Text

Copy of Improved Technical Specifications (ITS)
	ML083010076
Person / Time
Site:	Davis Besse
Issue date:	10/21/2008
From:	Allen B; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, L-08-338, TAC MD6398
	Download: ML083010076 (291)
	v • d • e

FENOC 5501 North State Route 2 FirstEnergyNuclear Operating Company Oak Harbor,Ohio 43449 Barry S. Allen 419-321-7676 Vice President- Nuclear Fax: 419-321-7582 October 21, 2008 L-08-338 10 CFR 50.90 ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, D. C. 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Copy of Improved Technical Specifications (ITS) TAC No. MD6398 By letter dated August 3, 2007, as supplemented by letters dated October 29, 2007, May 16, 2008 (2 letters), July 23, 2008, August 07, 2008, August 26, 2008 and September 3, 2008, FirstEnergy Nuclear Operating Company (FENOC) submitted an application to amend the Technical Specifications of Davis-Besse Nuclear Power Station, Unit 1.(DBNPS), revising the current Technical Specifications (CTS) to the Improved Technical Specifications (ITS) consistent with the Improved Standard Technical Specifications (ISTS) as described in NUREG-1430, "Standard Technical Specifications Babcock and Wilcox Plants," Revision 3.1, and certain generic changes to the NUREG.

The Attachment provides a copy of the DBNPS ITS for issuance with the associated License Amendment Request (LAR) and is a replacement for the existing CTS. This copy incorporates changes based on the original application and supplements, with one exception. A typographical error to ITS 3.8.1 Condition H was identified. The first condition of ITS 3.8.1 Condition H should reference Condition "G", not "F" as shown in the August 7, 2008 letter (Attachment 1, Volume 13, Rev. 1, Page 36 of 323). This error has been corrected in the attached copy of the DBNPS ITS.

Davis-Besse Nuclear Power Station L-08-338 Page 2 of 2 There are no regulatory commitments contained in this, letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -

Fleet Licensing, at (330) 761-6071.

I declare under penalty of perjury that the foregoing is true and correct.,..

Executed on. 20 016O Sincerely, Barry S. AlleK, Vice President-Nuclear

Attachment:

Copy of Improved Technical Specifications (ITS) cc: (all w/o Attachment)

NRC Region III Administrator NRR Project Manager NRC Resident Inspector Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board

Attachment 1 L-08-338 Copy of Improved Technical Specifications (ITS)

TABLE OF CONTENTS Page Number v TABLE OF CONTENTS Page Number 1.0 USE AND APPLICATION 1.1 D efinitions .............................................................................................................. 1.1-1 1.2 Logical C onnectors ................................................................................................ 1.2-1 1.3 C om pletion T im es .................................................................................................. 1.3-1 1.4 .

Frequency ............................................................................ ... ....... ............... i 1.4-1 2.0 SA FETY LIM ITS (SLs) ................................................................................................ 2.0-1 2.1 SLs 2.2 SL Violations 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ............ 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .......................................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) ........................................................................... 3.1.1-1 3.1.2 R eactivity B alance .............................................................................................. 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC) .......................... 3.1.3-1 3.1.4 CONTROL ROD Group Alignment Limits .......................................................... 3.1.4-1 3.1.5 Safety Rod Insertion Lim its ................................................................................ 3.1.5-1 3.1.6 AXIAL POWER SHAPING ROD (APSR) Alignment Limits ................................ 3.1.6-1 3.1.7 Position Indicator Channels ............................................................................... 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions - MODE 1 ........................................................... 3.1.8-1 3.1.9 PHYSICS TESTS Exceptions - MODE 2 ........................................................... 3.1.9-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Regulating Rod Insertion Limits ......................................................................... 3.2.1-1 3.2.2 AXIAL POWER SHAPING ROD (APSR) Insertion Limits .................................. 3.2.2-1 3.2.3 AXIAL POWER IMBALANCE Operating Limits ................................................ 3.2.3-1 3.2.4 QUADRANT POWER TILT (QPT) ..................................................................... 3.2.4-1 3.2.5 Pow er Peaking Factors ...................................................................................... 3.2.5-1 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation ............................................ 3.3.1-1 3.3.2 Reactor Protection System (RPS) Manual Reactor Trip .................................... 3.3.2-1 3.3.3 Reactor Protection System (RPS) - Reactor Trip Module (RTM) ....................... 3.3.3-1 3.3.4 CONTROL ROD Drive (CRD) Trip Devices ...................................................... 3.3.4-1 3.3.5 Safety Features Actuation System (SFAS) Instrumentation .............................. 3.3.5-1 3.3.6 Safety Features Actuation System (SFAS) Manual Initiation ............................. 3.3.6-1 3.3.7 Safety Features Actuation System (SFAS) Automatic A ctuation Logic ............................................................................................. 3.3.7-1 3.3.8 Emergency Diesel Generator (EDG) Loss of Power Start (LOPS) .......... 3.3.8-1 3.3.9 Source Range Neutron Flux .............................................................................. 3.3.9-1 3.3.10 Intermediate Range Neutron Flux .................................................................... 3.3.10-1 3.3.11 Steam and Feedwater Rupture Control System (SFRCS)

Instrum entation ........................................................................................... 3.3.11-1 3.3.12 Steam and Feedwater Rupture Control System (SFRCS)

Manual Initiation ........................................................................................ 3.3.12-1 3.3.13 Steam and Feedwater Rupture Control System (SFRCS)

Actuation ................................................................................................... 3.3 .13-1 Davis-Besse i Amendment 279

TABLE OF CONTENTS Page Number 3.3 INSTRUMENTATION (continued) 3.3.14 Fuel Handling Exhaust - High Radiation ........................... 3.3.14-1 3.3.15 Station Vent Normal Range Radiation Monitoring ............................................ 3.3.15-1 3.3.16 Anticipatory Reactor Trip System (ARTS) Instrumentation .............................. 3.3.16-1 3.3.17 Post Accident Monitoring (PAM) Instrumentation ............................................. 3.3.17-1 3.3.18 Remote Shutdown System .............................................................................. 3.3.18-1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (D NB ) Limits ..................................................................................... 3.4 .1-1 3.4.2 RCS Minimum Temperature for Criticality .......................................................... 3.4.2-1 3.4.3 RCS Pressure and Temperature (PIT) Limits .................................................... 3.4.3-1 3.4.4 RCS Loops - MODES 1 and 2 ............................................................................ 3.4.4-1 3.4.5 RCS Loops - MODE 3 ......................................... 3.4.5-1 3.4.6 RCS Loops - MODE 4 ........................................................................................ 3.4.6-1 3.4.7 RCS Loops - MODE 5, Loops Filled ................................................................... 3.4.7-1 3.4.8 RCS Loops - MODE 5, Loops Not Filled ........................................................... 3.4.8-1 3 .4.9 P ressurizer :.....

.............................................. ......................... ....................... 3.4.9-1 3.4.10 Pressurizer Safety Valves ................................................................................ 3.4.10-1 3.4.11 Pressurizer Pilot Operated Relief Valve (PORV) ..................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) ........................................ 3.4.12-1 3.4.13 RCS Operational LEAKAGE ............................................................................ 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ....................... 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ......................................................... 3.4.15-1 3.4.16 RCS Specific Activity ........................................................................................ 3.4.16-6 3.4.17 Steam Generator (SG) Tube Integrity ............................. 3.4.17-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Core Flooding Tanks (CFTs) .............................................................................. 3.5.1-1 3.5.2 E C C S - O perating .............................................................................................. 3.5.2-1 3.5.3 E C C S - S hutdow n .............................................................................................. 3.5.3-1 3.5.4 Borated Water Storage Tank (BWST) ....... ................................ 3.5.4-1 3.6 CONTAINMENT SYSTEMS 3.6.1 C ontainm ent ...................................................................................................... 3.6.1-1 3.6.2 C ontainm ent A ir Locks ....................................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves ............................................................................. 3.6.3-1 3.6.4 C ontainm ent Pressure........................................................................................ 3.6.4-1 3.6.5 Containment Air Temperature ............................................................................ 3.6.5-1 3.6.6 Containment Spray and Air Cooling Systems .................................................... 3.6.6-1 3.6.7 Trisodium Phosphate Dodecahydrate (TSP) Storage ........................................ 3.6.7-1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) ........................................... ...................... 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ................................................................ 3.7.2-1 3.7.3 Main Feedwater Stop Valves (MFSVs), Main Feedwater Control Valves (MFCVs), and associated Startup Feedwater Control Valves (SFCVs) ........................................... 3.7.3-1 Davis-Besse ii Amendment 279

TABLE OF CONTENTS Page Number 3.7 PLANT SYSTEMS (continued) 3.7.4 Turbine Stop Valves (TSVs) ....................................................... .... 3.7.4-1 3.7.5 Emergency Feedwater (EFW) ....................................................... ..... 3.7.5-1 3.7.6 Condensate Storage Tanks (CSTs) ................................ .......................... 3.7.6-1 3.7.7 Component Cooling Water (CCW) System ........................................................ 3.7.7-1 3.7.8 Service Water System (SWS) ........... ......................... 3.7.8-1 3.7.9 Ultimate Heat Sink (UHS) ....................................... 3.7.9-1 3.7.10 Control Room Emergency Ventilation System (CREVS) ................................. 3.7.10-1 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS) ....... 3.7.11-1 3.7.12 Station Emergency Ventilation System (EVS) .................................................. 3.7.12-1 3.7.13 Spent Fuel Pool Area Emergency Ventilation System (EVS) ........................... 3.7.13-1 3.7.14 Spent Fuel Pool Water Level .......................................................................... 3.7.14-1 3.7.15 Spent Fuel Pool Boron Concentration .............................................................. 3.7.15-1 3.7.16 Spent Fuel Pool Storage .................................................................................. 3.7.16-1 3.7.17 Secondary Specific Activity .............................................................................. 3.7.17-1 3.7.18 Steam Generator Level .................................................................................... 3.7.18-1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 A C Sources - O perating .................................................................................... 3.8.1-1 3.8.2 AC Sources - Shutdown .................................................................................... 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ......................................................... 3.8.3-1 3.8.4 DC Sources - O perating ...................................................................................... 3.8.4-1 3.8.5 DC Sources - Shutdown ..................................................................................... 3.8.5-1 3.8.6 Battery Param eters ........................................................................................... 3.8.6-1 3.8.7 Inverters - O perating ............................................. ..................................... 3.8.7-1 3.8.8 Inverters - Shutdow n .......................................................................................... 3.8.8-1 3.8.9 Distribution Systems - Operating ....................................................................... 3.8.9-1 3.8.10 Distribution Systems - Shutdown ..................................................................... 3.8.10-1 3.9 REFUELING OPERATIONS 3.9.1 Boron C oncentration .......................................................................................... 3.9.1-1 3.9.2 Nuclear Instrumentation ...................................................................... ............... 3.9.2-1 3.9.3 D ecay T im e ........................................................................................................ 3.9.3-1 3.9.4 Decay Heat Removal (DHR) and Coolant Circulation - High Water Level ........ 3.9.4-1 3.9.5 Decay Heat Removal (DHR) and Coolant Circulation - Low Water Level ......... 3.9.5-1 3.9.6 Refueling Canal Water Level .............................................................................. 3.9.6-1 4.0 DES IG N FEATU R ES .................................................................................................. 4.0-1 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage 5.0 ADMINISTRATIVE CONTROLS 5 .1 R espo nsibility ........................................................................................................ 5 .1-1 5.2 Organization .................................................. 5.2-1 5.3 Unit Staff Q ualifications ......................................................................................... 5.3-1 5.4 P rocedures ........................................................................................... ................... 5.4-1 5.5 Program s and Manuals ......................................................................................... 5.5-1 Davis-Besse iii¸ Amendment 279

TABLE OF CONTENTS Page Number 5.0 ADMINISTRATIVE CONTROLS (continued) 5.6 Reporting Requirements ............................ I........................................................... 5.6-1 5.7 High Radiation Area .............................................................................................. 5.7-1 Davis-Besse iv Amendment 279

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.

ALLOWABLE THERMAL ALLOWABLE THERMAL POWER shall be the maximum POWER reactor core heat transfer rate to the reactor coolant permitted by consideration of the number and configuration of reactor coolant pumps (RCPs) in operation.

AXIAL POWER IMBALANCE AXIAL POWER IMBALANCE shall be the power in the top half of the core, expressed as a percentage of RATED THERMAL POWER (RTP), minus the power in the bottom half of the core, expressed as a- percentage of RTP.

AXIAL POWER SHAPING APSRs shall be control components used to control the axial RODS (APSRs) power distribution of the reactor core. The APSRs are positioned manually by the operator and are not tnppable.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

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 1.1-1 Amendment 279 Davis-Besse Davis-Besse 1.1-1 Amendment 279

Definitions 1.1 1.1 Definitions CHANNEL CHECK (continued) the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total steps.

CONTROL RODS CONTROL RODS shall be all full length safety and regulating rods that are used to shut down the reactor and control power level during maneuvering operations-CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. 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 III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or those listed in Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977, or those listed in ICRP 30, Supplement to Part 1, page 192-212, table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity".

- AVERAGE E shall be the average (weighted in proportion to the DISINTEGRATION ENERGY concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.

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Definitions 1.1 1.1 Definitions LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except RCP seal return flow), that is captured andconducted to collection systems or a sump or collecting tank;

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

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE),

b. Unidentified LEAKAGE All LEAKAGE (except RCP seal return flow) that is not identified LEAKAGE; and

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

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

NUCLEAR HEAT FLUX HOT FQ shall be the maximum local linear power density in the CHANNEL FACTOR (FQ) core divided by the core average fuel rod linear power density, assuming nominal fuel pellet and fuel rod dimensions.

NUCLEAR ENTHALPY RISE FNH shall be the ratio of the integral of linear power along the HOT CHANNEL fuel rod on which minimum departure from nucleate boiling FACTOR (FNH) ratio occurs, to the average fuel rod power.

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Definitions 1.1 1.1 Definitions OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related supportfunction(s).

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

These tests are:

a. Described in Section 14, "Initial Tests and Operation," of the UFSAR;

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

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. The pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.4.

QUADRANT POWER TILT QPT shall be defined by the following equation and is (QPT) expressed as a percentage of the Power in any Core Quadrant (Pquad) to the Average Power of all Quadrants (Pavg).

QPT = 100 [ (Pquad I Pavg) - 1]

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2817 MWt.

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Definitions 1.1 1.1 Definitions REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval from SYSTEM (RPS) RESPONSE when the monitored parameter exceeds its RPS trip setpoint at TIME the channel sensor until electrical power is interrupted at the control rod drive trip breakers. 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.

SAFETY FEATURES The SFAS RESPONSE TIME shall be that time interval from ACTUATION SYSTEM (SFAS) when the monitored parameter exceeds its SFAS actuation RESPONSE TIME setpoint at the channel sensor until the SFAS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All full length CONTROL RODS (safety and regulating) are fully inserted except for the single CONTROL ROD of highest reactivity worth, which is assumed to be fully withdrawn. With any CONTROL ROD not capable of being fully inserted, the reactivity worth of these CONTROL RODS must be accounted for in the determination of SDM;

b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design level; and

c. There is no change in APSR position.

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

1.1-5 Amendment 279 Davis-Besse Davis-Besse 1.1-5 Amendment 279

Definitions 1.1 1.1 Definitions STEAM AND FEEDWATER The SFRCS RESPONSE TIME shall be that time interval from RUPTURE CONTROL when the monitored parameter exceeds its SFRCS actuation SYSTEM (SFRCS) setpoint at the channel sensor until the SFRCS equipment is RESPONSE TIME capable of performing its safety function (i.e., valves travel to their required positions, pumps discharge pressures reach their required values, etc.). 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.

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

Davis-Besse 1.1-6 Amendment 279

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

MODES REACTIVITY % RATED AVERAGE MODE TITLE CONDITION THERMAL REACTOR COOLANT (keff) POWER(a) TEMPERATURE (OF) 1 Power Operation > 0.99 >5 NA 2 Startup Ž0.99 <5 NA 3 Hot Standby < 0.99 NA > 280 4 Hot Shutdown(b) < 0.99 NA 280 > Tavg > 200 5 Cold Shutdown(b) < 0.99 NA < 200 6 Refueling(c) NA NA NA (a) Excluding decay heat.

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

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

Davis-Besse 1.1-7 Amendment 279

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

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

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples. illustrate the use of logical connectors.

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Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify...

AND A.2 Restore...

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

Davis-Besse 1.2-2 Amendment 279

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip...

OR A.2.1 Verify...

AND A.2.2.1 Reduce...

OR A.2.2.2 Perform...

OR A.3 -Align...

This example represents a more complicated use of logical connectors.

Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented

,position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Davis-Besse 1.2-3 Amendment 279

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions,, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

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

a. Must exist concurrent with the first inoperability; and

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

1.3-1 Amendment 279 Davis-Besse Davis-Besse 1.3-1 Amendment 279

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)

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

a. The stated Completion Time, as measured from the initial entry into the Condition,. plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated'Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 .hours," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery..

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 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.

Davis-Besse 1.3-2 Amendment 279

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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

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

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

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

Davis-Besse 1.3-3 Amendment 279

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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.

Davis-Besse 1.3-.4 Amendment 279

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore Function X 7 days Function X train to OPERABLE train status.

inoperable.

B. One B.1 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y train to OPERABLE train status.

inoperable.

C. One C.1 Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X train to OPERABLE train status.

inoperable.

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

train inoperable.

Davis-Besse 1.3-5 Amendment 279

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

1.3-6 Amendment 279 Davis-Besse Davis-Besse 1.3-6 Amendment 279

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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

1.3-7 Amendment 279 Davis-Besse 1.3-7 Amendment 279

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-5 ACTIONS

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

Separate Condition entry is allowed for each inoperable valve.

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

inoperable.

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

1.3-8 Amendment 279 Davis-Besse Davis-Besse 1.3-8 Amendment 279

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform SR 3.x.x.x. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

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

50% RTP.

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

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2),

Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

1.3-9 Amendment 279 Davis-Besse Davis-Besse 1.3-9 Amendment 279

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem isolated.

inoperable. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two Completion Times. The'l hour Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time 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.

1.3-10 Amendment 279 Davis-Besse Davis-Besse 1.3-10 Amendment 279

Completion Times 1.3 1.3 Completion Times IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

Davis-Besse 1.3-11 Amendment 279

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, "Surveillance Requirement (SR)

Applicability." The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

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

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be preformed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an

..SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.

Some Surveillances contain Notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

Davis-Besse 1.4-1 Amendment 279

Frequency 1.4 1.4 Frequency DESCRIPTION (continued)

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

b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to be failed; or

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

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

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

Davis-Besse 1.4-2 Amendment 279

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

1.4-3 Amendment 279 Davis-Besse 1.4-3 Amendment 279

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

Ž25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased- from a power level

< 25% RTP to > 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the 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.

Davis-Besse 1.4-4 Amendment 279

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

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

Ž25% RTP.

Perform channel adjustment. 7 days The interval continues whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches _>25% RTP to perform the Surveillance.

The Surveillance is still considered to be performed within the "specified Frequency." Therefore, ifthe Surveillance was not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was

< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (plus the extension allowed by SR 3.0.2) with power

> 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance was not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Davis-Besse 1.4-5 Amendment 279

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE 'FREQUENCY

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

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance was 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), but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 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 was not met), SR 3.0.4 would require satisfying the SR.

1.4-6 Amendment 279 Davis-Besse 1.4-6 Amendment 279

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be performed in MODE 1.

Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1, 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 was not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1.

Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance was not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Davis-Besse 1.4-7 Amendment 279

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be met in MODE 3.

Verify parameter is within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 was 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 SR 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 was not met), SR 3.0.4 would require satisfying the SR.

Davis-Besse 1.4-8 Amendment 279

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor'Core SLs 2.1.1.1 In MODES 1 and 2, the combination of reactor THERMAL POWER and AXIAL POWER IMBALANCE shall not exceed the protective limit shown in the COLR for the various combinations of three and four reactor coolant pump operation.

2.1.1.2 In MODES I and 2, Reactor Coolant System (RCS) core outlet temperature and pressure shall be maintained above and to the left of the SL shown in Figure 2.1.1-1.

2.1.2 Reactor Coolant System Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained < 2750 psig.

2.2 SAFETY LIMIT VIOLATIONS With any SL violation, the following actions shall be completed:

2.2.1 In MODE 1 or 2, if SL 2.1.1.1 is violated, be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 In MODE 1 or 2, if SL 2.1.1.2 is violated, restore RCS pressure and temperature within limits and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.3 In MODE 1 or 2, if SL 2.1.2 is violated, restore compliance within limits and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.4 In MODES 3, 4, and 5, if SL 2.1.2 is violated, restore RCS pressure to

< 2750 psig within 5 minutes.

Davis-Besse 2.0-1 Amendment 279

SLs 2.0.

2500 2400 I

RC High Pressure Trip (618, 2355) 2300 (68, j55)_______

RC High 4 Temperature Trip 2200 ACCEPTABLE OPERATION (622.1, 2179.8)

(618, 2144/

2100 SAFETY I LIMIT E RC Pressure a) Temperature Tr/ip -

4-.

WI 2000- i +i

/(612.0, 1 979.8)

SAFETY LIMIT VIOLATED (603,1900) 1900- F - -

RC Low Pressure Trip

/66027, 1829.8) 1800-1700- I I I ý . I . I . I . I i . ; i . I ý . I . ý 580 590 600 610 620 630 640 650 Reactor Outlet Temperature (OF)

Figure 2.1.1-1 (page 1 of 1)

Reactor Coolant System Departure from Nucleate Boiling Safety Limits Davis-Besse 2.0-2 Amendment 279

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, LCO 3.0.7, and LCO 3.0.8.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or ifdirected by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

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

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

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

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall 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 Davis-Besse 3.0-1 Amendment 279

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 (continued)

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

This Specification 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.

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

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.14, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCOs 3.1.8 and 3.1.9 allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

Davis-Besse 3.0-2 Amendment 279

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:

a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; or

b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.

Davis-Besse 3.0-3 Amendment 279

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

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

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

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.

Davis-Besse 3.0-4 Amendment 279

SR Applicability 3.0 3.0 -SR Applicability SR 3.0.4 (continued)

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.

Davis-Besse 3.0-5 Amendment 279

SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 The SDM shall be within the limits specified in the COLR.

APPLICABILITY: MODES 3, 4, and 5.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is within the limits specified in the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months COLR.

Davis-Besse 3.1.1-1 Amendment 279

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

APPLICABILITY: MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core reactivity A.1 Re-evaluate core design 7 days balance not within limit, and safety analysis and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 7 days operating restrictions and SRs.

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

Davis-Besse 3.1.2-1 Amendment 279

Reactivity Balance 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

+

SR 3.1.2.1 ----------------- NOTES----------

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

2. This Surveillance is not required to be performed prior to entry into MODE 2.

Verify measured core reactivity balance is within Prior to entering

+/- 1% Ak/k of predicted values. MODE 11after each fuel loading AND NOTE-------- -

Only required after 60 EFPD 31 EFPD thereafter Davis-Besse 3.1.2-2 Amendment 279

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

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR. The maximum upper limit shall be < 0.9 x 10-4 Ak/k/°F at < 95% RTP and

< 0.0 x 1 0 4 Ak/k/°F at > 95% RTP.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within limits. A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within the upper limit specified in the Prior to entering COLR. MODE 1 after each fuel loading Davis-Besse 3.1.3-1 Amendment 279

MTC 3.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.3.2 NOTE-.. .....-

If the MTC is more negative than the COLR limit when extrapolated to the end of cycle, SR 3.1.3.2 may be repeated. Shutdown must occur prior to exceeding the minimum allowable boron concentration at which MTC is projected to exceed the lower limit.

Verify extrapolated MTC is within the lower limit Each fuel cycle specified in the COLR. within 7 EFPDs after reaching an equilibrium boron concentration equivalent to 300 ppm Davis-Besse 3.1.3-2 Amendment 279

CONTROL ROD Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 CONTROL ROD Group Alignment Limits LCO 3.1.4 Each CONTROL ROD shall be OPERABLE.

AND Each CONTROL ROD shall be aligned to within 6.5% of its group average height.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CONTROL ROD A.1.1 Verify SDM is within limit. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not aligned to within 6.5% of its group OR average height.

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

AND A.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to _<60% of the ALLOWABLE THERMAL POWER.

AND A.3 Reduce the High Flux trip 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months setpoint to _<70% of the ALLOWABLE THERMAL POWER.

AND Davis-Besse 3.1.4-1 Amendment 279

CONTROL ROD Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Verify SDM is within limit. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND A.5 Verify the potential ejected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months rod worth is within the assumptions of the rod ejection analysis.

AND A.6 ------- NOTE---

Only required when THERMAL POWER is

> 20% RTP.

Perform SR 3.2.5.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met.

C. More than one C.1.1 Verify SDM is within limit. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CONTROL ROD not aligned within 6.5% of its OR group average height.

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

AND C.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Davis-Besse 3.1.4-2 Amendment 279

CONTROL ROD Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more CONTROL D.1.1 Verify SDM is within limit. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RODS inoperable.

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

AND D.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual CONTROL ROD positions are 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months within 6.5% of their group average height.

SR 3.1.4.2 Verify CONTROL ROD freedom of movement 92 days (trippability) by moving each individual CONTROL ROD that is not fully inserted _>3% in any direction.

SR 3.1.4.3 --------------

With rod drop times determined with less than four reactor coolant pumps operating, operation may proceed provided operation is restricted to the pump combination operating during the rod drop time determination.

Verify the rod drop time for each CONTROL ROD, Prior to reactor from the fully withdrawn position, is < 1.58 seconds criticality after from power interruption at the CONTROL ROD drive each removal of cabinets to 3/4 insertion (25% withdrawn position) the reactor vessel with Tavg > 525 0 F. head Davis-Besse 3.1.4-3 Amendment 279

Safety Rod Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Safety Rod Insertion Limits LCO 3.1.5 Each safety rod shall be fully withdrawn.

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

Not required for any safety rod inserted to perform SR 3.1.4.2.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One safety rod not fully A.1I.1 Verify SDM is within limit. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months withdrawn.

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

AND A.2 Declare the rod misaligned. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. More than one safety B.1.1 Verify SDM is within limit. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months rod not fully withdrawn.

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

AND B.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Davis-Besse 3.1.5-1 Amendment 279

Safety Rod Insertion Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each safety rod is fully withdrawn. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.1.5-2 Amendment 279

APSR Alignment Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 AXIAL POWER SHAPING ROD (APSR) Alignment Limits LCO 3.1.6 Each APSR shall be OPERABLE, unless fully withdrawn, and shall be aligned within 6.5% of its group average height.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One APSR inoperable, A.1 Perform SR 3.2.3.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months not aligned within its limits, or both. AND 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each APSR movement B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify position of each APSR is within 6.5% of the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months group average height.

Davis-Besse 3.1.6-1 Amendment 279

Position Indicator Channels 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Position Indicator Channels LCO 3.1.7 The absolute position indicator channel and the relative position indicator channel for each CONTROL ROD and APSR shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS ACTIONS NOTE ------------------------------------- - --------------------

Separate Condition entry is allowed for each inoperable position indicator channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. The relative position A.1 Determine the absolute 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months indicator channel position indicator channel inoperable for one or for the rod(s) is AND more rods. OPERABLE.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter B. The absolute position B.1.1 Determine position of the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months indicator channel rods with inoperable inoperable for one or absolute position indicator more rods. by actuating the affected rod's zone position reference indicators.

AND Davis-Besse 3.1.7-1 Amendment 279

Position Indicator Channels 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.1.2 Determine rods with 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable position indicators are maintained at AND the zone reference indicator position and within the Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months limits specified in thereafter LCO 3.1.5, "Safety Rod Insertion Limit," LCO 3.2.1, "Regulating Rod Insertion Limits," or LCO 3.2.2, "AXIAL POWER SHAPING ROD (APSR) Insertion Limits," as applicable.

OR B.2.1 Place the control groups 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with nonindicating rods under manual control.

AND B.2.2 Determine the position of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the nonindicating rods indirectly with fixed incore AND instrumentation.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND

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

Not applicable during first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after motion of nonindicating rods, which exceeds 11%

in one direction since the last determination of the rod's position Davis-Besse 3.1.7-2 Amendment 279

Position Indicator Channels 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Declare the rod(s) Immediately associated Completion inoperable.

Time of Condition A or B not met.

OR The absolute position indicator channel and the relative position indicator channel inoperable for one or more rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify the absolute position indicator channels and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months the relative position indicator channels agree within the limit specified in the COLR.

Davis-Besse 3.1.7-3 Amendment 279

PHYSICS TESTS Exceptions - MODE 1 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions - MODE 1 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of:

LCO 3.1.4, "CONTROL ROD Group Alignment Limits;"

LCO 3.1.5, "Safety Rod Insertion Limits;"

LCO 3.1.6, "AXIAL POWER SHAPING ROD (APSR) Alignment Limits;"

LCO 3.2.1, "Regulating Rod Insertion Limits," for the restricted operation region only; LCO 3.2.2, "AXIAL POWER SHAPING ROD (APSR) Insertion Limits;"

LCO 3.2.3, "AXIAL POWER IMBALANCE Operating Limits;" and LCO 3.2.4, "QUADRANT POWER TILT (QPT)"

may be suspended, provided:

a. THERMAL POWER is maintained *85% RTP;

b. High Flux trip setpoint is _<10% RTP higher than the THERMAL POWER at which the test is performed, with a maximum setting of 90% RTP;

'1I, U Ir C. ------------------------------------------------ I ,Jt" Ir-....- ..-

Only required when THERMAL POWER is > 20% RTP.

F0 and F2H are maintained within the limits specified in the COLR; and

d. SDM is within the limits specified in the COLR.

APPLICABILITY: MODE I during PHYSICS TESTS.

Davis-Besse 3.1.8-1 Amendment 279

PHYSICS TESTS Exceptions - MODE 1 3.1.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

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

B. THERMAL POWER B.1 Suspend PHYSICS TESTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

> 85% RTP. exceptions.

OR High Flux trip setpoint

> 10% higher than PHYSICS TESTS power level.

OR High Flux trip setpoint

> 90% RTP.

OR

- ---- NOTE-Only required when THERMAL POWER is

> 20% RTP.

FQ or FNH not within limits.

Davis-Besse 3.1.8-2 Amendment 279

PHYSICS TESTS Exceptions - MODE I 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Verify THERMAL POWER is *85% RTP. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.1.8.2 ---------- NOTE--- ------

Only required to be met when THERMAL POWER is

> 20% RTP.

Perform SR 3.2.5.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months SR 3.1.8.3 Verify High Flux trip setpoint is < 10% RTP higher 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months than the THERMAL POWER at which the test is performed, with a maximum setting of 90% RTP.

SR 3.1.8.4 Verify SDM is within the limits specified in the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months COLR.

Davis-Besse 3.1.8-3 Amendment 279

PHYSICS TESTS Exceptions - MODE 2 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.9 During performance of PHYSICS TESTS, the requirements of:

LCO 3.1.3, "Moderator Temperature Coefficient (MTC);"

LCO 3.1.4, "CONTROL ROD Group Alignment Limits;"

LCO 3.1.5, "Safety Rod Insertion Limits;"

LCO 3.1.6, "AXIAL POWER SHAPING ROD (APSR) Alignment Limits;"

LCO 3.2.1, "Regulating Rod Insertion Limits," for the sequence and overlap limits, and the insertion limits for the restricted operation region only; LCO 3.2.2, "AXIAL POWER SHAPING ROD (APSR) Insertion Limits;"

and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspended provided that:

a. THERMAL POWER is *5% RTP;

b. Reactor trip setpoints on the OPERABLE High Flux channels are set to < 25% RTP;

c. Nuclear instrumentation high startup rate control rod withdrawal inhibit is OPERABLE;

d. SDM is within the limits specified in the COLR; and

e. RCS lowest loop average temperature is > 520 0 F.

APPLICABILITY: During PHYSICS TESTS initiated in MODE 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. THERMAL POWER not A.1 Open control rod drive trip Immediately within limit, breakers.

Davis-Besse 3.1.9-1 Amendment 279

PHYSICS TESTS Exceptions - MODE 2 3.1.9 ACTIONS (continued)

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

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

C. RCS lowest loop C.1 Suspend PHYSICS TESTS 30 minutes average temperature not exceptions.

within limit.

D. High Flux trip setpoint is D.1 Suspend PHYSICS TESTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limit, exceptions.

OR Nuclear instrumentation high startup rate control rod withdrawal inhibit inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Perform a CHANNEL FUNCTIONAL TEST on each Once within nuclear instrumentation high startup rate control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to withdrawal inhibit and High Flux channel. initiating PHYSICS TESTS SR 3.1.9.2 Verify the RCS lowest loop average temperature is 30 minutes

> 520 0F.

SR 3.1.9.3 Verify THERMAL POWER is *5% RTP. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Davis-Besse 3.1.9-2 Amendment 279

PHYSICS TESTS Exceptions - MODE 2 3.1.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.9.4 Verify SDM is within the limits specified in the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months COLR.

Davis-Besse 3.1.9-3 Amendment 279

Regulating Rod Insertion Limits 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Regulating Rod Insertion Limits LCO 3.2.1 Regulating rod groups shall be within the physical insertion, ýequence, and overlap limits specified in the COLR.

ILJ r--------------------------------------------

Not required for any regulating rod repositioned to perform SR 3.1.4.2.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Regulating rod groups A.1 ---------- NOTE-------

inserted in restricted Only required when operation region. THERMAL POWER is

> 20% RTP.

Perform SR 3.2.5.1. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.2 Restore regulating rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from groups to within limits, discovery of failure to meet the LCO B. Required Action and B.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER to less than or Time of Condition A not equal to THERMAL met. POWER allowed by regulating rod group insertion limits.

Davis-Besse 3.2.1-1 Amendment 279

Regulating Rod Insertion Limits 3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Regulating rod groups C.1 NOTE sequence or overlap Only required when limits not met. THERMAL POWER is

> 20% RTP.

Perform SR 3.2.5.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND C.2 Restore regulating rod 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months groups to within limits.

D. Regulating rod groups D.1 Initiate boration to restore 15 minutes inserted in unacceptable SDM to within the limit.

operation region.

AND D.2.1 Restore regulating rod 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months groups to within restricted operation region.

OR D.2.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to less than or equal to the THERMAL POWER allowed by the restricted operation region of the regulating rod group insertion limits.

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

Davis-Besse 3.2.1-2 Amendment 279

Regulating Rod Insertion Limits 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify regulating rod groups are within the sequence 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and overlap limits as specified in the COLR.

SR 3.2.1.2 Verify regulating rod groups meet the insertion limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as specified in the COLR.

SR 3.2.1.3 Verify SDM is within the limit specified in the COLR. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving criticality Davis-Besse 3.2.1-3 Amendment 279

APSR Insertion Limits 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 AXIAL POWER SHAPING ROD (APSR) Insertion Limits LCO 3.2.2 APSRs shall be positioned within the limits specified in the COLR.

APPLICABILITY: MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. APSRs not within limits. A.1 ----------- NOTE-Only required when THERMAL POWER is

> 20% RTP.

Perform SR 3.2.5.1. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.2 Restore APSRs to within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limits.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify APSRs are within acceptable limits specified 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in the COLR.

Davis-Besse .3.2.2-1 Amendment 279

AXIAL POWER IMBALANCE Operating Limits 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL POWER IMBALANCE Operating Limits LCO 3.2.3 AXIAL POWER IMBALANCE shall be maintained within the limits specified in the COLR.

APPLICABILITY: MODE I with THERMAL POWER > 40% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AXIAL POWER A.1 Perform SR 3.2.5.1. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months IMBALANCE not within limits. AND A.2 Reduce AXIAL POWER 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months IMBALANCE within limits.

B. Required Action and B.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER to < 40% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AXIAL POWER IMBALANCE is within limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as specified in the COLR.

Davis-Besse 3.2.3-1 Amendment 279

QPT 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT (QPT)

LCO 3.2.4 QPT shall be maintained less than or equal to the steady state limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPT greater than the A.1.1 Perform SR 3.2.5.1. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months steady state limit and less than or equal to the OR transient limit.

A.1.2.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER Ž 2% RTP from the ALLOWABLE OR THERMAL POWER for each 1% of QPT greater 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after last than the steady state limit, performance of SR 3.2.5.1 AND A.1.2.2 Reduce High Flux trip 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months setpoint and Flux-AFlux-Flow trip setpoint _>2% RTP for each 1% of QPT greater than the steady state limit.

AND A.2 Restore QPT to less than or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from equal to the steady state discovery of failure to limit, meet the LCO Davis-Besse 3.2.4-1 Amendment 279

QPT 3.2.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. QPT greater than the B.1 Reduce THERMAL 30 minutes transient limit and less POWER >_2% RTP from than or equal to the ALLOWABLE THERMAL maximum limit due to POWER for each 1% of misalignment of a QPT greater than the CONTROL ROD or an steady state limit.

APSR.

AND B.2 Restore QPT to less than or 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months equal to the transient limit.

C. Required Action and C.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER to < 60% of the Time of Condition A or B ALLOWABLE THERMAL not met. POWER.

OR AND QPT greater than the C.2 Reduce High Flux trip 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months transient limit and less setpoint to < 65.5% of the than or equal to the ALLOWABLE THERMAL maximum limit due to POWER.

causes other than the misalignment of either CONTROL ROD or APSR.

D. Required Action and D.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER to < 20% RTP.

Time for Condition C not met.

OR QPT greater than the maximum limit.

Davis-Besse 3.2.4-2 Amendment 279

QPT 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 Verify QPT is within limits as specified in the COLR. 7 days AND

NO TE --......

Only required to be performed if both Condition C was entered and THERMAL POWER is _> 60%

of ALLOWABLE THERMAL POWER When QPT has been restored to less than or equal to the steady state limit, once every hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or until verified acceptable at

>_95% RTP Davis-Besse 3.2.4-3 Amendment 279

Power Peaking Factors 3.2.5 3.2 POWER DISTRIBUTION LIMITS 3.2.5 Power Peaking Factors LCO 3.2.5 FQ and FNH shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. FQ not within limit. A.1 Reduce THERMAL 15 minutes POWER _Ž1% RTP for each 1 % that FQ exceeds limit.

AND A.2 Reduce High Flux trip 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months setpoint and Flux-AFlux-Flow trip setpoint Ž_1% RTP for each I % that FQ exceeds limit.

AND A.3 Restore FQ to within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. FAN not within limit. B.1 Reduce THERMAL 15 minutes POWER > RH(%) RTP (specified in the COLR) for each 1% that FAH exceeds.

limit.

AND Davis-Besse 3.2.5-1 Amendment 279

Power Peaking Factors 3.2.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Reduce High Flux trip 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months setpoint and Flux-AFlux-Flow trip setpoint > RH(%) RTP (specified in the COLR) for each 1% that FAH exceeds limit.

AND.

B.3 Restore F2H 'to within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. Required Action and C.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER < 20% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.5.1 --------------------- NOTE----- -------

Only required to be performed when specified in LCO 3.1.8, "PHYSICS TESTS Exceptions -

MODE 1," or when complying with Required Actions of LCO 3.1.4, "CONTROL ROD Group Alignment Limits," LCO 3.2.1, "Regulating Rod Insertion Limits," LCO 3.2.2, "AXIAL POWER SHAPING ROD (APSR) Insertion Limits," LCO 3.2.3, "AXIAL POWER IMBALANCE Operating Limits," or LCO 3.2.4, "QUADRANT POWER TILT (QPT)."

Verify FQ and FAH are within limits by using the As specified by Incore Detector System to obtain a power the applicable distribution map. LCO(s)

Davis-Besse 3.2.5-2 Amendment 279

RPS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1 Four channels of RPS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE:

AND The ultrasonic flow meter (UFM) instrumentation shall be used to perform SR 3.3.1.2 when THERMAL POWER is > 50% RTP.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable. A.1 Place channel in bypass or 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months trip.

B. Two channels B.1 Place one channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

AND B.2 Place second channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months bypass.

C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Table 3.3.1-1 Time of Condition A or B for the Function.

not met.

OR Three or more channels inoperable.

Davis-Besse 3.3.1-1 Amendment 279

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in AND Table 3.3.1-1.

D.2 ----------- NOTE --------------

Only applicable to Functions 1.a, 3, and 6.

Open all CONTROL ROD 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months drive (CRD) trip breakers.

E. As required by Required E.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in Table 3.3.1-1.

F. UFM instrumentation not F.1 ----------- NOTE--------

used to perform Only required if four reactor SR 3.3.1.2 when coolant pumps (RCPs) are THERMAL POWER is operating.

> 50% RTP.

Initiate action to reduce Immediately THERMAL POWER to

< 98.4% RTP.

AND F.2 ----------- NOTE-------

Only required if three RCPs are operating.

Initiate action to reduce Immediately THERMAL POWER to

< 73.8% RTP.

AND Davis-Besse 3.3.1-2 Amendment 279

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. (continued) F.3 ------------ NOTE ---.......--

Only required iffour RCPs are operating.

Reset High Flux - High 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months Setpoint Allowable Value to

< 103.3% RTP SURVEILLANCE REQUIREMENTS

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

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

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

1. Adjust power range channel output if the calorimetric heat balance calculation results exceed power range channel output by

> 2% RTP.

2. Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is _>15% RTP.

Compare result of calorimetric heat balance 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months calculation to power range channel output.

Davis-Besse 3.3.1-3 Amendment 279

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.3 ------------- NOTES -----------.------------.

1. Neutron detectors are excluded from CHANNEL CALIBRATION.

2. For Function 8, flow rate measurement sensors may be excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 23 days on a STAGGERED TEST BASIS SR 3.3.1.4 ----------------- NOTES --------

1. Adjust the power range channel imbalance output if the absolute value of the offset error is

Ž2.5%.

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

Compare results of out of core measured AXIAL 31 days POWER IMBALANCE (APIo) to incore measured AXIAL POWER IMBALANCE (API 1) as follows:

(RTP/TP)(API0 - API1 ) = offset error.

SR 3.3.1.5 Perform CHANNEL FUNCTIONAL TEST. 46 days on a STAGGERED TEST BASIS SR 3.3.1.6 Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.7 - NOTE -.-..............---------

For Function 8, flow rate measurement sensors are only required to be calibrated.

Perform CHANNEL CALIBRATION. 24 months Davis-Besse 3.3.1-4 Amendment 279

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

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

Neutron detectors are excluded from RPS RESPONSE TIME testing.

Verify that RPS RESPONSE TIME is within limits. 24 months on a STAGGERED TEST BASIS Davis-Besse 3.3.1-5 Amendment 279

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

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS ACTION C.1 REQUIREMENTS VALUE

1. High Flux -

a. High Setpoint 1 ,2(a), 3 (b) D SR 3.3.1.1 < 104.9% RTP(e) with four SR 3.3.1.2 pumps operating, and SR 3.3.1. 3 (c)(d) <_80.6% RTP when reset SR 3.3.1.8 for three pumps operating per LCO 3.4.4, "RCS Loops - MODES 1 and 2"

b. Low Setpoint 2 (O,3 (f),4 (r, E SR 3.3.1.1 *5% RTP 5 (f) SR 3.3.1.3

2. RC High Temperature 1,2 D SR 3.3.1.1 _ 6181F SR 3.3.1.5 SR 3.3.1.7

-3. RC High Pressure 1 ,2 (a),3 (b) D SR 3.3.1.1 < 2355 psig SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.8

4. RC Low Pressure 1,2(a) D SR 3.3.1.1 > 1900 psig SR 3.3.1.5 SR 3.3:1.7 SR 3.3.1.8 (a) When not in shutdown bypass operation.

(b) With any CRD trip breaker in the closed position, the CRD System capable of rod withdrawal, and not in shutdown bypass operation.

(c) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint, or a value that is more conservative than the Limiting Trip Setpoint; otherwise, the channel shall be declared inoperable. The Limiting Trip Setpoint and the methodology used to determine the Limiting Trip Setpoint, the predefined as-found acceptance criteria band and the as-left setpoint tolerance band are specified in the Technical Requirements Manual.

(e) < 103.3% RTP when reset per ACTION F due to UFM instrumentation not being used to perform SR 3.3.1.2 when THERMAL POWER is > 50% RTP.

(f) During shutdown bypass operation with any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal.

Davis-Besse 3.3.1-6 Amendment, 279

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

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS ACTION C.A REQUIREMENTS VALUE

5. RC Pressure - Temperature 1,2(a) D SR 3.3.1.1 _(16.25. Tot-SR 3.3.1. 5 (c)(d) 7899.0) psig SR 3 .3.1. 7 (c)(d)

6. Containment High Pressure 1,2,3(g) D SR 3.3.1.1 <4 psig SR 3.3.1.5 SR 3.3.1.6

7. High Flux/Number of 1,2(a) D SR 3.3.1.1 < 55.1% RTP with one Reactor Coolant Pumps On SR 3.3.1.3 pump operating in each SR 3.3.1.8 loop,

< 0.0% RTP with two pumps operating in one loop and no pumps operating in the other loop,

< 0.0% RTP with one pump or no pumps operating

8. Flux - AFlux - Flow 1,2(a) D SR 3.3.1.1 Flux - AFlux - Flow SR 3.3.1.3 Allowable Value envelope SR 3.3.1.4 in COLR SR 3.3.1.7 SR 3.3.1.8

9. Shutdown Bypass High 2 (0,3 () 4 (o, E SR 3.3.1.1 < 1820 psig Pressure 5(f; SR 3.3.1.5 SR 3.3.1.7 (a) When not in shutdown bypass operation.

(c) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint, or a value that is more conservative than the Limiting Trip Setpoint; otherwise, the channel shall be declared inoperable. The Limiting Trip Setpoint and the methodology used to determine the Limiting Trip Setpoint, the predefined as-found acceptance criteria band and the as-left setpoint tolerance band are specified in the Technical Requirements Manual.

(f) During shutdown bypass operation with any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal.

(g) With any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal.

Davis-Besse 3.3.1-7 Amendment 279

RPS Manual Reactor Trip 3.3.2 3.3 INSTRUMENTATION 3.3.2 Reactor Protection System (RPS) Manual Reactor Trip LCO 3.3.2 Two RPS Manual Reactor Trip channels shall be OPERABLE.

APPLICABILITY: MODES i and 2, MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in the closed position and the CRD System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Manual Reactor A.1 Restore Manual Reactor 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Trip channel inoperable. Trip channel to OPERABLE status.

B. Two Manual Reactor B.1 Restore one Manual 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Trip channels Reactor Trip channel to inoperable. OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3. C.2 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. Required Action and D.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B not met in MODE 4 or 5.

Davis-Besse 3.3.2-1 Amendment 279

RPS Manual Reactor Trip 3.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL FUNCTIONAL TEST. Once prior to each reactor startup if not performed within the previous 7 days Davis-Besse 3.3.2-2 Amendment 279

RPS - RTM 3.3.3 3.3 INSTRUMENTATION 3.3.3 Reactor Protection System (RPS) - Reactor Trip Module (RTM)

LCO 3.3.3 Four RTMs shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in the closed position and the CRD System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RTM inoperable. A.1.1 Trip the associated CRD 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months trip breaker.

OR A. 1.2 Remove power from the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated CRD trip breaker.

AND A.2 Physically remove the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable RTM.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met in MODE 1, 2, or 3.

B.2.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR OR Two or more RTMs inoperable in MODE 1, B.2.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 2, or 3. CRD trip breakers.

Davis-Besse 3.3.3-1 Amendment 279

RPS - RTM 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not OR met in MODE 4 or 5.

C.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR CRD trip breakers.

Two or more RTMs inoperable in MODE 4 or 5.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL FUNCTIONAL TEST. 23 days on a STAGGERED TEST BASIS Davis-Besse 3.3.3-2 Amendment 279

CRD Trip Devices 3.3.4 3.3 INSTRUMENTATION 3.3.4 CONTROL ROD Drive (CRD) Trip Devices LCO 3.3.4 The following CRD trip devices shall be OPERABLE:

a. Four CRD trip breakers; and

b. Two silicon controlled rectifier (SCR) relay trip channels.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5 when any CRD trip breaker is in the closed position and the CRD System is capable of rod withdrawal.

ACTIONS

N I .------------------

Separate Condition entry is allowed for each CRD trip device.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more CRD trip A.1 Trip the associated CRD 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months breakers undervoltage trip breaker(s).

or shunt trip Functions inoperable. OR A.2 Remove power from the 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months associated CRD trip breaker(s).

B. One or more CRD trip B.1 Trip the associated CRD 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months breakers inoperable for trip breaker(s).

reasons other than those in Condition A. OR B.2 Remove power from the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated CRD trip breaker(s).

Davis-Besse 3.3.4-1 Amendment 279

CRD Trip Devices 3.3.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3. C.2.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR C.2.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months CRD trip breakers.

D. Required Action and D.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B OR'ý not met in MODE 4 or 5.

D.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months CRD trip breakers.

E.-------- w....NOTE --------- E.1 Restore the channel(s) to Prior to entering, Required Action E.1 OPERABLE status. MODE 4, when in shall be completed MODE 5 for whenever this Condition > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is entered.

One or both SCR relay trip channels inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL FUNCTIONAL TEST on CRD 23 days on a trip breakers. STAGGERED TEST BASIS Davis-Besse 3.3.4-2 Amendment 279

CRD Trip Devices 3.3.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2 Perform CHANNEL FUNCTIONAL TEST on SCR 24 months relay trip channels.

Dav~is-Besse 3.3.4-3 Amendment 279

SFAS Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Safety Features Actuation System (SFAS) Instrumentation LCO 3.3.5 Four channels of SFAS instrumentation for each Parameter in Table 3.3.5-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS

NOTE Separate Condition entry is allowed for each Parameter.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Parameters A.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one channel inoperable.

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

B.2 ----- NOTE ----------...

OR Only required for Reactor Coolant System (RCS)

One or more Parameters Pressure - Low channels.

with two or more ----------

channels inoperable.

Reduce RCS pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

< 1800 psig.

AND Davis-Besse 3.3.5-1 Amendment 279

SFAS Instrumentation 3.3.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 ------- NOTE-------

Only required for RCS Pressure - Low Low channels.

Reduce RCS pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

< 660 psig.

AND B.4 ----------- NOTE-------

Only required for Containment Pressure -

High, Containment Pressure - High High, and Borated Water Storage Tank - Low Low channels.

Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.5-1 to determine which SRs apply to each SFAS instrumentation Parameter.

SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.3.5-2 Amendment 279

SFAS Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.2 ---------------- NOTE----------------

When an SFAS channel is placed in an inoperable status solely for performance of this Surveillance, entry into associated Conditions and Required Actions may be delayed for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , provided two other channels of the same SFAS instrumentation Parameter are OPERABLE.

Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.5.3 Perform CHANNEL CALIBRATION. 18 months SR 3.3.5.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.5 Verify SFAS RESPONSE TIME within limits. 24 months on a STAGGERED TEST BASIS Davis-Besse 3.3.5-3 Amendment 279

SFAS Instrumentation 3.3.5 Table 3.3.5-1 (page 1 of 1)

Safety Features Actuation System Instrumentation APPLICABLE MODES OR OTHER SURVEILLANCE ALLOWABLE PARAMETER SPECIFIED CONDITIONS REQUIREMENTS VALUE 1 Reactor Coolant System Pressure - 1, 2, 3(a) SR 3.3.5.1 > 1576.2 psig Low SR 3.3.5.2 SR 3.3.5.4 SR 3.3.5.5

2. Reactor Coolant System Pressure - 1, 2, 3 (P) SR 3.3.5.1 > 441.42 psig Low Low SR 3.3.5.2 SR 3.3.5.4 SR 3.3.5.5

3. Containment Pressure - High 1,2, 3,4 SR 3.3.5.1 < 19.38 psia SR 3.3.5.2 SR 3.3.5.3 SR 3.3.5.5

4. Containment Pressure - High High 1, 2, 3, 4 SR 3.3.5.1

41.65 psia SR 3.3.5.2 SR 3.3.5.3 SR 3.3.5.5

5. Borated Water Storage Tank 1, 2, 3,4 SR 3.3.5.1 > 101.6 and Level - Low Low SR 3.3.5.2 < 115.4 inches of SR 3.3.5.3 water (a) With Reactor Coolant System (RCS) pressure > 1800 psig.

(b) With RCS pressure >_660 psig.

Davis-Besse 3.3.5-4 Amendment 279

SFAS Manual Initiation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Safety Features Actuation System (SFAS) Manual Initiation LCO 3.3.6 Two manual initiation channels of each one of the SFAS Functions below shall be OPERABLE:

a. SFAS; and

b. Containment Spray.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when associated engineered safety features equipment is required to be OPERABLE.

ACTIONS

NOTE----

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SFAS A.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Functions with one OPERABLE status.

channel inoperable.

B., Required-Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL FUNCTIONAL TEST. 24 months Davis-Besse 3.3.6-1 Amendment 279

SFAS Automatic Actuation Logic 3.3.7 3.3 INSTRUMENTATION 3.3.7 Safety Features Actuation System (SFAS) Automatic Actuation Logic LCO 3.3.7 All the SFAS automatic actuation output logics shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when associated engineered safety features equipment is required to be OPERABLE.

ACTIONS S-------------------INjill I---- - ----------- - ------------- ---- -

I* I f'*,"l'l'--

b ------ - --- - --------

Separate Condition entry is allowed for each automatic actuation output logic.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more automatic A.1 Place associated output 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months actuation output logics logic in trip.

inoperable.

OR A.2 Place associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months component(s) in engineered safety features configuration.

OR A.3 Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months component(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform automatic actuation output logic CHANNEL 31 days on a FUNCTIONAL TEST. STAGGERED TEST BASIS Davis-Besse 3.3.7-1 Amendment 279

EDG LOPS 3.3.8 3.3 INSTRUMENTATION 3.3.8 Emergency Diesel Generator (EDG) Loss of Power Start (LOPS)

LCO 3.3.8 Two channels of Loss of Voltage Function and two channels of Degraded Voltage Function EDG LOPS instrumentation per bus shall be OPERABLE.

.I3fIU IR .1- ! -------------------------------------

All Degraded Voltage channels may be bypassed for _<1 minute when starting a reactor coolant pump or circulating water pump.

APPLICABILITY: MODES 1, 2, 3, and 4, When associated EDG is required to be OPERABLE by LCO 3.8.2, "AC Sources - Shutdown."

ACTIONS

NOTE----

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place channelin trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one channel per bus inoperable.

B. One or more Functions B.1 Restore one channel to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with two channels per OPERABLE status.

bus inoperable.

C. Required Action and C.1 Declare associated EDG Immediately associated Completion inoperable.

Time not met.

Davis-Besse 3.3.8-1 Amendment 279

EDG LOPS 3.3.8 SURVEILLANCE REQUIREMENTS

.-- ----- -N0 When EDG LOPS instrumentation is placed in an inoperable status solely for performance of a Surveillance, entry into associated Conditions and Required Actions may be delayed up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , provided the other channel monitoring the Function for the bus is OPERABLE and the two channels monitoring the Function for the other bus are OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.8.1 -------------------- NOTE---------------

The as-left instrument setting shall be returned to a setting within the tolerance band of the trip setpoint established to protect the safety limit.

Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.8.2 --------------------- NOTE---------------

The as-left instrument setting shall be returned to a setting within the tolerance band of the trip setpoint established to protect the safety limit.

Perform CHANNEL CALIBRATION with Allowable 12 months Value as follows:

a. Degraded Voltage > 3712 volts (dropout) and

_<3771 volts (pickup) with a time delay of

> 6.4 seconds and <_7.9 seconds; and

b. Loss of Voltage > 2071 volts (dropout) and

<2492 volts (pickup) with a time delay of

_0.42 seconds and _< 0.58 seconds.

Davis-Besse 3.3.8-2 Amendment 279

Source Range Neutron Flux 3.3.9 3.3 INSTRUMENTATION 3.3.9 Source Range Neutron Flux LCO 3.3.9 Two source range neutron flux channels shall be OPERABLE.

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

High voltage to detector may be de-energized with neutron flux

> 1E-10 amp on intermediate range channels.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One source range A.1 Restore channel to Prior to increasing neutron flux channel OPERABLE status. neutron flux inoperable with neutron flux < 1E-10 amp on the intermediate range neutron flux channels.

B. Two source range B.1 ---------- NOTE ----------

neutron flux channels Plant temperature changes inoperable with neutron are allowed provided the flux 11E-10 amp on the temperature change is intermediate range accounted for in the neutron flux channels. calculated SDM.

Suspend operations Immediately involving positive reactivity changes.

AND B.2 Initiate action to insert all Immediately CONTROL RODS.

AND Davis-Besse 3.3.9-1 Amendment 279

Source Range Neutron Flux 3.3.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B: (continued) B.3 Open CONTROL ROD 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months drive trip breakers.

AND B.4 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits specified in the COLR. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter C. One or more source C.1 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months range neutron flux affected channel(s) to channels inoperable with OPERABLE status.

neutron flux

> 1E-10 amp on the intermediate range neutron flux channels.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.9.2 ----------------------- NOTE-------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Davis-Besse 3.3.9-2 Amendment 279

Intermediate Range Neutron Flux 3.3.10 3.3 INSTRUMENTATION 3.3.10 Intermediate Range Neutron Flux LCO 3.3.10 Two intermediate range neutron flux channels shall be OPERABLE.

APPLICABILITY: MODE 2, MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in the closed position and the CRD System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable. A.1 Reduce neutron flux to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

< E-10 amp.

B. Required Action and' B.1 ------------ NOTE-------

associated Completion Plant temperature changes Time of Condition A not are allowed provided the met. temperature change is accounted for in the OR calculated SDM.

Two channels inoperable. Suspend operations Immediately involving positive reactivity changes.

AND B.2 Open CRD trip breakers. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.10.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.3.10-1 Amendment 279

Intermediate Range Neutron Flux 3.3.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.10.2 ----- 7.....--------.------NOTE --.---.----.------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Davis-Besse 3.3.10-2 Amendment 279

SFRCS Instrumentation 3.3.11 3.3 INSTRUMENTATION 3.3.11 Steam and Feedwater Rupture Control System (SFRCS) Instrumentation LCO 3.3.11 The SFRCS instrumentation channels for each Function in Table 3.3.11-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.11-1.

ACTIONS

----- NO r ------------ - -- - --- - ------------------ - ------ - -------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one channel inoperable.

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

B.2 ----- NOTE-OR Only required for Function 1.

One or more Functions ----------

with two or more channels inoperable. Reduce main steam line 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months pressure < 750 psig.

AND B.3 ---.----.----- NOTE ---

Only required for Functions 2, 3, and 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.3.11-1 Amendment 279

SFRCS Instrumentation 3.3.11 SURVEILLANCE REQUIREMENTS Refer to Table 3.3.11-1 to determine which SRs shall be performed for each SFRCS Function.

SURVEILLANCE FREQUENCY SR 3.3.11.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.11.2 --.. ...........------------ NOTE-------- - - - -

When a channel is placed in an inoperable status solely for performance of the CHANNEL FUNCTIONAL TEST, entry into the associated Conditions and Required Actions may be delayed for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months provided the channels providing input to the other actuation channel are OPERABLE.

Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.11.3 Perform CHANNEL CALIBRATION. 18 months SR 3.3.11.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.11.5 ------------- NOTE---- ----------------........

"N" equals 2 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.

Verify SFRCS RESPONSE TIME is within limits. 24 months on a STAGGERED TEST BASIS Davis-Besse 3.3.11-2 Amendment 279 nt

SFRCS Instrumentation 3.3.11 Table 3.3.11-1 (page 1 of 1)

Steam and Feedwater Rupture Control System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1. Main Steam Line 1 ,2 ,3 (a) 4 per steam line SR 3.3.11.1 _600.2 psig Pressure - Low SR 3 ;3.1 1 .2 (b)(c)

SR 3 .3. 1 1 .3b)(c)

SR 3.3.11.5

2. Feedwater/Steam 1,2,3 4 per feedwater SR 3.3.11.1 *176.8 psid Generator Differential line SR 3 .3. 1 1 .2(b)(c)

Pressure - High SR 3.3.11.3(b)1c)

SR 3.3.11.5

3. Steam Generator Level - 1,2,3 4 per steam SR 3.3.11.1 >17.3 inches Low generator (SG) SR 3 .3. 11 .2(b)(c)

SR 3 .3. 1 1 .4 (b)(c)

SR 3.3.11.5

4. LossofRCPs 1,2,3 4 SR 3.3.11.1 <1384.6amps SR 3.3.11.2 and SR 3.3.11.3 >106.5 amps SR 3.3.11.5 (a) With main steam line pressure _ 750 psig during a shutdown and with main steam line pressure > 800 psig during a heatup.

(b) Ifthe as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint, or a value that is more conservative than the Limiting Trip Setpoint; otherwise, the channel shall be declared inoperable. The Limiting Trip Setpoint and the methodology used to determine the Limiting Trip Setpoint, the predefined as-found acceptance criteria band and the as-left setpoint tolerance band are specified in the Technical Requirements Manual.

Davis-Besse 3.3.11-3 Amendment 279

SFRCS Manual Initiation 3.3.12 3.3 INSTRUMENTATION 3.3.12 Steam and Feedwater Rupture Control System (SFRCS) Manual Initiation LCO 3.3.12 One manual initiation push button for each of the following SFRCS Functions shall be OPERABLE:

a. Auxiliary Feedwater Pump Turbine 1 Initiation;

b. Auxiliary Feedwater Pump Turbine 2 Initiation;

c. Auxiliary Feedwater Pump Turbine 1 Initiation and Steam Generator 1 Isolation; and

d. Auxiliary Feedwater Pump Turbine 2 Initiation and Steam Generator 2 Isolation.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE----

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SFRCS A.1 Restore SFRCS Function to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Functions inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.3.12-1 Amendment 279

SFRCS Manual Initiation 3.3.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.12.1 Perform CHANNEL FUNCTIONAL TEST. 24 months Davis-Besse 3.3.12-2 Amendment 279

SFRCS Actuation 3.3.13 3.3 INSTRUMENTATION 3.3.13 Steam and Feedwater Rupture Control System (SFRCS) Actuation LCO 3.3.13 Channels 1 and 2 of each Logic Function shown below shall be OPERABLE:

a. Auxiliary Feedwater Initiation;

b. Auxiliary Feedwater and Main Steam Valve Control;

c. Main Steam Line Isolation; and

d. Main Feedwater Isolation.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS Separate Condition-entry i s allowe for each-NOTEgi

-- Functi Separate Condition entry is allowed for each Logic Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channel 1 A.1 Restore inoperable channel 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Logic Functions to OPERABLE status.

inoperable with all channel 2 Logic Functions OPERABLE.

OR One or more channel 2 Logic Functions inoperable with all channel I Logic Functions OPERABLE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.3.13-1 Amendment 279

SFRCS Actuation 3.3.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.13.1 ---------------------- NOTE ---------

When a channel is placed in an inoperable status solely for performance of the CHANNEL FUNCTIONAL TEST, entry into the associated Conditions and Required Actions may be delayed for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months provided the other actuation channel is OPERABLE.

Perform CHANNEL FUNCTIONAL TEST. 31 days Davis-Besse 3.3.13-2 Amendment 279

Fuel Handling Exhaust - High Radiation 3.3.14 3.3 INSTRUMENTATION 3.3.14 Fuel Handling Exhaust - High Radiation LCO 3.3.14 Two channels of Fuel Handling Exhaust - High Radiation shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel pool building.

ACTIONS

II*ll OTE-LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Declare the associated Immediately inoperable. Spent Fuel Pool Area Emergency Ventilation System train inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.14.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.14.2 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.14.3 Perform CHANNEL CALIBRATION with a trip 18 months setpoint of < 2 times Background.

Davis-Besse 3.3.14-1 Amendment 279

Station Vent Normal Range Radiation Monitoring 3.3.15 3.3 INSTRUMENTATION 3.3.15 Station Vent Normal Range Radiation Monitoring LCO 3.3.15 Two channels of station vent normal range radiation monitoring instrumentation shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable. Ak- Isolate the Control Room 7 days Normal Ventilation System.

AND A.2 -------- NOTE-Only applicable in MODES 1, 2, 3, and 4.

Place one OPERABLE 7 days Control Room Emergency Ventilation System (CREVS) train in operation.

B. Two channels B.1 Isolate the Control Room 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. Normal Ventilation System.

AND B.2 ---------- NOTE-------

Only applicable in MODES 1, 2, 3, and 4.

Place one OPERABLE 1hour CREVS train in operation.

Davis-Besse 3.3.15-1 Amendment 279

Station Vent Normal Range Radiation Monitoring 3.3.15 ACTIONS (continued)

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

Time of Condition A or B not met during movement of irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.15.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.15.2 - ------------------ NOTE ---------------

When a channel is placed in an inoperable status solely for performance of this Surveillance, entry into associated Conditions and Required Actions may be delayed for up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months provided the other channel is OPERABLE.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.15.3 Perform CHANNEL CALIBRATION. 18 months Davis-Besse 3.3.15-2 Amendment 279

ARTS Instrumentation 3.3.16 3.3 INSTRUMENTATION 3.3.16 Anticipatory Reactor Trip System (ARTS) Instrumentation LCO 3.3.16 The ARTS instrumentation channels for each Function in Table 3.3.16-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.16-1.

ACTIONS

NOTE----.

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 ----------- NOTE-----------

with one required Only applicable for channel inoperable. Function 3.

Trip the control rod drive 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months trip breaker associated with the inoperable channel.

AND A.2 ----------- NOTE --------------

Only applicable for Functions 1 and 2.

Restore required channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

Davis-Besse 3.3.16-1 Amendment 279

ARTS Instrumentation 3.3.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 ------------. NOTE -----

associated Completion Only applicable for Time not met. Function 1.

Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months POWER to < 45% RTP.

AND B.2 ----------- NOTE --------------

Only applicable for Functions 2 and 3.

Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.16-1 to determine which SRs apply to each ARTS instrumentation Function.

SURVEILLANCE FREQUENCY SR 3.3.16.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.16.2 Perform CHANNEL FUNCTIONAL TEST. 23 days on a STAGGERED TEST BASIS SR 3.3.16.3 Perform CHANNEL CALIBRATION. 46 days on a STAGGERED TEST BASIS Davis-Besse 3.3.16-2 Amendment 279

ARTS Instrumentation 3.3.16 Table 3.3.16-1 (page 1 of 1)

Anticipatory Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS

1. Turbine Trip > 45% RTP 3 SR 3.3.16.1 SR 3.3.16.3

2. Trip of Both Main Feed Pump Turbines 1 3 SR 3.3.16.1 SR 3.3.16.3

3. Output Logic 1 4 SR 3.3.16.2 Davis-Besse 3.3.16-3 Amendment 279

PAM Instrumentation 3.3.17 3.3 INSTRUMENTATION 3.3.17 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.17 The PAM instrumentation for each Function in Table 3.3.17-1 shall -be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

- - - - - - - - - - -- - - - - - - - - - - - - - - - - - ~ rv~rr-ki I I -------------------------------------------------------

Separate Condition entry is allowed for each Function.

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

channel inoperable.

B. Required Action and B.1 ---------- NOTE-------

associated Completion Only applicable to Time of Condition A not Functions other than met. Functions 13, 14, and 15.

Initiate action in accordance Immediately with Specification 5.6.5.

OR B.2 ---------- NOTE-------

Only applicable to Functions 13, 14, and 15.

Enter the Condition Immediately referenced in Table 3.3.17-1 for the channel.

Davis-Besse 3.3.17-1 Amendment 279

PAM Instrumentation 3.3.17 ACTIONS (continued)

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

channels inoperable.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C not Table 3.3.17-1 for the met. channel.

E. As required by Required E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action B.2 or D.1 and referenced in AND Table 3.3.17-1.,

E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. As required by Required F.1 Initiate action in accordance Immediately Action D.1 and with Specification 5.6.5.

referenced in Table 3.3.17-1 SURVEILLANCE REQUIREMENTS NOTE -.-.---.-...-.-.-.-.-.------......----------------------

These SRs apply to each PAM instrumentation Function in Table 3.3.17-1 except where identified in the SR.

SURVEILLANCE FREQUENCY SR 3.3.17.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

Davis-Besse 3.3.17-2 Amendment 279

PAM Instrumentation 3.3.17 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.17.2 --------- NOTE-- ---------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for Functions 1, 18 months 11, 12, 14,15, 16, and 17.

SR 3.3.17.3 Perform CHANNEL CALIBRATION for Functions 2, 24 months 3,4, 5, 6,7, 8, 9, 10, and 13.

Davis-Besse 3.3.17-3 Amendment 279

PAM Instrumentation 3.3.17 Table 3.3.17-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION B.2 or D.1

1. Wide Range Neutron Flux 2 E

2. Reactor Coolant Loop Outlet Temperature 2 per loop E

3. Reactor Coolant Loop Pressure 2 per loop E

4. Reactor Coolant Hot Leg Level (Wide Range) 2 E

5. Containment Water Level (Wide Range) 2 E

6. Containment Pressure (Wide Range) 2 E

7. Penetration Flow Path Containmentlsolation 2 per penetration flow path(a)(b) E Valve Position

8. Containment High Range Radiation 2 F

9. Pressurizer Level 2 E

10. Steam Generator Startup Range Level 2 per SG E

11. Incore Thermocouples 2 per core quadrant E

12. Auxiliary Feedwater Flow Rate 2 per SG E

13. Steam Generator Outlet Steam Pressure 1 per SG E

14. High Pressure Injection Flow 1 per injection line E

15. Low Pressure Injection (Decay Heat Removal) 1 per train E Flow

16. Borated Water Storage Tank Level 2 E

17. Neutron Flux (Source Range) 2 E (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

Davis-Besse 3.3.17-4 Amendment 279

Remote Shutdown System 3.3.18 3.3 INSTRUMENTATION 3.3.18 Remote Shutdown System LCO 3.3.18 The remote shutdown monitoring instrumentation Functions shall be OPERABLE.

AND The control circuit and transfer switch Functions required for a serious control room or cable spreading room fire shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOT rý -------------------- ---- - - ----------------- -

Separate Condition entry is allowed for each Func 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. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met for remote shutdown monitoring B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months instrumentation Functions.

C. Required Action and C.1 Initiate action in accordance Immediately associated Completion with Specification 5.6.7.

Time of Condition A not met for control circuit and transfer switch Functions.

Davis-Besse 3.3.18-1 Amendment 279

Remote Shutdown System 3.3.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.18.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.18.2- ------------------ NOTE --------

Reactor trip breaker indication and control rod position switches are excluded from this Surveillance.

Perform CHANNEL CALIBRATION for each 24 months required instrumentation channel.

SR 3.3.18.3 Verify each control circuit and transfer switch 24 months required for a serious control room or cable spreading room fire is capable of performing the intended function.

Davis-Besse 3.3.18-2 Amendment 279

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits LCO 3.4.1 RCS DNB parameters for loop pressure, hot leg temperature, and RCS total flow rate shall be within the limits specified below:

a. With four reactor coolant pumps (RCPs) operating:

RCS loop pressure shall be > 2064.8 psig, RCS hot leg temperature shall be _<610°F, and RCS total flow rate shall be _> 389,500 gpm; and

b. With three RCPs operating:

RCS loop pressure shall be >_2060.8 psig, RCS hot leg temperature shall be < 610 0 F, and RCS total flow rate shall be > 290,957 gpm.

APPLICABILITY: MODE 1.

RCS loop pressure limit does not apply during:

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

b. THERMAL POWER step > 10% RTP.

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

limits.

B. Required Action and B.1 Be in MODE 2. 6*hours associated Completion Time not met.

Davis-Besse 3.4.1-1 Amendment 279

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR' 3.4.1.1 ------------------ NOTE---------------

With three RCPs operating, the limits are applied to the loop with two RCPs in operation.

Verify RCS loop pressure _Ž 2064.8 psig with 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months four RCPs operating or > 2060.8 psig with three RCPs operating.

SR 3.4.1.2 ---------- NOTE -------------------.........

With three RCPs operating, the limits are applied to the loop with two RCPs in operation.

Verify RCS hot leg temperature < 610°F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.3 Verify RCS total flow > 389,500 gpm with four RCPs 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating or > 290,957 gpm with three RCPs operating.

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

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after stable thermal conditions are established at

> 70% RTP.

Verify RCS total flow rate is within limit by 18 months measurement.

Davis-Besse 3.4.1-2 Amendment 279

RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCOý 3.4.2 Each RCS loop average temperature (Tavg) shall be _ 5250 F.

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

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop > 5250 F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.4.2-1 Amendment 279

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

APPLICABILITY: At all times.

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

shall be completed whenever this Condition AND is entered.

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

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

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

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. ------- NOTE----...... C.1 Initiate action to restore Immediately Required Action C.2 parameter(s) to within limit.

shall be completed whenever this Condition AND is entered.

----- C.2 Determine RCS is' Prior to entering acceptable for continued MODE 4 Requirements of operation.

LCO not met in other than MODE 1, 2, 3, or 4.

Davis-Besse 3.4.3-1 Amendment 279

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 -------- ---------- ---- NOTE---------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS 30 minutes heatup and cooldown rates are within the limits specified in the PTLR.

Davis-Besse 3.4.3-2 Amendment 279

RCS Loops - MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops - MODES 1 and 2 LCO 3.4.4 Two RCS Loops shall be in operation, with:

a. Four reactor coolant pumps (RCPs) operating; or

b. Three RCPs operating and:

1. THERMAL POWER is < 80.6% RTP;

2. LCO 3.3.1, "Reactor Protection System (RPS) Instrumentation,"

Function 1.a (High Flux - High Setpoint), Allowable Value of Table 3.3.1-1 is reset for three RCPs operating; and

3. LCO 3.3.1, Function 8 (Flux-AFlux-Flow), Allowable Value of Table 3.3.1-1 is reset for three RCPs operating.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of A.1 Satisfy the requirements of 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months LCO 3.4.4.b.2 not met. LCO 3.4.4.b.2.

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

OR Requirements of LCO not met for reasons other than Condition A.

Davis-Besse 3.4.4-1 Amendment 279

RCS Loops - MODES 1 and 2 3.4.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify required RCS loops are in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.4.4-2 Amendment 279

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

APPLICABILITY: MODE 3.

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

B. Required Action and B.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

associated Completion Time of Condition A not met.

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

in operation.

AND C.2 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation..

Davis-Besse 3.4.5-1 Amendment 279

RCS Loops - MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify one RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify, for each required RCS loop, SG secondary 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months side water level is:

a. > 18 inches above the lower tube sheet if associated reactor coolant pump is operating; or

b. Ž 35 inches above the lower tube sheet if reactor coolant pumps are not operating.

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

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days power available to each required pump.

Davis-Besse 3.4.5-2 Amendment 279

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

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

All reactor coolant pumps (RCPs) and DHR pumps may be de-energized for _<1 hour provided:

a. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1, "SHUTDOWN MARGIN (SDM)"; and

b. Core outlet temperature is maintained at least 10OF below saturation temperature.

APPLICABILITY: MODE 4.

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

AND A.2 Only required if one DHR loop is OPERABLE.

Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Davis-Besse .3.4.6-1 Amendment 279

RCS Loops - MODE 4 3.4.6 ACTIONS (continued),

CONDITION REQUIRED ACTION COMPLETION TIME B. Two required loops B.1 Suspend operations that Immediately inoperable, would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required loop not in of LCO 3.1.1.

operation.

AND B.2 Initiate action to restore one loop to OPERABLE status and operation. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required DHR or RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.2 Verify, for each required RCS loop, SG secondary 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months side water level is:

a. > 18 inches above the lower tube sheet if associated reactor coolant pump is operating; or

b. > 35 inches above the lower tube sheet if reactor coolant pumps are not operating.

SR 3.4.6.3 ------------------- NOTE .---------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days power available to each required pump.

Davis-Besse 3.4.6-2 Amendment 279

RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops - MODE 5, Loops Filled LCO 3.4.7 Two loops consisting of any combination of RCS loops and decay heat removal (DHR) loops shall be OPERABLE and one loop shall be in operation.

,l*lJl r-.-------------------------------------------

I-JLJ The DHR pump of the loop in operation may be removed from operation for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided:

a. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1, "SHUTDOWN MARGIN (SDM)"; and

b. Core outlet temperature is maintained at least 101F below saturation temperature.

APPLICABILITY: MODE 5 with RCS loops filled.

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

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

operation.

AND B.2 Initiate action to restore one Immediately loop to OPERABLE status and operation.

Davis-Besse 3.4.7-1 sAmendment 279

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required DHR or RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify, for each required RCS loop, SG secondary 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

side water level is > 35 inches above the lower tube sheet.

SR 3.4.7.3 --------- NOTE--- -.. .--------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days power available to each required DHR pump.

Davis-Besse 3.4.7-2 Amendment 279

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two decay heat removal (DHR) loops shall be OPERABLE and one DHR loop shall be in operation.

-NOTEES-------- ------------- - --------

1. All DHR pumps may be removed from operation for _ 15 minutes when switching from one loop to another provided:

a. The maximum RCS temperature is < 1901F;

b. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1, "SHUTDOWN MARGIN (SDM);" and

c. No draining operations to further reduce the RCS water volume are permitted.

2. One DHR loop may be inoperable for < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Surveillance testing provided that the other DHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required DHR loop A.1 Initiate action to restore Immediately inoperable. DHR loop to OPERABLE status.

Davis-Besse 3.4.8-1 Amendment 279

RCS Loops MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No required DHR loop B.1 Suspend operations that Immediately OPERABLE. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required DHR loop not of LCO 3.1.1.

in operation.

AND B.2 Initiate action to restore one Immediately DHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required DHR loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.8.2 ------- NOTE---------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days power available-to each required DHR pump.

Davis-Besse 3.4.8-2 Amendment 279

Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level . 228 inches; and

b. A minimum of 85 kW of essential pressurizer heaters OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level A.1 Restore level to within limit. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limit.

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

B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. Capacity of essential C.1 Restore essential 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressurizer heaters less pressurizer heater capacity.

than limit.

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

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.4.9-1 Amendment 279

Pressurizer 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1, Verify pressurizer water level

228 inches. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.9.2 Verify capacity of essential pressurizer heaters is 24 months

> 85 kW.

Davis-Besse 3.4.9-2 Amendment 279

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Two pressurizer safety valves shall be OPERABLE with lift settings

< 2525 psig.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

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

B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Two pressurizer safety valves inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE In accordance in accordance with the Inservice Testing Program. with the Inservice Following testing, lift settings shall be within +/- 1%. Testing Program Davis-Besse 3.4.10-1 Amendment 279

Pressurizer PORV 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Pilot Operated Relief Valve (PORV)

LCO 3.4.11 The PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. PORV inoperable. A.1 Close block valve. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND A.2 Remove power from block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valve.

B. Block valve inoperable. B.1 Close block valve. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND B.2 Remove power from block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valve.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.4.11-1 Amendment 279

Pressurizer PORV 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -------- NOTE ---------

Not required to be performed with block valve closed in accordance with the Required Actions of this LCO.

Perform one complete cycle of the block valve. 92 days SR 3.4.11.2 Perform one complete cycle of the PORV. 24 months Davis-Besse 3.4.11-2 Amendment 279

LTOP 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP)

LCO 3.4.12 The Decay Heat Removal (DHR) System relief valve shall be OPERABLE with:

a. A lift setting of 5 330 psig; and

b. The Reactor Coolant System (RCS) to DHR System isolation valves open with control powerremoved.

APPLICABILITY: MODES 4 and 5, MODE 6 when the reactor vessel head is on.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DHR System relief valve A.1 Open RCS to DHR System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable due to one or isolation bypass valves.

more RCS to DHR System isolation valves AND closed.

A.2 Verify RCS to DHR System Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months isolation bypass valves open.

B. DHR System relief valve B.1 Remove control power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable due to one or RCS to DHR System more RCS to DHR isolation valves.

System isolation valves with control power not removed.

C. DHR System relief valve CA1 Restore DHR System relief 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for reasons valve to OPERABLE status.

other than Condition A or B.

Davis-Besse 3.4.12-1 Amendment 279

LTOP 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Disable capability of both 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Associated Completion high pressure injection Time not met. pumps to inject water into the RCS.

AND D.2 Disable makeup pump 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months suction automatic transfer to the borated water storage tank on low makeup tank level.

AND D.3 Verify makeup tank level 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

<73 inches.

AND D.4 Verify RCS pressure and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pressurizer level in Acceptable Region of Figure 3.4.12-1 or 3.4.12-2, as applicable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify RCS to DHR isolation valves open with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control power removed.

SR 3.4.12.2 Verify DHR System relief valve lift setpoint In accordance

< 330 psig in accordance with the Inservice Testing with the IST (IST) Program. Program Davis-Besse 3.4.12-2 Amendment 279

LTOP 3.4.12 400 350 - - - UNACCEPTABLE REGION 300 A.d 2500 0v

0. 0 150 --

100 ACCEPTABLE REGION 50 0 40 80 120 160 200 240 Initial Pressurizer Level (Inches)

Figure 3.4.*12-1 RCS Pressure Versus Pressurizer Level Limit for Inoperable DHR System Relief Valve in MODE 4 Davis-Besse 3.4.12-3 Amendment 279

LTOP 3.4.12 400 350 U,

300 UA --

ETAL -EIO a-a-U..

QJ I-250 200 z0 0

C 150 C a AC,"FaB REGINACETEERGO U

(U --- - - - - - -

100 50 0 40 80 -120g 160 LouU .14U Initial Pressurizer Level (Inches)

Figure 3.4.12-2 RCS Pressure ,Versus Pressurizer Level Limit for Inoperable DHR System Relief Valve in MODE 5 and MODE 6 when the reactor vessel head is on Davis-Besse 3.4.12-4 Amendment 279

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; and

d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A.1 Reduce LEAKAGE to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within limits.

limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

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

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

OR Primary to secondary LEAKAGE not within limit.

Davis-Besse 3.4.13-1 Amendment 279

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 - -------------- NOTES -----------------------------

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

2. Not applicable to primary to secondary LEAKAGE.

Verify RCS operational LEAKAGE is within limits by 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months performance of RCS water inventory balance.

SR 3.4.13.2- --------- -- NOTE ------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

<150 gallons per day through any one SG.

Davis-Besse 3.4.13-2 Amendment 279

RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limits.

AND The Decay Heat Removal (DHR) System interlock function shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4, except the valves in the DHR flow path when in, or during the transition to or from, the DHR mode of operation and the DHR System interlock function.

ACTIONS

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

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths ----

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

with leakage from one or Each valve used to satisfy Required more RCS PIVs not Action A.1 and Required Action A.2 within limit. must have been verified to meet SR 3.4.14.2.a and be on the RCS pressure boundary or the high pressure portion of the system.

A.1 Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND Davis-Besse 3.4.14-1 Amendment 279

RCS PIV Leakage 3.4.14 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Isolate the high pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic, or check valve.

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

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Decay Heat Removal C.1 Isolate the affected line by 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (DHR) System interlock use of two closed function inoperable, deactivated automatic valves.

OR C.2 -------- NOTE-------

Only applicable if RCS pressure < 328 psig.

Restore the interlock Prior to increasing function to OPERABLE RCS pressure status. > 328 psig Davis-Besse 3.4.14-2 Amendment 279

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 Perform CHANNEL CHECK on the DHR System 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interlock channel common to Safety Features Actuation System (SFAS) instrumentation.

SR 3.4.14.2 ------------ NOTE -------------------------------

Only required to be performed in MODES 1 and 2.

Verify: 24 months

a. Leakage from each RCS PIV is equivalent to AND

< 5.0 gpm at an RCS pressure of 2155 psig; and Prior to entering

b. When current measured rate is > 1 gpm, the MODE 2 current measured rate has not exceeded the whenever the unit rate determined by the previous test by an has been ,in amount that reduces the margin between MODE 5 for measured leakage rate and 5.0 gpm by 50%. 7 days or more, if leakage testing has not been performed in the previous 9 months SR 3.4.14.3 -------------------- NOTE -------

Not required to be met when the DHR System interlock function is disabled in accordance with LCO 3.4.12.

Verify DHR System interlock function prevents the 24 months valves from being opened with a simulated or actual RCS pressure signal > 328 psig.

SR 3.4.14.4 -- ------ NOTE ------------------------------

Not required to be met when the DHR System interlock function is disabled in accordance with LCO 3.4.12.

Verify DHR System interlock function causes the 24 months valves to close automatically with a simulated or actual RCS pressure signal >_328 psig.

Davis-Besse 3.4.14-3 Amendment 279

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.14.5 Perform CHANNEL CALIBRATION on the DHR 24 months System interlock channels.

Davis-Besse 3.4.14-4 Amendment 279

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. One containment sump monitor; and

b. One containment atmosphere radioactivity monitor (gaseous or particulate).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.1 ---------- NOTE-----------..

A. Required containment sump monitor Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable, after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore required 30 days containment sump monitor to OPERABLE status.

B. Required containment B.1.1 Analyze grab samples of Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months atmosphere radioactivity the containment monitor inoperable, atmosphere.

OR Davis-Besse 3-4.15-1 Amendment 279

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.1.2 --------- NOTE-------

Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2 Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.

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

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Both required monitors D.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of required containment 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months atmosphere radioactivity monitor.

SR 3.4.15.2 Perform CHANNEL FUNCTIONAL TEST of required 31 days containment atmosphere radioactivity monitor.

Davis-Besse 3.4.15-2 Amendment 279

RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

SR 3.4.15.3 Perform CHANNEL CALIBRATION of required 18 months containment atmosphere radioactivity monitor.

SR 3.4.15.4 Perform CHANNEL CALIBRATION of required 24 months containment sump monitor.

-Davis-Besse 3.4.15-3 Amendment 279

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be Within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) - 530'F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT --- NOTE----------

1-131 > 1.0 gCi/gm. LCO 3.0.4.c is applicable.

A.1 Verify DOSE EQUIVALENT Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B. Required Action and B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tavg < 530°F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131 in unacceptable region of Figure 3.4.16-1.

OR Gross specific activity of the reactor coolant not within limit.

Davis-Besse 3.4.16-1 Amendment 279

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific activity 7 days.

<1 00/i pCi/gm.

SR 3.4.16.2 -------------------- NOTE ------------

Only required to be performed in MODE 1.

Verify reactor. coolant DOSE EQUIVALENT 1-131 14 days specific activity < 1.0 gCi/gm.

AND Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after THERMAL POWER change of Ž> 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period SR 3.4.16.3 ------ ---------- NOTE -----------

Not required to be performed until 31 days after a minimum of 2 EFPD and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for > 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine E. 184 days Davis-Besse 3.4-16-2 Amendment 279

RCS Specific Activity 3.4.16

--- (275, 26) 2501 4-H-4+

225 200 E ItI UNACCEPTABLE.

OPERATION P1 175 E

150

-Z LLW125

__ýk I I I Ll _L

r.-FT

, I I I I N1 I I I I lII i ii L 100 ACCEPTABLE

,)

0 I OPERATION I I I r 7 - -

a7 (60, 100)

I 50 HI

-1 L I I _LJL 25 T~

0 n F-1 t I I 1 11 1 1 1 20 30 40 50 60 70 80 90 100 RTPP%)

Figure 3.4.16-1 (page 1 of 1)

Reactor Coolant DOSE EQUIVALENT 1-131 Specific Activity Limit Versus Percent of RATED THERMAL POWER With Reactor Coolant Specific Activity > 1.0 pCi/gm DOSE EQUIVALENT 1-131 Davis-Besse 3.4.16-3 Amendment 279

SG Tube Integrity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG tube integrity shall be maintained.

AND All SG tubes satisfying the tube repair criteria shall be plugged or repaired in accordance with the Steam Generator Program.

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

ACTIONS NO r-----------------------------------------------------------

Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION. TIME A. One or more SG tubes A.1 Verify tube integrity of the 7 days satisfying the tube repair affected tube(s) is criteria and not plugged maintained until the next or repaired in refueling outage or SG tube accordance with the inspection.

Steam Generator Program. AND A.2 Plug or repair the affected Prior to entering tube(s) in accordance with MODE 4 following the the Steam Generator next refueling outage Program. or SG tube inspection B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR SG tube integrity not maintained.

Davis-Besse 3.4.17-1 Amendment 279

SG Tube Integrity 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the In accordance Steam Generator Program. with the Steam Generator Program SR 3.4.17.2 Verify that each inspected SG tube that satisfies the Prior to entering tube repair criteria is plugged or repaired in MODE 4 following accordance with the Steam Generator Program. a SG tube inspection Davis-Besse 3.4.17-2 Amendment 279

CFTs 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Core Flooding Tanks (CFTs)

LCO 3.5.1 Two CFTs shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with Reactor Coolant System (RCS) pressure > 800 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CFT inoperable due A.1 Restore boron 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to boron concentration concentration to within not within limits. limits.

B. One CFT inoperable for B.1 Restore CFT to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

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

C.2 Reduce RCS pressure to 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months

<800 psig.

D. Two CFTs inoperable. D.1 Enter LCO 3.0.3. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each CFT isolation valve is fully open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3-5-1-1 Amendment 279

CFTs 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.2 Verify borated water volume in each CFT is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> 12.6 feet and < 13.3 feet.

S R 3.5.1.3 Verify nitrogen cover pressure in each CFT is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> 580 psig and _< 620 psig.

SR 3.5.1;4 Verify boron concentration in each CFT is 31 days

> 2600 ppm and _ 3500 ppm.

AND

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

Only required to be performed for affected CFT Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of

Ž_80 gallons that is not the result of addition from the borated water storage tank SR 3.5.1.5 Verify power is removed from each CFT isolation 31 days valve operator.

Davis-Besse 3.5.1-2 Amendment 279

ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating ILCO 3.5.2 Two ECCS trains shall be OPERABLE.

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

The borated water storage tank (BWST) outlet and containment emergency sump valves may be considered OPERABLE when the associated valve motors are de-energized, provided the valves are not otherwise inoperable.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure A.1 Restore LPI subsystem to 7 days injection (LPI) OPERABLE status.

subsystem inoperable.

B. One or more trains B.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable for reasons OPERABLE status.

other than Condition A.

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

C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. Less than 100% of the D.1 Enter LCO 3.0.3. Immediately ECCS flow equivalent to a single OPERABLE train available.

Davis-Besse 3.5.2-1 Amendment 279

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify each ECCS manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.2 Verify each ECCS pump's developed head at the In accordance test flow point is greater than or equal to the with the Inservice required developed head. Testing Program SR 3.5.2.3 Verify ECCS piping is full of water by venting the 24 months ECCS pump casings and discharge piping high points. AND Prior to declaring ECCS OPERABLE after draining ECCS piping SR 3.5.2.4 Verify each ECCS automatic valve in the flow path 24 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.2.5 Verify each ECCS pump starts automatically on an 24 months actual or simulated actuation signal.

SR 3.5.2.6 Verify the correct position of each mechanical stop 24 months for the following valves:

a. DH-14A; and

b. DH-14B.

Davis-Besse 3.5.2-2 Amendment 279

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.7 Verify, by visual inspection, each ECCS train 24 months containment sump suction inlet is not restricted by debris and suction inlet trash racks and screens show no evidence of structural distress or abnormal corrosion.

SR 3.5.2.8 Verify the following: 24 months

a. Each BWST outlet valve and containment emergency sump valve actuate to the correct position on a manual actuation of the containment emergency sump valve; and

b. The actuation time of each BWST outlet valve and containment emergency sump valve is

< 75 seconds.

Davis-Besse 3.5.2-3 Amendment 279

ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - Shutdown LCO 3.5.3 One ECCS low pressure injection (LPI) subsystem shall be OPERABLE.

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

The borated water storage tank (BWST) outlet and containment emergency sump valves may be considered OPERABLE when the associated valve motors are de-energized, provided the valves are not otherwise inoperable.

APPLICABILITY: MODE 4.

ACTIONS

-NOTE-LCO 3.rO.4.b is not applicable to ECCS LPI subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS LPI A.1 Initiate action to restore Immediately subsystem inoperable, required ECCS LPI subsystem to OPERABLE status.

Davis-Besse 3.5-3-1 Amendment 279

ECCS - Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 For all equipment required to be OPERABLE, the In accordance following SRs are applicable: with applicable SRs SR 3.5.2.1 SR 3.5.2.6 SR 3.5.2.2 SR 3.5.2.7 SR 3.5.2.3 SR 3.5.2.8 SR 3.5.2.4 SR 3.5.2.5 Davis-Besse 3.5.3-2 Amendment 279

BWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Borated Water-Storage Tank (BWST)

LCO 3.5.4 The BWST shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. BWST boron A.1 Restore BWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not within OPERABLE status.

limits.

OR BWST water temperature not within limits.

B. BWST inoperable for B.1 Restore BWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

C. Required Action and CA1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Davis-Besse 3.5.4-1 Amendment 279

BWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SIR 3.5.4.1 --------------------- NOTE ......--------

Only required to be performed when ambient air temperature is < 35 0 F or > 90 0 F.

Verify BWST borated water temperature is > 35 0 F 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and < 90 0 F.

SR 3.5.4.2 Verify BWST borated water volume is 7 days

> 500,100 gallons and _<550,000 gallons.

SR 3.5.4.3 Verify BWST boron concentration is Ž_2600 ppm 7 days and < 2800 ppm.

Davis-Besse 3.5.4-2 Amendment 279

Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment inoperable. A.1 Restore containment to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and leakage In accordance rate testing except for containment air lock testing, with the in accordance with the Containment Leakage Rate Containment Testing Program. Leakage Rate Testing Program Davis-Besse 3.6.1-1 Amendment 279

Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 Two containment air locks shall be OPERABLE.

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

ACTIONS

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

1. Entry and exit is permissible to perform repairs on the affected air lock components.

2. Separate Condition entry is allowed for each air lock.

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when air lock leakage results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more NOTES ---------

containment air locks 1. Required Actions A.1, A.2, with one containment air and A.3 are not applicable if both lock door inoperable, doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls if both air locks are inoperable.

A.1 Verify the OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed in the affected air lock.

AND Davis-Besse 3.6.2-1 Amendment 279

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Lock the OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock.

AND A.3 ..... .NOTE-------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify the OPERABLE door Once per 31 days is locked closed in the affected air lock.

B. One or more ---------------- NOTES ---------

containment air locks 1. Required Actions B.1, B.2, with containment air lock and B.3 are not applicable if both interlock mechanism doors in the same air lock are inoperable, inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed in the affected air lock.

AND Davis-Besse 3.6.2-2 Amendment 279

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock.

AND B.3 -- NOTE-Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify an OPERABLE door Once per 31 days is locked closed in the affected air lock.

C. One or more C.1 Initiate action to evaluate Immediately containment air locks overall containment inoperable for reasons leakage rate per LCO 3.6.1.

other than Condition A or B. AND C.2 Verify a door is closed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the affected air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND-D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Davis-Besse 3.6.243 Amendment 279

Containment Air Locks 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 NOTES ----------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.

Perform required air lock leakage rate testing in In accordance accordance with the Containment Leakage Rate with the Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be opened at 24 months a time.

Davis-Besse 3.6-2-4 Amendment 279

Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.-

ACTIONS

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

1. Penetration flow paths except for 48 inch containment purge and exhaust 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 system(s) made inoperable by containment isolation valves.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A.------- NOTE -------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two or more and de-activated automatic containment isolation valve, closed manual valve, valves, blind flange, or check valve with flow through the valve secured.

One or more penetration flow paths with one AND containment isolation valve inoperable for reasons other than Condition D or E.

Davis-Besse 3.6.3-1 Amendment 279

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 -- NOTES-

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment B. --------- NOTE---------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two or more and de-activated automatic containment isolation valve, closed manual valve, valves, or blind flange.

One or more penetration flow paths with two or more containment isolation valves inoperable for reasons other than Condition D or E.

Davis-Besse 3.6.3-2 Amendment 279

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. NOTE--..-..... C.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with only one and de-activated automatic containment isolation valve, closed manual valve, valve, or blind flange.

AND One or more penetration flow paths with one C.2 ----- NOTES-------

containment isolation 1. Isolation devices in high valve inoperable, radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

Davis-Besse 3.6.3-3 Amendment 279

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration D.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months flow paths with one or penetration flow path by more containment purge use of at least one closed or exhaust valves not and de-activated automatic within purge and valve, closed manual valve, exhaust valve leakage or blind flange.

limits.

AND D.2 -------------- NOTES-

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment AND D.3 Perform SR 3.6.3.5 for the Once per 92 days resilient seal containment purge and exhaust valves closed to comply With Required Action D.1.

Davis-Besse 3.6.3-4 Amendment 279

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Secondary containment E.1 Restore secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months bypass leakage not containment bypass within limit, leakage to within limit.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 48 inch containment purge and exhaust 31 days valve is closed with control power removed.

SR 3.6.3.2 --------------------- NOTE --------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each containment isolation manual valve and 31 days blind flange that is located outside containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

Davis-Besse 3.6.3-5 Amendment 279

Containment Isolation Valves 3.6'3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.3 --------------------- NOTE -----.-.--........----------

Valves and blind flanges in high radiation areas may be verified by use of administrative means. ,

Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed, or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed, except for containment isolation valves that the previous are open under administrative controls. 92 days SR 3.6.3.4 Verify the isolation time of each automatic power In accordance operated containment isolation valve is within limits, with the Inservice Testing Program Davis-Besse 3.6.3-6 Amendment 279

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.5 Perform leakage rate testing for containment purge Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and exhaust valves with resilient seals. after each valve closure, if valve opened in MODE 1,2,3,.

or 4 AND Prior to entering MODE 4 from MODE 5 if valve opened in, other than MODE 1, 2, 3, or4 AND Prior to entering MODE 2 from MODE 3 each time the plant has been in any combination of MODE 3, 4, 5, or 6 for

> 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , if not performed in the previous 184 days SR 3.6.3.6 Verify each automatic containment isolation valve 24 months that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

SR 3.6.3.7 Verify the combined leakage for all secondary in accordance containment bypass leakage paths is < 0.03 La. with the Containment Leakage Rate Testing Program Davis-Besse 3.6-3-7 Amendment 279

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be > -14 inches water gauge and

+25 inches water gauge.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limits, pressure to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limits. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.6.4-1 Amendment 279

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be <_120 0 F.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average air A.1 Restore containment 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within average air temperature to limit, within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature is within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit.

Davis-Besse 3.6.5-1 Amendment 279

Containment Spray and Air Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray and Air Cooling Systems LCO 3.6.6 Two containment spray trains and two containment air cooling trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment spray 7 days train inoperable, train to OPERABLE status.

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

B.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months C. One required C.1 Restore required 7 days containment air cooling containment air cooling train inoperable, train to OPERABLE status.

D. One containment spray D.1 Restore containment spray 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train and one required train to OPERABLE status.

containment air cooling train inoperable. OR D.2 Restore required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months containment air cooling train to OPERABLE status.

Davis-Besse 3.6.6-1 Amendment 279

Containment Spray and Air Cooling Systems 3.6.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two required E.1 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months containment air cooling containment air cooling trains inoperable, train to OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C, D, AND or E not met.

F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Two containment spray G.1 Enter LCO 3.0.3. Immediately trains inoperable.

OR Any combination of three or more required trains inoperable.,

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.6.2 Operate each required containment air cooling train 31 days for >_15 minutes.

Davis-Besse 3.6.6-2 Amendment 279

Containment Spray and Air Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.3 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the Inservice the required developed head. Testing Program SR 3.6.6.4 Verify each required containment air cooling train 18 months starts automatically on an actual or simulated actuation signal.

SR 3.6.6.5 Verify each required containment air cooling train 24 months cooling water flow rate is _>1150 gpm.

SR 3.6.6.6 Verify each automatic containment spray valve in 24 months the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.6.7 Verify each containment spray pump starts 24 months automatically on an actual or simulated actuation signal.

SR 3.6.6.8 Verify each spray nozzle is unobstructed. 10 years Davis-Besse 3.6.6-3 Amendment 279

TSP Storage 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Trisodium Phosphate Dodecahydrate (TSP) Storage LCO 3.6.7 The TSP storage baskets shall contain > 290 ft3 of TSP.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. TSP storage baskets A.1 Restore TSP storage 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months contain < 290 ft3 of TSP. baskets to > 290 ft 3 of TSP.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Verify contained volume of TSP in the TSP storage 24 months baskets is within limit.

Davis-Besse 3.6.7-1 BAmendment 279

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS NOT r------------------------------------------------------------

Separate Condition entry is allowed for each MSS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MSSVs A.1 Reduce power to less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable, the reduced power requirement of Equation 3.7.1-1.

AND A.2 Reduce the High Flux trip 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months setpoint in accordance with Equation 3.7.1-1.

Davis-Besse 3.7.1-1 Amendment 279

MSSVs 3.7.1 ACTIONS (continued)

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

B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR One or more steam generators with less than two MSSVs OPERABLE.

OR One or more steam generators with no MSSVs with a lift setting of 1050 psig +/- 3%

OPERABLE.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 N - -.

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

Only required to be performed in MODES 1 and 2.

Verify each MSSV lift setpoint per Table 3.7.1-1 in In accordance accordance with the Inservice Testing Program. with the Inservice Following testing, lift settings shall be within +/- 1%. Testing Program Davis-Besse 3.7.1-2 Amendment 279

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

Main Steam Safety Valve Lift Settings LIFT SETTING NUMBER OF VALVES (psig +/- 3%)

2 MSSVs/steam generator 1050 7 MSSVs/steam generator 1100

. Davis-Besse 3.7.1-3 Amendment 279

MSSVs 3.7.1 WY = SP; RP = Y x 100%

Z Z W = High Flux trip setpoint for four pump operation as specified in LCO 3.3.1, "Reactor Protection System (RPS) Instrumentation."

Y = Total OPERABLE MSSV relieving capacity per steam generator based on summation of individual OPERABLE MSSV relief capacities per steam generator lb/hour.

Z = Required relieving capacity per steam generator of 6,585,600 lb/hour.

SP = High Flux trip setpoint (not to exceed W).

RP = Reduced power requirement (not to exceed RTP).

Equation 3.7.1-1 (page 1 of 1)

Reduced Power and High Flux Trip Setpoint Versus OPERABLE Main Steam Safety Valves Davis-Besse 3.7.1-4 Amendment 279

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Two MSIVs shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 except when all MSIVs are closed.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months MODE 1. OPERABLE status.

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

C. ---------- NOTE ---------- C.I Close MSIV. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Separate Condition entry is allowed for each AND MSIV.

C.2 Verify MSIV is closed. Once per 7 days One or more MSIVs inoperable in MODE 2 or 3.

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

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.7.2-1 Amendment 279

MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify isolation time of each MSIV is within limits. In accordance with the Inservice Testing Program SR 3.7.2.2 Verify each MSIV actuates to the isolation position 24 months on an actual or simulated actuation signal.

Davis-Besse 3.7.2-2 Amendment 279

MFSVs, MFCVs, and associated SFCVs 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Stop Valves (MFSVs), Main Feedwater Control Valves (MFCVs),

and associated Startup Feedwater Control Valves (SFCVs)

LCO 3.7.3 Two MFSVs, MFCVs, and associated SFCVs shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 except when all MFSVs, MFCVs, and associated SFCVs are closed or isolated by a closed manual valve.

ACTIONS

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

Separate Condition entry is allowed for each MFSV, MFCV, and SFCV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MFSVs A.1 Close or isolate MFSV. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

AND A.2 Verify MFSV is closed or Once per 7 days isolated.

B. One or more MFCVs B.1 Close or isolate MFCV. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

AND B.2 Verify MFCV is closed or Once per 7 days isolated.

C. One or more SFCVs C.1 Close or isolate SFCV. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

AND C.2 Verify SFCV is closed or Once per 7 days isolated.

Davis-Besse 3.7.3-1 Amendment 279

MFSVs, MFCVs, and associated SFCVs 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two valves in the same D.1 Isolate affected flow path. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow path inoperable.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the isolation time of each MFSV is within In accordance limits. with the Inservice Testing Program SR 3.7.3.2 Verify the isolation time of each MFCV and SFCV is 24 months within limits.

SR 3.7.3.3 Verify each MFSV, MFCV, and SFCV actuates to 24 months the isolation position on an actual or simulated actuation signal.

Davis-Besse 3.7.3-2 Amendment 279

TSVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Turbine Stop Valves (TSVs)

LCO 3.7.4 Four TSVs shall be OPERABLE.

APPLICABILITY: MODES 1, MODES 2 and 3 except when all TSVs are closed.

ACTIONS

.-.-.-.-..-.----.-.-.-.-.------.-------------- NOT r - -- -- -- -- -- -- - -- -- - - -- -- - - -- -- -- -- -- -- - --- -- - -- - - -

Separate Condition entry is allowed for each TSV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more TSVs A.1 Close inoperable TSV. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

AND A.2 Verify inoperable TSV is Once per 7 days closed B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify isolation time of each TSV is within limits. 24 months SR 3.7.4.2 Verify-each TSV actuates to the isolation position on 24 months an actual or simulated actuation signal.

Davis-Besse 3.7.4-1 Amendment 279

EFW 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Emergency Feedwater (EFW)

LCO 3.7.5 Three EFW trains shall be OPERABLE, consisting of:

a. Two Auxiliary Feedwater (AFW) trains; and

b. The Motor Driven Feedwater Pump (MDFP) train.

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

Only the MDFP train is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

.----.---.---- ..-------------..----------- NOTE-LCO 3.0.4.b is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION-TIME A. One AFW train A.1 Restore AFW train to 7 days inoperable due to one OPERABLE status.

inoperable steam supply.

OR

- -NOTE------

Only applicable if MODE 2 has not been entered following refueling.

One AFW train inoperable in MODE 3 following refueling.

Davis-Besse 3.7.5-1 Amendment 279

EFW 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One EFW train B.1 Restore EFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable for reasons OPERABLE status.

other than Condition A in MODE 1,2, or 3.

C. One AFW train C.1 Restore the steam supply 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable due to one to the AFW train to inoperable steam OPERABLE status.

supply.

OR AND C.2 Restore the MDFP train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months MDFP train inoperable. OPERABLE status.

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

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Two EFW trains inoperable for reasons other than Condition C in MODE 1,2, or 3.

E. Three EFW trains E.1 ---------- NOTE -------

inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3. LCO Required Actions requiring MODE changes are suspended until one EFW train is restored to OPERABLE status.

Initiate action to restore Immediately one EFW train to OPERABLE status.

Davis-Besse 3.7.5-2 Amendment 279

EFW 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required MDFP train F.1 Initiate action to restore Immediately inoperable in MODE 4. MDFP train to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 ----------------------- NOTE --------------

In MODE 1 < 40% RTP and MODES 2, 3, and 4, the MDFP train valves are allowed to be in the non-correct position, provided the valves are capable of being locally realigned to the correct position.

Verify each EFW manual, power operated, and 31 days automatic valve in each water flow path and in both steam supply flow paths to the AFW pumps, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 -- -------- NOTE ---------------------------.

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching 800 psig in the steam generators.

Verify the developed head of each AFW pump at the 92 days flow test point is greater than or equal to the required developed head.

SR 3.7.5.3 NOTE ----- --------

Not required to be performed until 73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months after MDFP train is aligned to the AFW System.

Operate the MDFP train. 92 days Davis-Besse 3.7.5-3 Amendment 279

EFW 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.4-- --- -.-----.. NOTE ------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching 800 psig in the steam generators.

Verify each AFW automatic valve that is not locked, 24 months sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.5.5 ---- ----------- NOTE ------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching 800 psig in the steam generators.

Verify each AFW pump starts automatically on an 24 months actual or simulated actuation signal.

SR 3.7.5.6 Verify proper alignment of the required AFW flow Prior to entering paths by verifying flow from the condensate storage MODE 2 following tanks to each steam generator. refueling or whenever plant has been in MODE 5, MODE 6, or defueled for a cumulative period of > 30 days SR 3.7.5.7 Verify proper alignment of the required MDFP flow Prior to entering paths by verifying flow from the condensate storage MODE 3 following tanks to each steam generator. refueling or whenever plant has been in MODE 5, MODE 6, or defueled for a cumulative period of > 30 days Davis-Besse ..3.7.5-4 Amendment 279

EFW 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.8 Perform CHANNEL CHECK on each AFW train 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Steam Generator Level Control System.

SR 3.7.5.9 Perform CHANNEL FUNCTIONAL TEST on each 31 days AFW train Steam Generator Level Control System.

SR 3.7.5.10 Perform CHANNEL CALIBRATION on each AFW 24 months train Steam Generator Level Control System.

Davis-Besse 3.7.5-5 Amendment 279

CSTs 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tanks (CSTs)

LCO 3.7.6 The CSTs shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The CSTs inoperable. A.1 Verify by administrative 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months means OPERABILITY of backup water supply. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND A.2 Restore CSTs to 7 days OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4 without 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reliance on steam generator for heat removal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify usable volume in the CSTs is > 270,300 gal. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.7.6-1 Amendment 279

CCW System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW loops shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCW loop A.1 ---------- NOTES-----

inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources -

Operating," for emergency diesel generator made inoperable by CCW.

2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops

- MODE 4,', for decay heat removal loop made inoperable by CCW.

Restore CCW loop to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status..

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Davis-Besse 3.7.7-1 Amendment 279

CCW System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 --------------.----.-.----- NOTE -------..........--.----

Isolation of CCW flow to individual components does not render CCW System inoperable.

Verify each CCW manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.7.2 Verify each CCW automatic valve in the flow path 24 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.7.3 Verify each required CCW pump starts automatically 24 months on an actual or simulated actuation signal.

Davis-Besse 3.7.7-2 Amendment 279

SWS 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water System (SWS)

LCO 3.7.8 Two SWS loops shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SWS loop A.1 --------- NOTES --...-------

inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating,"

for emergency diesel generator made inoperable by SWS.

2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops

- MODE 4," for decay heat removal loop made inoperable by SWS.

Restore SWS loop to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Davis-Besse 3.7.8-1 Amendment 279

SWS 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 ---- ------ --NOTE ----------------

Isolation of SWS flow to individual components does not render the SWS inoperable.

Verify each SWS manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.8.2 Verify each SWS automatic valve in the flow path 24 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.8.3 Verify each required SWS pump starts automatically 24 months on an actual or simulated actuation signal.

Davis-Besse 3.7.8-2 Amendment 279

UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS inoperable. A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is _ 562 ft International 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Great Lakes Datum.

SR 3.7.9.2 Verify average water temperature of UHS is < 90°F. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Davis-Besse 3.7.9-1 Amendment 279

CREVS 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Ventilation System (CREVS)

LCO 3.7.10 Two CREVS trains shall be OPERABLE.

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

1. The control room envelope (CRE).boundary may be opened intermittently under administrative control.

2. Only the CRE boundary is required to be OPERABLE during movement of irradiated fuel assemblies.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREVS train A.1 Restore CREVS train to 7 days inoperable for reasons OPERABLE status.

other than Condition B.

B. One or more CREVS B.1 Initiate action to implement Immediately trains inoperable due to mitigating actions.

inoperable CRE boundary in MODE 1, 2, AND 3, or4.

B.2 Verify mitigating actions 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to 90 days OPERABLE status.

Davis-Besse 3.7.10-1 Amendment 279

CREVS 3.7.10 ACTIONS (continued)

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

movement of irradiated fuel assemblies.

E. Two CREVS trains E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train for 15 minutes. 31 days SR 3.7.10.2 Perform required CREVS filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.7.10.3 Verify Control Room Normal Ventilation System 24 months isolates on an actual or simulated actuation signal.

SR 3.7.10.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program Davis-Besse 3.7.10-2 Amendment 279

CREVS 3.7.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.10.5 270 cfm and Verify the system makeup flow rate is _> 24 months

< 330 cfm when supplying the control room with outside air.

Davis-Besse 3.7.10-3 Amendment 279

CREATCS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS)

LCO 3.7.11 Two CREATCS trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREATCS train A.1 Restore CREATCS train to 30 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CREATCS train has the capability to 24 months remove the assumed heat load.

Davis-Besse 3.7.11-1 Amendment 279

Station EVS 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Station Emergency Ventilation System (EVS)

LCO 3.7.12 Two Station EVS trains shall be OPERABLE.

NOTE-ý ----

The shield building area negative pressure boundary may be opened intermittently under administrative control.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Station EVS train A.1 Restore Station EVS train 7 days inoperable, to OPERABLE status.

B. Two Station EVS trains B.1 Restore shield building area 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable due to negative pressure boundary inoperable shield to OPERABLE status.

building area negative pressure boundary.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Davis-Besse 3.7.12-1 Amendment 279

Station EVS 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each Station EVS train forŽ 15 minutes. 31 days SR 3.7.12.2 Perform required Station EVS filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).

SR 3.7.12.3 Verify each Station EVS train actuates on an actual 24 months or simulated actuation signal.

SR 3.7.12.4 Verify one Station EVS train can attain a negative 24 months on a pressure 2 0.25 inches water gauge in the annulus STAGGERED

< 4 seconds after the flow rate is >-7200 cfm and TEST BASIS

< 8800 cfm.

SR 3.7.12.5 Verify each Station EVS filter cooling bypass 24 months damper can be opened.

Davis-Besse 3.7.12-2 Amendment 279

Spent Fuel Pool Area EVS 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Spent Fuel Pool Area Emergency Ventilation System (EVS)

LCO 3.7.13 Two Spent Fuel Pool Area EVS trains shall be OPERABLE.

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

The spent fuel pool area negative pressure boundary may be opened under administrative control.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel pool building.

ACTIONS

------------------------------ N I ! OTE-LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One Spent Fuel Pool A.1 Restore Spent Fuel Pool 7 days Area EVS train Area EVS train to inoperable. OPERABLE status.

B. Required Action and B.1 Place OPERABLE Spent Immediately associated Completion Fuel Pool Area EVS train in Time of Condition A not operation.

met.

OR B.2 Suspend movement of Immediately irradiated fuel assemblies in the spent fuel pool building.

Davis-Besse 3.7.13-1 Amendment 279

Spent Fuel Pool Area EVS 3.7.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two Spent Fuel Pool C.1 Suspend movement of Immediately Area EVS trains irradiated fuel assemblies in inoperable, the spent fuel pool building.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each Spent Fuel Pool Area EVS train for 31 days

> 15 minutes.

SR 3.7.13.2 Perform required Spent Fuel Pool Area EVS filter In accordance testing in accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.7.13.3 Verify each Spent Fuel Pool Area EVS train 24 months actuates on an actual or simulated actuation signal.

SR 3.7.13.4 Verify one Spent Fuel Pool Area EVS train can 24 months on a maintain a negative pressure > 0.125 inches water STAGGERED gauge relative to outside atmosphere. TEST BASIS SR 3.7.13.5 Verify each Spent Fuel Pool Area EVS filter cooling 24 months bypass damper can be opened.

Davis-Besse 3.7.13-2 Amendment 279

Spent Fuel Pool Water Level 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Water Level LCO 3.7.14 The spent fuel pool water level shall be _>23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool water A.1 ----------- NOTE---

level not within limit. LCO 3.0.3 is not applicable.

Suspend movement of Immediately irradiated fuel assemblies in spent fuel pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the spent fuel pool water level is > 23 ft above 7 days the top of irradiated fuel assemblies seated in the storage racks.

Davis-Besse 3.7.14-1 Amendment 279

Spent Fuel Pool Boron Concentration 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool Boron Concentration LCO 3.7.15 The spent fuel pool boron concentration shall be >_630 ppm.

APPLICABILITY: When fuel assemblies are stored in the spent fuel pool and a spent fuel pool verification has not been performed since the last movement of fuel assemblies in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool boron - ------------- NOTE----------

concentration not within LCO 3.0.3 is not applicable.

limit. -------------

A.1 Suspend movement of fuel Immediately assemblies in the spent fuel pool.

AND A.2.1 Initiate action to restore Immediately spent fuel pool boron concentration to within limit.

OR A.2.2 Initiate action to perform a Immediately fuel storage pool verification.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the spent fuel pool boron concentration is 7 days within limit.

Davis-Besse 3.7.15-1 Amendment 279

Spent Fuel Pool Storage 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Spent Fuel Pool Storage LCO 3.7.16 Fuel assemblies stored in the spent fuel pool shall be placed in the spent fuel pool storage racks in accordance with the criteria shown in Figure 3.7.16-1.

APPLICABILITY: Whenever any fuel assembly is stored in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 -- NOTE--------

LCO not met. LCO 3.0.3 is not applicable.

Initiate action to move the Immediately noncomplying fuel assembly to an allowable location.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify by administrative means the initial enrichment Prior to storing the and burnup of the fuel assembly is in accordance fuel assembly in with Figure 3.7.16-1. the spent fuel pool Davis-Besse 3.7.16-1 Amendment 279

AL Spent Fuel Pool Storage 3.7.16 75 70 65 60 55 50 45 40

. 35.

E30 25 20

15 10 5

0 4-2.00 2.50 3.00 3.50 4.00 4.50 5.00. 5.50 Initial Enrichment (wt% U,235)

Figure 3.7.16-1 (page 1 of 1)

Burnup versus Enrichment Curve for Spent Fuel Pool Storage Racks NOTE: Fuel assemblies with initial enrichments less than 2.0 wt% U-235 will conservatively be required to meet the burnup requirements of 2.0 wt% U-235 assemblies. The approved loading patterns applicable to Category "A," "B," and "C" assemblies are specified in the Bases.

Davis-Besse 3.7.16-2 Amendment 279

Secondary Specific Activity 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Secondary Specific Activity LCO 3.7.17 The specific activity of the secondary coolant shall be <0. 10 ptCi/gm DOSE EQUIVALENT 1-131.

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

ACTIONS I CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit.

AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify the specific activity of the secondary coolant 31 days is

0.10 pCi/gm DOSE EQUIVALENT 1-131.

Davis-Besse 3.7.17-1 Amendment 279

Steam Generator Level 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Steam Generator Level LCO 3.7.18 Water Level of each steam generator shall be:

a. Less than or equal to the maximum water level shown in Figure 3.7.18-1 when in MODE 1 or 2;

b. < 96% Operate Range with LCO 3.3.11, "Steam and Feedwater Rupture Control System (SFRCS)

Instrumentation," Function 1 (Main Steam Line Pressure -

Low) not bypassed when in MODE 3;

c. < 96% Operate Range with LCO 3.3.11, Function 1 bypassed and both main feedwater (MFW) pumps not capable of supplying feedwater to the steam generators when in MODE 3; and

d.

50 inches Startup Range with LCO 3.3.11, Function 1 bypassed and one or both MFW pumps capable of supplying feedwater to the steam generators when in MODE 3.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Enter applicable Conditions and Required Actions of LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," when high steam generator water level results in exceeding the SDM limits.

CONDITION REQUIRED ACTION COMPLETION TIME A. Water level in one or A.1 Restore steam generator 15 minutes more steam generators level to within limit.

not within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. / 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.7.18-1 Amendment 279

Steam Generator Level 3.7.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify steam generator water level to be within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits.

Davis-Besse 3.7.18-2 Amendment 279

Steam Generator Level 3.7.18 100 (43,96) 90 80 Unacceptable Operating Region 70 60 Acceptable Operating Region 50 40 -

I ZO 30 40 50 60 0 10 Figure 3.7.18-1 (page 1 of 1)

Maximum Allowable Steam Generator Level Davis-Besse 3.7.18-3 Amendment 279

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 OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System;

b. Two emergency diesel generators (EDGs) each capable of supplying one train of the onsite Class 1E AC Electrical Power Distribution System; and

c. Two load sequencers for Train I and two load sequencers for Train 2.

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

ACTIONS LCO 3.0.4.b is not applicable to EDGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE offsite circuit.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required feature(s) .24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power discovery of no offsite available inoperable when power to one train its redundant required concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND Davis-Besse 3.8.1-1 Amendment 279ý

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. One EDG inoperable. B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required feature(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from supported by the inoperable discovery of EDG inoperable when its Condition B redundant required concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months EDG is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE EDG.

AND B.4 Restore EDG to 7 days OPERABLE status.

Davis-Besse 3.8-1-2 Amendment 279

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two offsite circuits C01 Declare required feature(s) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from

.inoperable. inoperable when its discovery of redundant required Condition C feature(s) is inoperable, concurrent with inoperability of redundant required feature(s)

AND C.2 Restore one offsite circuit to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D. One offsite circuit ---- NOTE---------

inoperable. Enter applicable Conditions and Required Actions of LCO. 3.8.9, AND "Distribution Systems - Operating,"

when' Condition D is entered with no One EDG inoperable. AC power source to any train.

D.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

OR D.2 Restore EDG to OPERABLE status. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two EDGs inoperable. E.1 Restore one EDG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OPERABLE status.

Davis-Besse 3-8-1-3 Amendment 279

AC Sources,- Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A, B, AND C, D, or E not met.

F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. --- NOTE ----------. G.A Remove inoperable load 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Separate Condition entry sequencer.

is allowed for each train.

One or more trains with one load sequencer inoperable.

H. --- NOTE ----------. H.1 Declare associated EDG Immediately Separate Condition entry inoperable.

is allowed for each train.

Required Action and associated Completion Time of Condition G not met.

OR One or more trains with two load sequencers inoperable.

Three or more AC 1.1 Enter LCO 3.0.3. Immediately sources inoperable.

Davis-Besse 3.8.1-4 Amendment 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated 7 days power availability for each offsite circuit.

SR 3.8.1.2 --.-.---..........-------- -NOTES---------------

1. All EDG starts may be preceded by an engine prelube period and followed by a warmup, period prior to loading.

2. A modified EDG start involving idling and/or 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 3.8.1.8 must be met.

Verify each EDG starts from standby conditions and 31 days achieves steady state voltage > 3744 V and

<4400 V, and frequency _Ž 59.5 Hz and _< 60.5 Hz.

SR 3.8.1.3 ---------- NOTES -------...---...-----.--

1. EDG 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 EDG at a time.

4. This SR shall-be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2 or SR 3.8.1.8.

Verify each EDG is synchronized and loaded and 31 days operates for > .60 minutes at a load _> 2340 kW and

<2600 kW.

SR 3.8.1.4 Verify each day tank contains Ž>4000 gal of fuel oil. 31 days Davis-Besse 3.8.1-5 Amendment 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.5 Check for and remove accumulated water from each 31 days day tank.

SR 3.8.1.6 Verify interval between each sequenced load block 31 days is within +/- 10% of design interval for each emergency load sequencer and each emergency time delay relay.

SR 3.8.1.7 Verify the fuel oil transfer system operates to 92 days

,. transfer fuel oil from fuel oil storage tank to the day tank.

SR 3.8.1.8 --------------------- NOTE---------------

All EDG starts may be preceded by an engine prelube period.

Verify each EDG starts from standby condition and 184 days achieves:

a. In < 10 seconds, voltage _> 4031 V and frequency _>58.8 Hz; and

b. Steady state voltage > 3744 V and _< 4400 V, and frequency >_59.5 Hz and < 60.5 Hz.

Davis-Besse 3.8.1-6 Amendment 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY S R 3.8.1.9 ------------------ NOTES ---.-.------------......

1. SR 3.8.1.9.a is only required to be met when the unit auxiliary source is supplying the electrical power distribution subsystem.

2. The automatic transfer portion of SR 3.8.1.9.a and all of SR 3.8.1.9.b shall not normally be performed in MODE 1 or 2. However, they may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify automatic and manual transfer of AC power 24 months sources from:

a. The unit auxiliary source to the pre-selected offsite circuit; and

b. The normal offsite circuit to the alternate offsite circuit.

Davis-Besse 3.8.1-7 Amendment 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.10 ---- - -------- NOTES----------

1. This Surveillance shall not norfnally be performed in MODE I or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

2.. If performed with the EDG synchronized with offsite power, it shall be performed within the power factor limit. However, ifgrid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each EDG rejects a load greater than or equal 24 months to its associated single largest post-accident load, and following load rejection, the frequency is

< 66.75 Hz.

Davis-Besse 3.8.1-8 Amendment 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 ----..---..---- ---- ------ NOTES --------------

1. All EDG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power 24 months signal:

a. De-energization of essential buses;

b. Load shedding from essential buses; and

c. EDG auto-starts from standby condition and:

1. Energizes permanently connected loads in _<10 seconds;

2. Energizes auto-connected shutdown loads through individual time delay relays;

3. Maintains steady-state voltage >_3744 V and _< 4400 V;

4. Maintains steady-state frequency

> 59.5 Hz and < 60.5 Hz; and

5. , Supplies permanently connected and auto-connected shutdown loads for

>_5 minutes.

-J.

Davis-Besse 3.8.1-9 Amendment 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 - ------------------ NOTE ---------------

This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify each EDG's noncritical automatic trips are 24 months bypassed on actual or simulated loss of voltage signal on the essential bus or an actual or simulated Safety Features Actuation System (SFAS) actuation signal.

SR 3.8.1.13 ---------- ------- NOTES----------- ----

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

3. If performed with EDG synchronized with offsite power, it shall be performed within the power factor limit. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each EDG operates for >_8 hours: 24 months

a. For > 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded _Ž2730 kW and

< 2860 kW; and

b. For the remaining hours of the test loaded

> 2340 kW and < 2600 kW.

Davis-Besse 3.8.1-10 Amendment 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.14 --------- NOTES--------------

1. This Surveillance shall be performed within 5 minutes of shutting down the EDG after the EDG has operated > 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months loaded _> 2340 kW and < 2600 kW.

Momentary transients outside of load range do not invalidate this test.

2. All EDG starts may be preceded by an engine prelube period.

Verify each EDG starts and achieves: 24 months

a. In < 10 seconds, voltage _ 4031 V and frequency >_58.8 Hz; and

b. Steady state voltage _>3744 V and < 4400 V, and frequency > 59.5 Hz and < 60.5 Hz.

Davis-Besse 3.8.1-11 Amendment 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 -------- NOTES -...........

1. All EDG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance .may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power 24 months signal in conjunction with an actual or simulated SFAS actuation signal:

a. De-energization of essential buses;

b. Load shedding from essential buses;

c. EDG auto-starts from standby condition and:

1. Energizes permanently connected loads in < 10 seconds;

2. Energizes auto-connected emergency loads through load sequencer and individual time delay relays;

3. Achieves steady-state voltage >_3744 V and < 4400 V;

4. Achieves steady-state frequency

> 59.5 Hz and < 60.5 Hz; and

5. Supplies permanently connected and auto-connected emergency loads for

> 5 minutes.

Davis-Besse 3.8.1-12 Amendment 279

AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1 E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and

b. One emergency diesel generator (EDG) capable of supplying one train of the onsite Class 1 E AC electrical power distribution subsystem(s) required by LCO 3.8.10.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite ------------ NOTE --....------------

circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.

A.1 Declare affected required Immediately feature(s) with no offsite power available inoperable.

OR Davis-Besse 3.8.2-1 Amendment 279

AC Sources - Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.3 Initiate action to restore Immediately required offsite circuit to OPERABLE status.

B. One required EDG B.1 Suspend movement of Immediately inoperable, irradiated fuel assemblies.

AND B.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND

/

B.3 Initiate action to restore Immediately required EDG to OPERABLE status.

Davis-Besse 3.8.2-2 Amendment 279

AC Sources - Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SIR 3.8.2.1 ----

N OTE ..................

The following SRs are not required to be performed:

SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.13, and SR 3.8.1.14.

For AC sources required to be OPERABLE, the SRs In accordance of Specification 3.8.1, "AC Sources - Operating," with applicable except SR 3.8.1.6, SR 3.8.1.9, and SR 3.8.1.15, are SRs applicable.

Davis-Besse 3.8.2-3 Amendment 279

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 emergency diesel generator (EDG).

APPLICABILITY: When associated EDG is required to be OPERABLE.

ACTIONS

NOT r-- ------------------------------------

Separate Condition entry is allowed for each EDG CONDITION REQUIRED ACTION COMPLETION TIME A. One or more EDGs with A.1 Restore fuel oil level to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months fuel level < 32,000 gal within limits.

and > 26,800 gal in storage tank.

B. One or more EDGs with B.1 Restore lube oil inventory to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months lube oil inventory within limits.

< 260 gal and > 236 gal.

C. One or more EDGs with C.1 Restore fuel oil total 7 days stored fuel oil total particulates to within limits.

particulates not within limit.

D. One or more EDGs with D.1 Restore stored fuel oil 30 days new fuel oil properties properties to within limits.

not within limits.

E. One or more EDGs with E.1 -Restore starting air receiver 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months required starting air pressure to >_210 psig.

receiver pressure

< 210 psig and

> 139 psig.

Davis-Besse 3.8.3-1 Amendment 279

Diesel Fuel Oil; Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 'Declare associated EDG Immediately associated Completion inoperable.

Time of Condition A, B, C, D, or E not met.

OR One or more EDGs with diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains 31 days

> 32,000 gal of fuel.

S R 3.8.3.2 Verify lube oil inventory for each EDG is _ 260 gal. 31 days SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance are tested in accordance with, and maintained within with the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuel Oil Testing Program S R 3.8.3.4 Verify each required EDG air start receiver pressure 31 days is > 210 psig.

SR 3.8.3.5 Check for and remove accumulated water from each 31 days fuel oil storage tank.

Davis-Besse 3.8.3-2 Amendment 279

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 The Train 1 and Train 2 DC electrical power sources shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Restore battery terminal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months battery chargers on one voltage to greater than or train inoperable, equal to the minimum established float voltage.

AND A.2 Verify battery float current Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

< 2 amps.

AND A.3 Restore required battery 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months charger(s) to OPERABLE status.

B. One DC electrical power B.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months source inoperable for power source to reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Davis-Besse 3.8.4-1 Amendment 279

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or 7 days equal to the minimum established float voltage.

SR 3.8.4.2 Verify each required battery charger supplies 18 months

> 475 amps at greater than or equal to the minimum established float voltage for >_8 hours.

OR Verify each required battery charger can recharge the battery to the fully charged state within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SR 3.8.4.3 ---------- .-------

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

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and 24 months maintain in OPERABLE status, the required actual or simulated emergency loads for the design duty cycle when subjected to a battery service test.

Davis-Besse 3.8.4-2 Amendment 279

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 One Train 1 or Train 2 DC electrical power source shall be OPERABLE to support one train of the DC Electrical Power Distribution System required by LCO 3.8.10, "Distribution System - Shutdown."

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS N I r"v-rrC li

.iv !.m ----------------------------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required DC A.1 Suspend movement of Immediately electrical power source irradiated fuel assemblies.

inoperable.

AND A.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.3 Initiate action to restore Immediately required DC electrical power source to OPERABLE status.

Davis-Besse 3.8.5-1 Amendment 279

DC Sources - Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 ----- NOTE -----------------------.....

The following SR is not required to be performed:

SR 3.8.4.3.

For the DC source required to be OPERABLE, the In accordance following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 Davis-Besse 3.8.5-2 Amendment 279

Battery Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters LCO 3.8.6 Battery parameters for the Train 1 and Train 2 batteries shall be within limits.

APPLICABILITY: When associated DC electrical power sources are required to be OPERABLE.

-ACTIONS

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Perform SR 3.8.4.1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with one or more battery cells float voltage AND

2.07 V.

A.2 Perform SR 3.8.6.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.3 Restore affected cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months voltage > 2.07 V.

B. One or more batteries B.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with float current

> 2 amps. AND B.2 Restore battery float current 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to *_2 amps.

Davis-Besse 3.8.6-1 Amendment 279

Battery Parameters 3.8.6 ACTIONS (continued)

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

Required Action C.2 Required Actions C.1 and C.2 are shall be completed if only applicable if electrolyte level electrolyte level was was below the top of plates.

below the top of plates.--------------------

C.1 Restore electrolyte level to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months One or more batteries above top of plates.

with one or more cells electrolyte level less AND than minimum established design C.2 Verify no evidence of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits, leakage.

AND C.3 Restore electrolyte level to 31 days greater than or equal to minimum established design limits.

D. One or more batteries D.1 Restore battery pilot cell 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with pilot cell electrolyte temperature to greater than temperature less than or equal to minimum minimum established established design limits.

design limits.

E. Batteries in redundant E.1 Restore battery parameters 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months trains with battery for batteries in one train to parameters not within within limits.

limits.

Davis-Besse 3.8.6-2 Amendment 279

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Declare associated battery Immediately associated Completion inoperable.

Time of Condition A, B, C, D, or E not met.

OR One or more batteries with one or more battery cells float voltage

< 2.07 V and float current > 2 amps.

OR SR 3.8.6.6 not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 NOTE--------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is < 2 amps. 7 days SR 3.8.6.2 Verify each battery pilot cell voltage is > 2107 V. 31 days SR 3.8.6.3 Verify each battery connected cell electrolyte level is 31 days greater than or equal to minimum established design limits.

SR 3.8.6.4 Verify each battery pilot cell temperature is greater 31 days than or equal to minimum established design limits.

Davis-Besse 3.8.6-3 Amendment 279

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.5 Verify each battery connected cell voltage is 92 days

> 2.07 V.

SR 3.8.6.6 ----------------- NOTE ------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is > 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 the expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity

>_100% of manufacturer's rating Davis-Besse 3.8.6-4 Amendment 279,

Inverters - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters - Operating LCO 3.8.7 The Train 1 and Train 2 inverters shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One inverter inoperable. A.1 ---------- NOTE ------.....---

Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems - Operating" with any 120 VAC vital bus de-energized.

Restore inverter to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

B. Two inverters in one B.1 Restore one inverter to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months train inoperable. OPERABLE status C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Davis-Besse 3.8.7-1 Amendment 279

Inverters - Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify, for each inverter, correct inverter voltage, 7 days frequency, and alignment to the associated 120 VAC vital bus.

Davis-Besse 3.8.7-2 Amendment 279

Inverters - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters - Shutdown LCO 3.8.8 One inverter shall be OPERABLE to support the 120 VAC vital electrical distribution subsystem required by LCO 3.8.10, "Distribution Systems -

Shutdown."

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

-NOTE.

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required inverter A.1 Suspend movement of Immediately inoperable, irradiated fuel assemblies.

AND A.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.3 Initiate action to restore Immediately required inverter to OPERABLE status.

Davis-Besse 3.8.8-1 Amendment 279

Inverters - Shutdown

-3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify, for the required inverter, correct inverter 7 days voltage, frequency, and alignment to the associated 120 VAC vital bus.

Davis-Besse 3.8.8-2 Amendment 279

Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Train 1 and Train 2 AC, DC, and AC vital bus electrical power distribution subsystems shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC ---- NOTE--

electrical power Enter applicable Conditions and distribution subsystems Required Actions of LCO 3.8.4, "DC inoperable. Sources - Operating," for DC sources made inoperable by inoperable power distribution subsystems.

A.1 Restore AC electrical power 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months distribution subsystem(s) to OPERABLE status.

B. One or more AC vital B.I1 Restore AC vital bus(es) to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months buses inoperable. OPERABLE status.

C. One DC electrical power C.A Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months distribution subsystems power distribution inoperable, subsystem to OPERABLE status.

Davis-Besse 3.8.9-1 Amendment 279

Distribution Systems - Operating 3.8.9 ACTIONS (continued)

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

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Two or more electrical E.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to. 7 days required AC, DC, and AC vital bus electrical power distribution subsystems.

Davis-Besse 3.8.9-2 Amendment 279

Distribution Systems - Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portions of AC,'DC, and AC vital bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS I.,U I'r

I'Jt

" r - - -- -- -- -- -- -- -- -- -- - -- -- - -- -- -- -- -- -- -- -- -- -- -- -- -- -- - -

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC, or AC vital bus supported required electrical power feature(s) inoperable.

distribution subsystems inoperable. OR A.2.1 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.3 Initiate actions to restore Immediately required AC, DC, and AC vital bus electrical power distribution subsystems to OPERABLE status.

AND Davis-Besse 3.8.10-1 Amendment 279

Distribution Systems - Shutdown 3.8.10 ACTIONS (continued)

CONDITION REQUIRED ACTION, COMPLETION TIME A. (continued) A.2.4 Declare associated Immediately required decay heat removal subsystem(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to 7 days required AC, DC, and AC vital bus electrical power distribution subsystems.

Davis-Besse 3.8.10-2 Amendment 279

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System (RCS) and the refueling canal shall be maintained within the limit specified in the COLR.

APPLICABILITY: MODE 6.

- .4*IU 17 - -- -- -- - - -- -- - -- - -- -- - - -- -- -- -- --

Only applicable to the refueling canal when connected to the RCS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not A.1 Suspend positive reactivity Immediately within limit, additions.

AND A.2 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months specified in the COLR.

Davis-Besse 3.9.1-1 Amendment 279

Nuclear Instrumentation 3.9.2

. 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range neutron flux monitors shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source A.1 Suspend positive reactivity Immediately range neutron flux additions, except the monitor inoperable, introduction of coolant into the RCS.

AND A.2 Suspend operations that Immediately would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

B. Two required source B.1 Initiate action to restore one Immediately range neutron flux source range neutron flux monitors inoperable, monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Davis-Besse 3.9.2-1 Amendment 279

Nuclear Instrumentation 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s-SR 3.9.2.2- ---------- ----- NOTE -----

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Davis-Besse 3.9.2-2 Amendment 279

Decay Time 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Decay Time LCO 3.9.3 The reactor shall be subcritical for > 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

APPLICABILITY: During movement of irradiated fuel assemblies within the reactor pressure vessel.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor not subcritical A.1 Suspend movement of Immediately for > 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . irradiated fuel assemblies within the reactor pressure vessel.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify reactor subcritical for Ž 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Prior to movement of irradiated fuel assemblies within the reactor pressure vessel Davis-Besse 3.9.3-1 Amendment 279

DHR and Coolant Circulation - High Water Level 3.9.4 3.9 REFUELING OPERATIONS 319.4 Decay Heat Removal (DHR) and Coolant Circulation - High Water Level LCO 3.9.4 One DHR loop shall be OPERABLE and in operation.

I~

PslL J I 1~~

The required DHR loop may be removed from operation for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1, "Boron Concentration."

APPLICABILITY: MODE 6 with the water level _>23 ft above the top of reactor vessel flange.

ACTIONS CONDITI6N REQUIRED ACTION COMPLETION TIME A. DHR loop requirements A.1 Suspend operations that Immediately not met. would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND A.2 Suspend loading irradiated Immediately fuel assemblies in the core.

AND A.3 Initiate action to satisfy Immediately DHR loop requirements.

AND Davis-Besse 3.9.4-1 Amendment 279

DHR and Coolant Circulation - High Water Level 3.9.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Close equipment hatch and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months secure with four bolts.

AND A.5, Close one door in each air 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months lock.

AND A.6 Verify each penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months providing direct access from the containment atmosphere to the outside atmosphere is either closed with a manual or automatic isolation valve, blind flange, or equivalent, or is capable of being closed by a Containment Purge and Exhaust Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one DHR loop is in operation and circulating 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor coolant at a flow rate of > 2800 gpm.

Davis-Besse 3.9.4-2 Amendment 279

DHR and Coolant Circulation - Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Decay Heat Removal (DHR) and Coolant Circulation - Low Water Level LCO 3.9.5 Two DHR loops shall be OPERABLE, and one DHR loop shall be in operation.

- ----- ILJ I ':----------------------- ----- - --------------

1. All DHR pumps may be removed from operation for < 15 minutes when switching from one train to another provided:

a. The core outlet temperature is maintained > 10 degrees F below saturation temperature;

b. No operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1, "Boron Concentration;" and

c. No draining operations to further reduce RCS water volume are permitted.

2. One required DHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided that the other DHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than required A.1 Initiate action to restore Immediately number of DHR loops DHR loop to OPERABLE OPERABLE. status.

OR A.2 Initiate action to establish Immediately

> 23 ft of water above the top of reactor vessel flange.

Davis-Besse 3.9.5-1 Amendment 279

DHR and Coolant Circulation - Low Water Level 3.9.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No DHR loop B.1 Suspend operations that Immediately OPERABLE or in would cause introduction of operation. coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND B.2 Initiate action to restore one Immediately DHR loop to OPERABLE status and to operation.

AND B.3 Close equipment hatch and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months secure with four bolts.

AND B.4 Close one door in each air 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months lock.

AND j

B.5 Verify each penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months providing direct access from the containment atmosphere to the outside atmosphere is either closed with a manual or automatic isolation valve, blind flange, or equivalent, or is capable of being closed by a Containment Purge and Exhaust Isolation System.

Davis-Besse 3.9.5-2 Amendment 279

DHR and Coolant Circulation - Low Water Level 3.9.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one DHR loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.5.2 ----- ...----------.. .-------NOTE -----------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

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

Davis-Besse 3.9.5-3 Amendment 279

Refueling Canal Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Canal Water Level LCO 3.9.6 Refueling canal water level shall be maintained > 23 ft above the top of the reactor vessel flange.

APPLICABILITY: During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling canal water A.1 Suspend movement of Immediately level not within limit, irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling canal water level is > 23 ft above the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months top of reactor vessel flange.

Davis-Besse 3.9.6-1 Amendment 279

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The Davis-Besse Nuclear Power Station is located on Lake Erie in Ottawa County, Ohio, approximately six miles northeast from Oak Harbor, Ohio and 21 miles east from Toledo, Ohio. The exclusion area boundary has a minimum radius of 2400 feet from the center of the plant.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 177 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy M5 or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U02) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used.

Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rods The reactor core shall contain 53 CONTROL RODS and 8 APSRs. The material shall be silver indium cadmium for the CONTROL RODS and inconel for the APSRs, as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel pool storage racks are designed and shall be maintained with:

a. keff<* 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

b. A nominal 9.22 inch center to center distance between fuel assemblies; and

c. Fuel assemblies stored in the spent fuel storage racks in accordance with LCO 3.7.16.

Davis-Besse 4.0-1 Amendment 279

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;

b. keff - 0.95 iffully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; C. keff < 0.98 when immersed in a hydrogenous mist, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and

d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below 9 feet above the top of the spent fuel storage racks.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1624 fuel assemblies.

Davis-Besse 4.0-2 Amendment 279

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affects 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, 3, or 4, an individual with an active Senior Operator 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 5 or 6, an individual with an active Senior Operator license or Operator license shall be designated to assume the control room command function.

Davis-Besse 5.1-1 Amendment 279

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, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the UFSAR.

b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a. A non-licensed operator shall be assigned if the reactor contains fuel and an additional non-licensed operator shall be assigned ifthe reactor is operating in MODES 1, 2, 3, or 4;

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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is.taken to restore the shift crew composition to within the minimum requirements; 5.2-1 Amendment 279 Davis-Besse 5.2-1 Amendment 279

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

c. A radiation protection- technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position;

d. Administrative controls shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g.,

licensed Senior Operators, licensed Operators, health physicists, auxiliary operators, and key maintenance personnel).

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 designee, in accordance with approved administrative procedures, and with 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 such that the individual overtime shall be reviewed monthly by the plant manager or designee to ensure that excessive hours have not been assigned;

e. The operations manager shall either hold or have held a Senior Operator license. The assistant operations manager shall hold a Senior Operator license for the Davis-Besse Nuclear Power Station; and

f. When the reactor is operating in MODE 1, 2, 3, or 4 an individual shall provide advisory technical support to the unit operations shift 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.

Davis-Besse 5.2-2 Amendment 279

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the radiation protection manager and the operations manager. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The operations manager shall be qualified as required by Specification 5.2.2.e.

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Operator and a licensed Operator are those individuals who, in addition to meeting the requirements of Specification 5.3.1, perform the functions described in 10 CFR 50.54(m).

Davis-Besse 5.3-1 Amendment 279

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and 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.

Davis-Besse *5.4-1 Amendment 279

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 5.6.1 and Specification 5.6.2.

c. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

a) Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s); and b) A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

2. Shall become effective after the approval of the plant manager; and

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire 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.

Davis-Besse 5.5-1 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include makeup, letdown, seal injection, seal return, low pressure injection, containment spray, high pressure injection, waste gas, primary sampling, and reactor coolant drain systems. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at least once per 24 months.

The provisions of SR 3.0.2 are applicable.

5.5.3 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 the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20;

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 I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days; Davis-Besse 5.5-2 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.3 Radioactive Effluent Controls Program (continued)

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 I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas beyond the site boundary shall be in accordance with Appendix B, Table 2, Column 1 to 10 CFR 20;

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 I; i.. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program Surveillance Frequencies.

5.5.4 Reactor Vessel Internals Vent Valves Program A program shall be established to implement the testing of the reactor vessel internals vent valves every 24 months as follows:

a. Verify by visual inspection that the valve body and valve disc exhibit no abnormal degradation;

b. Verify the valve is not stuck in an open position; and

c. Verify by manual actuation that the valve is fully open when a force of

<400 lbs is applied vertically upward.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Vessel Internals Vent Valves Program test Frequencies.

5-5-3 Amendment 279 Davis-Besse

-Davis-Besse 5.5-3 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Allowable Operating Transient Cycles Program This program provides controls to track the UFSAR, Section 5, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel. Inservice inspection of each reactor coolant pump flywheel shall be performed every 10 years. The inservice inspection shall be either an ultrasonic examination of the volume from the inner bore of the flywheel to the circle of one-half the outer radius, or a surface examination of exposed surfaces of the disassembled flywheel. The recommendations delineated in Regulatory Positions C.4.b(3), (4), and (5) of Regulatory Guide 1.14, Revision 1, August 1975, shall apply.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program Surveillance Frequency.

5.5.7 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves.

a. Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Codes) and applicable Addenda as follows:

ASME OM Code and applicable Required Frequencies for Addenda terminology for inservice performing inservice testing testing activities activities Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 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 and other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program 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 OM Code shall be construed to supersede the requirements of any TS.

Davis-Besse 5.5-4 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following provisions:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging or repair of tubes. Condition monitoring assessments shall be conducted during each

.outage during which the SG tubes are inspected, plugged, or repaired to confirm that the performance criteria are being met.

b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.

1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied .to the design basis accident primary-to-secondary pressure differentials.

Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 1 gpm per SG except during, a steam generator tube rupture.

5.5-5 Amendment 279 Davis-Besse 5.5-5 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Proqram (continued)

3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE."

c. Provisions for SG tube repair criteria:

1. Tubes found by inservice inspection to contain flaws, in a region of the tube that contains no repair, with a depth equal to or exceeding 40% of the nominal tube wall thickness shall be plugged or repaired;

2. Sleeves found by inservice inspection to contain flaws, in a region of the sleeve that contains no sleeve joint, with a depth equal to or exceeding 40% of the nominal sleeve wall thickness shall be plugged*

3. Tubes with a flaw, in either parent tube or the sleeve, within a sleeve to tube joint shall be plugged; and

4. Tubes with a flaw in a repair roll shall be plugged.

d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube repair criteria. The tube-to-tubesheet weld is not part of the tube. For tubes that have undergone repair rolling, the tube and tube roll, outboard of the new roll area in the tube sheet, can be excluded from inspections because it is no longer part of the pressure boundary once the repair roll is installed. For tubes that have undergone sleeving repairs, the segment of the parent tube between the upper-most sleeve roll and the top of the middle sleeve roll can be excluded from inspection because it is no longer part of the pressure boundary once the sleeve is installed. In addition to meeting the requirements of d.1 through d.5 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. An assessment of degradation shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the first refueling outage.

following SG replacement.

Davis-Besse 5.5-6 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued)

2. Inspect 100% of the tubes at sequential periods of 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. No SG shall operate for more than 24 effective full power months or one refueling outage (whichever is less) without being inspected.

3. If crack indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever is less). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

4. During each periodic SG tube inspection, inspect 100% of the tubes that have been repaired by the repair roll process. This special inspection shall be limited to the repair roll joint and the roll transitions of the roll repair.

5. Inspect peripheral tubes in the vicinity of the secured internal auxiliary feedwater header between the. upper tube sheet and the 15th tube support plate during each periodic SG tube inspection. The tubes selected for inspection shall represent the entire circumference of the steam generator and shall total at least 150 peripheral tubes.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

f. Provisions for SG tube repair methods. Steam generator tube repair methods shall provide the means to reestablish the RCS pressure boundary integrity of SG tubes without removing the tube from service. For the purposes of these Specifications, tube plugging is not a repair. All acceptable tube repair methods are listed below.

1. Sleeving in accordance with Topical Report BAW-2120P.

2. Repair rolling in accordance with Topical Report BAW-2303P, Revision 4. The new roll area must be free of flaws in order for the repair to be considered acceptable.

5.5-7 Amendment 279 Davis-Besse Davis-Besse 5.5-7 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued)

g. Special visual inspections: Visual inspections of the secured internal auxiliary feedwater header, header to shroud attachment welds, and the external header thermal sleeves shall be performed on each SG through the auxiliary feedwater injection penetrations. These inspections shall be performed during the third period of each 10 year Inservice Inspection Interval (ISI).

5.5.9 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation. The program shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables;

b. Identification of the procedures used to measure the values of the critical variables;

c. Identification of process sampling points;

d. Procedures for the recording and management of data;

e. Procedures defining corrective actions for all off control point chemistry conditions; and

f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

5.5.10 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of safety related filter ventilation systems in accordance with Regulatory Guide 1.52, Revision 2, ANSI/ASME N510-1980, and ASTM D 3803-1989.

a. Demonstrate for each of the safety related systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 1.0% when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSI/ASME N510-1980 at the system flowrate specified below.

Safety Related Ventilation System Flowrate (cfm)

Station Emergency Ventilation System (EVS) > 7200 and < 8800 Control Room Emergency Ventilation System > 2970 and < 3630 (CREVS)

Davis-Besse 5.5-8 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (continued)

b. Demonstrate for each of the safety related systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 1.0%

when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSI/ASME N510-1980 at the system flowrate specified below.

Safety Related Ventilation System Flowrate (cfm)

Station EVS > 7200 and < 8800 CREVS -2970 and <3630

c. Demonstrate for each of the safety related systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30°C (86 0 F) and the relative humidity (RH) specified below.

Safety Related Ventilation System Penetration (%) RH Station EVS

2.5 95 CREVS < 2.5 70

d. Demonstrate for each of the safety related systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSI/ASME N510-1980 at the system flowrate specified below.

Delta P Safety Related Ventilation System (inches wq) Flowrate (cfm)

Station EVS <6 > 7200 and < 8800 CREVS < 4.4 > 2970 and 5 3630 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas System and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

Davis-Besse 5.5-9 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Waste Gas System and a surveillance program to ensure the limits are maintained.

Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion); and

b. A surveillance program to ensure that the quantity of radioactivity contained in each outdoor liquid storage tank that is not surrounded by liners, dikes, or walls, capable of holding the tank's contents and that does not have tank overflows and surrounding* area drains connected to the Liquid 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 tank's 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.

5.5.12 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. An API gravity or an absolute specific gravity within limits;

2. A flash point and kinematic viscosity within limits for ASTM 2D fuel oil; and

3. A clear and bright appearance with proper color, or a water and sediment content within limits;

b. Within 31 days following addition of the new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in a.,

above, are within limits for ASTM 2D fuel oil; and

c. Total particulate concentration of the fuel oil is _<10 mg/I when tested every 31 days.

Davis-Besse 5.5-10 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Diesel Fuel Oil Testing Program (continued)

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program testing Frequencies.

5.5.13 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the updated UFSAR 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 UFSAR.

d. Proposed changes that meet the criteria of Specification 5.5.13.b above shall be reviewed and approved by theNRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e).

5.5.14 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.

a. The SFDP shall contain the following:

1. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

2. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists; Davis-Besse 5.5-11 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Safety Function Determination Program (continued)

3. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

4. Other appropriate limitations and remedial or compensatory actions.

b. A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power, or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable; and

1. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

2. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or.

3. A required system redundant to the support system(s) for the supported systems described in Specifications 5.5.14.b.1 and 5.5.14.b.2 above is also inoperable.

c. The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.15 Containment Leakage Rate Testing Program

a. A program shall establish 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 exceptions:

1. A reduced duration Type A test may be performed using the criteria and Total Time method specified in Bechtel Topical Report BN-TOP-1, Revision 1.

Davis-Besse 5.5-12 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Containment Leakage Rate Testing Program (continued)

2. The fuel transfer tube blind flanges (containment penetrations 23 and

24) will not be eligible for extended test frequencies. Their Type B, test frequency will remain at 30 months. However, as-found testing will not be required.

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 38 psig.

c. The maximum allowable containment leakage rate, La, at Pa, shall be 0.50% of containment air weight per day.

d. Leakage rate acceptance criteria are:

1. Containment leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests and < 0.75 La for Type A tests.

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage rate is _ 0.015 La when tested at >_Pa.

b) For each door, leakage rate is < 0.01 La when the volume between the door seals is pressurized to > 10 psig.

e. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

5.5.16 Battery Monitoring and Maintenance Program This Program provides for battery restoration and maintenance, including the following:

a. Actions to restore battery cells with float voltage < 2.13 V;

b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates; and

c. Actions to verify that the remaining cells are > 2.07 V when a pilot cell or cells have been found to be < 2.13 V.

5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE Davis-Besse 5-5-13 Amendment 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Control Room Envelope Habitability Program (continued) occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary;

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance;

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Section C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0;

d. Measurements, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVS, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary;

e. The quantitative limits on unfiltered air leakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in Specification 5.5.17.c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences.

Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis; and

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by Specifications 5.5.17.c and 5.5.17.d, respectively.

Davis-Besse 5.5-14 Amendment 279

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Annual Radioloqical Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

5.6.3 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. SL 2.1.1.1, "Reactor Core Safety Limits";

2. LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";

3. LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";

4. LCO 3.1.7, "Position Indicator Channels," (SR 3.1.7.1 limits);

Davis-Besse 5.6-1 Amendment 279

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued)

5. LCO 3.1.8, "PHYSICS TEST Exceptions - MODE 1";

6. LCO 3.1.9, "PHYSICS TEST Exceptions - MODE 2";

7. LCO 3.2.1, "Regulating Rod Insertion Limits";

8. LCO 3.2.2, "AXIAL POWER SHAPING ROD (APSR) Insertion Limits";

9. LCO 3.2.3, "AXIAL POWER IMBALANCE Operating Limits";

10. LCO 3.2.4, "QUADRANT POWER TILT (QPT)";

11. LCO 3.2.5, "Power Peaking Factors";

12. LCO 3.3.1,"Reactor Protection System (RPS) Instrumentation,"

Function 8 (Flux - AFlux - Flow) Allowable Value; and

13. LCO 3.9.1, "Boron Concentration."

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, as described in BAW-10179P-A, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," or any other new NRC approved analytical methods used to determine core operating limits that are not yet referenced in the applicable approved revision of BAW-10179P-A. The applicable approved revision number for BAW-10179P-A at the time of the reload analyses are performed shall be identified in the CORE OPERATING LIMITS REPORT (COLR). The COLR shall also list any new NRC approved analytical methods used to determine core operating limits that are not yet referenced in the applicable approved revision of BAW-101 79P-A.

c. As described in reference documents listed in accordance with the instructions given above, when an initial assumed power level of 102% of RTP is specified in a previously approved method, an actual value of 100.37% of RTP may be used when the input for reactor thermal power measurement of feedwater mass flow and temperature is from the Ultrasonic Flow Meter. The following NRC approved documents are applicable to the use of the Ultrasonic Flow Meter with a 0.37%

measurement uncertainty:

1. Caldon Inc. Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM4TM System," Revision 0, dated March, 1997.

5.6-2 Amendment 279 Davis-Besse 5.6-2 Amendment 279

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued)

2. Caldon Inc. Engineering Report-157P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMq1TM or LEFM CheckPlusTM System," Revision 5, dated October, 2001.

d. 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 System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

e. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.4 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

1. LCO 3.4.3, "RCS Pressure and Temperature (PIT) Limits."

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. BAW-10046A, Rev. 2, "Methods of Compliance with Fracture Toughness and Operational Requirements of 10 CFR 50 Appendix G,"

June 1986.

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

5.6.5 Post Accident Monitorinq Report When a report is required by Condition B or F of LCO 3.3.17, "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.

5.6-3 Amendment 279 Davis-Besse 5.6-3 Amendment 279

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.8, "Steam Generator (SG) Program." The report shall include:

a. The scope of inspections performed on each SG;

b. Active degradation mechanisms found;

c. Nondestructive examination techniques utilized for each degradation mechanism;

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications;

e. Number of tubes plugged or repaired during the inspection outage for each active degradation mechanism;

f. Total number and percentage of tubes plugged or repaired to date;

g. The results of condition monitoring, including the results of tube pulls and in-situ testing;

h. The effective plugging percentage for all plugging and tube repairs in each SG; and

i. Repair method utilized and the number of tubes repaired by each repair method.

5.6.7 Remote Shutdown System Report When a report is required by Condition C of LCO 3.3.18, "Remote Shutdown System," a report shall be submitted within the following 30 days. The report shall outline the action taken, the cause of the inoperability, and the plans and schedule for restoring the control circuit or transfer switch of the Function to OPERABLE status.

Davis-Besse 5.6-4 Amendment 279

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 (whether alone or in a group) entering such an area shall possess one of the following:

1. A radiation monitoring device that continuously displays radiation dose rates in the area;

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;

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area; or

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, Davis-Besse 5.7-1 Amendment 279

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

(i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door, gate, or other barrier that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee; and

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.

Davis-Besse 5.7-2 Amendment 279

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 Hiqh 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)

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 (whether alone or in a group) entering such an area shall possess one of the following:

1. 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;

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area; or

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under 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 Specifications 5.7.2.d.2 and 5.7.2.d.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.

5.7-3 Amendment 279 Davis-Besse 5.7-3 Amendment 279

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)

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.

Davis-Besse 5.7-4 Amendment 279

v t e Letter Sequence Other
TAC:MD6398, Increase Flexibility in Mode Restraints, Addition of LCO 3.0.8, Inoperability of Snubbers, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec, Changes to Reflect Revision of 10 CFR 50.55A, Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Correct Example 1.4-1, Containment Structural Integrity, TSTF-28, Correct LCO 3.0.6 Bases, Add Restriction for Lowest LOOP Tave During Mode 2 Physics Testing (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance, Acceptance, Acceptance Supplement, Supplement Administration Meeting, Meeting, Meeting Questions 18 June 2008 20 June 2008 Answers 23 July 2008 3 September 2008 Results Approval Other: L-08-161, Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.0, L-08-241, Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website, Section 3.5 RAIs, L-08-338, Copy of Improved Technical Specifications (ITS), L-08-378, Implementation of Improved Technical Specification Amendment No. 279, ML073531253, ML081350505, ML082000451, ML082270661, ML082270662, ML082270663, ML082270664, ML082270665, ML082270666, ML082270667, ML082270669, ML082270670, ML082600577, ML082840099, ML082900630, ML082900882, ML082910125
MONTHYEAR2008-02-04 [Table View]

L-08-338, Copy of Improved Technical Specifications (ITS)

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SUBJECT:

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