met.

B.2 Be in 36 hours1.5 days 0.214 weeks 0.0493 months MODE 4..

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 "Orhce per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter" interval begins upon performance of Required Action A.1.

(continued)

.ElFN-UNIT 2 1.3-14 Amendment No. 253

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

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 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.

E3FN-UNIT 2 1.3-15 Amendment Nlo. 253

Frequency 1.4 1.() USE AND APPLICATION 1.4 Frequency s

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 Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both. I 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.

(continued)

BFN-UNIT 2 1.4-1 Amendment No 2It~53 ,2,I 266

Frequency 1.4 1.4 Frequency DESCRIPTION The use of "met" or "performed" in these instances conveys (continued) specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria. Some Surveillances contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

a. The Surveillance is not required to be met in the MODE-. or other specified condition to be entered; or

b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed

.within the specified Frequency (i.e;, it is current) and is known not to be failed; or

c. The Surveillance is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed.

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discusses these special situations.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3.

(continued)

BFNq-UNIT 2 1.4-2 Amendment No. 2i 266 IL. .l - ..

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours0.5 days 0.0714 weeks 0.0164 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 hours0.5 days 0.0714 weeks 0.0164 months , an extension of the time interval to 1.25 times the interval specified in the 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 Examples 1.4-3 and 1.4-4), 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)

BFN-UNIT 2 1.4-3 Amendment No. 253; 266

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2

.(continued)

SURVEILLANCE REQUIREMENTS :

SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours0.5 days 0.0714 weeks 0.0164 months after

Ž25% RTP AND 24 hours1 days 0.143 weeks 0.0329 months thereafter Example 1.4-2 has two Frequencies. The first is a one tirrie 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 < 25% RTP to Ž 25% RTP, the Surveillance must be performed within 12 hours0.5 days 0.0714 weeks 0.0164 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 extension allowed by SR 3.0.2.

"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

(continued)

BFN-UNIT 2 1.4-4 Amendment N~o.253, 266

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after Ž 25% RTP.

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

< 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours0.5 days 0.0714 weeks 0.0164 months after power reaches Ž 25% RTP to perform the Surveillance. The Surveillance is still considered to be 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 hours0.5 days 0.0714 weeks 0.0164 months with power Ž 25% RTP.

Once the unit reaches 25% RTP, 12 hours0.5 days 0.0714 weeks 0.0164 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.

(continued)

BFN-UNIT 2 1.4-5 Amendment No. I2' 266 TJ." 1 br , ~,,-_

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-4 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1.

Verify: leakage rates are within limits. 24 hours1 days 0.143 weeks 0.0329 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unitis in MODE 1.

The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance.

Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (plus the extension allowed by SR 3.0.2) interval, but the unit was not in MODE 1,there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SFR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE I (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 woulc' require satisfying the SR.

(continued)

BFN-UNIT 2 1 .4-6 Amendment No.. 25I . 266 I i-..!

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-5 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be performed in MODE 1.

Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1,2, or 3 (the assumed Applicability of the associated LCO) between performances.

As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1.

Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1,it would not constitute a fai lure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1.

Once the unit reaches MODE 1,the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance were not performed prior to (continued)

BFN-UNIT 2 1 .4-7 Amendment No. 266

hv. ram not

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-5 (continued) entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be met in MODE 3.

Verify parameter is within limits. 24 hours1 days 0.143 weeks 0.0329 months Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However,' the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance.

Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the S;R nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met),

SR 3.0.4 would require satisfying the SR.

BF'N-UNIT 2 1.4-8 Amendment No. 266 I- I .. .. )

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow

<10% rated core flow:

THERMAL POWER shall be <25% RTP.

2.1.1.2 With the reactor steam dome pressure Ž 785 psig and core flow

Ž 10% rated core flow:

MCPR shall be 21.08 for two recirculation loop operation orŽ21.10 l for single loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hours0.0833 days 0.0119 weeks 0.00274 months :

2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

BF1N-UNIT 2 2.0-1 Amendment No. 2 5 3 , 2 56, 2 7 -0 280

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

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.

LC O 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 2 within 10 hours0.417 days 0.0595 weeks 0.0137 months ; l

b. MODE 3 within 13 hours0.542 days 0.0774 weeks 0.0178 months ; and

c. MODE 4 within 37 hours1.542 days 0.22 weeks 0.0507 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, and 3.

(continued)

BFN-UNIT 2 3.0-1 Amendment No. 2 53 r 266

,,FiZ', ff ;:.--

LCO Applicability 3.0 3.0 LCO APPLICABILITY (continued)

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. Inthis event, an evaluation shall be performed in accordance with Specification 5.5.11, "Safety Function Determination Program (SFDP)." If a loss of safety function is (continued)

BFN-UNIT 2 3.0-2 Amendment No. 25&3 286

LCO Applicability 3.0 3.0 LCO APPLICABILITY I-CO 3.0.6 determined to exist by this program, the appropriate Conditions (continued) 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 applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

I.CO 3.0.7 Special Operations LCOs in Section 3.10 allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged.

Compliance with Special Operations LCOs is optional. When a Special Operations LCO is desired to be met but is not met, the ACTIONS of the Special Operations LCO shall be met. When a Special Operations LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.

a -

13FN-UNIT 2 3.0-3 Amendment No. 253

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 perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above Interval extension does not apply. If a Completion Time requires periodic performance on a "once per. . ." basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours1 days 0.143 weeks 0.0329 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours1 days 0.143 weeks 0.0329 months and the risk impact shall be managed.

(continued)

BFN-UNIT 2 3.0-4 Amendment No. 2637 278

SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.3 If the Surveillance is not performed within the delay period, the (continued) LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances, have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

BFN-UNIT 2 3.0-5 Amendment No. 2;3T 286

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: MODES 1, 2, 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits in A.1 Restore SDM to within 6 hours0.25 days 0.0357 weeks 0.00822 months MODE 1 or 2. limits.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A not met.

C. SDM not within limits in C.1 Initiate action to fully Immediately MODE 3. insert all insertable control rods.

D. SDM not within limits in D.I Initiate action to fully Immediately

. MODE 4. insert all insertable control rods.

AND

_ (continued)

'BFN-UNIT 2 3.1 -1 Amendment No. 253

SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) D.2 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment to OPERABLE status.

AND D.3 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months two standby gas treatment (SGT) subsystems to OPERABLE status.

AND D.4 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolation capability in each required secondary containment penetration flow path not isolated.

E. SDM not within limits in. E.1 Suspend CORE Immediately MODE 5. ALTERATIONS except for control rod insertion and fuel assembly removal.

AND E.2 Initiate action to fully Immediately.

insert all insertable control rods in core cells containing one or more fuel assemblies.

AND

._ (continued) 13FN-UNIT 2 3.1-2 Amendment No. 253

SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. (continued) E.3 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment to OPERABLE status.

AND E.4 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months two SGT subsystems to OPERABLE status.

AND E.5 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolation capability in each required secondary containment penetration flow path not isolated.

BFN-UNIT 2 3.1-3 Amendment No. 253

SDM 3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is within the limits provided in the Prior to each in COLR. vessel fuel movement during fuel loading sequence AND Once within 4 hours0.167 days 0.0238 weeks 0.00548 months sifter criticality following fuel movement within the reactor pressure vessel or control rod replacement 13FN-UNIT 2 3.1-4 Amendment No. 253

Reactivity Anomalies 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 The reactivity difference between the actual critical rod configuration and the expected configuration shall be within +/- 1%

Ak/k.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity difference A.1 Restore core reactivity 72 hours3 days 0.429 weeks 0.0986 months not within limit. difference to within limit.

B. Required Action and B.1 Be in MODE 2. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met.

I __ ____ ____ ____ __.

B3FNUNIT 2 3.1-5 Amendment No. 253

Reactivity Anomalies 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify core reactivity difference between the Once within actual critical rod configuration and the 24 hours1 days 0.143 weeks 0.0329 months after expected configuration is within i 1% Ak/k. reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AND 1000 MWFDIT thereafter during operation in MODE 1 BFN-UNIT 2 3.1-6 Amendment No. 253

Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 36.1.3 Control Rod OPERABILITY L.CO 3.1.3 Each control rod shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS NOTE Separate Condition entry is allowed for each control rod.

CONDITION REQUIRED ACTION COMPLETION TIME A. One withdrawn control NOTE rod stuck. Rod worth minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation," if required, to allow continued operation.

A.1 Verify stuck control rod Immediately separation criteria are met.

AND A.2' Disarm the associated 2 hours0.0833 days 0.0119 weeks 0.00274 months control rod drive (CRD).

AND (continued)

BFN-UNIT 2 3.1-7 Amendment No. 253

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Perform SR 3.1.3.2 and 24 hours1 days 0.143 weeks 0.0329 months from SR 3.1.3.3 for each discover/ of withdrawn OPERABLE Condition A control rod. concurrent with THERMAL POWER greater than the low power setpoint (LPSP) oF the RWM AND A.4 Perform SR 3.1.1.1. 72 hours3 days 0.429 weeks 0.0986 months B. Two or more withdrawn B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months control rods stuck.

C. One or more control rods C.1 NOTE inoperable for reasons RWM may be bypassed other than Condition A or as allowed by B. LCO 3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.

Fully insert inoperable 3 hours0.125 days 0.0179 weeks 0.00411 months control rod.

AND C.2 Disarm the associated 4 hours0.167 days 0.0238 weeks 0.00548 months CRD.

(continued)

BFN-UNIT 2 3.1-8 Amendment No. 253

Control Rod OPERABILITY 3.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. -N NOTE D.1 Restore compliance with 4 hours0.167 days 0.0238 weeks 0.00548 months Not applicable when BPWS.

THERMAL POWER

> 10% RTP. OR D.2 Restore control rod to 4 hours0.167 days 0.0238 weeks 0.00548 months Two or more inoperable OPERABLE status.

control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods.

E. Required Action and E.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A, C, or D not met.

OR Nine or more control rods inoperable.

ElFN-UNIT 2 3.1-9 Amendment No. 253

Control Rod OPERABILITY 3.1.3

("I IDI;:II I tKurfr DI2Fl ll~r2FAIFNTQt SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod. 24 hours1 days 0.143 weeks 0.0329 months SR 3.1.3.2 NOTE Not required to be performed until 7 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

Insert each fully withdrawn control rod at 7 days least one notch.

SR 3.1.3.3 NOTE Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

Insert each partially withdrawn control rod at 31 days least one notch.

SR 3.1.3.4 Verify each control rod scram time from fully In accordance withdrawn to notch position 06 is

7 with SR 3.1.4.1, seconds. SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 (continued)

ElFN-UNIT 2 3.1-10 Amendment No. 253

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE I FREQUENCY i

SR 3.1.3.5 Verify each control rod does not go to the Each time the withdrawn overtravel position. control rod is withdrawn to "full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could aff3ct coupling I

BFN-UNIT 2 3.1-11 Amendment No. 253

Control Rod Scram Times 3.1.4 3:1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4 a. No more than 13 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1; and

b. No more than 2 OPERABLE control rods that are "slov/n shall occupy adjacent locations.

APPLICABILITY: MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.. Requirements of the LCO A.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months not met.v.

13FN-UNIT 2 3.1-12 Amendment No. 253

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS

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

During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

.

SURVEILLANCE FREQUENCY S R 3.1.4.1 Verify each control rod scram time is within Prior to the limits of Table 3.1.4-1 with reactor steam exceeding dome pressure 2 800 psig. 40% RTP after each reactor shutdown

-120 days SR 3.1.4.2 Verify, for a representative sample, each 200 days 'I tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam operation in dome pressure 2 800 psig. MODE 1 (continued)

BFN-UNIT 2 3.1-13 Amendment No. 253,2 26, 295

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.3 Verify for each affected control rod scram Prior to declaring time is within the limits of Table 3.1.4-1 with control rod any reactor steam dome pressure. OPERABLE: after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is Prior to within the limits of Table-3.1.4-1 with reactor exceeding steam dome pressure Ž 800 psig. 40% RTP after fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time BF N-UNIT 2 3.1-14 Amendment No.E2537 266

'. ,,X!; , -,_

Control Rod Scram Times 3.1.4 Table 3.1.4-1 (page 1 of 1)

Control Rod Scram Times

- NOTES

1. OPERABLE control rods with scram times not within the limits of this Table are considered "slow."

,2. Enter applicable Conditions and Required Actions of LCO 3.1.3, "Control Rod OPERABILITY," for control rods with scram times > 7 seconds to notch position 06.

These control rods are inoperable, in accordance with SR 3.1.3.4, and are not considered "slow."

SCRAM TIMES(a)(b)

(seconds)

NOTCH POSITION REACTOR STEAM DOME PRESSURE

> 800 psig

_I 46 0.45 36 1.08 26 1.84 06 3.36

- I -

(a) Maximum scram time from fully withdrawn position, based on de-energizaticn of scram pilot valve solenoids at time zero.

(b) Scram times as a function of reactor steam dome pressure, when < 800 psig are.

within established-limits.

13FN-UNIT 2 3.1-15 Amendment No. 253

Control Rod Scram Accumulators 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3-.1.5 Control Rod Scram Accumulators L.CO 3.1.5 Each control rod scram accumulator shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS i - u I--

separate Condition entry is allowed for each control rod scram accumulator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One control rod scram A.1 NOTE accumulator inoperable Only applicable if the with reactor steam dome associated control rod pressure Ž 900 psig. scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the associated 8 hours0.333 days 0.0476 weeks 0.011 months control rod scram time "slow."

OR.

A.2 Declare the associated 8 hours0.333 days 0.0476 weeks 0.011 months control rod inoperable.

(conlinued)

ElFN-UNIT 2 3.1-16 Amendment No. 253

Control Rod Scram Accumulators 3.1.5 B. Two or more control rod B.1 Restore charging water 20 minutes from scram accumulators header pressure to > 940 discovery of inoperable with reactor psig. Condition B steam dome pressure concurrent. with 2 900 psig. charging water header pressure

< 940 psig AND B.2.1 NOTE Only applicable if the associated control rod scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rod scram time "slow."

OR B.2.2 Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rod inoperable.

(continued)

BFN-UNIT 2 3.1-17 Amendment No. 253

Control Rod Scram Acc-mulators 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control rod C.1 Verify all control rods Immediately upon scram accumulators associated with discovery of inoperable with reactor inoperable accumulators charging water steam dome pressure' are fully inserted. header pressure

< 900 psig. < 940 psig AND C.2 Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rod inoperable.

D. Required Action and D.1 NOTE.

associated Completion Not applicable if all Time of Required Action -inoperable control rod B.1 or C.1 not met. scram accumulators are associated with fully inserted control rods.

Place the reactor mode Immediately switch in the shutdown position.

U. .

BFN-UNIT 2 3.1-18 Amendment No. 253

Control Rod Scram Accumulators 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator 7 days pressure is > 940 psig. I.

S --

13FN-UNIT 2 3.1-19 Amendment No. 253

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

APPLICABILITY: MODES 1 and 2 with THERMAL POWER <10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLEITION TIME A. One or more OPERABLE A.1 -NOTE control rods not in Rod worth minimizer compliance with BPWS. (RWM) may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation."

Move associated control 8 hours0.333 days 0.0476 weeks 0.011 months rod(s) to correct position.

OR A.2 Declare associated 8 hours0.333 days 0.0476 weeks 0.011 months control rod(s) inoperable.

(con:inued)

[3FN-UNIT 2 3.1-20 Amendment No. 253

Rod Pattern Control 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Nine or more OPERABLE B.1 N NOTE control rods not in Rod worth minimizer compliance with BPWS. (RWM) may be bypassed as allowed by LCO 3.3.2.1.

Suspend withdrawal-of Immediately control rods.

AND B.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

S -

13FN-UNIT 2 3.1-21 Amendment No. 253

Rod Pattern Control 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply with 24 hours1 days 0.143 weeks 0.0329 months BPWS.

I .__ _. __ _ . , _ __ __

ElFN-UNIT 2 3.1-22 Amendment No. 253

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCC 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

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

B. Two SLC subsystems B.1 Restore one SLC 8 hours0.333 days 0.0476 weeks 0.011 months inoperable. subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met.

AND C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months BFN-UJNIT 2 3.1-23 Amendment No. 2R, :290

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate 24 hours1 days 0.143 weeks 0.0329 months solution (SPB) is 24000 gallons.

SR 3.1.7.2 Verify continuity of explosive charge. 31 days SR 3.1.7.3 Verify the SPB concentration is > 8.0% by 31 days weight.

AND Once within 24 hours1 days 0.143 weeks 0.0329 months after water or bo ron is added to solution SR 3.1.7.4 Verify the SPB concentration is

9.2% by 31 days weight.

AND Once within 24 hours1 days 0.143 weeks 0.0329 months after water or boron is added to solution OR (continued)

BFN-LJNIT 2 3.1-24 Amendment No. 2W, 290

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

+

Verify the concentration and temperature of Once within boron in solution are within the limits of 8 hours0.333 days 0.0476 weeks 0.011 months aiter Figure 3.1.7-1. discovery that SPB concentration is

> 9.2% by weight AND 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter SR 3.1.7.5 Verify the minimum quantity of Boron-10 in the 31 days SLC solution tank and available for injection is 2 186 pounds.

SR 3.1.7.6 Verify the SLC conditions satisfy the following 31 days equation:

AND (C )( Q)( E )

(13,wt. %)(86 gpm)(19.8 atom%) Once within 24 hours1 days 0.143 weeks 0.0329 months alter

-water or boron is where, added to the solution C = sodium pentaborate solution concentration (weight percent)

Q = pump flow rate (gpm)

E = Boron-1 0 enrichment (atom percent Boron-1 0)

SR 3.1.7.7 Verify each pump develops a flow rate 2 39 24 months gpm at a discharge pressure > 1325 psig.

(continued)

BFN-UNIT 2 3.1-25 Amendment No. 2H, 290

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.8 Verify flow through one SLC subsystem from 24 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS So 3.1.7.9 Verify all piping between storage tank and 24 months pump suction is unblocked.

SR 3.1.7.10 Verify sodium pentaborate enrichment is within 24 months the limits established by SR 3.1.7.6 by calculating within 24 hours1 days 0.143 weeks 0.0329 months and verifying by AND analysis within 30 days.

After addition to SLC tank SR 3.1.7.11 Verify each SLC subsystem 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, or can be aligned to the correct position.

_ =

BFN-UNIT 2 3.1-26 Amendment No. , 290

Sl-C System 3.1.7 130 120 110

_ I _ 1 _

=-~ACCEPTABLEA

. ' Plavidcd ethcrour; A \

_ ~100 M 90 w 80 2:

i_ 70 = = ,AJ ACCEP AB 60 50 40

. U .5 U- jU 1: :0 2) .3U CONCENTRATION

{Weight Percent Sodium Pentaborate in Solution)

Figure 3.1.7-1 Sodium Pentaborate Solution Temperature Versus Concentration Requirements 13FN-UNIT 2 3.1 -27 Amendment No. 253

SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves LCO 3.1.8 Each SDV vent and .drain valve shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

--- ax----------NOTES -------------------------------------------

I. Separate Condition entry is allowed for each SDV vent and drain line.

2. An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent or A.1 Isolate the associated 7 days drain lines with one valve line.

inoperable.

B. One or more SDV vent or B.1 Isolate the associated 8 hours0.333 days 0.0476 weeks 0.011 months drain lines with both line.

valves inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met.

BFN-UNIT 2 3.1-28 Amendment No. 2-637 285 l

SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 ---------------------- NOTE --------------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. 31 days SR 3.1.8.2 Cycle each SDV vent and drain valve to the 92 days fully closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months

a. Closes in < 60 seconds after receipt of an actual or simulated scram signal; and

b. Opens when the actual or simulated scram signal is reset.

BFN-UNIT 2 3.1-29 Amendment No. 255 November 30, 1998

APLHGR 3.2.1

3.2 POWER DISTRIBUTION LIMITS

3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

I-CO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER > 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours0.0833 days 0.0119 weeks 0.00274 months limits. within limits.

B. Required Action and B.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion POWER to < 25% RTP.

Time not met.

13FN-UNIT 2 3.2-1 Amendment No. 253

APLHGR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal to Once within the limits specified in the COLR. 12 hours0.5 days 0.0714 weeks 0.0164 months after 2 25% RTP AND 24 hours1 days 0.143 weeks 0.0329 months thereafter BFN-UNIT 2 3.2-2 Amendment No. 253

MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

APPLICABILITY: THERMAL POWER Ž 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours0.0833 days 0.0119 weeks 0.00274 months limits. within limits.

B. Required Action and B.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion POWER to < 25% RTP.

Time not met.

BFN-UNIT 2 3.2-3 Amendment No. 253

MCPR 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to Once within the limits specified in the COLR. 12 hours0.5 days 0.0714 weeks 0.0164 months after

Ž 25% RTP AND 24 hours1 days 0.143 weeks 0.0329 months thereafter SR 3.2.2.2 Determine the MCPR limits. Once within 72 hours3 days 0.429 weeks 0.0986 months after each completion of SR 3.1.4.1 AND Once within 72 hours3 days 0.429 weeks 0.0986 months after each completion of SR 3.1.4.2 13FN-UNIT 2 3.2-4 Amendment No. 253

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER >25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to 2 hours0.0833 days 0.0119 weeks 0.00274 months limits. within limits.

B. Required Action and B.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion POWER to < 25% RTP.

Time not met.

13FN-UNIT 2 3.2-5 Amendment No. 253

LHGR 3.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the Once within limits specified in the COLR. 12 hours0.5 days 0.0714 weeks 0.0164 months after 2 25% RTP AND 24 hours1 days 0.143 weeks 0.0329 months thereafter EHFN-UNIT 2 3.2-6 Amendment No. 253

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3. 1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS

_-- - t e---------------------------- ----- ---- -

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours0.5 days 0.0714 weeks 0.0164 months channels inoperable.

OR A.2 -------------NOTE-------------

Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

Place associated trip 12 hours0.5 days 0.0714 weeks 0.0164 months system in trip.

(continued)

BFN-UNIT 2 3.3-1 Amendment No. 258 March 05, 1999

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.-NOTE-B.1 Place channel in one trip 6 hours0.25 days 0.0357 weeks 0.00822 months Not applicable for system in trip.

Functions 2.a, 2.b, 2.c, 2.d, or 2.f. OR B.2 Place one trip system in 6 hours0.25 days 0.0357 weeks 0.00822 months One or more Functions trip.

with one or more required channels inoperable in both trip systems.

C. One or more Functions C.1 Restore RPS trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with RPS trip capability capability.

not maintained.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, B, or Table 3.3.1.1-1 for the C not met. channel.

E. As required by Required E.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months Action D.1 and POWER to < 30% RTP.

referenced in Table 3.3.1.1-1.

F. As required by Required F.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months Action D.1 and referenced in Table 3.3.1.1-1.

(continued)

BFN-UNIT 2 3.3-2 Amendment No. 258 March 05, 1999

RPS Instrumentation 3.3.' .1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by Required H.1 Initiate action to fully. Immediately Action D.1 and insert all insertable referenced in control rods in core cells Table 3.3.1.1-1. containing one or more fuel assemblies.

I. As required by Required 1.1 Initiate alternate method 12 hours0.5 days 0.0714 weeks 0.0164 months Action D.1 and to detect and suppress referenced in Table thermal hydraulic 3.3.1.1-1. instability oscillations.

J. Required Action and J.1 Be in Mode 2. 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion Time of Condition I not met.

BFN-UNIT 2 3.3-3 Amendment No. 2587 273 JUL 26 X

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS NOTES

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Func~tion.

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

SURVEILLANCE FREQU'ENCY SR 3.3.1.1.1 Perform CHANNEL CHECK 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.1.1.2 NOTE Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after THERMAL POWER 25% RTP..

Verify the absolute difference between the 7 days average power range monitor (APRM) channels and the calculated power is

2% RTP while operating at ; 25% RTP.

SR 3.3.1.1.3 NOTE Not required to be performed when entering MODE 2 from MODE I until 12 hours0.5 days 0.0714 weeks 0.0164 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days (continued)

EIFN-UNIT 2 3.3-4 Amendment No. 253

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. 7 days SR 3.3.1.1.5 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels withdrawing overlap. SRMs from the fully inserted position SR 3.3.1.1.6 NOTE Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap. 7 days SR 3.3.1.1.7 Calibrate the local power range monitors. 1000 MWDIT average core exposure SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.1.1.9 NOTES

1. Neutron detectors are excluded.

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

Perform CHANNEL CALIBRATION. 92 days (continued)

BFN-U NIT 2 3.3-5 Amendment No. 253

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. 184 days SR 3.3.1.1.11 (Deleted)

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.13 ---------- ------------- NOTE-------------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.1.14 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

SR 3.3.1.1.15 Verify Turbine Stop Valve - Closure and 24 months Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are not bypassed when THERMAL POWER is 2 30% RTP.

SR 3.3.1.1.16 --------------------------NOTE-------------------------

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

Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.1.1.17 Verify OPRM is not bypassed when APRM 24 months Simulated Thermal Power is Ž 25% and recirculation drive flow is < 60% of rated recirculation drive flow.

BFN-UNIT 2 3.3-6 Amendment No. 258 March 05, 1999

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrurrenton APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

1. Intermediate Range Monitors

a. Neuon Flm - High 2 3 . G SR 3.3.1.1.1 S 1:O125 SR 3.3.1.1.3 dMv;ions of full SR 3.3.1.1.5 scale SR 3.3.1.1.6 SR 3.3.1.1.9 SR 3.3.1.1.14 5 (a) 3 H SR 3.3.1.1.1 S 1:0125 SR 3.3.1.1.4 dlvkions of full SR 3.3.1.1.9 sca'e SR 3.3.1.1.14

b. Inop 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.14 5(a) 3 H SR 3.3.1.1.4 NA SR 3.3.1.1.14

2. Average Power Range Monlto

a. Neutron Flia - High, 2 3 (b) G SR 3.3.1.1.1 S 1!i% RTP (Setdown) SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16

b. Flow BIasd Simulated I 3 (b) F SR 3.3.1.1.1 S0.66W Thermal Power - High SR 3.3.1.1.2 +66%RTP SR 3.3.1.1.7 and S 120%

SR 3.3.1.1.13 1 SR 3.3.1.1.16 RTI(c) I

c. Neutron Flx - High 3 (b) F SR 3.3.1.1.1 s 1 0% RTP SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) Each APRM channel pvides Inputs to both trip systems.

(c) [.66W + 66% - .66 AW] RTP when reset for single loop operation per LCO 3.4.1, 'Recirculaton Loops Operatn.

I BFN-UNIT 2 3.3-7 Amendment No. 256 DEC 2 1998 Nte: This page is applicable after carrencing Cycle 11 operation.

RPS Instrumentation 3.3.1.1 Table 3.3.1.1 -1 (page 1 of 3)

Reactor Protection System Instrumentation APPUCABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

1. Intermediate Range Monitors

a. Neutron Flux - High 2 3 G SR 3.3.1.1.1 S 20/125 SR 3.3.1.1.3 dhisions of fun SR 3.3.1.1.5 scale SR 3.3.1.1.6 SR 3.3.1.1.9 SR 3.3.1.1.14 s(a) 3 H SR 3.3.1.1.1 s 120W125 SR 3.3.1.1.4 disbns of full SR 3.3.1.1.9 scale SR 3.3.1.1.14

b. Inop 2 3 G SR 3.3.1.1.3 Nm SR 3.3.1.1.14 5 (a) 3 H SR 3.3.1.1.4 NA SR 3.3.1.1.14

2. Average Power Range Monitors

a. Neutron Flux - High, 2 .3(b) G SR 3.3.1.1.1 S'15%RTP (Setdown) SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16

b. FlowBlasedSlmulated 1 3 (b) F SR 3.3.1.1.1 Sl).66W Thermal Power - High SR 3.3.1.1.2 +71%RTP SR 3.3.1.1.7 and s 120%

SR 3.3.1113 R-p(c)

SR 3.3.1.1.16

c. NeurnFlxa- High 1 3 (b) F SR 3.3.1.1.1 s 120% RTP SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 (continued)

(a) Wlth any control rod wIthdrawn from a core cell containbV one or more fuel assemblies.

(b) Each APRM channel provides Inuts to both trip systems.

(c) 1.66 W +71%- .66 A WVRTP when reset for single loop operatIon per LCO 3.4.1, 'Recirculation Loops Opeating.

I BFN-UNIT 2 Amendment No. 256 DEC 2 a VI S R te: This page is applicable only for Cycle 10 operation.

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

2. Average Power Range Monitors (continued)

d. Inop 1,2 3 (b) G SR 3.3.1.1.16 NA

e. 2-Out-Of-4 Voter. 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.14 SR 3.3.1.1.16

f. OPRM Upscale 3 (b) SR 3.3.1.1.1 NA SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1.1.17

3. Reactor Vessel Steam Dome 1,2 2 G SR 3.3.1.1.1

1030 psig Pressure - High SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14

4. Reactor Vessel Water Level - 1,2 2 G SR 3.3.1.1.1 2 523 inches Low, Level 3 SR 3.3.1.1.8. above vessel SR 3.3.1.1.13 zero SR 3.3.1.1.14

5. Main Steam Isolation Valve - 1,2 8 F SR 3.3.1.1.8 . s 10%6 closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14

6. Drywell Pressure - High 1,2 2 G SR 3.3.1.1.8 S2.5 psig SR 3.3.1.1.13 SR 3.3.1.1.14

7. Scram Discharge Volume Water Level - High

a. Resistance Temperature 1,2 2 G SR 3.3.1.1.8 S50 gallons Detector SR 3.3.1.1.13 SR 3.3.1.1.14 5(a) 2 H SR 3.3.1.1.8 S50 gallons SR 3.3.1.1.13 SR 3.3.1.1.14

(-:ontinued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) Each APRM channel provides inputs to both trip systems.

BFN-UNIT 2 3.3-8 Amendment No. 253,254,-58, 260

,, "j..

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABL SPECIFIED PER TRIP REQUIRED REQUIREMENTS E VALUE CONDITIONS SYSTEM ACTION D.]

7. Scram Discharge Volume Water Level - High (continued)

b. Float Switch ..1,2 2 G SR 3.3.1.1.8 *46 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) 2 H SR 3.3.1.1.8 s46 gallons SR 3.3.1.1.13 SR 3.3.1.1.14

8. Turbine Stop Valve - 230%RTP 4 E SR 3.3.1.1.8 *10% closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15

9. Turbine Control Valve Fast 230%RTP 2 E SR 3.3.1.1.8 55 0psig Closure, Trip Oil Pressure - SR 3.3.1.1.13 Low SR 3.3.1.1.14 SR 3.3.1.1.15

10. Reactor Mode Switch - 1,2 1 G SR 3.3.1.1.12 NA Shutdown Position SR 3.3.1.1.14 5 (a) I H SR 3.3.1.1.12 NA SR 3.3.1.1.14

11. Manual Scram 1,2 I G SR 3.3.1.1.8 NA SR 3.3.1.1.14 5 (a) I . SR 3.3.1.1.8 NA SR 3.3.1.1.14

12. RPS ChannelTest Switches 1,2 2 G SR 3.3.1.1.4 NA 5(a) 2 H SR 3.3.1.1.4 NA

13. Deleted (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

BFN-UNIT 2 3.3-9 Amendment No. 258. 276 APR 0 8 202

SRM Instrunentation 3.3.1.2 3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor (SRM) Instrumentation L.CO 3.3.1.2 The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

APPLICABiLITY: According to Table 3.3.1.2-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required SRMs to 4 hours0.167 days 0.0238 weeks 0.00548 months SRMs inoperable in OPERABLE status.

MODE 2 with intermediate range monitors (IRMs) on Range 2 or below.

B. Three required SRMs B.1 Suspend control rod Immediately inoperable in MODE 2 withdrawal.

with IRMs on Range 2or below.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months

.associated Completion Time of Condition A or B not met.

(continued) 13FN-LINIT 2 3.3-10 Amendment Ngo. 253

SRM Instrumentation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more required D.1 Fully insert all insertable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SRMs inoperable in control rods.

MODE 3 or 4.

AND D.2 Place reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

E. One or more required E.1 Suspend CORE Immediately SRMs inoperable in - ALTERATIONS except for MODE 5. control rod insertion.

AND E.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

13FN-UNIT 2 3.3-11 Amendment No. 253

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS I Mu F-Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.1.2.2 NOTES

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is 12 hours0.5 days 0.0714 weeks 0.0164 months located in:

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

SR 3.3.1.2.3 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months (continued)

[3FN-UNIT 2 3.3-12 Amendment No. 253

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.4 NOTE Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

Verify count rate is 2 3.0 cps with a signal to 12 hours0.5 days 0.0714 weeks 0.0164 months during noise ratio Ž 3:1. CORE ALTERATIONS AND 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.1.2.5 Perform CHANNEL FUNCTIONAL TEST and 7 days determination of signal to noise ratio.

SR 3.3.1.2.6 NOTE Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST and 31 days determination of signal to noise ratio.

(continued)

BFN-UNIT 2 3.3-1 3 Amendment No. 253

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQ JENCY SR 3.3.1.2.7 NOTES

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION. 92 days 13FN-UNIT 2 3.3-1 4 Amendment No. 253

SRM Instrumentation 3.3.1.2 Table 3.3.1.2-1 (page 1 of 1)

Source Range Monitor Instrumentation APPLICABLE MODES OR OTHER REQUIRED SURVEILLANCE FUNCTION SPECIFIED CONDITIONS CHANNELS REQUIREMENTS

1. Source Range Monitor 2(a) 23 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3 1.2.7 3,4 . 2 SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5 2 (b)(c)

SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 a -

(a) Wth IRMs on Range 2 or below.

(t ) Only one SRM channel is required to be OPERABLE during spiral ooad or reload when the fueled region includes only that SRM detector.

(c) Special movable detectors may be used inplace of SRMs If connected to normal SRM circuits.

EIFN-UNIT 2 3.3-15 Amendment No. 253

Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation LCO 3.3.2.1 The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rod block monitor A.1 Restore RBM channel to 24 hours1 days 0.143 weeks 0.0329 months (RBM) channel OPERABLE status.

inoperable.

B. Required Action and B.1 Place one RBM channel 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion in trip.

Time of Condition A not met.

OR Two RBM channels inoperable.

C. Rod worth minimizer C.1 Suspend control rod Immediately (RWM) inoperable during movement except by reactor startup. scram.

OR (continued)

EIFN-UNIT 2 3.3-16 Amendment No. 253

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1.1 Verify Ž 12 rods Immediately withdrawn.

OR-C.2.1.2 Verify by administrative Immediately methods that startup with RWM inoperable has not been performed in the last calendar year.

AND C.2.2 Verify movement of During control rod control rods is in movement compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

D. RWM inoperable during D.1 Verify movement of During control rod reactor shutdown. control rods is in movement compliance with BPWS by a second licensed' operator or other qualified member of the technical staff.

(continued)

EFN-UNIT 2 3.3-17 Amendment ND. 253

Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more Reactor E.1 Suspend control rod Immediately Mode Switch - Shutdown withdrawal.

Position channels inoperable.

AND E.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

EIFN-UNIT 2 3.3-1 8 Amendment No. 253

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days 0.0357 weeks 0.00822 months provided the associated Function maintains control rod block capability.

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

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at

< 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 --------------------------NOTE-------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is < 10% RTP in MODE1.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.4 -------------------------- NOTE-------------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months (continued)

BFN-UNIT 2 3.3-19 Amendment No. 255 November 30, 1998

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.5 Verify the RWM is not bypassed when 24 months THERMAL POWER is < 10% RTP.

SR 3.3.2.1.6 NOTE----------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.2.1.7 Verify control rod sequences input to the Prior to declaring RWM are in conformance with BPWS. RWM OPERABLE following loading of sequence into RWM SR 3.3.2.1.8 ------------------------- NOTE-------------------------

Neutron detectors are excluded.

Verify the RBM: 24 months

a. Low Power Range -- Upscale Function is not bypassed when THERMAL POWER is

Ž 27% and < 62% RTP.

b. Intermediate Power Range -- Upscale Function is not bypassed when THERMAL POWER is > 62% and < 82% RTP.

c. High Power Range -- Upscale Function is not bypassed when THERMAL POWER is

> 82% RTP.

BFN-UNIT 2 3.3-20 Amendment No. 255 November 30, 1998

Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1)

Control Rod Block Instrumentation APPLICABLE MODES OR FUNCTION OTHER REQUIRED SURVEILLANCE ALLOWABLE SPECIFIED CHANNELS REQUIREMENTS VALUE CONDITIONS

1. Rod Block Monitor

a. Low Power Range- Upscale (a) 2 SR 3.3.2.1.1 (e)

SR 3.3.2.1.4 SR 3.3.2.1.8

b. IntermediatePowerRange-Upscale (b) 2 SR 3.3.2.1.1 (e)

SR 3.3.2.1.A SR 3.3.2.1.8

c. High Power Range- Upscale (f, (g) 2 SR 3.3.2.1.1 (e)

SR 3.3.2.1.4 SR 3.3.2.1.8

d. Inop (g).(h) 2 SR 3.3.2.1.1 NA

e. Downscale (g),(h) 2 SR 3.3.2.1.1 (i)

SR 3.3.2.1.4

2. Rod Worth Minimizer 1(c)@(c) 1 SR 3.3.2.12 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.7

3. ReactorModeSwitch - Shutdown Position. (d) 2 SR 3.32.1.6 NA (a) THERMAL POWER 2 27% and S 62% RTP and MCPR ess than the value specified I the COLR.

(b) THERMAL POWER > 62% and S 82% RTP and MCPR less than the value specified I the COLR.

lc) Wth THERMAL POWER 510% RTP.

(d) Reactor mode switch Inthe shutdown position.

(e) Less than or equal to the Allowable Value specified In the COLR.

(I) THERMAL POWER > 82% and c 90% RTP and MCPR kss than the value specified in the COLR.

(g) THERMAL POWER . 90% RTP and MCPR less than the value specified In the COLR.

(h) THERMAL POWER 2 27% and e 90% RTP and MCPR less than the value specified inthe COLR.

(I) Greater than or equal to the Allowable Value specified Inthe COLR.

13FN-UNIT 2 3.3-21 Amendment No. 253

Feeawater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation I-CO 3.3.2.2 Two channels of feedwater and main turbine high water level trip instrumentation per trip system shall be OPERABLE.

APPLICABILITY: THERMAL POWER Ž 25% RTP.

ACTIONS NOT r-Separate Condition entr' is allowed for each cl CONDITION REQUIRED ACTION COMPLETION TIME A. One or more feedwater A.1 Place channel(s) in trip. 7 days and main turbine high water level trip channels inoperable, in one trip system.

B. One or more feedwater B.1 Restore feedwater and 2 hours0.0833 days 0.0119 weeks 0.00274 months and main turbine high main turbine high water water level trip channels level trip capability.

inoperable in each trip system.

C. Required Action and C.I Reduce THERMAL - 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion POWER to < 25% RTP.

Time not met.

.13FN-UNIT 2 3.3-22 I-23Amendment No. 253

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

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

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

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.2.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The 24 months Allowable Value shall be < 586 inches above vessel zero.

SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST including valve actuation.

BFN-UNIT 2 3.3-23 Amendment No. 255 November 30, 1998

PAM Instrumentation 3.3.3.1 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

1. Separate Condition entry is allowed for each Function.

2. For Function 6, Separate Condition entry is allowed for each penetration flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required channel to OPERABLE status.

inoperable.

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

met.

(continued)

BFFI-UNIT 2 3.3-24 Amendment No. 253 286

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions C.1 Restore one required channel to OPERABLE 7 days I with two required channels inoperable. status.

D. (Deleted).

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C not Table 3.3.3.1-1 for the I met. channel.

F. As required by Required F.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Action E.1 and referenced in Table 3.3.3.1-1.

G. As required by Required G.1 Initiate action in Immediately Action E.1 and referenced accordance with in Table 3.3.3.1-1. Specification 5.6.6.

BFN-UNIT 2 3.3-25 Amendment No. 2-53. 292

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

,SR 3.3.3.1.1 Perform CHANNEL CHECK for each required 31 days PAM instrumentation channel.

c;R 3.3.3.1.2 (Deleted)

SR 3.3.3.1.3 Perform CHANNEL CALIBRATION of the 184 days Reactor Pressure Functions.

SR 3.3.3.1.4 Perform CHANNEL CALIBRATION for each 24 months required PAM instrumentation channel except for the Reactor Pressure Function. I1' BFN-UNIT 2 3.3-26 Amendment No. 255 292

PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1of 1)

Post Accident Monitoring Instrumentation CONDITIONS REQUIRED REFERE NCED FUNCTION CHANNELS FROM REQUIRED ACTION E.1

1. Reactor Pressure 2 F

2. Reactor Vessel Water Level

3. Emergency Systems Range 2 F I,. Post-Accident Flood Range 2 F

3. Suppression Pool Water Level 2

4. Drywell Pressure

a. Normal Range 2 F

b. Wide Range 2 F

5. Primary Containment Area Radiation 2 G

6. F'CIV Position 2 per penetration flow pathn"')b F

7. (D)eleted)

8. E-uppresslon Pool Water Temperature :2

.F

9. Drywell Atmosphere Temperature 2 (a) lot required for Isolation valves whose associated penetration flow path is Isolated by at least one closed and deactivated automatic salve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one postion indication channel Is required for penetration flow paths with only one Installed control room PAM category 1 Indication channel.

BFN -UNIT 2 3.3-27 Amendment No. 2&N 292

Backup Control System 3.3.3.2 3.3 INSTRUMENTATION 3.',.3.2 Backup Control System LCO 3.3.3.2 The Backup Control System Functions shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTIONS SpaCntnero-- -d-------r-C a----------dNOTE ------

Separate Condition entry is allowed for each Function.

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

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met.

_ . .=

1BFN-IJNIT 2 3.3-28 Amendment No. 2 3T 286

Backup Control System 3.3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Verify each required control circuit and 24 months transfer switch is capable of performing the intended function.

SR 3.3.3.2.2 Perform CHANNEL CALIBRATION for the 184 days Suppression Pool Water Level Function.

SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each 24 months required instrumentation channel except for the Suppression Pool Water Level Function.

BFN-UNIT 2 3.3-29 Amendment No. 255 November 30, 1998

EOC-RPT Instrumentation 3.3.4.1

',.3 INSTRUMENTATION 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation L.CO 3.3.4.1 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE_:

1. Turbine Stop Valve (TSV) - Closure; and

2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure

- Low.

OR

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),'

limits for inoperable EOC-RPT as specified in the COLR are made applicable; and

c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR), "

limits for inoperable EOC-RPT as specified in the COLR are made applicable.

APPLICABILITY: THERMAL POWER > 30% RTP.

BFN-UNIT 2 3.3-30 Amendment No. 253-,287

EOC-RPT Instrumentation

.3.3.4.1 ACTIONS

NOTE--------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 72 hours3 days 0.429 weeks 0.0986 months inoperable. OPERABLE status.

OR A.2 ------------NOTE--------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months

13. One or more Functions B.1 Restore EOC-RPT trip 2 hours0.0833 days 0.0119 weeks 0.00274 months with EOC-RPT trip capability.

capability not maintained.

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

C. Required Action and C.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion POWER to < 30% RTP.

Time not met.

==

Bl=N-UNIT 2 3.3-31 Amendment No. 2g,-287

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS

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

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

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

> 30% RTP.

SR 3.3.4.1.3 Perform CHANNEL CALIBRATION. The 24 months Allowable Values shall be:

TSV - Closure: < 10% closed; and TCV Fast Closure, Trip Oil Pressure - Low:

Ž 550 psig.

SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST including breaker actuation.

BFN-UNIT 2 3.3-32 Amendment No. 255 November 30, 1998

ATWS-RPT Instrumentation 3.3.4.2 3.3 INSTRUMENTATION 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)

Instrumentation LCO 3.3.4.2 Two channels per trip system for each ATWS-RPT instrumentation Function listed below shall be OPERABLE:

a. Reactor Vessel Water Level - Low Low, Level 2; and

b. Reactor Steam Dome Pressure - High.

APPLICABILITY: MODE 1.

ACTIONS NOTE -

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 14 days inoperable. OPERABLE status.

OR A.2 NOTE-Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in trip. 14 days (continued)

BFN-UN IT 2 3.3-33 Amendment No. 253

ATWS-RPT Instrumentation 3.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One Function with B.1 Restore ATWS-RPT trip 72 hours3 days 0.429 weeks 0.0986 months ATWS-RPT trip capability capability.

not maintained.

C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability capability for one not maintained. Function.

D. Required Action and D.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

a -.

13FN-UNIT 2 3.3-34 Amendment No. 253

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK of the Reactor 24 hours1 days 0.143 weeks 0.0329 months Vessel Water Level - Low Low, Level 2 Function.

SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The 24 months Allowable Values shall be:

a. Reactor Vessel Water Level - Low Low, Level 2: Ž 471.52 inches above vessel zero; and

b. Reactor Steam Dome Pressure - High:

< 1175 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST including breaker actuation.

BFN-UNIT 2 3.3-35 Amendment No. 255 November 30, 1998

ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation I-CO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5. 1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.1-1.

ACTIONS

_ i separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.1-1 for the channel.

(continued)

.EFN-UNIT 2 3.3-36 Amendment No. 253

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. As required by Required B.1 -NOTES Action A.1 and referenced 1. Only applicable in in Table 3.3.5.1-1. MODES 1, 2, and 3.

2. Only applicable for Functions 1.a, 1.b, 2.a, and 2.b.

Declare supported ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of loss when its redundant of initiation feature ECCS initiation capability for capability is inoperable. features in both divisions AND B.2 - NOTE-Only applicable for Functions 3.a and 3.b.

Declare High Pressure I hourfrom Coolant Injection (HPCI) discovery of loss System inoperable. of HPCI initiation capability AND B.3 Place channel in trip. 24 hours1 days 0.143 weeks 0.0329 months (continued)

BFN-UNIT 2 3.3-37 Amendment No. 253

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 N NOTES Action A.1 and referenced 1. Only applicable in in Table 3.3.5.1-1. MODES 1, 2, and 3.

2. Only applicable for Functions 1.c, 1.e, 2.c, 2.d, and 2.f.

Declare supported ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of loss when its redundant of initiation feature ECCS initiation capability for capability is inoperable. features in both divisions AND C;2 Restore channel to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

D. As required by Required D.1 NOTE Action A.1 and referenced Only applicable if HPCI in Table 3.3.5.1-1. pump suction is not aligned .to the suppression pool.

Declare HPCI System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

(con':inued)

E3FN-UNIT 2 3.3-38 Amendment No. 253

ECCS Instrumentation 3.3.5.1 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 -NOTES Action A.1 and referenced 1. Only applicable in in Table 3.3.5.1-1. MODES 1, 2, and 3.

2. Only applicable for Function 1.d.

Declare supported ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of loss when its redundant of initiation feature ECCS initiation capability for capability is inoperable. subsystems in both divisions AND E.2 Restore channel to 7 days OPERABLE status.

(continued)

BF-N-UNIT 2 3.3-39 Amendment No. 253

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required F. 1 Declare Automatic 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced Depressurization System discovery of loss in Table 3.3.5.1-1. (ADS) valves inoperable. of ADS initiation capability in both trip systems AND F.2 Place channel in trip. 96 hours4 days 0.571 weeks 0.132 months from discovery of inoperable channel concurrent: with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days (continued)

EFN-UNIT 2 3.3-40 Amendment No. 253

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required G.1 Declare ADS valves 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced inoperable. discovery of loss in Table 3.3.5.1-1. of ADS initiation capability,in both.

trip systems AND G.2 Restore channel to 96 hours4 days 0.571 weeks 0.132 months from OPERABLE status. discovery of inoperable channel concurrent with HPCI or R(IC inoperable AND 8 days I.H. Required Action and H.1 Declare associated Immediately associated Completion supported ECCS Time of Condition B, C, feature(s) inoperable.

D, E, F, or.G not met.

Bl-N-UNIT 2 3.3 41 Amendment No. 253

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

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

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 184 days SR 3.3.5.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 2 3.3-42 Amendment No. 255 November 30, 1998

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A.1

1. Core Spray System

a. Reactor Vessel Water 1,2,3, 4 (b) 8 SR 3.3.5.1.1 .398 inches Level - Low Low Low, 4 (a) 5 (a) SR 3.3.5.1.2 atove vessel Level I SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. Drywell Pressure - High 1,2,3 4 (b) B SR 3.3.5.1.2 S:2.5psig SR 3.3.5.1.5 SR 3.3.5.1.6

c. Reactor Steam Dome 1,2,3 4 (b) C SR 3.3.5.1.2 2:435 psig Pressure - Low (injection 2 SR 3.3.5.1.4 and Permissive and ECCS 2pertrip SR 3.3.5.1.6 S465 psig Initiation) system 4 (a) 5 (a) 4 B SR 3.3.5.1.2 2435psig 2pertrip SR 3.3.5.1.4 anc system SR 3.3.5.1.6 S 435 psig

d. CoreSprayPump 1,2,3, 2 E SR 3.3.5.12 211i47gpm Discharge Flow - Low 4 (a) 5 (a) 1per SR 3.3.5.1.5 and (Bypass) subsystem s2109gpm

e. Core Spray Pump Start -

Toe Delay Relay Pumps A,B,C,D (with 1.2,3, 4 C SR 3.3.5.1.5 26 econds diesel power) 4 (a) 5 (a) I per pump SR 3.3.5.1.6 and s 8 seconds PumpA(wlthnormal 1,2,3, 1 C SR 3.3.5.1.5 20seconds power) 4 (a) 5 (a) SR 3.3.5.1.6 and S i second Pump B(withnormal 1,2,3, 1 C SR 3.3.5.1.5 26seconds power) 4(a) s(a) SR 3.3.5.1.6 and s 8 s9conds PumpC(withnormal 1,2,3. 1 C SR 3.3.5.1.5 a212reconds power) 4 (a) 5 (a) SR 3.3.5.1.6 and S 16 Seconds (aontinued)

(E) When associated subsystem(s) are required to be OPERABLE.

(k) Channels affect Common Accident Signal Logic. Refer to LCO 3.8.1, 'AC Sources - Operating.'

E;FN-UNIT 2 3.3-43 Amendment No. 253

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A.1

1. Core Spray System (continued)

e. Core Spray Pump Start -

Time Delay Relay (continued)

Pump D (with normal power) 1.2,3, 1 C SR 3.3.5.1.5 21Bseconds 4 (a) 5 (a) SR 3.3.5.1.6 and S 24 seconds

2. Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water Level- 1,2,3, 4 E SR 3.3.5.1.1 2 398 inches Low Low Low, Level I 4(a) 5 (a) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 . zero SR 3.3.5.1.6

b. Drywetl Pressure - High 1,2,3 4 B SR 3.3.5.1.2 S2.5 psig SR 3.3.5.1.5 SR 3.3.5.1.6

c. ReactorSteamDome 1,2,3 4 C SR 3.3.5.1.2 2435psigand Pressure - Low (injection SR 3.3.5.1.4 S465 psig Permissive and ECCS SR 3.3.5.1.6 Initiation) 4 (a), 5 (a) 4 B SR 3.3.5.1.2 a 435 psig and SR 3.3.5.1.4 s465 psig SR 3.3.5.1.6

d. Reactor Steam Dome 1 (c) 2 (c) 4 C SR 3.3.5.1.2 2215 psig Pressure - Low ;c SR 3.3.5.1.4 andS245psig (Recirculation Discharge 3('. SR 3.3.5.1.6 Vahve Permissive)

e. ReactorVesselWater Level - 1,2,3 2 B SR 3.3.5.1.1

312 5/16 Level0 I per SR 3.3.5.1.2 inches above subsystem SR 3.3.5.1.5 *essel zero SR 3.3.5.1.6 (continued) la) When associated subsystem(s) are required to be OPERABLE.

Ib) Deleted.

I c) With associated recirculation pump discharge valve open.

13FN-UNIT 2 3.3-44 Amendment No. 253

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A.1

2. LPCI System (continued)

1. Low Pressure Coolant Injection Pump Start - Time Delay Relay Pump A,B,C,D (with diesel 1,2,3, 4 C SR 3.3.5.1.5 0seconds l power) 4 (a), 5(a) SR 3.3.5.1.6 and I1 second Pump A (with normal power) i,2,3, 1 C SR 3.3.5.1.5 2 0 seconds 4(a) 5(a) SR 3.3.5.1.6 and S 1 second Pump B (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 Ž6 seconds 4(a), 5(a) SR 3.3.5.1.6 and S 8 seconds Pump C (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 - 12 seconds l 4 (a), 5(a) SR 3.3.5.1.6 and 16 seconds Pump D (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 . 18 seconds l 4(a), 5(a) SR 3.3.5.1.6 and

, 24 seconds

3. High Pressure Coolant Injection (HPCI) System

a. ReactorVesselWaterLevel - 1, 4 B SR 3.3.5.1.1 <:470 inches Low Low, Level 2 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6 (continued)

(a) When the associated subsystem(s) are required to be OPERABLE.

(d) 'Nith reactor steam dome pressure > 150 psig.

I BFN\-UNIT 2 3.3-45 Amendment No.-253- 289

ECCS InstrLimentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A.1

3. HPCI System (continued)

b. Drywell Pressure - High 1, .4 B SR 3.3.5.1.2 S 2.5 psig 2 (d), 3 (d) SR 3.3.5.1.5 SR 3.3.5.1.6

c. Reactor Vessel Water Level - 1, 2.- C SR 3.3.5.1.1 S 583 inches High, Level 8 2 (d), 3 (d)

SR 3.3.5.1.2 .above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

d. Condensate Header Level - 1, I D SR 3.3.5.1.2 2 Elev. 551 Low SR 3.3.5.1.3 feet 2 (d), 3 (d)

SR 3.3.5.1.6'

e. Suppression Pool Water 1, 1 D SR 3.3.5.1.2 S 7 inches Level - High 2 (d). 3 (d) SR 3.3.5.1.3 above SR 3.3.5.1.6 insturnent zero

f. High Pressure Coolant 1, 1 E SR 3.3.5.1.2 2671 gpm Injecfion Pump Discharge .2 (d), 3(d) SR 3.3.5.1.5 Flow - Low (Bypass) SR 3.3.5.1.6

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel Water Level - 1I 2 F SR 3.3.5.1.1 .2 398 inches Low Low Low, Level 1 2 (d), 3 (d) SR 3.3.5.1.2 ;above vessel SR 3.3.5.1.5 'zero SR 3.3.5.1.6

b. Drjwell Pressure - High 1, 2 F SR 3.3.5.1.2 :.; 2.5 psig 2 (d), 3 (d)

.SR 3.3.5.1.5 SR 3.3.5.1.6

c. Automatic Depressunzation 1. I G SR 3.3.5.1.5 ' 115 seconds System Initiation Timer (d), SR 3.3.5.1.6 2 3 (d)

(continued)

( ) With reactor steam dome pressure: 150 psig.

E3FN-UNIT 2 3.3-46 Amendment No. 253

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A.1

4. ADS Trip System A (continued)

d. Reactor Vessel Water Level - 1, 1 F SR 3.3.5.1.1 2 528 inches Low, Level 3 (Confirmatory) 2 (d) 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

e. Core Spray Pump Discharge 1, 4 G SR 3.3.5.1.2 2 175 psig and Pressure - High 2 (d), 3 (d) SR 3.3.5.1.3 S195psig SR 3.3.5.1.6

f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2 2 90 psig and Injection Pump Discharge 2 (d) 3 (d) SR 3.3.5.1.3 5 110 psig Pressure- High SR 3.3.5.1.6

g. Automatic Depressurization 1, 2 G SR 3.3.5.1.5 :5322 seconds System High Drywell 2 (d), 3 (d) SR 3.3.5.1.6 Pressure Bypass Timer

5. ADS Trip System B

a. Reactor Vessel Water Level - 1, 2 F SR 3.3.5.1.1 2 398 inches Low Low Low, Level 1 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 ;zero SR 3.3.5.1.6

b. Drywell Pressure - High 1, 2 F SR 3.3.5.1.2 -; 2.5 psig 2 (d), 3 (d) SR 3.3.5.1.5 SR 3.3.5.1.6

c. Automatic Depressurization 1, 1 G SR 3.3.5.1.5 : 115 seconds System Initiation Timer 2 (d), 3 (d) SR 3.3.5.1.6

d. Reactor Vessel Water Level - 1, 1 F SR 3.3.5.1.1 -: 528 inches l Low, Level 3 (Confirmatory) 2 (d) 3 (d) SR 3.3.5.1.2 aibove vessel SR 3.3.5.1.5 ;:ero SR 3.3.5.1.6 (continued)

(d) With reactor steam dome pressure> 150 psig.

BF1N-UNIT 2 3.3-47 Amendment No. 253, 260 AUG - S -%,

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 6 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A.1 5; ADS Trip System B (continued)

e. Core Spray Pump Discharge 1, 4 G SR 3.3.5.1.2 2 175 psig and Pressure - High 2 (d) 3 (d) SR 3.3.5.1.3 S 195 psig SR 3.3.5.1.6

f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2 Ž90 psig and Injecion Pump Discharge 2 (d) 3 (d) SR 3.3.5.1.3 S110psig Pressure - High SR 3.3.5.1.6

g. Automatic Depressurization 1 2 G SR 3.3.5.1.5 S 322 seconds System High Drywell 2 (d) 3 (d) SR 3.3.5.1.6 Pressure Bypass Timer id) WIth reactor steam dome pressure > 150 psig.

13FN-UNIT 2 3.3-48 Amendment No. 253

RCIC System Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation I.C O 3.3.5.2 The RCIC System instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS NOTE Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition ImmediatelY inoperable. referenced in Table 3.3.5.2-1 for the channel.

B. As required by Required B.1 Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced inoperable.. discovery of loss

.in Table 3.3.5.2-1. of RCIC initiation capability AND B.2 Place channel in trip. 24 hours1 days 0.143 weeks 0.0329 months (continued)

BFN-UN IT 2 3.349 Amendment No. 253

RCIC System InstrUmentation 3.3.5.2 ACTIONS (continued) . -

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 Restore channel to 24 hours1 days 0.143 weeks 0.0329 months Action A.1 and referenced OPERABLE status.

in Table 3.3.5.2-1.

D. Required Action and D.1 Declare RCIC System Immediately associated Completion inoperable.

Time of Condition B or C not met.

13FN-UN IT 2 3.3-50 Amendment No. 253

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours0.25 days 0.0357 weeks 0.00822 months for Function 2 and (b) for up to 6 hours0.25 days 0.0357 weeks 0.00822 months for Function I provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.2.3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.2.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 2 3.3-51 Amendment No. 255 November 30, 1998

. RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS PER FROM REQUIRED REQUIREMENTS VALUE FUNCTION ACTION A.1

1. Reactor Vessel Water Level - 4 8 SR 3.3.5.2.1 - 470 inches Low Low, Level 2 SR 3.3.5.2.2 above vessel zero SR 3.3.5.2.3 SR 3.3.5.2.4

2. Reactor Vessel Water Level - 2 C SR 3.3.5.2.1 S 583 inches High, Level 8 SR 3.3.5.2.2 above vessel zero SR 3.3.5.2.3 SR 3.3.5.2.4 13FN-UNIT 2 3.3-52 Amendment No. 253

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation L.CO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

Bl-N-UNIT 2 3.3-53 Amendment No. 253

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS

-- NOTE Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION

______________________I J TIME.

A. One or more required A.1 NOTE channels inoperable. Only applicable for

Function I.d if two or more channels are inoperable.

Place channel in trip. 12 hours0.5 days 0.0714 weeks 0.0164 months f Dr Functions 2.a, 2.b, 5.h, 6.b, and 6.c.

AND 24 hours1 days 0.143 weeks 0.0329 months for Functions other than Functions 2'.a, 2.b, 5.h, 6.b, and 6.c AND A.2 NOTE-Only applicable for Function 1.d when 15 of 16 channels are OPERABLE.

Place channel in trip. 30 days (continued)

.EIFN-UNIT 2 3.3-54 Amendment No. 253

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with isolation capability capability.

not maintained. OR 4 hours0.167 days 0.0238 weeks 0.00548 months for Function 1.d when normal ventilation is not available C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A or B Table 3.3.6.1-1 for the not met. channel.

D. As required by Required D.1 Isolate associated Main 12 hours0.5 days 0.0714 weeks 0.0164 months Action C.1 and Steam Line (MSL).

referenced in Table 3.3.6.1-1.

OR D.2.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months

- AND D.2.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

Bl-N-UNIT 2 3.3-55 Amendment Nco. 253

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months Action C.1 and referenced in Table 3.3.6.1-1.

F. As required by Required F.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and penetration flow path(s).

referenced in Table 3.3.6.1-1.

G. As required by Required G.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Action C.1 and referenced in AND Table 3.3.6.1-1.

G.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months OR Required Action and associated Completion Time for Condition F not met.

(continued)

E;FN-UNIT 2 3.3-56 Amendment No. 253

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required H.1 Declare standby liquid 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and control system (SLC) referenced in inoperable.

Table 3.3.6.1-1.

OR H.2 Isolate the Reactor Water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Cleanup System.

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

Table 3.3.6.1-1.

OR 1.2 Initiate action to isolate Immediately the Residual Heat Removal (RHR)

Shutdown Cooling System.

Bl-N-UNIT 2 3.3-57 Amendment No. 253

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

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

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 122 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 2 3.3-58 Amendment No. 255 November 30, 1998

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS . FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1

1. Main Steam Line Isolation

a. Reactor Vessel Water 1,2,3 2 D SR 3.3.6.1.1 2 398 inches Level - Low Low Low, SR 3.3.6.1.2 above vessel Level 1 SR 3.3.6.1.5 zero SR 3.3.6.1.6

b. Main Steam Line Pressure 2 E SR 3.3.6.1.2 2 82i psig

- Low SR 3.3.6.1.5 SR 3.3.6.1.6 c.. Main Steam Line Flow - 1,2,3 2 per D SR 3.3.6.1.1. 5 14C1% rated High MSL SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6

d. Main Steam Tunnel 1,2,3 8 D SR 3.3.6.1.2

20C1F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

2. Primary Containment Isolation

a. Reactor Vessel Water .1,2,3 2 G SR 3.3.6.1.1 2t528 inches Level - Low, Level 3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6

b. Drywell Pressure - High .1,2,3 2 G SR 3.3.6.1.2 S2.5 psig SR 3.3.6.1.5 SR 3.3.6.1.6

3. High Pressure Coolant Injection (HPCI) System Isolation

a. HPCI Steam Line Flow - 1,2,3 I F SR 3.3.6.1.2 S 90 psi High SR 3.3.6.1.5 SR 3.3.6.1.6

b. HPCI Steam Supply Line 1,2,3 F SR 3.3.6.1.2 2 100 psig Pressure- Low SR 3.3.6.1.5 SR 3.3.6.1.6

c. HPCI Turbine 1,2,3 3 F SR 3.3.6.1.2 s 20 psig Exhaust Diaphragm SR 3.3.6.1.5 Pressure - High SR 3.3.6.1.6 (continued)

BFN-UNIT 2 3.3-59 Amendment No. 253, 260 AllG 6G! 9

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)

Primary Containment Isolation Instrumentation APPLICABLE - CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1

3. HPCI System Isolation (continued)

d. HPCI Steam Une Space 1,2,3 2 F SR 3.3.6.1.2 £S:200F HPCI Pump Room Area SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.6

e. HPCI Steam Une Space 1,2,3 2 F SR 3.3.6.1.2 S 180'F Torus Area (Exit) SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.6

t. HPCI Steam Une Space 1,2,3 2 F SR 3.3.6.1.2 S 180IF Torus Area (Midway) SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.6

g. HPCI Steam Une Space 1,2,3 2 F SR 3.3.6.1.2 S 1BO-F Torus Area (Entry) SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.6

4. Reactor Core Isolation Cooling (RCIC) System Isolation

a. RCIC Steam Une Flow . 12,3 1 F SR 3.3.6.1.2 S 4t0"T H2 0 High SR 3.3.6.1.5 SR 3.3.6.1.6

b. RCIC Steam Supply Une 1.2,3 3 F SR 3.3.6.1.2 2 50 psig Pressure - Low SR 3.3.6.1.5 SR 3.3.6.1.6

c. RCIC Turbine 123 F SR 3.3.6.1.2 S20 psig Exhaust Diaphragm SR 3.3.6.1.5 Pressure - High SR 3.3.6.1.6

d. RCIC Steam Une Space 12,3 2 F SR 3.3.6.1.2 S18 -F RCIC Pump Room Area SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.6

e. RCIC Steam Une Space 1.2,3 2 F SR 3.3.6.1.2 S155-F Torus Area (Exdt) SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.6

t. RCIC Steam Line Space 1,2,3 2 F SR 3.3.6.1.2 5 1551F Torus Area (Midway) SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.6

g. RCIC Steam Une Space 1,2,3 2 F SR 3.3.6.1.2 s 155'F Torus Area (Entry) SR 3.3.6.1.3 Temperature - High SR 3.3.6.1.6 (ccntmnued)

EIFN-UNIT 2 IM30 Amendment No. 253

Primary Containment Isolation Ihstrumentarion 3.3.6.1 Tahw. 3.3 6. I-1Ipage 3ot'3 Primary Conitinment Isolation Insrumentation APPLICA.tRLF CONDITIONS MODES (R REQUIRED REFERENCED FUNCTIN O)TfLER CII.-\NNELS FROM SURVEILLA NCE ALLOWABLE' SPECIFIED PER TRIP REiQUIRED REQUIREMNENTS V'A.LUE 0)u'~D!TI'ONS SYSTi:M ACTION C.I

5. Reactor Water Cleanup (RWCU) System Isolation

a. Main Steam Valve Vault 1.2.3 F SR 3.3.6.1.2 S188'F Area Temperature - High SR 3.3.6.1.5 I SR 3.3.6.1.6

b. Pipe Trench Area 1,2.3 F SR 3.3.6.1.2 S135°F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6

c. Pump Room A Area F SR 3.3.6.1.2 s 152 F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6

d. Pump Room B Area 1.2.3 2 F SR 3.3.6.1.2 S 152'F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6 e Heat Exchanger Room 1.2,3 F SR 3.3.6.1.2 5 143'F Area (West Wall) SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.6

f. Heat Exchanger Room 1,2.3 F SR 3.3.6.1.2 5170'F Area (East Wall) SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.6

g. SLC System Initiation 1,2 (a) H SR 3.3.6.1.6 NA

h. Reactor Vessel Water 1.2:3 21 F SR 3.3.6.1.1 2528 inches Level - Low, Level 3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6

6. Shutdown Cooling System Isolation

a. Reactor Steam Dome 1.2,3 SR 3.3.6.1.2 S I I.; psig Pressure - High SR 3.3.6.1.5 SR 3.3.6.1.6

b. Reactor Vessel Water 3.4.5 2(b) SR 3.3.6.1.1 2 5281 inches Level - Low, Level 3 SR 3.3.6.1.2 abov: vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6

c. Drywell Pressure - High 1.2,3 2 .F SR 3.3.6.1.2 *2.!;psig SR 3.3.6.1.5 SR 3.3.6.1.6 (a) One SLC System Initiation signal provides logic input to close both RWCU valves.

(b) Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

BFN-UNIT 2 3.3-61 Amendment No. 5 254 , 277

Secondary Containment Isolation Instrumentation

- 3.3.6.2 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.2-1.

ACTIONS IM NJ r-Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in trip. 12 hours0.5 days 0.0714 weeks 0.0164 months for inoperable. Functions 1 and 2 AND 24 hours1 days 0.143 weeks 0.0329 months for Functions other than Functions 1 and 2 B. One or more automatic B.1 Restore secondary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with-secondary containment isolation containment isolation capability.

capability not maintained.

(continued)

B3FN-UNIT 2 3.3-62 Amendment No. 253

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1.1 Isolate the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion secondary containment Time of Condition A or B isolation valves.

not met.

OR C.1.2 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment isolation valves inoperable.

AND C.2.1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months standby gas treatment (SGT) subsystem(s) in operation.

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

13FN-UNIT 2 3.3-63 Amendment No. 253

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days 0.0357 weeks 0.00822 months provided the associated Function maintains secondary containment isolation capability.

3. For Functions 3 and 4, when a channel is placed in an inoperable status solely for performance of a CHANNEL CALIBRATION or maintenance, entry into associated Conditions and Required Actions may be delayed for up to 24 hours1 days 0.143 weeks 0.0329 months provided the downscale trip of the inoperable channel is placed in the tripped condition.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.2.4 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 2 3.3-64 Amendment No. 255 November 30, 1998

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED FUNCTION OTHER CHANNELS SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIREMENTS VALUE CONDITIONS TRIP SYSTEM

1. Reactor Vessel Water Level - 1,2,3, 2 SR 3.3.6.2.1 2 528 inches above Low, Level 3 (a) SR 3.3.6.2.2 vessel zero SR 3.3.6.2.3 SR 3.3.6.2.4

2. Drywell Pressure - High 1,2,3 2 SR 3.3.6.2.2 S2.5 psig SR 3.3.6.2.3 SR 3.3.6.2.4

3. Reactor~ore Exhaust 1,2.3, 1 SR 3.3.6.2.1 100m Rlhr Radiation - High (a) SR 3.3.6.2.2 I SR 3.3.6.2.3 SR 3.3.6.2.4

4. Refueling Floor Exhaust 1,2.3. 1 SR 3.3.6.2.1 S100 mRlhr Radiation - High (a) SR 3.3.6.2.2 I SR 3.3.6.2.3 SR 3.3.6.2.4 (a) Curing operations wdth a potental for draining Ihe reactor vessel.

I BFN-UNIT 2 3.3-65 Amendment No. M, 26Q, 290

CREV System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Ventilation (CREV) System Instrumentation L.CO 3.3.7.1 The CREV System instrumentation for each Function in Table 3.3.7.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.7.1 ACTIONS NOTI I-separate Condition entry is allowed for each c&

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Enter the Condition Immediately channels inoperable. referenced in Table 3.3.7.1-1 for the channel.

B. As required by Required B.1 Declare associated CREV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced subsystem inoperable. discovery of loss in Table 3.3.7.1-1. of CREV initiation capability AND B.2 Place channel in trip. 12 hours0.5 days 0.0714 weeks 0.0164 months (continued)

EIFN-UNIT 2 3.3-66 Amendment No. 253

CREV System Instrumentation 3.3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 Declare associated CREV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced subsystem inoperable. discovery of loss in Table 3.3.7.1-1. of CREV. initiation capability AND C.2 Place channel in trip. 24 hours1 days 0.143 weeks 0.0329 months D. As required by Required D.1 Perform SR 3.3.7.1.2 on Once per Action A.1 and referenced the OPERABLE channel. 24 hours1 days 0.143 weeks 0.0329 months in Table 3.3.7.1-1.

AND D.2 Verify alternate Once per monitoring capability. 12 hours0.5 days 0.0714 weeks 0.0164 months from discovery of both channels inoperable AND D.3 Restore one channel to 30 days from OPERABLE status. discovery of both i

channels inoperable (continued)

E3FN-UNIT 2 3.3-67 Amendment No. 253

CREV System Instrumentation 3.3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and EA1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion CREV subsystem(s) in Time of Condition B, C, or the pressurization mode D not met. of operation.

OR E.2 Declare associated CREV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable.

S __ _ _ _ _ _ _ _ _

EIFN-UNIT 2 3.M*8 Amendment No. 253

CREV System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS NOTES-------------------------------------------------

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREV Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days 0.0357 weeks 0.00822 months provided the associated Function maintains CREV initiation capability.

3. For Functions 3 and 4, when a channel is placed in an inoperable status solely for the performance of a CHANNEL CALIBRATION or maintenance, entry into the associated Conditions and Required Actions may be delayed for up to 24 hours1 days 0.143 weeks 0.0329 months provided the downscale trip of the inoperable channel is placed in the trip condition.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. 24 hours1 days 0.143 weeks 0.0329 months SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL 184 days TEST.

SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 2 3.3-69 Amendment No. 255 November 30, 1998

CREV System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)

Control Room Emergency Vertilation System Instrumentation APPLICAELE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOy/ABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION A.1

1. Reactor Vessel Water Level- 1,2,3,(a) 2 S SR 3.3.7.1.1 Ž 528 irches I.ow, Level 3 SR 3.3.7.1.2 above vmssel SR 3.3.7.1.5 zero SR 3.3.7.1.6

2. Dryvell Pressure - High 1,2.3 2 B SR 3.3.7.1.2 S2.5 ps'g SR 3.3.7.1.5 SR 3.3.7.1.6

3. Reactor Zone Exhaust 1t,2,3 1 C SR 3.3.7.1.1 s1 0mrhr Radiation- High (a) SR 3.3.7.1.2 I SR 3.3.7.1.5 SR 3.3.7.1.6

4. Refueling Floor Exhaust 1,2.3, 1 C SR 3.3.7.1.1 S 100 mRihr Ftadiation - High (a) SR 3.3.7.1.2 I SR 3.3.7.1.5 SR 3.3.7.1.6

5. Control Room Air Supply Duct 1,2.3, 1 D SR 3.3.7.1.1 s270 cpin Fadiatlon - High (a) SR 3.3.7.1.2 atove I SR 3.3.7.1.3 background SR 3.3.7.1.4 (a) DLring operations with a potential for draining the reactor vessel.

I BFN-LJNIT 2 3.3-70 Amendment No. 25, M6 , 290

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation I-CO 3.3.8.1 The LOP instrumentation for each Table 3.3.8.1-1 Function on 4 kV shutdown boards A, B, C, and D shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, When the associated diesel generator is required to be OPERABLE by LCO 3.8.2, "AC Sources - Shutdown."

ACTIONS NOT - ----

Separate Condition entry is allowed for each ci CONDITION REQUIRED ACTION COMPLETION TIME A. One degraded voltage A.1: Verify by administrative Immediately relay channel inoperable means that the other two on one or more shutdown degraded voltage relay board(s). . channels and associated timers on the affected AND shutdown board(s) are OPERABLE.

The loss of voltage relay channels on the affected AND shutdown board(s) are OPERABLE. *A.2 Place the degraded 15 days voltage relay channel in

trip.

(conl inued) 13FN-UNIT 2 3.3-71 Amendment No. 253

LOP Instrumentation 3.3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two or more B.1 Place the inoperable 10 days degraded voltage degraded voltage relay relay channels channel(s) in trip.

inoperable on one or more shutdown board(s) or one or more associated timer(s) inoperable on one or more shutdown board(s).

AND The loss of voltage relay channels on each affected shutdown board are OPERABLE.

C. One or more loss of C.1 Place the inoperable loss 10 days voltage relay of voltage relay channels inoperable channel(s) in trip.

on one or more shutdown board(s).

AND Two or more degraded voltage relay channels and associated timers on each affected.

shutdown board are OPERABLE.

(cont nued)

El3FN-UNIT 2 3.3-72 Amendment No. 253

LOP Instrumentation 3.3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two or more degraded D.1 Verify by administrative Immediately voltage relay channels or means that the other one or more associated shutdown boards and timers inoperable on one undervoltage relay shutdown board. channels and associated timers are OPERABLE.

AND AND The loss of voltage relay channel(s) inoperable on D.2 Place the inoperable 5 days the same shutdown channels in trip.

board.

E. Required Action and E.1 Declare associated diesel Immediately associated Completion generator (DG)

Time not met. inoperable.

B3FN-UNIT 2 3.3-73 Amendment No. 253

LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CALIBRATION. 184 days SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. 12 months SR 3.3.8.1.3 Perform LOGIC SYSTEM FUNCTIONAL 24 months TEST.

BFN-UNIT 2 3.3-74 Amendment No. 255 November 30, 1998

LOP Instrumentation

. 3.3.8.1 Table 3.3.8.1-1 (page 1 of 1)

Loss of Power Instrumentation FUNCTION REQUIRED CHANNELS SURVEILLANCE ALLOWABLE PER BOARD REQUIREMENTS VAI.UE

1. 4.16 kV Shutdown Board Undervoltage (Loss of Voltage) 2 SR 3.3.8.1.2 Reset at 2813 Vand

a. Board Undervoltage SR 3.3.8.1.3 52927 V

b. Diesel Start Initiation Time Delay 2 SR 3.3.8.1.2 Z 1.4 seconds and SR 3.3.8.1.3 £1.6 seconcls

2. 4.16kV Shutdown Board Undervoltage (Degraded Voltage)

a. Board Undervoltage 3 SR 3.3.8.1.1i 3900 V and 3940 V SR 3.3.8.1.3 b.1 Time Delay . 1 SR 3.3.8.1.2 20.2 second:; and SR 3.3.8.1.3 S 0.4 secondc; b2 Time Delay 1 SR 3.3.8.1.2 2 3 seconds sind SR 3.3.8.1.3 s5seconds b.3 Time Delay 1 SR 3.3.8.1.2 a 5.15 seconcs and SR 3.3.8.1.3 £5.65 seconds b.4 Time Delay 1 SR 3.3.8.1.2 a 0.9 seconds and SR 3.3.8.1.3 s 1.7 seconds BFN-UNIT 2 3.3-75 Amendment No. 253

RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION

3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring I-CO 3.3.8.2 Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply.

APPLICABILITY: MODES 1, 2, and 3, MODES 4 and 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours3 days 0.429 weeks 0.0986 months power supplies with one inservice power supply(s) electric power monitoring from service.

assembly inoperable.

B. One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power supplies with both inservice power supply(s) electric power monitoring from service.

assemblies inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or

3. C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

E3FN-UNIT 2 3.3-76 Amendment No. 253

RPS Electric Power Monitoring

- 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to fully Immediately associated Completion insert all insertable Time of Condition A or B control rods in core cells not met in MODE 4 or 5 containing one or more with any control rod fuel assemblies.

withdrawn from a core cell containing one or more fuel assemblies.

U ._ _ _ __._ _

EFN-UN1T 2 3.3-77 Amendment No. 253

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The 184 days Allowable Values shall be:

a. Overvoltage < 132 V, with time delay set to < 4 seconds.

b. Undervoltage 2 108.5 V, with time delay set to < 4 seconds.

c. Underfrequency 2 56 Hz, with time delay set to < 4 seconds.

SR 3.3.8.2.3 Perform a system functional test. 24 months BFN-UNIT 2 3.3-78 Amendment No. 255 November 30, 1998

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation. I OR One recirculation loop may be in operation provided the following I limits are applied when the associated LCO is applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

single loop operation limits specified in the COLR;

c. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power - High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation; APPLICABILITY: MODES 1 and 2.

BFN-UNIT 2 3.4-1 Amendment No. 258 March 05, 1999

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 24 hours1 days 0.143 weeks 0.0329 months not met. of the LCO.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A not met.

OR No recirculation loops in operation.

I BFN-UNIT 2 3.4-2 Amendment No. 258 March 05, 1999

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 ---------------------NOTE--------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow 24 hours1 days 0.143 weeks 0.0329 months mismatch with both recirculation loops in operation is:

a. < 10% of rated core flow when operating at < 70% of rated core flow; and

b. < 5% of rated core flow when operating at

Ž 70% of rated core flow.

I BFN-UNIT 2 3.4-3 Amendment No. 258 March 05, 1999

Recirculation Loops Operating 3.4.1 Figure 3.4.1-1 (Deleted Per TS 354)

BFN-UNIT 2 3.4-4 Amendment No. 258 March 05, 1999

Jet Pumps 3.4.2

3.4 REACTOR COOLANT SYSTEM (RCS)

3.4.2 Jet Pumps LCO 3.4.2 All jet pumps shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more jet pumps A.1 . Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months inoperable.

13FN-UNIT 2 3.4-5 Amendment No. 253

.Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 NOTES

1. Not required to be performed until 4 hours0.167 days 0.0238 weeks 0.00548 months after associated recirculation loop is in operation.

2. Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after > 25% RTP.

Verify at least one of the following criteria (a, 24 hours1 days 0.143 weeks 0.0329 months kb, or c) is satisfied for each operating recirculation loop:

a. Recirculation pump flow to speed ratio differs by

5% from established patterns, and jet pump loop flow to recirculation pump speed ratio differs by <5% from established patterns.

b. Each jet pump diffuser to lower plenum differential pressure differs by < 20% from established patterns.

c. Each jet pump flow differs by < 10% from established patterns.

U -

EFN-UNIT 2 3.4-6 Amendment No. 253

S/RVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (S/RVs)

L.CO 3.4.3 The safety function of 12 S/RVs shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months S/RVs inoperable.

AND A.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months U .- ..

.EFN-UNIT 2 3.4-7 Amendment No. 253

S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS I-SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift settings of the In accordance required 12 S/RVs are within +/- 3% of the with the Inservice setpoint as follows: Testing Program Number of Setpoint S/RVs (iSia' 4 1135 4 1145 5 1155 Following testing, lift settings shall be within

+/- 1%.

SR 3.4.3.2 ---------------------------NOTE------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after reactor steam pressure and flow are adequate to perform the test.

Verify each required S/RV opens when 24 months manually actuated.

BFN-UNIT 2 3.4-8 Amendment No. 255 November 30, 1998

w - -

RCS Operational LEAKAGE 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE I.CO 3.4.4 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. < 5 gpm unidentified LEAKAGE; and

c.

30 gpm total LEAKAGE averaged over the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period; and

d.

2 gpm increase in unidentified LEAKAGE within the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period in MODE 1.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS a -

CONDITION REQUIRED ACTION COMPLETION TIME A. Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours0.167 days 0.0238 weeks 0.00548 months not within limit. . within limits.

OR Total LEAKAGE not within limit.

B. Unidentified LEAKAGE B.1 Reduce LEAKAGE 4 hours0.167 days 0.0238 weeks 0.00548 months increase not within limit. increase to within limits.

OR (continued)

EIFN-UNIT 2 3.4-9 Amendment No. 253

RCS Operational LEAKAGE 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION THAE B. (continued) B.2 Verify source of 4 hours0.167 days 0.0238 weeks 0.00548 months unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months OR Pressure boundary LEAKAGE exists.

1BFN-UNIT 2 3.4-1 0 Amendment No. 253

RCS Operational LEAKAGE 3.4.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 12 hours0.5 days 0.0714 weeks 0.0164 months and unidentified LEAKAGE increase are within limits.

EIFN-UNIT 2 3.4-1 1 Amendment No. 253

RCS Leakage Detection Instrumentation 3.4.5

'3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Leakage Detection Instrumentation I.CO 3.4.5 The following RCS leakage detection instrumentation shall be OPERABLE:

a. Drywell floor drain sump monitoring system; and

b. One channel of either primary containment atmospheric particulate or atmospheric gaseous monitoring system.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell floor drain sump A.1 Restore drywell floor 24 hours1 days 0.143 weeks 0.0329 months monitoring system drain sump monitoring inoperable. system to OPERABLE status.

(continued)

E;FN-UNIT 2 3.4-1 2 Amendment No. 253

RCS Leakage Detection Instrumentation 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required primary B.1 Analyze grab samples of Once per I containment atmospheric primary containment 12 hours0.5 days 0.0714 weeks 0.0164 months monitoring system atmosphere.

inoperable.

AND B.2 Restore required primary 30 days containment atmospheric monitoring system to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months D. All required leakage D.1 Enter LCO 3.0.3. Immediately detection systems inoperable.

BFN-UNIT 2 3.4-1 3 Amendment No. 253 286

RCS Leakage Detection Instrumentation 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Perform a CHANNEL CHECK of required 12 hours0.5 days 0.0714 weeks 0.0164 months primary containment atmospheric monitoring system instrumentation.

SR 3.4.5.2 Perform a CHANNEL FUNCTIONAL TEST of 31 days required primary containment atmospheric monitoring system instrumentation.

SR 3.4.5.3 Perform a CHANNEL CALIBRATION of 184 days required drywell sump flow integrator instrumentation.

SR 3.4.5.4 Perform a CHANNEL CALIBRATION of 24 months required leakage detection system instrumentation.

BFN-UNIT 2 3.4-14 Amendment No. 255 November 30, 1998

RCS Specific Activity 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Specific Activity LCO 3.4.6 The specific activity of the reactor coolant shall be limited to DOSE EQUIVALENT 1-131 specific activity *3.2 ,ICi/gm.

APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME:

A. Reactor coolant specific - --- NOTE-activity > 3.2 giCi/gm and LCO 3.0.4.c is applicable. I

< 26.0 jiCi/gm DOSE EQUIVALENT 1-131.

A.1 Determine DOSE Once per 4 hours0.167 days 0.0238 weeks 0.00548 months EQUIVALENT 1-131.

AND A.2 Restore DOSE 48 hours2 days 0.286 weeks 0.0658 months EQUIVALENT 1-131 to within limits.

(continued)

BFN-UNIT 2 3.4-15 Amendment No. 2 &iT 286

RCS Specific Activity 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Determine DOSE Once per 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion EQUIVALENT 1-131.

Time of Condition A not met. AND O1R 8.2.1 Isolate all main steam 12 hours0.5 days 0.0714 weeks 0.0164 months lines.

Reactor coolant specific OR activity > 26.0 p.Cilgm DOSE EQUIVALENT B.2.2.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months AND B.2.2.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months BFN-UNIT 2 3.4-1 6 Amendment No. 253

RCS Specific Activity 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 ' NOTE Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 7 days 1-131 specific activity is < 3.2 g.Ci/gm.

BFN-UNIT 2 3.4-1 7 Amendment No. 253

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCD 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

IN I_ 13 - - -_- - - _

1. Both required RHR shutdown cooling subsystems and' recirculation pumps may not be in operation for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months for performance of Surveillances.

APPLICABILITY: MODE 3, with reactor steam dome pressure less than the RHR low pressure permissive pressure.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required RHR A.1 Initiate action to restore Immediately shutdown cooling required RHR shutdown subsystems inoperable. cooling subsystem(s) to OPERABLE status.

AND (continued)

BFN-UNIT 2 3.4-18 Amendment No. 2-53 286

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months method of decay heat removal is available for each inoperable required RHR shutdown cooling subsystem.

AND A.3 Be in MODE 4. 24 hours1 days 0.143 weeks 0.0329 months B. No RHR shutdown B.1 Initiate action to restore Immediately cooling subsystem in one RHR shutdown operation. cooling subsystem or one recirculation pump to AND operation.

No recirculation pump in AND operation.

B.2 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from circulation by an alternate discovery of no method. reactor coolant circulation AND Once per 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter AND B.3 Monitor reactor coolant Once per hour temperature and pressure.

E3FN-UNIT 2 3.4-1 9 Amendment blo. 253

RHR Snutaown Cooling System - Hot shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 NOTE Not required to be met until 2 hours0.0833 days 0.0119 weeks 0.00274 months after reactor steam dome pressure is less than the RHR low pressure permissive pressure.

Verify one required RHR shutdown cooling 12 hours0.5 days 0.0714 weeks 0.0164 months subsystem or recirculation pump is operating.

E3FN-UNIT 2 3.4-20 Amendment No. 253

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS)

3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown iLCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

-NOTES-

1. Both required RHR shutdown cooling subsystems and recirculation pumps may not be in operation for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months for performance of Surveillances.

APPLICABILITY: MODE 4.

ACTIONS kIfUrr No _ _ _

_ IfI L_

S'eparate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME:

A. One or two required RHR. AA Verify an alternate I hour, shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable required RHR shutdown cooling Once per subsystem. 24 hours1 days 0.143 weeks 0.0329 months thereafter (continued)

BFN-UNIT 2 3.4-21 Amendment No. 253

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in circulating by an alternate discovery of no operation. method. reactor coolant circulation AND AND No recirculation pump in operation. Once per 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter AND B.2 Monitor reactor coolant. Once per hour temperature and pressure.

BFN-UNIT 2. 3.4-22 Amendment No. 253

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQULENCY SR 3.4.8.1 Verify one required RHR shutdown cooling 12 hours0.5 days 0.0714 weeks 0.0164 months subsystem or recirculation pump is operating.

.EFN-UNIT2 3.4-23 Amendment No. 253

RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (PIT) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within the limits.

APPLICABILITY: At all times.

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

be completed if this Condition is entered. AND A.2 Determine RCS is 72 hours3 days 0.429 weeks 0.0986 months Requirements of the LCO acceptable for continued not met in MODE 1, 2, or operation.

3.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued) 13FN-UNIT 2 3.4-24 Amendment No. 253

RCS P/T Limits 3.4.9 ACTIONS (continued)

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

Condition is entered.

AND Requirements of the LCO C.2 Determine RCS is Prior to entering not met in other than acceptable for operation. MODE 2 or 3 MODES 1,2, and 3.

BFN-UNIT 2 3.4-25 Amendment ND. 253

RCS PT Limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -N-------------------------- NOTES -----------------------

1. Only required to be performed during RCS heatup and cooldown operations or RCS inservice leak and hydrostatic testing when the vessel pressure is > 312 psig.

2. The limits of Figure 3.4.9-2 may be applied during nonnuclear heatup and ambient loss cooldown associated with inservice leak and hydrostatic testing provided that the heatup and cooldown rates are

151F/hour.

3. The limits of Figures 3.4.9-1 and 3.4.9-2 do not apply when the tension from the reactor head flange bolting studs is removed.

Verify: 30 minutes

a. RCS pressure and RCS temperature are within the limits specified by Curves No. 1 and No. 2 of Figures 3.4.9-1 and 3.4.9-2; and

b. RCS heatup and cooldown rates are

< 1000 F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

SFR 3.4.9.2 Verify RCS pressure and RCS temperature Once within 15 are within the criticality limits specified in minutes prior to Figure 3.4.9-1, Curve No. 3. control rod withdrawal for the purpose of achieving criticality (continued)

BFN-UNIT 2 3.4-26 Amendment No.-2i3- 288

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQIJEN4CY SR 3.4.9.3 NOTE Only required to be met in MODES 1,2, 3, and 4 during recirculation pump startup.

Verify the difference between the bottom Once within 15 head-coolant temperature and the reactor minutes prior to pressure vessel (RPV) coolant temperature is each startup of a

145 0F. recirculation pump SR 3.4.9.4 NOTES

1. Only required to be met in MODES 1,2, 3, and 4 during recirculation pump startup.

2. In MODE 2 with both recirculation pumps not in operation, the difference may be s750 F.

Verify the difference between the reactor Once within 15 coolant temperature in the recirculation loop minutes prior to to be started and the RPV coolant each startup of a temperature is< 500F. recirculation pump (con inued)

E3FN-UNIT 2 3.4-27 Amendment No. 253

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 1-SR 3.4.9.5 ---- ---- ---- --- .-NOTES.,

1. Only required to be performed when tensioning the reactor vessel head bolting studs.

2. The reactor vessel head bolts may be partially tensioned (four sequences of the seating pass) provided the studs and flange materials are > 701F.

Verify reactor vessel flange and head flange 30 minutes temperatures are > 830F.

SR 3.4.9.6 --------------------------NOTE-------------------------

Not required to be performed until 30 minutes; .

after RCS temperature < 850F in MODE 4.

Verify reactor vessel flange and head flange 30 minutes temperatures are > 830F.

SR 3.4.3.7 -------------------------- NOTE-------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after RCS temperature < 100'F in MODE 4.

Verify reactor vessel flange and head flange 12 hours0.5 days 0.0714 weeks 0.0164 months temperatures are > 830F.

=

BFN-UNII'2 3.4-28 Amendment No. 253- 288

RCS P/T Limits 3.4.9 1490 Curve No. 1 Minimum temperature for bottom head during 13)0 mechanical heatup or cooldown following 121)0 BROWNS FERRY UNIT 2 _ -

-/ - -

nuclear shutdown.

CURVES 1, 2, AND 3 l lt 3

-ARE VALID FOR 23 EFPY Curve No. 2

_-OF OPERATION _ Minimum temperature for H 110 upper RPV and beltline pi during mechanical I 10(0 heatup or cooldown Q following nuclear 9(0 shutdown.

0 Es Curve No. 3 W 8) 0 Minimum temperature for o:

core operation (criticality).

7C)0 H

0 5

CH Es4 610O Notes These curves include sufficient margin to provide protection.

5C'0 against feedwate::

nozzle degradation.

The curves allow for q 40C0 shifts in RTw of the Reactor vessel beltline Ea 3C0 materials, in accordance with Reg.

Guide 1.99, Rev. 2, to 200 compensate for radiation embritt:lement 100 BOTTOM HEA_F 1 1 FLANGE - .

for 23 EFPY.

0 68 F - i , REGION 83%'F- The acceptable area for 0 operation is to the right of the applicable 0 50 100 150 200 250 curves.

MINIMUM REACTOR VESSEL METAL TEMPERATURE C(F)

Figure 3.4.9-1 PressurelTemperature Limits for Mechanical Heatup, Cooldown following Shutdown, and Reactor Critical Operations BFWLINIT 2 3.4-29 Amendment No. 257, 275, 288

RCS P/T Limits 3.4.9 Curve No. 1 1 4.00 Minimum temperature for bottom head 1 .00 during in-service

-BROWNS FERRY UNIT 2 __ leak or hydrostatic CURVES 1 AND 2 ARE testing.

12:00 -VALID FOR 23 EFPY OF _ t- _ -1 OPERATION Curve No. 2 1100 Minimum temperat:ure for upper RPV and H beltline during in-cn lC00 service leak or hydrostatic testing.

900 Pd o1 0 800 Notes These curves include sufficient margin to 700 provide protection against feedwater N

H E4 600

_~~~~_

I__ I __/}1____ _

nozzle degradation.

The curves allow for shifts in RT= oE the IT 500 W.

Reactor vessel P-beltline materials, 400 in accordance with CO1 Reg. Guide 1.99, Rev.

2, to compensate for 300 radiation embrittlement for 23 200 BOTTOM - EFPY.

HEAD FLANGE 68F _ =--

- REGION The acceptable area 100 for operation is to

- __3_F 8 the right of the 0 applicable curves.

0 50 100 150 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)

Figure 3.4.9-2 Pressure/Temperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNI1 2 3.4-29a Amendment No. 288

RCS P/T Limits 3.4.9 14,00 Curve No. 1 Minimum temperature

-BROWNS FERRY UNIT 1-2_

-- CURVES 1, 2, AND 3I _ l for bottom hea.d 1i 00 during mechanical ARE VALID FOR 30 2

_EFPY OF OPERATION -- heatup or cooldown following nuclear 1200 shutdown.

Curve No. 2 OH 1100 H Minimum temperature 02 Pd for upper RPV and beltline during R 1000 mechanical heatup or cooldown following P4 900 nuclear shutdown.

0 E-4 Curve No. 3 to 800 Minimum temperature to for core operation (criticality).

PX 700 0

E4 Notes These curves include 600 I_ I- -- -- -- 183 -F sufficient margin to provide protection H against feedwa:er H

Es 5 00 nozzle degradation.

The curves allow for H

shifts in RT= of the W 4110 Reactor vessel beltline materials, 3o in accordance with Reg. Guide 1.99, Rev.

Pt 2, to compensate for radiation 200 embrittlement for 30 EFPY.

1()0 The acceptable area 68 REIO for operation is to the right of the 0

applicable curves.

0 50 100 150 200 250 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)

Figure 3.4.9-1 Pressure/Temperature Limits for Mechanical Heatup, Cooldown following Shutdown, and Reactor Critical Operations BFN-UNIT 2 3.4-29b Amendment No. 288

RCS P/T Limits 3.4.9 1400 Curve No. 1 Minimum temperature 1330 for bottom head BROWNS FERRY UNIT 2 during in-service

-CURVES 1 AND 2 ARE VALID FOR 30 EFPY 12)0 -OF OPERATION 1--- leak or hydrostatic testing.

Curve No. 2 111)0 Minimum temperat:ure H for upper RPV and to beltline during in-10()0 I- - 7 service leak or hydrostatic test~ing.

I of 9()0 0

E-4 W 800 Notes tn U2 These curves include sufficient margin to 700 provide protection against feedwater I 6C'0 nozzle degradation.

The curves allow for shifts in RTx of the M

P:

5C0 Reactor vessel beltline materials,

.in accordance with 400 Reg. Guide 1.99, Rev.

2, to compensate for N 300 radiation embrittlement for 30 EFPY.

-m.. J:14L X: -

200 The acceptable area BOTTO- I- - - - for operation is to HEAD _ _

the right of the 100 680 F - FLANGE -

II REGION applicable curves.

830F 0

0 50 100 150 200 250 MINIMnM REACTOR VESSEL METAL TEMPERATURE (OF)

Figure 3.4.9-2 Pressure/Temperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNIT 2 3.4-29c Amendment No. 288

Reactor Steam Dome Pressure 3.4.10

3.4 REACTOR COOLANT SYSTEM (RCS)

3.4.10 Reactor Steam Dome Pressure I-CO 3.4.10 The reactor steam dome pressure shall be < 1050 psig.

APPLICABILITY: MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within limit. dome pressure to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met.

BFN-UNIT 2 3.4-30 Amendment ND. 254 SEP 0 3 13 S

Reactor Steam Domi3 Pressure 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 12 hours0.5 days 0.0714 weeks 0.0164 months

< 1050 psig. _

BFIN-UNIT 2 3.4-31 Amendment No. 254 SEP 0 (0 198

ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CC)RE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (IHPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure < 150 psig.

ACTIONS I If*T*

- ------------------------------------- 14 kJ I =--------------------- ----------------- 11------- - -

LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days(')

injection/spray subsystem ECCS injection/spray inoperable. subsystem(s) to OPERABLE status.

OR One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.

(continued)

') - This Completion Time may be extended to 14 days on a one-time basis. This temporary approval expires June 1, 2005. I 13FN-UNIT 2 3.5-1 Amendment No. 253,269,i-26, 294

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME El. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

BFN-UNIT 2 3.5-1 a Amendment No. 286 1

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. HPCI System inoperable. C.1 Verify by administrative Immediately means RCIC System is OPERABLE.

AND C.2 Restore HPCI System to 14 days OPERABLE status.

D. HPCI System inoperable. D.1 Restore HPCI System to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

AND OR Condition A entered. 72 hours3 days 0.429 weeks 0.0986 months D.2 Restore low pressure ECCS injection/spray

.1I subsystem to OPERABLE status.

E. One ADS valve E.1 Restore ADS valve to 14 days inoperable. OPERABLE status.

F. One ADS valve F.1 Restore ADS valve to 72 hours3 days 0.429 weeks 0.0986 months inoperable. OPERABLE status.

AND OR F.2 Restore low pressure 72 hours3 days 0.429 weeks 0.0986 months Condition A entered. ECCS injection/spray subsystem to OPERABLE I status.

(continued) 13FN-UNIT 2 3.5-2 Amendment No. 253 209

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Two or more ADS valves G.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months inoperable.

AND OR G.2 Reduce reactor steam 36 hours1.5 days 0.214 weeks 0.0493 months Required Action and dome pressure to associated Completion < 150 psig.

Time of Condition C, D, E, or F not met.

H. Two or more low pressure H.1 Enter LCO 3.0.3. Immediately ECCS injection/spray subsystems inoperable for reasons other than Condition A.

OR HPCI System and one or more ADS valves inoperable.

BFN-UNIT 2 3.5-3 Amendment No. 23T 2'69 I . . : ;...- .. i

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.1.2 NOTE.

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) low pressure permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.1.3 Verify ADS air supply header pressure is 2Ž81 31 days psig.

SR 3.5.1.4 Verify the LPCI cross tie valve is closed and 31 days power is removed from the valve operator.

(continued)

.E;FN-UNIT 2 3.5-4 Amendment No. 253

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.5 NOTES

1. Only required to be performed when in MODE 4 > 48 hours2 days 0.286 weeks 0.0658 months .

2. Not required to be performed if performed within the previous 31 days.

Verify each recirculation pump discharge Once prior to valve cycles through one complete cycle of entering MODE 2 full travel. from MODE 3 or 4

SR 3.5.1.6 Verify the following ECCS pumps develop the In accordance specified flow rate against a system head. with the Inservice corresponding to the specified pressure. Testing Program SYSTEM HEAD CORRESPONDING TO A VESSEL TO TORUS NO. OF DIFFERENTIAL SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray 2 6250 gpm 2 2 105 psid INDICATED NO. OF SYSTEM SYSTEM FLOW RATE PUMPS PRESSURE LPCI 2 12,000 gpm 2 - 250 psig LPCI . 9,000 gpm 225 1 psig (continued)

E FN-UNIT 2 3.5-5 Amendment No. 253

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.7 ----------------------- NOTE-------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 1040 and 92 days 2 950 psig, the HPCI pump can develop a flow rate Ž 5000 gpm against a system head corresponding to reactor pressure.

SR 3.5.1.8 --------------------------NOTE----------- -------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 165 psig, the 24 months HPCI pump can develop a flow rate Ž 5000 gpm against a system head corresponding to reactor pressure.

SR 3.5.1.9 ------------------------ NOTE-------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem 24 months actuates on an actual or simulated automatic initiation signal.

(continued)

BFN-UNIT 2 3.5-6 Amendment No. 255 November 30, 1998

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.10 --------------------NOTE-----------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.

SR 3.5.1.11 ------------------------ NOTE-------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after reactor steam pressure and flow are adequate to perform the test.

Verify each ADS valve opens when manually 24 months actuated.

SR 3.5.1.12 Verify automatic transfer of the power supply 24 months from the normal source to the alternate source for each LPCI subsystem inboard injection valve and each recirculation pump discharge valve.

BFN-UNIT 2 3.5-7 Amendment No. 255 November 30, 1998

ECCS - Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 ECCS - Shutdown L.CO 3.5.2 Two low pressure ECCS injection/spray subsystems shall be OPERABLE.

APPLICABILITY: MODE 4, MODE 5, except with the spent fuel storage pool gates remroved and water level Ž 22 ft over the top of the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ECCS A.1 Restore required ECCS 4 hours0.167 days 0.0238 weeks 0.00548 months injection/spray subsystem injection/spray subsystem inoperable. to OPERABLE status.

B. Required Action and B.1 Initiate action to suspend Immediately associated Completion OPDRVs.

Time of Condition A not met.

C. Two required ECCS C.1 Initiate action to suspend Immediately injection/spray OPDRVs.

subsystems inoperable.

AND C.2 Restore one ECCS 4 hours0.167 days 0.0238 weeks 0.00548 months injection/spray subsystem to OPERABLE status.

(continued)

BFN-UNIT 2 3.5-8 Amendment No. 253

ECCS - Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and D.1 Initiate action to restore Immediately associated Completion secondary containment to Time not met. OPERABLE status.

AND D.2 Initiate action to restore Immediately two standby gas treatment subsystems to OPERABLE status.

AND D.3 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

U -

EIFN-UNIT 2 3.5-9 Amendment No. 253

ECCS - ',hutdown 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required ECCS 12 hours0.5 days 0.0714 weeks 0.0164 months injection/spray subsystem, the suppression pool water level is 2 -6.25 inches with or

-7.25 inches without differential pressure control.

SR 3.5.2.2 Verify, for each required ECCS 31 days injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.2.3 NOTE One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued)

BFN-UNIT 2 I3.5-10 Amendment No. 253

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify each required ECCS pump develops In accordance the specified flow rate against a system head with the Inservice corresponding to the specified pressure. Testing Program SYSTEM HEAD CORRESPONDING TO A VESSEL TO TORUS NO. OF DIFFERENTIAL SYSTEM FLOW RATE PUMPS PRESSURE OF CS Ž6250gpm 2 2 105 psid INDICATED NO. OF SYSTEM SYSTEM FLOW RATE PUMPS PRESSURE LPCI 2 9,000 gpm 1 2 125 psig SR 3.5.2.5 -------------------------- NOTE-------------------------

Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray 24 months subsystem actuates on an actual or simulated automatic initiation signal.

BFN-UNIT 2 3.5-11 Amendment No. 255 November 30, 1998

RCIC System 3.5.3 3.E5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS KI rArT i------ - ---- ---- ------------------------- I U I -----

LCO 3.0.4.b is not applicable to RCIC.

I CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable. A.1 Verify by administrative Immediately means High Pressure Coolant Injection System is OPERABLE.

AND A.2 Restore RCIC System to 14 days OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met. AND B.2 Reduce reactor steam 36 hours1.5 days 0.214 weeks 0.0493 months dome pressure to

150 psig.

BFN-UNIT 2 3.5-12 Amendment No. 253T 286

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled with 31 days water from the pump discharge valve to the injection valve.

SR 3.5.3.2 Verify each RCIC System 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 3.5.3.3 -------------------------NOTE-------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 1040 psig and 92 days

Ž 950 psig, the RCIC pump can develop a flow rate Ž 600 gpm against a system head corresponding to reactor pressure.

SR 3.5.3.4 ---------- NOTE-------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 165 psig, the 24 months RCIC pump can develop a flow rate Ž 600 gpm against a system head corresponding to reactor pressure.

(continued)

BFN-UNIT 2 3.5-13 Amendment No. 255 November 30, 1998

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5 ---------------------- NOTE-------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an 24 months actual or simulated automatic initiation signal.

BFN-UNIT 2 3.5-14 Amendment No. 255 November 30, 1998

Primary Containment 3.6.1.1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment LCO 3.6.1.1 Primary containment shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. containment to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months U -

.EIFN-UNIT 2 3.6-1 Amendment No. 253

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and In accordance leakage rate testing except for primary with the Primary containment air lock testing, in accordance Containment with the Primary Containment Leakage Rate Leakage Rate Testing Program. Testing Program SR 3.6.1.1.2 Verify drywell to suppression chamber 24 months differential pressure does not decrease at a rate > 0.25 inch water gauge per minute over a 10 minute period at an initial differential pressure of 1 psid.

BFN-UNIT 2 3.6-2 Amendment No. 255 November 30, 1998

Primary Containment Air Lock 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Lock ILCO 3.6.1.2 The primary containment air lock shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS K1 rTCe

.. LM' I r- .1

1. Entry and exit is permissible to perform repairs of the air lock components.

2'. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. One primary containment NOTES air lock door inoperable. 1. Required Actions A.1, A.2, and A.3 are not applicable if both doors in the air lock 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 (continued)

E3FN-UNIT 2 3.6-3 Amendment No. 253

Primary Containment Air Lock 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Lock the OPERABLE 24 hours1 days 0.143 weeks 0.0329 months door closed.

AND A.3 NOTE Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked'closed by administrative means.

Verify the OPERABLE Once per 31 days door is locked closed.

(continued)

EIFN-UNIT 2 3.6-4 Amendment No. 253

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Primary containment air B.1 NOTES -

lock interlock mechanism 1. Required Actions B.1, inoperable. B.2, and B.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2. Entry into and exit from containment is

-permissible under the control of a dedicated individual.

Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

AND

._ ._ (continued) 13FN-UNIT 2 3.6-5 Amendment No. 253

Primary Containment Air Lock 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Lock an OPERABLE door 24 hours1 days 0.143 weeks 0.0329 months closed.

AND B.3 NOTE Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify an OPERABLE Once per :31 days door is locked closed.

C. Primary containment air C.1 Initiate action to evaluate Immediately lock inoperable for primary containment reasons other than overall leakage rate per Condition A or B. LCO 3.6.1.1, using

. current air lock test results.

AND C.2 Verify a door is closed. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND C.3 Restore air lock to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

(continued) 13FN-UNIT 2 3.6-6 Amendment No. 253

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months 13FN-UNIT 2 3.6-7 Amendment No. 253

Primary Containment Air Lock 3.6.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 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 applicable to SR 3.6.1.1.1.

Perform required primary containment air lock In accordance leakage rate testing in accordance with the with the Primary Primary Containment Leakage Rate Testing Containment Program. Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary 24 months containment air lock can be opened at a time.

13FN-UNIT 2 3.6-8 Amendment No. 253

PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS

3.6.1.3 Primary Containment Isolation Valves (PCIVs)

I-CO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."

!BFN-U NIT 2 3.6-9 Amendment No. 253

PCIVs 3.6.1.3 ACTIONS

_ TOM, Uo'___

1. Penetration flow paths except for 18 and 20 inch purge valve penetration flow paths 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 PCIVs.

i4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primanr Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.

CONDITION REQUIRED ACTION COMPLETION TIM;:

A. -. NOTE A.1 Isolate the affected .4 hours0.167 days 0.0238 weeks 0.00548 months except for Only applicable to penetration flow path by main steam line penetration flow paths use of at least one closed with two PCIVs. and de-activated AND automatic valve, closed manual valve, blind 8 hours0.333 days 0.0476 weeks 0.011 months for main One or more penetration flange, or check valve steam line flow paths with one PCIV with flow through the inoperable except due to valve secured.

MSIV leakage not within limits.

AND (continued)

BFN-UNIT 2' 3.6-1 0 Amendment No. 253

PCIVs 3.6.1.3 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 is for isolation isolated. devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4, if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment (continued)

EIFN-UNIT 2 3.6-1 1 Amendment No. 253

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 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 by penetration flow paths use of at least one closed with two PCIVs. and de-activated automatic valve, closed manual valve, or blind One or more penetration flange.

flow paths with two PCIVs inoperable except due to MSIV leakage not within limits.

C. . NOTE C.1 Isolate the affected 4 hours0.167 days 0.0238 weeks 0.00548 months except for Only applicable to penetration flow path by excess flow check penetration flow paths use of at least one closed valves (EFCVs) with only one PCIV. and de-activated automatic valve, closed AND manual valve, or blind One or more penetration flange. 12 hours0.5 days 0.0714 weeks 0.0164 months for flow paths with one PCIV EFCVs inoperable. AND C.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 is isolated.

(continued)

EIFN-UNIT 2 3.6-1 2 Amendment No. 253

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration D.1 Restore leakage rate to 4 hours0.167 days 0.0238 weeks 0.00548 months flow paths with MSIV within limit.

leakage not within limits.

E. Required Action and E.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A, B, C, AND or D not met in MODE 1, 2, or 3. E.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months F. Required Action and F.1 Initiate action to suspend Immediately associated Completion operations with a Time of Condition A, B, C, potential for draining the or D not met for PCIV(s) reactor vessel (OPDRVs).

required to be OPERABLE during OR MODE 4 or 5..

F.2 ~ NOTE Only applicable for inoperable RHR Shutdown Cooling Valves.

Initiate action to restore Immediately valve(s) to OPERABLE status.

13FN-UNIT 2 3.6-1 3 Amendment No. 253

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 -NOTE Not required to be met when the 18 and 20 inch primary containment purge valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 18 and 20 inch primary 31 days containment purge valve is closed.

SR 3.6.1.3.2 NOTES

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

3. Not required to be performed for instrument panel valves, vent and drain valves, leak-off lines, and test connection valves.

Verify each primary containment isolation 31 days manual valve and blind flange that is located outside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

(con :inued) 13FN-UNIT 2 3.6-14 Amendment No. 253

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued) ---

SURVEILLANCE FREQUENCY SR 3.6.1.3.3 I 1mJ r-.11

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

3. Not required to be performed for vent and drain valves, leak-off lines, and test connection valves.

Verify each primary containment manual Prior to entering isolation valve and blind flange that is located MODE 2 or 3 inside primary containment and not locked, from MODE 4 if sealed, or otherwise secured and is required primary to be closed during accident conditions is containment was closed. de-inerted while in MODE 4W, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore 31 days probe (TIP) shear isolation valve explosive charge.

A

.EIFN-UNIT 2 3.6-1 5 Amendment No. 253

6ClVs 3.6. 1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.5 Verify the isolation time of each power In accordance operated, automatic PCIV, except for MSIVs, with the Inservice is within limits. Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV is 23 In accordance seconds and s 5 seconds. with the Inseivice Testing Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to the 24 months isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify a representative sample of reactor 24 months instrumentation line EFCVs actuate to the isolation position on a simulated instrument line break signal.

SR 3.6.1.3.9 Remove and test the explosive squib from 24 months on a each shear isolation valve of the TIP System. STAGGEREC TEST BASIS SR 3.6.1.3.10 Verify leakage rate through each MSIV is In accordance S 100 scfh and that the combined leakage with the Primary rate for all four main steam lines is

150 scfh Containment when tested at Ž 25 psig. Leakage Rate Testing Program' SR 3.6.1.3.11 Verify combined leakage through water In accordance tested lines that penetrate primary with the Primary containment are within the limits specified in Containment the Primary Containment Leakage Rate Leakage Rate Testing Program. Testing Program BF:N-UNIT 2 3.6-16 Amendment No. 268 :

253, 255, 263, :.g

Drywell Air Temperature 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Drywell Air Temperature LCO 3.6.1.4 Drywell average air temperature shall be < 1500F.

APPLICABILITY: MODES 1,2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell average 8 hours0.333 days 0.0476 weeks 0.011 months temperature not within air temperature to within limit. limit.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months BFN-UNIT 2 3.6-1 7 Amendment ND. 253

Drywell Air Temperature 3.6.1.4 SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQIJENCY SR 3.6.1.4.1 Verify drywell average air temperature is 24 hours1 days 0.143 weeks 0.0329 months within limit.

BFN-UNIT 2 3.6-1 8 Amendment N~o. 253

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Reactor Building-to-Suopression Chamber Vacuum Breakers I.CO 3.6.1.5 Each reactor building-to-suppression chamber vacuum breaker shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

- NU I-separate Condition entry is allowed for each line.

U __ _ _ _ __ _ _ _ _ -

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more lines with A.1 Close the open vacuum 72 hours3 days 0.429 weeks 0.0986 months one reactor breaker.

building-to-suppression chamber vacuum breaker

.not closed.

B. One or more lines with B.1 Close one open vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months two reactor breaker.

building-to-suppression chamber vacuum breakers not closed.

(continued)

EI;FN-UNIT 2 3.6-1 9 Amendment No. 253

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One line with one or more C.1 Restore the vacuum 72 hours3 days 0.429 weeks 0.0986 months reactor breaker(s) to OPERABLE building-to-suppression status.

chamber vacuum breakers inoperable for opening.

D. Two lines with one or D.1 Restore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months more reactor breakers in one line to building-to-suppression OPERABLE status; chamber vacuum breakers inoperable for opening.

E. Required Action and E.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months

. U EIFN-UNIT 2 3.6-20 Amendment No. 253

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 - NOTES--

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed. 14 days SR 3.6.1.5.2 Perform a functional test of each vacuum 92 days breaker.

SR 3.6.1.5.3 Verify the opening setpoint of each vacuum 24 months breaker is < 0.5 psid.

BFN-UNIT 2 3.6-21 Amendment No. 255 November 30, 1998

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6

3.6 CONTAINMENT SYSTEMS

3.6.1.6. Suppression Chamber-to-Drywell Vacuum Breakers ILCO 3.6.1.6 Ten suppression chamber-to-drywell vacuum breakers shall be OPERABLE for opening.

AND Twelve suppression chamber-to-drywell vacuum breakers shall be closed, except when performing their intended function.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required suppression A.1 Restore one vacuum 72 hours3 days 0.429 weeks 0.0986 months chamber-to-drywell breaker to OPERABLE vacuum breaker status.

inoperable for opening.

B. One suppression B.1 Close the open vacuum 2 hours0.0833 days 0.0119 weeks 0.00274 months chamber-to-drywell breaker; vacuum breaker not closed.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months EIFN-UNIT 2 3.6-22 Amendment No. 253

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 --------------------- NOTES----------------------

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. One drywell suppression chamber vacuum breaker may be nonfully closed so long as it is determined to be not more than 30 open as indicated by the position lights.

Verify each vacuum breaker is closed. 14 days SR 3.6.1.6.2 Perform a functional test of each required In accordance vacuum breaker. with the Inservice Testing Program SR 3.6.1.6.3 Verify the differential pressure required to 24 months open each vacuum breaker is < 0.5 psid.

BFN-UNIT 2 3.6-23 Amendment No. 255 November 30, 1998

Suppression Pool Average Temperature 3.6.2.1 3.6 CONTAINMENT SYSTEMS 3.6.2.1 Suppression Pool Average Temperature LCO 3.6.2.1 Suppression pool average temperature shall be:

a.

951F when any OPERABLE intermediate range monitor (IRM) channel is > 70/125 divisions of full scale on Range 7 and no testing that adds heat to the suppression pool is being performed;

b.

105OF when any OPERABLE IRM channel is > 70/125 divisions of full scale on Range 7 and testing that adds heat to the suppression pool is being performed; and

c.

110F when all OPERABLE IRM channels are < 70/1:25 divisions of full scale on Range 7.

APPLICABILITY: MODES 1,2, and 3.

13FNs-UNIT 2 3.6-24 Amendment No. 253

Suppression Pool Average Temperature 3.6.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool A.1 Verify suppression pool Once per hour average temperature average temperature

> 950 F but* 11 00 F.

11 0OF.

AND AND Any OPERABLE IRM A.2 Restore suppression pool 24 hours1 days 0.143 weeks 0.0329 months channel > 70/125 average temperature to divisions of full scale on

950F.

Range 7.

AND Not performing testing that adds heat to the suppression pool.

B. Required Action and B.1. Reduce THERMAL 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion POWER until all Time of Condition A not OPERABLE IRM met. channels are

70/125.

divisions of full scale on Range 7.

(continued)

BFN-UNIT 2 3.6-25 Amendment No. 253

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued) _

CONDITION REQUIRED ACTION COMPLETION TIMIE C. Suppression pool C.1 Suspend all testing that Immediately average temperature adds heat to the

> 1 050 F. suppression pool.

AND Any OPERABLE IRM channel > 701125 divisions of full scale on Range 7.

AND Performing testing that adds heat to the suppression pool.

D. Suppression pool D.1 Place the reactor-mode Immediately average temperature switch in the shutdown

> 1 10F but

1200F. position.

AND D.2 Verify suppression pool Once per 30 average temperature minutes s1200 F.

AND D.3 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

EIFN-UNIT 2 3.6-26 Amendment No. 253

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool E.1 Depressurize the reactor 12 hours0.5 days 0.0714 weeks 0.0164 months average temperature vessel to < 200 psig.

> 120 0F.

AND E.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months BFN-UNIT 2 3.6-27 Amendment No. 253

Suppression Pool Average Temperature 3.6.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature 24 hours1 days 0.143 weeks 0.0329 months is within the applicable limits.

AND 5 minutes when performing testing that adds heat to the suppression pool BFN-UNIT 2 3.6-28 Amendment No. 253

Suppression Pool Water Level 3.6.2.2

3.6 CONTAINMENT SYSTEMS

3.6.2.2 Suppression Pool Water Level I-CO 3.6.2.2 Suppression pool water level shall be Ž -6.25 inches with and -7.25 inches without differential pressure control and * -1.0 inches.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression pool 2 hours0.0833 days 0.0119 weeks 0.00274 months level not within limits. water level to within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met. AND 8.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months

. EIFN-UNIT 2 3.6-29 Amendment No. 253

Suppression Pool Water Level 3.6.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQIJENCY SR 3.6.2.2.1 Verify suppression pool water level is within 24 hours1 days 0.143 weeks 0.0329 months limits.

EIFN-UNIT 2 3.6-30 Amendment No. 253

RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 --Four RHR suppression pool cooK~ng subsystems shall be- z OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore the RHR 30 days pool cooling subsystem suppression pool cooling inoperable. subsystem to OPERABLE status.

B. Two RHR suppression B.1 Restore one RHR 7 days pool cooling subsystems suppression pool cooling inoperable. subsystem to OPERABLE status.

C. Three or more RHR C.1 Restore required RHR 8 hours0.333 days 0.0476 weeks 0.011 months suppression pool cooling suppression pool cooling subsystems inoperable. subsystems to OPERABLE status.

.1 (continued)

E3FN-UNIT 2 3.6-31 Amendment No. 253,272 Jlh!i,S, ) n

RHR Suppression Pool Cooling 3.6.2.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

-..L - Required Action and D.1 Be in MODE 3. 12 hous ^ -? --

associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months U L _____________________________ I BFN-UNIT 2 3.6-32 Amendment No. 2,53, 272

.: - I . :

RHR Suppression Pool Cooling

. 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each RHR pump develops a flow rate In accordance 2 9000 gpm through the associated heat with the Inservice exchanger while operating in the suppression Testing Program pool cooling mode.

U ___ ____ __ ,,

BFN-UNIT 2 3.6-33 Amendment No. 253

RHR Suppression Pool Spray 3.6.2.4

3.6 CONTAINMENT SYSTEMS

3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ILCO 3.6.2.4 Four RHR suppression pool spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS - .

CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore the RHR 30 days pool spray subsystem suppression pool spray inoperable. subsystem to OPERABLE status.

B. Two RHR suppression B.1 Restore one RHR 7 days pool spray subsystems suppression pool spray inoperable. subsystem to OPERABLE status.

C. Three or more RHR C.1 *Restore required RHR 8 hours0.333 days 0.0476 weeks 0.011 months suppression pool spray suppression pool spray subsystems inoperable. subsystems to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months EIFN-UNIT 2 3.6-34 Amendment No. 253

RHR Suppression Pool Spray 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.4.2 Verify each suppression pool spray nozzle is 5 years unobstructed.

EFN-UNIT 2 3.6-35 Amendment No. 253

RHR Drywell Spray 3.6.2.5 3.6 CONTAINMENT SYSTEMS 3.6.2.5 Residual Heat Removal (RHR) Drywell Spray L.CO 3.6.2.5 Four RHR drywell spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR drywell spray A.1 Restore the RHR drywell 30 days subsystem inoperable. spray subsystem to OPERABLE status.

B. Two RHR drywell spray B.1 Restore one RHR drywell 7 days subsystems inoperable. spray subsystem to OPERABLE status.

C. Three or more RHR C.1 Restore required RHR 8 hours0.333 days 0.0476 weeks 0.011 months drywell spray subsystems drywell spray subsystems inoperable. to OPERABLE status.

D. Required Action and D.A Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months EIFN-UNIT 2 3.6-36 Amendment No. 253

RHR Drywell Spray 3.6.2.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY S R 3.6.2.5.1 Verify each RHR drywell spray subsystem 31 days manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.5.2 Verify each drywell spray nozzle is 5 years unobstructed.

S

[3F N-U NIT 2 3.6-37 Amendment No. 253

Drywell-to-Suppression Chamber Differentia' Pressure 3.6.2.6 3.6 CONTAINMENT SYSTEMS 3.6.2.6 Drywell-to-Suppression Chamber Differential Pressure LCO 3.6.2.6 The drywell pressure shall be maintained > 1.1 psid above the pressure of the suppression chamber.

NOTE This differential may be decreased to < 1.1 psid for a maximum of 4 hours0.167 days 0.0238 weeks 0.00548 months during required operability testing of the HPCI system, the RCIC system or the suppression chamber-to-drywell vacuum breakers.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours1 days 0.143 weeks 0.0329 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours1 days 0.143 weeks 0.0329 months prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME:

A. Drywell-to-suppression A.1 Restore differential 8 hours0.333 days 0.0476 weeks 0.011 months chamber differential pressure to within limit.

pressure not within limit.

B. Required Action and B.1 Reduce THERMAL 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion POWER to < 15% RTP.

Time not met.

E)FN-UNIT 2 3.6-38 Amendment No. 253

Drywell-to-Suppression Chamber Differential Pressure 3.6.2.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.6.1 Verify drywell-to-suppression chamber 12 hours0.5 days 0.0714 weeks 0.0164 months differential pressure is within limit.

13FN-UNIT 2 3.6-39 Amendment No. 253

CAD System 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Containment Atmosphere Dilution (CAD) System LCO 3.6.3.1 Two CAD subsystems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME:

A. One CAD subsystem A.1 Restore CAD subsystem 30 days inoperable. to OPERABLE status.

B. Two CAD subsystems B.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. means that the hydrogen control function is AND maintained.

Once per 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter AND B.2 Restore one CAD 7 days subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time not met.

BFN-UNIT 2 3.6-40 Amendment No. 253, 26 5 286

CAD System 3.6.3.1 S'URVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify 2 2500 gal of liquid nitrogen are 31 days contained in each nitrogen storage tank.

SR 3.6.3.1.2 Verify each CAD subsystem 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 or can be aligned to the correct position.

13FN-UNIT 2 3.641 Amendment No. 253

Primary Containment Oxygen Con-entration 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Primary Containment Oxygen Concentration I.CO 3.6.3.2 The primary containment oxygen concentration shall be < 4.0 volume percent.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours1 days 0.143 weeks 0.0329 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours1 days 0.143 weeks 0.0329 months prior to reducing THERMAL POWER to < 15%, RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours1 days 0.143 weeks 0.0329 months oxygen concentration not concentration to within within limit. limit.

B. Required Action and B.1 Reduce THERMAL 8 hours0.333 days 0.0476 weeks 0.011 months associated Completion POWER to

15% RTP.

Time not met.

EIFN-UNIT 2 3.6-42 Amendment No. 253

Primary Containment Oxygen Concentration 3.6.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Verify primary containment oxygen 7 days concentration is within limits.

S EFN-UNIT 2 3.6-43 Amendment No. 253

Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During operations with a potential for draining the reactor vessel I (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours0.167 days 0.0238 weeks 0.00548 months inoperable in MODE 1, 2, containment to.

or 3. OPERABLE status.

B. Required Action and B.l Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A not AND--

met.

B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

BFN-ULN IT 2 3.6-44 Amendment No. 2i3, 290

Secondary Containment 3.6.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION

._ TIME C. Secondary containment C.1 Initiate action to suspend Immediately inoperable during OPDRVs.

OPDRVs.

BFN-LlNIT 2 3.6-45 Amendment No. -22, 290

Secondary Coitainment 3.6.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment 31 days hatches are closed and sealed.

SR 3.6.4.1.2 Verify one secondary containment access 31 days door in each access opening is closed.

SR 3.6.4.1.3 Verify two standby gas treatment (SGT) 24 months on a subsystems will draw down the secondary STAGGERED containment to Ž 0.25 inch of vacuum water TEST BASIS gauge in

120 seconds.

SR 3.6.4.1.4 Verify two SGT subsystems can maintain 24 months on a 2 0.25 inch of vacuum water gauge in the STAGGERED secondary containment at a flow rate TEST BASIS

< 12,000 cfm.

Bl-N-UNIT 2 3.6-46 Amendment No. 253-,255, 264

, , i i

SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCJ 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2,and 3, During operations with a potential for draining the reactor vessel I (OPDRVs).

ACTIONS

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

1. Penetration flow paths 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 SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration A.1 Isolate the affected 8 hours0.333 days 0.0476 weeks 0.011 months flow paths with one SCIV penetration flow path by inoperable. use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND

._ (continued)

BFN-UNlT 2 3.6-47 Amendment No. 2Ia, :290

SCIVs 3.6.4.2 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 is isolated.

B. NOTE B.1 Isolate the affected 4 hours0.167 days 0.0238 weeks 0.00548 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two isolation valves. and de-activated automatic valve, closed manual valve, or blind One or more penetration flange.

flow paths with two SCIVs inoperable.

C. Required Action and CA1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or

3. C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

B3FN-UNIT 2 3.6-48 Amendment 1N'o. 253

SCIVs 3.6.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to suspend Immediately associated Completion OPDRVs.

Time of Condition A or B not met during OPDRVs.

BFN-UNITS 3.6-49 Amendment No. i, 290

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS .

SURVEILLANCE FREQUENCY SR 3.6.4.2.1 Verify the isolation time of each power 92 days operated, automatic SCIV is within limits.

SR 3.6.4.2.2 Verify each automatic SCIV actuates to the 24 months isolation position on an actual or simulated actuation signal.

BFN-UNIT 2 3.6-50 Amendment No. 255 November 30, 1998

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS .

3.6.4.3 Standby Gas Treatment (SGT) System LCC' 3.6.4.3 Three SGT subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During operations with a potential for draining the reactor vessel I (OPDRVs).

ACTIONS ._._,. _

CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem A.1 Restore SGT subsystem 7 days inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A not AND met in MODE 1, 2, or 3.

B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

BFN-UNIT 2 3.6 -5 1 Amendment No. 253, :290

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Place two OPERABLE Immediately associated Completion SGT subsystems in Time of Condition A not operation.

met during OPDRVs.

OR C.2 Initiate action to suspend Immediately OPDRVs.

D. Two or three SGT D.1 Enter LCO 3.0.3. Immediately subsystems inoperable Jn MODE 1, 2, or 3.

(continued)

BFN-IJNIT 2 3.6-52 Amendment No. 25, ;290

SGT System

3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two or three SGT E.1 Initiate action to suspend Immediately subsystems inoperable OPDRVs.

during OPDRVs.

BFNI-UNIT 9 3.6-53 Amendment No. 23, 290

SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for> 10 31 days continuous hours with heaters operating.

SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an 24 months actual or simulated initiation signal.

SR 3.6.4.3.4 Verify the SGT decay heat discharge 12 months dampers are in the correct position.

BFN-UNIT 2 3.6-54 Amendment No. 255 November 30, 1998

RHRSW System and UHS l 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System and Ultimale Heat Sink (UHS)

LCO 3.7.1 NOTE The number of required RHRSW pumps may be reduced by one for each fueled unit that has been in MODE 4 or 5 for 224 hours9.333 days 1.333 weeks 0.307 months .

Four RHRSW subsystems and UHS shall be OPERABLE with the number of OPERABLE pumps as listed below:

1. 1 unit fueled - four OPERABLE RHRSW pumps.

2. 2 units fueled - six OPERABLE RHRSW pumps.

3. 3 units fueled - eight OPERABLE RHRSW pumps.

APPLICABILITY: MODES 1,2, and 3.

Bl-N-UNIT 2 3.7-1 Amendment No. 254 SEP tI; 1338

RHRSW Systern and UHS I 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RHRSW A.1 - NOTES pump inoperable. '1. Only applicable for the.

2 units fueled condition.

2. Only four RHRSW pumps powered from a separate 4 kV shutdown board are required to be OPERABLE if the other fueled unit has been in MODE 4 or 5 for > 24 hours1 days 0.143 weeks 0.0329 months .

Verify five RHRSW Immediately pumps powered from separate 4 kV shutdown boards are OPERABLE.

OR A.2 Restore required RHRSW 30 days pump to OPERABLE status.

(continued)

BFN-UNIT 2 3.7-2 Amendment hi. I. No. ,:254 "r

RHRSW Systern and UHS l 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMF'LETION TIME B. One RHRSW subsystem B.1 - NOTE inoperable. "Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling

- Hot Shutdown," for RHR shutdown cooling made inoperable by the RHRSW system.

Restore RHRSW 30 days subsystem to OPERABLE status.

C. Two required RHRSW C.1 Restore one inoperable 7 days pumps inoperable. RHRSW pump to OPERABLE status.

ID. Two RHRSW subsystems D.1 NOTE inoperable.. Enter applicable Conditions and Required Actions of LCO 3.4.7, for RHR shutdown cooling made inoperable by the RHRSW System.

Restore one RHRSW 7 days subsystem to OPERABLE status.

(continued)

BFN-UNIT 2 3.7-3 Amendment No. 254 SEP 0 i? 1.C38

RHRSW System and UHS l 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Three or more required E.1 Restore one RHRSW 8 hours0.333 days 0.0476 weeks 0.011 months RHRSW pumps -pump to OPERABLE inoperable. status.

F. Three or more RHRSW F.1 NOTE E subsystems inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7 for RHR shutdown cooling made inoperable by the RHRSW System.

Restore one RHRSW 8 hours0.333 days 0.0476 weeks 0.011 months subsystem to OPERABLE status.

G. Required Action and G.: Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months ; associated Completion Time not met. AND G.2 Be in MODE 4. 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ; OR UHS inoperable BF-N-UNIT 2 3.7-4 Amendment No. 254 SEP 0 a

RHRSW System and UHS l 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each RHRSW manual and power 31 days operated valve in the flow path, that is not locked, sealed, orbtherwise secured in position, is in the correct position or can be aligned to the correct position.

SR 3.7.1.2 Verify the average water temperature of UHS 24 hours1 days 0.143 weeks 0.0329 months UHS is within the limits specified in Figure 3.7.1-1. temperature

91 'F AND

- 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months LIHS temperature

>910 F BF N-UNIT 2 3.7-5 Amendment No. 254 SEP C:i,'9g

RHRSW System and UHS 3.7.1 Figure 3.7.1.1 Reactor Thermal Power Versus Ultimate Heat Sink Temperature Limit 101.

100.

199

~98 2253Acceptable l 97 ..

91 92 82.5 93 93.5 94 9.

94.5 UlKnate Hot Sink Twnpetur (degrees F)

BFN-UNIT 2 3.7-6 Amendment ND. 254

' _, ,,- ' 'E "I 1

EECW System and UHS 3.7.2

3.7 PLANT SYSTEMS

3.7.2 Emergency Equipment Cooling Water (EECW) System and Ultimate Heat Sink (UHS)

I-CO 3.7.2 The EECW System with three pumps and UHS shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS q CONDITION REQUIRED ACTION COMPLETION

'TIME A. One required EECW A.1 Restore the required 7 days pump inoperable. EECW pump to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hourS associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months OR Two or more required EECW pumps inoperable.

OR UHS inoperable.

m -

BFN-UNIT 2 3.7-7 Amendment No. 254 SEP D8 1398

EECW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 --------------------------NOTE-------------------------

Refer to SR 3.7.1.2 for additional UHS requirements.

Verify the average water temperature of UHS 24 hours1 days 0.143 weeks 0.0329 months is < 950 F.

SR 3.7.2.2 --------------------------NOTE-----------------------

Isolation of flow to individual components does not render EECW System inoperable.

Verify each EECW system manual and power 31 days operated valve in the flow paths servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.2.3 Verify each required EECW pump actuates 24 months on an actual or simulated initiation signal.

BFN-UNIT 2 3.7-8 Amendment No. 255 November 30, 1998

CREV system 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation (CREV) System LCO 3.7.3* Two CREV subsystems shall be OPERABLE.

NOTE ------------ --- I - -

The main control room boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, and 3, During operations with a potential for draining the reactor vessel I (OPDRVs).

ACTIONS CONDID ACT ION COMPLETION TIME A. One CREV subsystem A.1 Restore CREV subsystem 7 days inoperable. to OPERABLE status.

B. Two CREV subsystems B.1 Restore control room 24 hours1 days 0.143 weeks 0.0329 months inoperable due to boundary to OPERABLE inoperable control room status.

boundary in MODES 1, 2, and 3.

C. Required Action and. C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or

3. C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

BFN-UNIT 2 3.7-9 Amendment No. 24-, a2n, 290

CREV System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place OPERABLE CREV Immediately associated Completion subsystem in Time of Condition A not pressurization mode.

met during OPDRVs.

OR D.2 Initiate action to suspend Immediately OPDRVs.

E. Two CREV subsystems E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued) 13FN-UNIT 2 3.7-1 0 Amendment No. 2&42,8X, 290

CREV System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREV subsystems F.1 Initiate action to suspend Immediately inoperable during OPDRVs..

OPDRVs.

BFN-UNIT 2 3.7-1 1 Amendment No. 2&47 2A, 290

CREV System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREV subsystem for 2 10 31 days continuous hours with the heaters operating.

SR 3.7.3.2 Perform required CREV filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).

SR 3.7.3.3 Verify each CREV subsystem actuates on an 24 months actual or simulated initiation signal.

SR 3.7.3.4 Verify each CREV subsystem can maintain a 24 months on a positive pressure of Ž 0.125 inches water STAGGERED gauge relative to the outdoors during the TEST BASIS pressurization mode of operation at a flow rate of 2 2700 cfm and < 3300 cfm.

BFN-UNIT 2 3.7-12 Amendment No. 255 November 30, 1998

Control Room AC System 3.7.4

3.7 PLANT SYSTEMS

3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two Unit I and 2 control room AC subsystems shall be OPERABLE. -

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION C.OMFLETION TIME A. One Unit 1 and 2 control A.1 Restore Unit 1 and 2 30 days room AC subsystem control room AC inoperable. subsystem to OPERABLE status.

(continued)

BF-N-UNIT 2 3.7-13 Amendment No. 254 SU- n jI

Control Room AC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two Unit 1 and 2 control B.1 Initiate action to restore Immediately room AC subsystems

one Unit I and 2 control inoperable. room AC subsystem to OPERABLE status.

AND B.2 Place an alternate 24 hours1 days 0.143 weeks 0.0329 months ; method of cooling in operation.

AND B.3 Restore one control room 7 days AC subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or

3. C.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months (continued)

BFN-UNIT 2 3.7-14 Amendment No. 254 I' SEP 0 c 1998

Control Room AC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMFLETION TiIME D. Required Action and D.1 NOTE

associated Completion LCO 3.0.3 is not Time of Condition A or B applicable.

not met during movement of irradiated fuel assemblies in the Place OPERABLE control Immediately secondary containment, room AC subsystem in during CORE operation.

ALTERATIONS, or during OPDRVs. OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to suspend Immediately OPDRVs.

BF N-UNIT 2 3.7-15 Amendment No. 254 SEP 0 E 1998

Control Room AC System 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has 24 months the capability to remove the assumed heat load.

BFN-UNIT 2 3.7-16 Amendment No. 255 November 30, 1998

Main Turbine Bypass System 3.7.5 3t.7 PLANT SYSTEMS 3.7.5 Main Turbine Bypass System LCO 3.7.5 The Main Turbine Bypass System shall be OPERABLE.

OR The following limits are made applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPF:),"

limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and

c. LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR),"

limits for an inoperable Main Turbine Bypass System, as specified in the COLR.

APPLICABILITY: THERMAL POWER > 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours0.0833 days 0.0119 weeks 0.00274 months not met. of the LCO.

13. Required Action and B.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion POWER to < 25% RTP.

Time not met.

B=N-UNIT 2 3.7-1 7 Amendment No. ART. 287

Main Turbine Bypass System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify one complete cycle of each main 31 days turbine bypass valve.

SR 3.7.5.2 Perform a system functional test. 24 months SR 3.7.5.3 Verify the TURBINE BYPASS SYSTEM 24 months RESPONSE TIME is within limits.

BFN-UNIT 2 3.7-18 Amendment No. 255 November 30, 1998

Spent Fuel Storage Pool Water Level 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Spent Fuel Storage Pool Water Level ILCO 3.7.6 The spent fuel storage pool water level shall be Ž 21.5 fl over the top of irradiated futl assemblies seated in the spent fuel storage pool racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel storage pool.

ACTIONS . -

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent 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 spent fuel storage pool.

BF-'N-UNIT 2 3.7-19 Amendment No. 254 to'*p0 r, Pri;.50 I

Spent Fuel Storage Pool Water Level 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the spent fuel storage pool water level 7 days is Ž 21.5 ft over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

BF:N-UNIT 2 3.7-20 Amendment No. 254 I

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 power sources shall be OPERA13LE:

a. Two qualified circuits between the offsite transmission network and the onsite Class I E AC Electrical Power Distribution System;

b. Unit 1 and 2 diesel generators (DGs) with two divisions of 480 V load shed logic and common accident signal logic OPERABLE; and

c. Unit 3 DG(s) capable of supplying the Unit 3 4.16 kV shutdown board(s) required by LCO 3.8.7, "Distribution Systems -

Operating."

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

-C34bi notaplicabeto-- ----- NOTEs LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite A.1 Verify power availability 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months circuit inoperable. from the remaining OPERABLE offsite AND transmission network.

Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND (continued)

BFN-UNIT 2 3.8-1 Amendment No. 2-3T 286

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Declare required 24 hours1 days 0.143 weeks 0.0329 months from feature(s) with no offsite discovery of no power available offsite pcwer to inoperable when the one shutdown redundant required board concurrent feature(s) are inoperable. with inoperability of redundant required feature(s)

AND A.3 Restore required offsite 7 days circuit to OPERABLE status. AND 14 days from discovery of failure to meet LCO B. One required Unit 1 and 2 B.1 Verify power availability 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months DG inoperable. from the offsite transmission network. AND Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND I

_____________________________________________________________ I.

(continued)'

13FN-UNIT 2 3.8-2 Amendment No. 253

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Declare required 4 hours0.167 days 0.0238 weeks 0.00548 months from feature(s), supported by discovery, of the inoperable Unit I and Condition B 2 DG, inoperable when concurrent with the redundant required inoperability of feature(s) are inoperable. redundant required feature(s)

AND B.3.1 Determine OPERABLE 24 hours1 days 0.143 weeks 0.0329 months Unit 1 and 2 DG(s) are not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.1 for 24 hours1 days 0.143 weeks 0.0329 months OPERABLE Unit 1 and 2 DG(s);

AND B.4 Restore Unit I and 2 DG 14 days to OPERABLE status.

AND 14 days from discovery of failure to meet LCO J.

(continued)

BFN-UNIT 2 3.8-3 Amendment No. 253, 259 AUG 0 2 -3~9

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T

C. One division of 480 V C.1 Restore required division 7 days load shed logic of 480 V load shed logic inoperable. to OPERABLE status.

D. One division of common D.1 Restore required division 7 days accident signal logic of common accident inoperable. signal logic to OPERABLE status.

E. Two required offsite E.1 Declare required 12 hours0.5 days 0.0714 weeks 0.0164 months from circuits inoperable. feature(s) inoperable discovery of when the redundant Condition IE required feature(s) are concurrent with inoperable. inoperability of redundant required feature(s)

AND E.2 Restore one required 24 hours1 days 0.143 weeks 0.0329 months offsite circuit to OPERABLE status.

(continued)

B 1FN-UNIT 2 3.8-4 Amendment No. 253

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME NOTE NOTE Only applicable when more Enter applicable Conditions and than one 4.16 kV shutdown Required Actions of LCO 3.8.7, board is affected. "Distribution Systems -

Operating," when Condition F is entered with no AC power source F. One required offsite to any 4.16 kV shutdown board.

circuit inoperable.

AND F.1 Restore required offsite 12 hours0.5 days 0.0714 weeks 0.0164 months circuit to OPERABLE One Unit 1 and 2 DG status.

inoperable.

OR F.2 Restore Unit I and 2 DG 12 hours0.5 days 0.0714 weeks 0.0164 months to OPERABLE status.

NOTE Applicable when only one 4:16 kV shutdown board is affected.

G.. One required offsite G.1 Declare the affected Immediate.ly circuit inoperable. 4.16 kV shutdown board inoperable.

AND One Unit 1 and 2 DG inoperable.

(continued)

BFN-UNIT 2 3.8-5 Amendment No. 253

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. Two or more Unit 1 H.1 Restore all but one Unit 1 2 hours0.0833 days 0.0119 weeks 0.00274 months and 2 DGs and 2 DG to OPERABLE inoperable. status.

1. Required Action and 1.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Associated Completion Time of AND Condition A, B, C, D, E, F, or H not ntmtmet. 1.2 Be in MODE

. 4. .o 36 hours1.5 days 0.214 weeks 0.0493 months J. One or more required J.1 Enter LCO 3.0.3.. Immediately offsite circuits and two or more Unit 1 and 2 DGs inoperable.

OR Two required offsite circuits and one or more Unit I and 2 DGs inoperable.

OR Two divisions of 480 V load shed logic inoperable.

OR Two divisions of common accident signal logic inoperable.

(continued)

BFN-UNIT 2 3.8-6 Amendment No. 253

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K. One or more required K.1 Declare required 4 hours0.167 days 0.0238 weeks 0.00548 months from Unit 3 DGs feature(s) supported by discovery of inoperable. the inoperable Unit 3 DG Condition K inoperable when the concurrent with redundant required inoperability of feature(s) are inoperable. redundant required feature(s)

AND K2 Declare affected SGT and 30 days CREVs subsystem(s) inoperable..

EFN-UN IT 2 3.8-7 Amendment No. 253

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS

-NOTE SR 3.8.1.1 through SR 3.8.1.9 are applicable to the Unit 1 and 2 AC sources.

SR 3.8.1.1 0 is applicable only to Unit 3 AC sources.

SURVEILLANCE - FREQUENCY SR 3.8.1.1 NOTES

1. Performance of SR 3.8.1.4 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 3.8.1.4 must be met.

Verify each DG starts from standby 31 days conditions and achieves steady state voltage 23940 V and

4400 V and frequency a 58.8 Hz and s 61.2 Hz.

(continued) 13FN-UNIT 2 3.8-8 Amendment No. 253

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.2 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 3.8.1.1 or SR 3.8.1.4.

Verify each DG is synchronized and loaded 31 days

. and operates for > 60 minutes at a load 2 2295 kW and < 2550 kW.

(continued)

EIFN-UNIT 2 3.8-9 Amendment No. 253

AC Sources - Operating 3.8.1 I- 1- ose ae rs at Ic t-

._1\ T __

,iUKVtILLANLtL Lt.UIt-tMtN 16 (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.3 Verify the fuel oil transfer system operates to 31 days automatically transfer fuel oil from 7-day storage tank to the day tank.

SR 3.8.1.4 NOTE All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition 184 days and achieves, in < 10 seconds, voltage 2 3940 V and frequency Ž 58.8 Hz. Verify after DG fast start from standby conditions that the DG achieves steady state voltage

Ž 3940 V and < 4400 V and frequency 58.8 Hz and < 61.2 Hz.

(continued)

E3FN-UNIT 2 3.8-10 Amendment No. 253

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.5 --------------------------NOTE-------------------------

If performed with the DG synchronized with offsite power, it shall be performed at a power factor < 0.9.

Verify each DG rejects a load greater than or 24 months equal to its associated single largest post-accident load, and:

a. Following load rejection, the frequency is

< 66.75 Hz; and

b. Following load rejection, the steady state voltage recovers to 2 3940 V and

< 4400 V.

c. Following load rejection, the steady state frequency recovers to Ž 58.8 Hz and

< 61.2 Hz.

SR 3.8.1.6 ------------------------NOTE---------------------

All DG starts may be preceded by an engine prelube period followed by a warmup period.

Verify on an actual or simulated accident 24 months signal each DG auto-starts from standby condition.

(continued)

BFN-UNIT 2 3.8-11 Amendment No. 255 November 30, 1998

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 4

SR 3.8.1.7 -------------------------- NOTE -------------------------

Momentary transients outside the load and power factor ranges do not invalidate this test.

Verify each DG operating at a power factor 24 months

< 0.9 operates for 2 24 hours1 days 0.143 weeks 0.0329 months :

a. For Ž 2 hours0.0833 days 0.0119 weeks 0.00274 months loaded Ž 2680 kW and

< 2805 kW; and

b. For the remaining hours of the test loaded 2 2295 kW and < 2550 kW.

SR 3.8.1.8 Verify interval between each timed load block 24 months is within the allowable values for each individual timer.

(continued)

BFN-UNIT 2 3.8-12 Amendment No. 255 November 30, 1998

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE I FREQUENCY SR 3.8.1.9 ---------------------- NOTE----------------------

All DG starts may be preceded by an engine prelube period.

Verify, on an actual or simulated loss of 24 months offsite power signal in conjunction with an actual or simulated ECCS initiation 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 < 10 seconds,

2. energizes auto-connected emergency loads through individual timers,

3. achieves steady state voltage 2 3940 V and < 4400 V,

4. achieves steady state frequency 2 58.8 Hz and < 61.2 Hz, and

5. supplies permanently connected and auto-connected emergency loads for 2 5 minutes.

SR 3.8.1.10 For required Unit 3 DGs, the SRs of Unit 3 In accordance Technical Specifications are applicable. with applicable SRs BFN-UNIT 2 3.8-13 Amendment No. 255 November 30, 1998

AC Sources - Shutdown 3.8.2

3.8 ELECTRICAL POWER SYSTEMS

3.8.2 AC Sources - Shutdown I-CO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit connected between the offsite transmission network and the onsite Class I E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown";

b. Two of the four Unit 1 and 2 diesel generators .(DGs).each capable of supplying one 4.16 kV shutdown board of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown"; and

c. Unit 3 DGs capable of supplying the Unit 3 4.16 kV shutdown boards required by LCO 3.8.8.

APPLICABILITY: MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

EIFN-UNIT 2 3.8-14 Amendment NcD. 253

AC Sources - Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite NOTE circuit inoperable. Enter applicable Condition and Required Actions of LCO 3.8.8, with any required 4.16 kV shutdown board not energized from a qualified source as a result of Condition A.

A.1 Declare affected required Immediately feature(s) with no qualified offsite power available inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of ImmediatelY irradiated fuel assemblies in secondary

- containment.

AND (continued)

EIFN-UNIT 2 3.8-1 5 Amendment No. 253

AC Sources - Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Initiate action to suspend Immediately operations with a potential for draining the reactor vessel (OPDRVs).

AND A.2.4 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. One or more required B.1.1 Suspend CORE Immediately Unit 1 and 2 DGs ALTERATIONS.

inoperable.

AND B.1.2 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND B.1.3 Initiate action to suspend Immediately OPDRVs.

AND B.1.4 Initiate action to restore Immediately required Unit 1 and 2 DGs to OPERABLE status.

____________________________________________ .1.

(continued)

ElFN-UNIT 2 3.8-16 Amendment No. 253

AC Sources - Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more required C.1 Declare affected SGT and 30 days Unit 3 DGs inoperable. CREV subsystem(s) inoperable. AND Immediately from discovery of Condition C.

concurrent with inoperability of redundant

.required feature(s)

E3FN-UNIT 2 3.8-17 Amendment No. 253

AC Sources - -Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQIJENCY SR 3.8.2.1 NOTE The following SRs are not required to be performed: SR 3.8.1.2, SR 3.8.1.5, SR 3.8.1.7, SR 3.8.1.8, and SR 3.8.1.9.

For Unit 1 and 2 AC sources required to be In accordance OPERABLE, the SRs of Specification 3.8.1 with applicable are applicable. SRs SR 3.8.2.2 For the required Unit 3 DG, the SRs of Unit 3 In accordance Technical Specifications are applicable. with applicable SRs m -

.BFN-UNIT 2 3.8-18 Amendment No. 253

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 -Diesel Fuel Oil, Lube Oil, and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits for each required diesel generator (DG).

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 level to 48 hours2 days 0.286 weeks 0.0658 months fuel oil level c35,280 gal within limits.

and > 30,240 gal in storage tank.

B. One or more DGs with B.1 Restore lube oil inventory 48 hours2 days 0.286 weeks 0.0658 months lube oil inventory < 175 to within limits.

gal and > 150 gal.

C. One or more DGs with C.1 Restore fuel oil total 7 days stored fuel oil total particulates to within limit.

particulates not within limits.

(continued)

E3FN-UNIT 2 3.8-19 Amendment No. 253

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more DGs with the D.1 Declare associated DG Immediately required starting air inoperable.

receiver unit pressure

< 165 psig.

E. Required Action and E.1 Declare associated DG Immediately associated Completion inoperable.

Time not met.

OR One or more DGs with diesel fuel oil, lube oil, or starting air subsystem inoperable for reasons other than Condition A, B, CorD.

13FN-UNIT 2 3.8-20 Amendment No. 253

Diesel Fuel Oil, Lube Oil, and starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains 31 days

> 35,280 gal of fuel.

SR 3.8.3.2 Verify lube oil inventory is 2175 gal. 31 days SR 3.8.3.3 Verify fuel oil total particulate concentration in In accordance stored fuel oil is tested in accordance with, with the Diesel and maintained within the limits of, the Diesel Fuel Oil Testing Fuel Oil Testing Program. Program SR 3.8.3.4 Verify each required DG air start receiver unit 31 days pressure is 2Ž165 psig.

BFN-UNIT 2 3.8-21 Amendment No. 253

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS

3.8.4 DC Sources - Operating LCO 3.8.4 The following DC electrical power systems shall be OPERABLE:

a. Unit DC subsystems 1, 2, and 3;

b. Shutdown Board DC subsystems A, B, C, and D;

c. Unit 1 and 2 Diesel Generator (DG) DC subsystems;

d. Unit 3 DG DC subsystem(s) supporting DG(s) required to be OPERABLE by LCO 3.8.1, "AC Sources - Operating"; and

e. Unit 3 Shutdown Board DC subsystem 3EB needed to support equipment required to be OPERABLE by LCO 3.7.3, "Control Room Emergency Ventilation (CREV) System."

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME-A. One Unit DC electrical A.1 Restore DC electrical 7 days power subsystem power subsystem to inoperable. . OPERABLE status.

OR One Unit 1 and 2 Shutdown Board DC electrical power subsystem inoperable.

(continued) 13FN-UNIT 2 3.8-22 Amendment No. 253

DC Sources - Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months C. One or more DG DC. C.1 Declare associated DG Immediately electrical power inoperable.

subsystem(s) inoperable.

D. Unit 3 3EB Shutdown D.1 Declare the affected Immediately Board DC electrical CREV subsystem power subsystem inoperable.

inoperable.

BFN-UNIT 2 3.8-23 Amendment No. 253

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 2 248 V for 7 days each Unit and Shutdown Board battery and 2 124 V for each DG battery on float charge.

SR 3.8.4.2 --------------------------NOTE-------------------------

Performance of SR 3.8.4.5 satisfies this SR.

Verify each required battery charger charges 24 months its respective battery after the battery's 24 month service test.

SR 3.8.4.3 ------------------------- NOTE------------------

The modified performance discharge test in SR 3.8.4.4 may be performed in lieu of the service test in SR 3.8.4.3 once per 60 months.

Verify battery capacity is adequate to supply, 24 months and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

(continued)

BFN-UNIT 2 3.8-24 Amendment No. 255 November 30, 1998

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.4 Verify battery capacity is Ž 80% of the 60 months manufacturer's rating when subjected to a performance discharge test or a modified AND performance discharge test.

12 months when battery shows degradation or has reached 85% of expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of expected life with capacity Ž 100%

of manufacturer's rating.

SR 3.8.4.5 NOTE Credit may be taken for unplanned events that satisfy this SR.

Verify each required battery charger supplies 60 months

Ž 300 amps for the Unit and 50 amps for the Shutdown Board subsystems at 2 210 V and

Ž 15 amps for DG subsystems at Ž 105 V.

EIFN-UNIT 2 3.8-25 Amendment No. 253

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 DC electrical power subsystems shall be OPERABLE to support the DC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown."

APPLICABILITY: MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required DC A.1 Declare affected required Immediately electrical power feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately/

irradiated fuel assemblies in the secondary containment.

AND (continued)

EIFN-UNiT 2 3.8-26 Amendment No. 253

DC Sources - Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Initiate action to suspend Immediately operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate action to restore Immediately required DC electrical power subsystems or systems to OPERABLE status.

EIFN-UNIT 2 3.8-27 Amendment No. 253

DC Sources - Shutdown 3.8.5

'SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 NOTE The following SRs are not required to be performed: SR 3.8.4.2, SR 3.8.4.3, SR 3.8.4.4, and SR 3.8.4.5.

For DC sources required to be OPERABLE In accordance the following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 SR 3.8.4.4 SR 3.8.4.5 BFN-UNIT 2 3.8-28 Amendment No. 253

Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3-.8.6 Battery Cell Parameters L.CO 3.8.6 Battery cell parameters for the Unit, Shutdown Board, and DG batteries shall be within the limits of Table 3.8.6-1.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS KlntrC

_ . M I -------

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verify pilot cells 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one or more battery electrolyte level and float cell parameters not within voltage meet Category A or B limits. Table 3.8.6-1 Category C limits.

AND A.2 Verify battery cell 24 hours1 days 0.143 weeks 0.0329 months parameters meet Table 3.8.6-1 Category C AND limits.

Once per 7 days

. thereafter AND (continued)

.BFN-UNIT 2 3.8-29 Amendment No. 253

Battery Cell Parameters 3.8.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.

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 not within limits.

OR One or more batteries with one or more battery cell parameters not within Category.C values.

I -

EIFN-UNIT 2 3.8-30 Amendment No. 253

Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days Table 3.8.6-1 Category A limits.

SR 3.8.6.2 Verify battery cell parameters meet 92 days Table 3.8.6-1 Category B limits.

SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells is Ž 600 F for each Unit and Shutdown Board battery (except Shutdown Board battery 3EB), and Ž 400 F for Shutdown Board battery 3EB and each DG battery.

U -

E;FN-UN IT 2 3.8-31 Amendment No. 253

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Cell Parameter Requirements CATEGORY A: CATEGORY C:

LIMITS FOR EACH CATEGORY B: ALLOWABLE VALUE DESIGNATED PILOT LIMITS FOR EACH FOR EACH PARAMETER CELL CONNECTED CELL CONNECTED CELL Electrolyte > Minimum level > Minimum level. Above top of plates, Level indication mark, and indication mark, and and not overflowing

< % inch above < %/4inch above maximum level maximum level indication mark(a) indication mark(a)

Float Voltage 2 2.13 V 2.13 V > 2.07 V Specific 21.20 >1.195 Not more than 0.020 Gravity (b) below average of all (c)(d) AND connected cell<;

Average of all AND connected cells

> 1.205 Average of all connected cells'

Ž 1.195 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum level during equalizing charges provided it is not overflowing.

(b) Corrected for electrolyte temperature.

(c) As an alternative to the specific gravity measurements, a battery charging current of < I amp for Unit and Shutdown Board batteries and < 0.5 amp for DG batteries when on float charge is acceptable only during a maximum of 7 days following a battery recharge. 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.

(d) Alternate values may be used for a limited number of cells provided demonstrated battery capacity at the last discharge test meets the minimum qualifying value.

EFN-UNIT 2 3.8-32 Amendment No. 253

Distribution Systems - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 -Distribution Systems - Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be OPERABLE:

a. Unit 1 and 2 4.16 kV Shutdown Boards;

b. Unit 2 480 V Shutdown Boards; C. Unit 2 480 V RMOV Boards 2A, 2B, 2D, and 2E;

d. Unit 1 and 2 DG Auxiliary Boards;

e. Unit DC Boards and 250 V DC RMOV Boards 2A, 28, aid 2C;

f. Unit 1 and 2 Shutdown Board DC Distribution Panels; and

g. Unit 1 and 3 AC and DC Boards needed to support equipment required to be OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," and LCO 3.7.3, "Control Room Emergency Ventilation (CREV) System."

APPLICABILITY: MODES 1,2, and 3.

BFN-U.NIT 2 3.8-33 Amendment No. 253

Distribution Systems - Operating 3.8.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Unit 1 and 2 4.16 kV NOTE Shutdown Board Enter applicable Conditions and inoperable. Required Actions of Condition B, C, D, and G when Condition A results in no power source to a required 480 volt board.

A.1 Restore the Unit 1 and 2 5 days 4.16 kV Shutdown .Board to OPERABLE status. AND 12 days from discovery of failure to rneet LCO AND A.2 Declare associated diesel Immediately generator inoperable.

(continued)

EIFN-UNIT 2 3.8-34 Amendment No. 253

Distribution Systems - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One Unit 2 480 V NOTE Shutdown Board Enter Condition C when inoperable. Condition B results in no power source to 480 volt RMOV board OR 2D or 2E.

480 V RMOV Board 2A B.1 Restore Board to 8 hours0.333 days 0.0476 weeks 0.011 months Inoperable. OPERABLE status.

OR AND 480 V RMOV Board 2B 12 days fr om inoperable. failure to meet LCO C. Unit 2 480 V RMOV C.1 Declare the affected RHR Immediately Board 2D inoperable. subsystem inoperable.

OR Unit 2 480 V RMOV Board 2E inoperable.

D. One Unit 1 and 2 DG D.1 Restore Unit 1 and 2 DG 5 days Auxiliary Board Auxiliary Board to inoperable. OPERABLE status. AND 12 days from discovery of failure to meet LCO (continued)

Bl-N-UNIT 2 3.8-35 Amendment No. 253

Distribution Systems - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Unit DC Board E.1 Restore required Board or 7 days inoperable. Shutdown Board DC Distribution Panel to AND OR OPERABLE status.

12 days from One Unit 1 and 2 discovery of Shutdown Board DC failure to meet Distribution Panel LCO inoperable.

OR 250 V DC RMOV Board 2A inoperable.

OR 250 V DC RMOV Board 2B inoperable.

OR 250 V DC RMOV Board 2C inoperable.

(continued) 13FN-UNIT 2~ 3.8-36 Amendment No. 253

Distribution Systems - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Unit 1 and 2 4.16 kV NOTE Shutdown Board A and B Enter applicable conditions and inoperable. required actions of Condition B, C, D, and G when Condition' F OR results in no power source to a required 480 volt board.

Unit 1 and 2 4.16 kV Shutdown Board C and D inoperable. F.1 Restore one 4.16 kV 8 hours0.333 days 0.0476 weeks 0.011 months Shutdown Board to OPERABLE status. AND 12 days from discovery of failure to meet LCO G. One or more required G.1 'Declare the affected SGT Immediately Unit 1 or 3 AC or DC or CREV subsystem Boards inoperable. inoperable.

H. Required Action and H.1 Be in MODE 3. 12'hours associated Completion Time of Condition A, B. D, AND E, or F not met.

H.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months I. Two or more electrical 1.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of function.

13FN-UNIT 2 3.8-37 Amendment No. 253

Distribution Systems - Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify indicated power availability to required 7 days AC and DC electrical power distribution subsystems.

E;FN-UNIT 2 3.8-38 Amendment No. 253

Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC A.1 Declare associated Immediately or DC electrical power supported required distribution subsystems feature(s) inoperable.

inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend handling of Immediately irradiated fuel assemblies in the secondary containment.

AND (continued) 13FN-UNIT 2 3.8-39 Amendment No. 253

Distribution Systems - Shutdown 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Initiate action to suspend Immediately operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate actions to restore Immediately required AC and DC electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling subsystem(s) inoperable and not in operation.

EFN-UNIT 2 3.840 Amendment ND. 253

Distribution Systems - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUJENCY SR 3.8.8.1 Verify indicated power availability to required 7 days AC and DC electrical power distribution subsystems.

U EFN-UN IT 2 3.8-41 Amendment No. 253

Refueling Equipment Interlocks B 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION l __ TIME X A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with equipment interlocks inoperable. associated with the inoperable interlock(s).

OR A.2.1 Insert a control rod Immediately withdrawal block.

AND A.2.2 Verify all control rods are Immediately

= _ __ fully inserted. -

BFN UNIT 2 3.9-1 Amendment No. 25e 274 MAR 0 6 2m

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on 7 days each of the following required refueling equipment interlock inputs:

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform main hoist, fuel loaded,

d. Refuel platform fuel grapple fully retracted position,

e. Refuel platform frame mounted hoist, fuel loaded,

f. Refuel platform monorail mounted hoist, fuel loaded, and

g. Service platform hoist, fuel loaded.

m -

EIFN-UNIT 2 3.9-2 Amendment No. 253

Refuel Position One-Rod-OLt Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIIME A. Refuel position A.1 Suspend control rod Immediately one-rod-out interlock withdrawal.

inoperable.

AND A.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

a _

EIFN-UNIT 2 3.9-3 Amendment No. 253

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel 12 hours0.5 days 0.0714 weeks 0.0164 months position.

SR 3.9.2.2 NOTE Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. 7 days EIFN-UNIT 2 3.9-4 Amendment No. 253

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control rods A.1 Suspend loading fuel Immediately not fully inserted. assemblies into the core.

.13FN-UNIT 2 3.9-5 Amendment No. 253

Control Rod Position 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. 12 hours0.5 days 0.0714 weeks 0.0164 months I -.

B3FN-UNIT 2 3.9-6 Amendment No. 253

Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS

3.9.4 Control Rod Position Indication LCO 3.9.4 The control rod full-in position indication for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS NOTE Separate Condition entry is allowed for each required full-in position indication.

CONDITION REQUIRED ACTION COMPLEITION TIME A. One or more required A.1.1 Suspend in-vessel fuel Immediately control rod full-in position movement.

indications inoperable.

AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

OR

._ _(conl:inued) l3FN-UNIT 2 3.9-7 Amendment No. 253

Control Rod Position Indication 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to fully Immediately insert the control rod associated with the inoperable position indicator.

AND A.2.2 Initiate action to disarm Immediately the control rod drive associated with the fully inserted control rod.

a -

E',FN-UNIT 2 3.9-8 Amendment No. 253

Control Rod Position Indication 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUIJENCY SR 3.9.4.1 Verify the position indication has no full-in Each time the indication on each control rod that is not control rod is full-in. withdrawn from the full-in position E;FN-UNIT 2 3.9-9 Amendment No. 253

Control Rod OPERABILITY - Refueling 3.9.5

%3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY - Refueling L.CO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to fully Immediately control rods inoperable. insert inoperable withdrawn control rods.

BFN-UNIT 2 3.9-10 N 2Amendment No. 253

Control Rod OPERABILITY - Refueling 3.9.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 NOTE Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least one 7 days notch.

SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is . 940 psig.

BFN-U NIT 2 3.9-11 Amendment No. 253

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be 2 22 ft above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the FRPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 *-Suspend movement of Immediately within limit. fuel assemblies and handling of control rods within the RPV.

BFN-UNIT 2 3.9-1 2 Amendment No. 253

RPV Water Level 3.9.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is > 22 ft above the 24 hours1 days 0.143 weeks 0.0329 months top of the RPV flange.

BFN-UNIT 2 3.9-1 3 Amendment No. 253

RHR-High Water Level 3.9.7 0.9 REFUELING OPERATIONS Z.9.7 Residual Heat Removal (RHR) - High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

NOTE-The required RHR shutdown cooling subsystem may not be in operation for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level 2 22 ft above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME:

A. Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat inoperable. removal is available. AND Once per 24 hours1 days 0.143 weeks 0.0329 months thereafter (conti nued)

B-..N-UNIT 2 3.9-1 4 Amendment No. 253

RHR-High Wlater Level 3.9.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel assemblies Time of Condition A not into the RPV.

met.

AND B.2 Initiate action to restore Immediately secondary containment to OPERABLE status.

AND B.3 Initiate action to restore Immediately two standby gas treatment subsystems to OPERABLE status.

AND B.4 Initiate action to restore Immediately isolation capability in each required secondary

. containment penetration flow path not isolated.

(con inued)

EFN-UNIT 2 3.9-15 Amendment No. 253

RHR-High Water Level 3.9.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. No RHR shutdown C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in circulation by an alternate discovery of no operation. method. reactor coolant circulation AND Once per 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

E;FN-UNIT 2 3.9-1 6 Amendment No. 253

RHR-High Water Level 3.9.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem 12 hours0.5 days 0.0714 weeks 0.0164 months is operating.

S --

13FN-UNIT 2 3.9-1 7 Amendment No. 253

RHR-Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR) - Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.

_ It r-The required operating shutdown cooling subsystem may not be in operation for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIIVE A. One or two required RHR A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each inoperable required RHR shutdown cooling Once per subsystem. 24 hours1 days 0.143 weeks 0.0329 months thereafter (continued) 13FN-UNIT 2 3.9-1 8 Amendment No. 253

RHR-Low Water Level 3.9.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMP[.ETION TIME B. Required Action and B.1 Initiate action to restore Immediately associated Completion secondary containment to Time of Condition A not OPERABLE status.

met.

AND B.2 Initiate action to restore Immediately two standby gas treatment subsystems to OPERABLE status.

AND B.3 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

(continued)

EIFN-UNIT 2 3.9-1 9 Amendment No. 253

RHR-Low Water Level 3.9.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPL.ETION TIME C. No RHR shutdown C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in circulation by an alternate discovery of no operation. method. reactor coolant circulation AND Once per 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

a -

EIFN-UNIT 2 3.9-20 Amendment No. 253

RHR-Low Water Level 3.9.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem 12 hours0.5 days 0.0714 weeks 0.0164 months is operating.

E;FNI-UNIT 2 3.9-21 Amendment No. 253

Decay Time 3.9.9 3.9 REFUELING OPERATIONS 3.9.9 Decay Time LCO 3.9.9 The reactor shall be subcritical for at least 24 hours1 days 0.143 weeks 0.0329 months .

APPLI CABILITY: During in-vessel fuel movement.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With the reactor A.1 Suspend in-vessel fuel Immediately subcritical for less than movement.

24 hours1 days 0.143 weeks 0.0329 months .

BFN-UNIT 2 3.9-22 Amendment No. 290

Decay Time 3.9.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.9.1 Verify the reactor has been subcritical for at Once prior tc the lleast 24 hours1 days 0.143 weeks 0.0329 months . movement of irradiated fuel in the reactor vessel BFN-UNIT '9 3.9-23 Amendment No. 290

Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.1 0.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA," and operation considered not to be in MODE 3; and the-requirements of LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown," may be suspended, to allow performance of an inservice leak or hydrostatic test provided the following MDDE 3 LCOs are met:

a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," Functions 1, 3, and 4 of Table 3.3.6.2-1;

b. LCO 3.6.4.1, "Secondary Containment";

c. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)"; and

d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."

APPLICABILITY: MODE 4 with average reactor coolant temperature > 212*F.

fBFN-UNIT 2 3.10-1 Amendment No. 253

Inservice Leak and Hydrostatic Testing Operation

3.10.1 ACTIONS

~I'dl - -- -----

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 NOTE requirements not met. Required Actions to be in MODE 4 include reducing average reactor coolant temperature to < 212TF.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Suspend activities that Immediately could increase the average reactor coolant temperature or pressure.

AND A.2.2 Reduce average reactor 24 hours1 days 0.143 weeks 0.0329 months coolant temperature to

5 212°F.

EBFN-UNlT 2 3.10-2 Amendment No. 253

Inservice Leak and Hydrostatic Testing Operation 3.10.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FRECUENCY SR 3.10.1.1 Perform the applicable SRs for the required According to the MODE 3 LCOs. applicable SRs BFN-UNIT 2 3.10-3 Amendment No. 253

Reactor Mode Switch Interlock Testing 3.10.2 3.10 SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testing I-CO 3.10.2 The reactor mode switch position specified in Table 1.1-1 for MODES 3, 4, and 5 may be changed to include the run, startup/hot standby, and refuel position, and operation considered not to be in MODE 1 or 2, to allow testing of instrumentation associated with the reactor mode switch interlock functions, provided:

a. All control rods remain fully inserted in core cells containing one or more fuel assemblies; and

b. No CORE ALTERATIONS are in progress.

APPLICABILITY: MODES 3 and 4 with the reactor mode switch in the run, startup/hot standby, or refuel position, MODE 5 with the reactor mode switch in the run or startup/hot standby position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Suspend CORE Immediately requirements not met. ALTERATIONS except for control rod insertion.

AND A.2 Fully insert all insertable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rods in core cells containing one or more fuel assemblies.

AND (conl inued) 13FN-UNIT 2 3.10-4 Amendment No. 253

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

OR A.3.2 - NOTE Only applicable in MODE 5.

Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the refuel position.

13FN-UNIT 2 3.10-5 Amendment No. 253

Reactor Mode Switch Interlock Testing 3.10.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted in 12 hours0.5 days 0.0714 weeks 0.0164 months core cells containing one or more fuel assemblies.

SR 3.10.2.2 Verify no CORE ALTERATIONS are in 24 hours1 days 0.143 weeks 0.0329 months progress.

U _ _ _ _ _ _ _ _

BFN-UNIT 2 3.10-6 Amendment No. 253

Single Control Rod Withdrawal - Hot Shutdown 3.10.3

3.10 SPECIAL OPERATIONS

3.10.3 Single Control Rod Withdrawal - Hot Shutdown lICO 3.10.3 The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, provided the following requirements are met:

a. LCO 3.9.2, "Refuel Position One-Rod-Out Interlock";

b. LCO 3.9.4, "Control Rod Position Indication";

c. All other control rods are fully inserted; and

d. 1. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions 1.a, 1.b, 7.a, 7.b, 10, 11, 12, and 13 of Table 3.3.1.1-1, and LCO 3.9.5, "Control Rod OPERABILITY - Refueling" OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 3 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY: MODE 3 With the reactor mode switch in the refuel position.

BFN-UNIT 2 3.10-7 Amendment ND. 253

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 ACTIONS

-- NOTE -

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 - NOTES requirements not met. 1. Required Actions to fully insert all

- insertable control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to fully' Immediately insert all insertable control rods.

- AND A.2.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

E3FN-UNIT 2 3.10-8 Amendment No. 253

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required According to the LCOs. applicable SRs SR 3.10.3.2 NOTE Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.

Verify all control rods, other than the control 24 hours1 days 0.143 weeks 0.0329 months rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.

SR 3.10.3.3 Verify all control rods, other than the control 24 hours1 days 0.143 weeks 0.0329 months rod being withdrawn, are fully inserted.

S -

' EFN-UNIT2 3.10-9 Amendment No. 253

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Single Control Rod Withdrawal - Cold Shutdown LCO 3.10.4 The reactor mode switch position specified in Table 1.1-1 for MODE 4 may be changed to include the refuel position, arid operation considered not to be in MODE 2, to allow withdrawal of a single control rod, and subsequent removal of the associa::ed control rod drive (CRD) if desired, provided the following requirements are met:

a. All other control rods are fully inserted;

b. 1. LCO 3.9.2, "Refuel Position One-Rod-Out Interlock," and LCO 3.9.4, "Control Rod Position Indication,"

OR

2. A control rod withdrawal block is inserted;

c. 1. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions 1.a, 1.b, 7.a, 7.b, 10,11, 12, and 13 of Table 3.3.1.1-1, anid LCO 3.9.5, "Control Rod OPERABILITY - Refueling,"

OR

.2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LC.O 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 4 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY: MODE 4 with the reactor mode switch in the refuel position.

E3FN-UNIT 2 3.10-10 Amendment No. 253

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS

- NOTE Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A1 NOTES requirements not met with 1. Required Actions to the affected control rod fully insert all insertable. insertable control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to fully Immediately insert all insertable control rods.

AND A.2.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

(continued)

EIFN-UNIT 2 3.10-11 Amendment No. 253

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more of the above B.1 Suspend withdrawal of Immediately requirements not met with the control rod and the affected control rod removal of associated not insertable. CRD.

AND B.2.1 Initiate action to fully. Immediately insert all control rods.

OR B.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

EFN-UNIT 2 3.10-12 Amendment No. 253

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for.the required According to the LCOs. applicable SRs SR 3.10.4.2 NOTE Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the control 24 hours1 days 0.143 weeks 0.0329 months rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.

SR 3.10.4.3 Verify all control rods, other than the control 24 hours1 days 0.143 weeks 0.0329 months rod being withdrawn, are fully inserted.

SR 3.10.4.4 NOTE Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is 24 hours1 days 0.143 weeks 0.0329 months inserted.

13FN-UNIT 2 3.10-13 Amendment No. 253

Single CRD Removal - Refueling 3.10.5

3.10 SPECIAL OPERATIONS

3.10.5 Single Control Rod Drive (CRD) Removal - Refueling I-CO 3.10.5 The requirements of LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation"; LCO 3.3.8.2, "Reactor Protection System (RPS) Electric Power Monitoring"; LCO 3.9.1, "Refueling Equipment Interlocks"; LCO 3.9.2, "Refuel Position One-Rod-Out Interlock"; LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY - Refueling," may be suspended in MODE 5 to allow the removal of a single CRD associated with a control rod withdrawn from a core cell containing one or more fuel assemblies, provided the following requirements are met:

a. All other control rods are fully inserted;

b. All other control rods in a five by five array centered on the withdrawn control rod are disarmed;

c. A control rod withdrawal block is inserted and LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 5 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod; and

d. No other CORE ALTERATIONS are in progress.

APPLICABILITY: MODE 5 with LCO 3.9.5 not met.

I3FN-UNIT 2 3.10-14 Amendment No. 253

Single CRD Removal - Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Suspend removal of the Immediately requirements not met. CRD mechanism.

AND A.2.1 Initiate action to fully Immediately insert all control rods.

OR A.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

13FN-UNIT 2 3.10-15 Amendment No. 253

Single CRD Removal - Refueling 3.10.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the control 24 hours1 days 0.143 weeks 0.0329 months rod withdrawn for the removal of the

associated CRD, are fully inserted.

SR 3.10.5.2 Verify all control rods, other than the control 24 hours1 days 0.143 weeks 0.0329 months rod withdrawn for the removal of the associated CRD, in a five by five array centered on the control rod withdrawn for the removal of the associated CRD, are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is 24 hours1 days 0.143 weeks 0.0329 months inserted.

SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hours1 days 0.143 weeks 0.0329 months progress.

13FN-UNIT 2 3.10-16 Amendment No. 253

Multiple Control Rod Withdrawal - Refueling 3.10.6

',.10 SPECIAL OPERATIONS

'3.10.6 Multiple Control Rod Withdrawal - Refueling L.CO 3.10.6 The requirements of LCO 3.9.3, "Control Rod Position"; LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY - Refueling," may be suspended, and the "full-in" position indicators may be bypassed for any number of control rods in MODE 5, to allow withdrawal of these control rods, removal of associated control rod drives (CRDs), or both, provided the following requirements are met:

a. The four fuel assemblies are removed from the core cells associated with each control rod or CRD to be removed;

b. All other control rods in core cells containing one or more fuel assemblies are fully inserted; and

c. Fuel assemblies shall only be loaded in compliance with an approved spiral reload sequence.

APPLICABILITY: MODE 5 with LCO 3.9.3, LCO 3.9.4, or LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME:

A. One or more of the above A.1 Suspend withdrawal of Immediately requirements not met. control rods and removal of associated CRDs.

AND A.2 Suspend loading fuel Immediately assemblies.

AND (continued)

EIFN-UNIT 2 3.10-17 Amendment No. 253

Multiple Control Rod Withdrawal - Refueling 3.10.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Initiate action to fully Immediately insert all control rods in core cells containing one or more fuel assemblies.

OR A.3.2 Initiate action to satisfy Immediately the requirements of this LCO.

EIFN-UNIT 2 3.10-1 8 Amendment No. 253

Multiple Control Rod Withdrawal - Refueling 3.10.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .s from core cells associated with each control rod or CRD removed.

SR 3.10.6.2 Verify all other control rods in core cells 24 hours1 days 0.143 weeks 0.0329 months containing one or more fuel assemblies are fully inserted.

SR 3.10.6.3 NOTE Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in 24 hours1 days 0.143 weeks 0.0329 months compliance with an approved spiral reload sequence.-

E3FN-UNIT 2 3.10-19 Amendment No. 253

Control Rod Testing - Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing - Operating LCO 3.10.7 The requirements of LCO 3.1.6, "Rod Pattern Control," may be suspended to allow performance of SDM demonstrations, control rod scram time testing, and control rod friction testing provided:

a. The banked position withdrawal sequence requirements of SR 3.3.2.1.7 are changed to require the control rod sequence to conform to the specified test sequence.

OR

b. The RWM is bypassed; the requirements of LCO 3.3.2.1, "Control Rod Block Instrumentation," Function 2 are suspended; and conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.

APPLICABILITY: MODES 1 and 2 with LCO 3.1.6 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME:

A. Requirements of the LCO A.1 Suspend performance of Immediately not met. the test and exception to LCO 3.1.6.

El.FN-UNIT 2 3.10-20 Amendment No. 253

Control Rod Testing - Operating 3.10.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.7.1 NOTE Not required to be met if SR 3.10.7.2 satisfied.

Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the specified test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.7.2 NOTE Not required to be met if SR 3.10.7.1 satisfied.

Verify control rod sequence input to the RWM Prior to control is in conformance with the approved control rod movement rod sequence for the specified test.

13FN-UNIT 2 3.1 0-21 Amendment No. 253

SDM Test - Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow.

SDM testing, provided the following requirements are met:

a. LCO 3.3.1.1, "Reactor Protection System Instrumentation,"

MODE 2 requirements for Functions 2.a, 2.d, and 2.e of Table 3.3.1.1-1;

b. 1. LCO 3.3.2.1, "Control Rod Block Instrumentation," MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence (BPWS) requirements of SR 3.3.2.1.7 changed to require the control rod sequence to conform to the SDM test sequence, OR

2. Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c. Each withdrawn control rod shall be coupled to the associated CRD;

d. All control rod withdrawals during out of BPWS control rad moves shall be made in notch out mode;

e. No other CORE ALTERATIONS are in progress; and

f. CRD charging water header pressure a 940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

EIFN-UNIT 2 3.10-22 Amendment No. 253

SDM Test - Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NOTES-NOTE Separate Condition entry Rod worth minimizer may be is allowed for each bypassed as allowed by control rod. LCO 3.3.2.1, "Control Rod Block Instrumentation," if required, to allow insertion of inoperable One or more control rods control rod and continued not coupled to its operation.

associated CRD.

A.1 Fully insert inoperable 3 hours0.125 days 0.0179 weeks 0.00411 months control rod.

AND A.2 Disarm the associated 4 hours0.167 days 0.0238 weeks 0.00548 months CRD.

B. One or more of the above B.1 Place the reactor mode Immediately requirements not met for switch in the shutdown or reasons other than refuel position.

Condition A.

13FN-UNIT 2 3.10-23 Amendment No. 253

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQ'JENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for According to the LCO 3.3.1.1, Functions 2.a, 2.d and 2.e of applicable SRs Table 3.3.1.1-1.

SR 3.10.8.2 NOTE Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for According to the LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1. applicable SRs SR 3.10.8.3 NOTE Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the SDM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours0.5 days 0.0714 weeks 0.0164 months progress.-

(continued) e FN-UNIT 2 3.10-24 Amendment No. 253

SDM Test - Refueling 3.10.8 SIURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQIJENCY SR 3.10.8.5 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position. control rod is withdrawn to "full out" position AND Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CR.D System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days

Ž 940 psig.

EFN-UNIT 2 3.10-25 Amendment No. 253

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The BFN site contains approximately 840 acres and is located on the north shore of Wheeler Lake at Tennessee River Mile 294 in Limestone County, Alabama.

The minimum distance from the outside of the secondary containment building to the boundary of the exclusion area as defined in 10 CFR 100.3 is > 4000 feet.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 764 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material,.and water rods or channels. 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 NRC staff approved codes and methods and have been shown by tests or analyses to comply with all 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 Control Rod Assemblies The reactor core shall contain 185 cruciform shaped control rod assemblies. The control material shall be boron carbide, hafnium metal, or both, as approved by the NRC.

(continued)

BFN-UNIT 2 4.0-1 Amendment No. 284

Design Features 4.0 4.0 DESIGN FEATURES (continued) 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. keff < 0.95 if fully flooded with unborated water, which includes I an allowance for uncertainties as described in Section 10.3 of the FSAR; and

b. A nominal 6.563 inch center to center distance between fuel I assemblies placed in the storage racks.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. keff < 0.95 if fully flooded with unborated water, which includes I an allowance for uncertainties as described in Section 10.2 of the FSAR;

b. keff < 0.90 if in a dry condition, or in the absence of moderator, I as described in Section 10.2 of the FSAR; and

c. A nominal 6.625 inch center to center distance between fuel I assemblies placed in storage racks.

(coni inued)

BFN-UNIT 2 4.0-2 Amendment No. 284

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 640 ft.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3471 fuel assemblies.

BFN-UNIT 2 4.0-3 Amendment No. 253

Res Donsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Site Vice-President shall be responsible for overall activities at the site, while the Plant Manager shall be responsible for overall unit operation. The Site Vice-President and the Plant Manager shall delegate in writing the succession to this responsibility during their absence.

The Plant Manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

5.1.2 The Shift Manager shall be responsible for the control room command function. During any absence of the Shift Manager from the control room while the unit is in MODE 1, 2, or 3, 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 Shift Manager from the control room while the unit is in MODE 4 or.5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

E3FN-UNIT 2 5.0-1 Amendment No. 253

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, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Nuclear Power Organization Topical Report (TVA-NPOD89-A);

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. The Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d. The individuals'who train the operating staff, carry out radiological controls, 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.

(continued)

BF N-UNIT 2 5.0-2 Amendment No. 253

Organization 5.2 5.2 Organization (continued) 5.2.2 Unit Staff The unit staff organization shall include the following:.

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, or 3.

When all three units are shutdown or defueled, a total of three non-licensed operators shall be assigned for all three units.

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours0.0833 days 0.0119 weeks 0.00274 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c. A radiological controls technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours0.0833 days 0.0119 weeks 0.00274 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g., licensed Senior Reactor Operators (SROs), licensed Reactor Operators (ROs), radiological controls technicians, auxiliary operators, and key maintenance personnel).

(continued)

BFN-UNIT 2 5.0-3 Amendment No. 25- 266

v v -- L; ,

Organization 5.2 5.:2 Organization 5.2.2 Unit Staff (continued)

The controls shall include guidelines on working hours that ensure

- adequate shift coverage shall be maintained without routine heavy use of overtime.

Any deviation from the above guidelines shall be authorized in advance by the Plant Manager or the Plant Manager's designee, in accordance with approved administrative procedures, and wit:h documentation of the basis for granting the deviation. Routine deviation from the working hour guidelines shall not be authorized.

Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.

(continued)

BFINI-UNIT 2 5.0-4 Amendment No. 2i5,~ 266

. ) . . 1 ; 2, 7om

, . v:; <d; .~ L'U v

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

e. The Operations Superintendent shall hold a current SRO license on a I Browns Ferry unit.

f. An individual shall provide advisory technical support to the shift operating crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

BFN-UNIT 2 5.0-5 Amendment N,! G .s266

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 referenced for comparable positions in Regulatory Guide 1.8, Revision 2 (April 1987) for all new personnel qualifying on positions identified in regulatory position C.1 after January 1, 1990. Persornel qualified on these positions prior to this date will still meet the requirements of Regulatory Guide 1.8, Revision 1-R (May 1977).

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

BF-N-UNIT 2 5.0-6 Amendment No. 2537 266

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 instructions required to implement the requirements of NUREG-0737 and to 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.

BFN-UNIT 2 5.0-7 Amendment ND. 253

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program; 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.

Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

1. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and

2. a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after review and acceptance by the process described in TVA-NQA-PLN89-A; and (continued)

EFN-UNIT 2 5.0-8 Amendment No. 253

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued)

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those poitions 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 the Core Spray, High Pressure Coolant Injection, Residual Heat Removal, and Reactor Core Isolation Cooling. The program shall include the following preventive maintenance:

a. Periodic visual inspection requirements; and

b. System leak test requirements for each system, to the extent permitted by system design and radiological conditions, at refueling cycle intervals or less.

(continued)

BFN-UNIT 2 5.0-9 Amendment No. 253

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5;3 (Deleted).

5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as 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 ten times the concentration values in Appendix B,Table 2, Column 2 to 10 CFR 20.1001-20.2402; (continued)

BF N-UNIT 2 5.0-10 Amendment No. 253, 266, 282

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls ProQram (continued)

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 from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix l;

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 doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix l;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with following:

1. . For noble gases: a dose rate of < 500 mrem/yr to the whole body and < 3000 mTemlyr to the skin, and

2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days: a dose rate of

< 1500 mrem/yr to any organ; (continued)

BFNq-UNIT 2 5.0-11 Amendment No. 25S3, 266

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix l;

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 from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix l; and

j. Limitations on the annual dose or dose commitment to any mem:er of the public beyond the site boundary due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

k. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR Section 4.2.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

a. Testing frequencies specified in Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda are as follows:

(continued)

BF N-UNIT 2 5.0-12 Amendment No. 2§T 26 6

Programs and Manuals 5.5

!5.5 Programs and Manuals 5.5.6 Inservice Testing Program (continued)

ASME Boiler and Pressure Vessel Code and applicable Required Frequencies for Addenda terminology for performing inservice testing inservice testing activities activities Weekly At least once per 7 clays Monthly . At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every At least once per 18'4 days 6 months 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 performing 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)

EIFN-UNIT 2 5.0-13 Amendment No. 253

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.7 Ventilation Filter Testing Program (VFTP)

The VFTP shall establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

a. Demonstrate for each of the ESF systems (Standby Gas Treatment (SGT) System and Control Room Emergency Ventilation (CREV)

System) that an inplace test of the HEPA filters shows a penetration and system bypass < 1.0% when tested in accordance with ANSI N510-1975 at the system flowrate specified below, +/- 10%.

ESF Ventilation System Flowrate (cfm)

SGT System 9000 CREV System 3000 This testing shall be performed 1) every 24 months, 2) after partial or complete replacement of HEPA filters, 3) after any structural maintenance on the system housing, or 4) following significant painting, fire, or chemical release in any ventilation zone communicating with the system.

(continued)

BFN-UNIT 2 5.0-14 Amendment No. 255 November 30, 1998

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testing Program (VFTP) (continued)

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 1.0%

when tested in accordance with ANSI N510-1975 at the system flowrate specified below, +/- 10%.

ESF Ventilation System Flowrate (cfm)

SGT System 9000 CREV System 3000 This testing shall be performed 1) every 24 months, 2) after partial or I complete replacement of the charcoal adsorber bank, 3) after any structural maintenance on the system housing, or 4) following significant painting, fire, or chemical release in any ventilation zone communicating with the system.

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, shows a methyl iodide efficiency

Ž 90% when tested in accordance with ASTM D3803-1989.

This testing shall be performed 1) every 24 months, 2) after every 720 I hours of system operation, or 3) following significant painting, fire, or chemical release in any ventilation zone communicating with the system.

(continued)

BFN-UNIT 2 5.0-15 Amendment No. 255 November 30, 1998

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testing Proaram (VFTP) (continued)

d. Once every 24 months demonstrate for each of the ESF systems that I the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below at the system flowrate specified below, +/- 10%:

ESF Ventilation System Delta P Flowrate (inches water) (cfm)

SGT System 7 9000 CREV System 6 3000

e. Once every 24 months demonstrate that the heaters for the SGT I System dissipate > 40 kW when tested in accordance with ANSI N510-1975.

5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained downstream of the offgas recombiners, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

a. The limits for concentrations of hydrogen downstream of the offgas recombiners and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion); and (continued)

BFN-UNIT 2 5.0-16 Amendment No. 255 November 30, 1998

Programs anrd Manuals 5.5 5.5 Programs and Manuals 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Proaram (continued)

b. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

5.5.9 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of the fuel oil in each 7-day fuel oil tank shall be established. The purpose of the program is to establish the following:

a. The quality of the fuel oil in each 7-day fuel oil tank is within the acceptable limits specified in Table I of ASTM D-975-1989 when tested every 92 days; and

b. Total particulate concentration of the fuel oil in each 7-day fuel oil tank is < 10 mg/I when tested every 92 days in accordance with ASTM D-2276, Method A-2 or A-3.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program testing frequencies.

(continued)

BFN-UNIT 2 5.0-1 7 Amendment No. 253

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.10 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following: I

1. a change in the TS incorporated in the license; or

2. a change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d.. Proposed changes that meet the criteria of Specification 5.5.10b 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).

(continued)

BFI4-UNIT 2 5.0-1 8 Amendment No.253T 266

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.11 Safety Function Determination Program (SFDP)

This program ensures 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 limitations and remedial or compensatory actions may be identified to be 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. The SFDP shall contain the following:

a. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

(con tinued')

EIFN-UNIT 2 5.0-19 Amendment No. 253

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Procram (SFDP) (continued)

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:

a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.

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.

5.5.12 Primary Containment Leakage Rate Testing Program A program shall be established to implement 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. 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:

NEI 94 1995, Section 9.2.3: The first Unit 2 Type A test performed after the November 6, 1994, Type A test shall be performed no later than November 6,2009.

(continued)

BFN-UNIT 2 5.0-20 Amendment No. 254, 293

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 50.6 psig. The maximum allowable primary containment leakage rate, La, shall be 2% of primary containment air weight per day at P8 .

Leakage Rate acceptance criteria are:

a. The primary containment leakage rate acceptance criteria is < 1.0 La.

During the first unit startup following the testing performed in accordance with this program, the leakage rate acceptance criteria are < 0.60 L, for the Type B and Type C tests, and < 0.75 L. for the Type A test; and

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate < 0.05 La when tested at > Pa.

2) Air lock door seals leakage rate is < 0.02 L. when the overall air lock is pressurized to 2 2.5 psig for at least 15 minutes.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

BFN.-UNIT 2 5.0-21 Amendment No. X3,293

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 (Deleted).

(continued)

BF1N-UNIT 2 5.0-22 Amendment No. a-3. 291

Reporting Requirements 5.6

.5.6 Reporting Requirements (continued) 5.6.2 Annual Radiological Environmental Operating Report NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the.

operation of the 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 in the Offs-ite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

5.6.3 Radioactive Effluent Release Report NOTE A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station; however for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the 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 Part 50, Appendix I, Section IV.B.1.

(coni inued)

.BFN-UNIT 2 5.0-23 Amendment No. 253

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 (Deleted).

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) The APLHGRs for Specification 3.2.1; (2) The LHGR for Specification 3.2.3; (3) The MCPR Operating Limits for Specification 3.2.2; and (4) The RBM setpoints and applicable reactor thermal power ranges for each of the setpoints for Specification 3.3.2.1, Table 3.3.2.1-1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel.

2. XN-NF-81-58(P)(A), RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model.

3. XN-NF-85-67(P)(A), Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel.

4. EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model.

5. ANF-89-98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs.

(continued)

BFN-LINIT 2 5.0-24 Amendment No. 253, 266, 287- 291

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

6. XN-NF-80-19(P)(A) Volume 1, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis.

7. XN-NF-80-19(P)(A) Volume 4, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads.

8. EMF-2158(P)(A), Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2.

9. XN-NF-80-19(P)(A) Volume 3, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description.

10. XN-NF-84-105(P)(A) Volume 1, XCOBRA-T: A Computer Coda for BWR Transient Thermal-Hydraulic Core Analysis.

11. ANF-524(P)(A), ANF Critical Power Methodology for Boiling Water Reactors.

12. ANF-913(P)(A) Volume 1, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses.

13. ANF-1358(P)(A), The Loss of Feedwater Heating Transient in Boiling Water Reactors.

14. EMF-2209(P)(A), SPCB Critical Power Correlation.

15. EMF-2245(P)(A), Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel.

16. EMF-2361(P)(A), EXEM BWR-2000 ECCS Evaluation Model.

17. EMF-2292(P)(A), ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients.

(continued)

BF:N-UNIT 2 5.0-24a Amendment No. 287

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (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 PAM Report When a report is required by Condition B or G of LCO 3.3.3.1, "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.

S -

BFN-UNIT 2 5.0-25 Amendment No. 253

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation dose rates in the area; or

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or (continued)

BFN-UNIT 2 5.0-26 Amendment No. 2I5 266

High Radiation Area 5.7 5 7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceedinq 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or

4. A self-reading dosimeter (e.g., pocket ionization chamber) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into sUch areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

(conti.iued)

BF-N-UNIT 2 5.0-27 Amendment No. 25$. 266 fs-Zfr : ,:

High Radiation Area 5.7 5.7 High Radiation Area (continued) 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift manager, radiological controls superintendent, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or (continued)

BFN-UNIT 2 5.0-28 Amendment No 266

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or

3. A self-reading dosimeter (e.g., pocket ionization chamber) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of

.personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

(continued)

BFN-UNIT 2 5.0-29 Amendment No. 266 UV0R ?,nzi

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continuec)

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

BFN-UNIT 2 5.0-30 Amendment No. 266 M011"

'f A1

APPENDIX B DELETED BFN-UNIT 2 1 Amendment No. 262 i.0V 2 3 1l29

APPENDIX B TO FACILITY OPERATING LICENSE DPR-52 FOR BROWNS FERRY NUCLEAR PLANT UNIT 2 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 (DELETED IN ITS ENTIRETY)

EIFN-UNIT 2 1 Amendment No. 196 April 29, 1991

APPENDIX B ADDITIONAL CONDITIONS Additional Conditions Nurber Implementation Date 253 The licensee is authorized to relocate certain requirements included in Appendix A and the former This amendment is effective Appendix B to licensee-controlled documents. immediately and shall be Implementation of this amendment shall include the implemented within 90 days relocation of these requirements to the appropriate of the date of this documents, as described in the licensee's application amendment.

dated September 6, 1996, as supplemented May 1, August 14, November 5 and 14, December 3, 4, 11, 22, 23, 29 and 30, 1997, January 23, March 12, April 16, 20 and 28, May 7, 14, 19 and 27, and June 2, 5, 10 and 19, 1998, evaluated in the NRC staffs Safety Evaluation enclosed with this amendment.

254 TVA will perform an analysis of the design basis loss- This amendment is effective of-coolant accident to confirm compliance with General immediately.

Design Criterion (GDC)-19 and offsite limits considering main steam isolation valve leakage and emergency core cooling system leakage. The results of this analysis will be submitted to the NRC for its review and approval by March 31,1999. Following NRC approval, any required modifications will be implemented during the refueling outages scheduled for Spring 2000 for Unit 3 and Spring 2001 for Unit 2.

TVA will maintain the ability to monitor radiological conditions during emergencies and administer potassium-iodide to control room operators to maintain doses within GDC-19 guidelines. This ability will be maintained until the required modifications, if any, are complete.

BFN Unit ;' Amendment No. 254 SEP 0 ) 1993

APPENDIX B ADDITIONAL CONDITIONS 254 Classroom and simulator training on all power uprate This amendment is effective related changes that affect operator performance will immediately.

be conducted prior to operating at uprated conditions.

Simulator changes that are consistent with power uprate conditions will be made and simulator fidelity will be validated in accordance with ANSI/ANS 3.5-1985. Training and the plant simulator will be modified, as necessary, to incorporate changes identified during startup testing.

BFN Unit 2 2 Amendment No. 254

APPENDIX B ADDITIONAL CONDITIONS An-lend. Additional Conditions Implementation Elate Nu nber 25'3 The licensee is authorized to relocate certain This amendment is effective.

' requirements included in Appendix A and the former immediately and shall be Appendix B to licensee-controlled documents. implemented within 90 days Implementation of this amendment shall include the of the date of this relocation of these requirements to the appropriate amendment.

documents, as described in the licensee's application dated September 6, 1996, as supplemented May 1, August 14, November 5 and 14, December 3, 4, 11, 22, 23, 29 and 30, 1997, January 23, March 12, April 16, 20 and 28, and May 7, 14, 19 and 27, and June 2, 5, 10 and 19, 1998, evaluated in the NRC staffs Safety Evaluation enclosed with this amendment.

BFN Unit 2 Amendment No. 253 JUL 1 4 ,998

v t e Letter Sequence Acceptance Review
TAC:MC1705, (Approved, Closed)
Initiation Request, Request Acceptance, Acceptance, Acceptance Supplement, Supplement, Supplement Administration Meeting, Meeting, Meeting Questions 28 June 2004 28 July 2004 26 August 2004 16 September 2004 31 August 2004 4 November 2004 4 November 2004 Answers Results Approval, Approval, Approval, Approval, Approval, Approval, Approval Other: ML040650206, ML040910016, ML041310029, ML042240255, ML042990519, ML051180464, ML051250308, ML060410288, ML060450582, ML060950060, ML061110094, ML061110102, ML061110126, ML061140322, ML061730464, ML091870509, ML11171A037, ML11171A038, ML11308A018
MONTHYEAR2005-05-04 [Table View]

ML061140209

Text

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