Text

Certification of Technical Specification & Technical Specification Bases Pages (License Amendment) as Part of Conversion to Improved Standard Technical Specifications
	ML021750467
Person / Time
Site:	FitzPatrick
Issue date:	06/12/2002
From:	Ted Sullivan; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML021750467 (180)
	v • d • e

-7Entey Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 June 12, 2002 JAFP-02-0125 T.A. Sullivan Vice President, Operations-JAF United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop O-P1-17 Washington, D.C. 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Certification of Technical Specification and Technical Specification Bases Pages (License Amendment) as part of the Conversion to Improved Standard Technical Specifications

References:

see last page of letter

Dear Sir,

This letter transmits a complete set of Technical Specification (TS) and TS Bases pages, which incorporates the initial TS submittal and all subsequent revisions (as provided in the list of references) for the conversion of the current Technical Specifications (CTS) to the Improved Technical Specifications (ITS), consistent with the Improved Standard Technical Specifications (NUREG-1433, Revision 1). Per the NRC Staff's request in Reference 9, Attachment 1 contains a certification that the TS and TS Bases provided in Attachment 2 are consistent with the original conversion submittal and associated revisions.

There are no new commitments contained in this letter. Should you have any questions, please contact Mr. Andrew Halliday at (315) 349-6055.

Very Truly Yours, Vice President, Operations - JAF Attachments: 1) Certification of the TS and TS Bases

2) Complete Set of TS and TS Bases Pages kocA

United States Nuclear Regulatory Commission Attn: Document Control Desk

Subject:

Certification of Technical Specification and Technical Specification Bases Pages (License Amendment) as part of the Conversion to Improved Standard Technical Specifications Page -2 cc:

Regional Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Guy Vissing, Project Manager Project Directorate I Division of Licensing Project Management U. S. Nuclear Regulatory Commission Mail Stop 8C2 Washington, DC 20555 Mr. N. B. Le U. S. Nuclear Regulatory Commission Mail Stop O-7H3 Washington, DC 20555 P. 0. Box 134 Resident Inspector's Office James A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission P. 0. Box 134 Lycoming, NY 13093 Mr. William M. Flynn New York State Energy Research and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, New York 12203-6399 Mr. Paul Eddy NYS Department of Public Service 3 Empire Plaza Albany, New York 12223 Mr. William D. Beckner, Chief Technical Specifications Branch U. S. Nuclear Regulatory Commission Mail Stop O-7H3 Washington, DC 20555

United States Nuclear Regulatory Commission Attn: Document Control Desk

Subject:

Certification of Technical Specification and Technical Specification Bases Pages (License Amendment) as part of the Conversion to Improved Standard Technical Specifications Page -3

References:

1.

NYPA letter, J. Knubel to USNRC Document Control Desk, Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications (JPN-99-008), dated March 31, 1999 (TAC No. MA5049)

2.

NYPA letter, J. Knubel to USNRC Document Control Desk, Revision B to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications (JPN-99-018), dated June 1, 1999

3.

NYPA letter, Michael J. Colomb to USNRC Document Control Desk, Revision C to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications (JAFP-99-0278), dated October 14, 1999

4.

Entergy Nuclear Northeast letter, T. A. Sullivan to USNRC Document Control Desk, Revisions D, E, F, G, and H to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications (JAFP-01 0133), dated May 31, 2001

5.

Entergy Nuclear Northeast letter, T. A. Sullivan to USNRC Document Control Desk, Revision I to Proposed Technical Specification Change (License Amendment)

Conversion to Improved Standard Technical Specifications (JAFP-01-0234), dated October 18, 2001

6.

Entergy Nuclear Northeast letter, T. A. Sullivan to USNRC Document Control Desk, James A. FitzPatrick (JAF) Improved Technical Specifications (ITS) Submittal (JAFP-02 0029), dated February 6, 2002

7.

Entergy Nuclear Northeast letter, T. A. Sullivan to USNRC Document Control Desk, Revision J to Proposed Technical Specification Change (License Amendment)

Conversion to Improved Standard Technical Specifications (JAFP-02-0098), dated April 26, 2002

8.

Entergy Nuclear Northeast letter, T. A. Sullivan to USNRC Document Control Desk, Revision K to Proposed Technical Specification Change (License Amendment)

Conversion to Improved Standard Technical Specifications (JAFP-02-0124), dated June 11, 2002

9.

USNRC to Mr. Michael Kansler, Entergy Nuclear Operations, Inc., Draft Safety Evaluation Regarding Proposed Conversion to Improved Standard Technical Specifications - James A. FitzPatrick Nuclear Power Plant, dated November 7, 2001

ATTACHMENT 1

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant

) )

Docket No. 50-333

)

CERTIFICATION Entergy Nuclear Operations, Inc. certifies that the attached TS and TS Bases pages (Attachment 2), are consistent with the initial ITS submittal and all subsequent revisions (as provided in the list of references) for the conversion of the CTS to the ITS.

This application is filed in accordance with Section 10 CFR 50.90 of the Nuclear Regulatory Commission's regulations.

This application for amendment to the FitzPatrick Technical Specifications is consistent with the Improved Standard Technical Specifications (ISTS) in NUREG-1433, Revision 1, dated April 1995. The proposed license amendment request was prepared considering the guidance of Nuclear Energy Institute (NEI) NEI 96-06, "Improved Technical Specifications Conversion Guidance," dated August 1996.

Entergy Nuclear Operations, Inc.

T. A. Sullivan Vice President, Operations-JAF STATE OF NEW YORK COUNTY OF OSWEGO Subscribed and sworn to before me this 4j&day ofJ-k1i2002.

Notary Public Barbafa V. Page Notary Pubic-Stte of WY Cam,. E~q~re Wo LG

ATTACHMENT 2

TABLE OF CONTENTS 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 3.2.4 USE AND APPLICATION Definitions Logical Connectors........................

Completion Times..........................

Frequency SAFETY LIMITS (SLs)

SLs SL Violations LIMITING CONDITION FOR OPERATION (LCO)

APPLICABILITY.

SURVEILLANCE REQUIREMENT (SR) APPLICABILITY REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)

Reactivity Anomalies......

Control Rod OPERABILITY Control Rod Scram Times Control Rod Scram Accumulators.................

Rod Pattern Control Standby Liquid Control (SLC) System Scram Discharge Volume (SDV)

Vent and Drain Valves POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

MINIMUM CRITICAL POWER RATIO (MCPR)

LINEAR HEAT GENERATION RATE (LHGR)..............

Average Power Range Monitor (APRM)

Gain and Setpoint INSTRUMENTATION Reactor Protection System (RPS) Instrumentation Source Range Monitor (SRM)

Instrumentation........

Control Rod Block Instrumentation Feedwater and Main Turbine High Water Level Trip Instrumentation Post Accident Monitoring (PAM)

Instrumentation.

Remote Shutdown System......................

Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation Emergency Core Cooling System (ECCS)

Instrumentation Reactor Core Isolation Cooling (RCIC) System Instrumentation Primary Containment Isolation Instrumentation Secondary Containment Isolation Instrumentation Control Room Emergency Ventilation Air Supply (CREVAS)

System Instrumentation Condenser Air Removal Pump Isolation Instrumentation Emergency Service Water (ESW)

System Instrumentation (continued)

Amendment 274 1.1-1 1.2-1 1.3-1 1.4-1 2.0-1 2.0-1 3.0-1 3.0-3 3.1.1-1 3.1.2-1 3.1.3-1 3.1.4-1 3.1.5-1 3.1.6-1 3.1.7-1 3.1.8-1 3.2.1-1 3.2.2-1 3.2.3-1 3.2.4-1 3.3.1.1-1 3.3.1.2-1 3.3.2.1-1 3.3.2.2-1 3.3.3.1-1 3.3.3.2-1 3.3.4.1-1 3.3.5.1-1 3.3.5.2-1 3.3.6.1-1 3.3.6.2-1 3.3.7.1-1 3.3.7.2-1 3.3.7.3-1 3.3 3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.2 3.3.3.1 3.3.3.2 3.3.4.1 3.3.5.1 3.3.5.2 3.3.6.1 3.3.6.2 3.3.7.1 3.3.7.2 3.3.7.3 i

JAFNPP

TABLE OF CONTENTS 3.3 3.3.8.1 3.3.8.2 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.5 3.5.1 3.5.2 3.5.3 3.6 3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 3.6.1.6 3.6.1.7 3.6.1.8 3.6.1.9 3.6.2.1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.3.1 3.6.3.2 3.6.4.1 3.6.4.2 3.6.4.3 Primary Containment Primary Containment Air Locks Primary Containment Isolation Valves (PCIVs).......

Drywell Pressure..............................

Drywell Air Temperature Reactor Building-to-Suppression Chamber Vacuum Breakers Suppression Chamber-to-Drywell Vacuum Breakers.

Main Steam Leakage Collection (MSLC)

System Residual Heat Removal (RHR)

Containment Spray System.

Suppression Pool Average Temperature............

Suppression Pool Water Level..............

Residual Heat Removal (RHR) Suppression Pool Cooling Drywell-to-Suppression Chamber Differential Pressure Primary Containment Oxygen Concentration.........

Containment Atmosphere Dilution (CAD)

System.......

Secondary Containment..................

Secondary Containment Isolation Valves (SCIVs)

Standby Gas Treatment (SGT) System..............

PLANT SYSTEMS Residual Heat Removal Service Water (RHRSW)

System Emergency Service Water (ESW)

System and Ultimate Heat Sink (UHS) 3.3.8.1-1 3.3.8.2-1 INSTRUMENTATION (continued)

Loss of Power (LOP)

Instrumentation Reactor Protection System (RPS) Electric Power Monitoring REACTOR COOLANT SYSTEM (RCS)

Recirculation Loops Operating Jet Pumps Safety/Relief Valves (SIRVs)................

RCS Operational LEAKAGE RCS Leakage Detection Instrumentation RCS Specific Activity Residual Heat Removal (RHR)

Shutdown Cooling System-Hot Shutdown.

Residual Heat Removal (RHR)

Shutdown Cooling System-Cold Shutdown RCS Pressure and Temperature (P/T) Limits EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM ECCS-Operating ECCS -Shutdown........................

RCIC System CONTAINMENT SYSTEMS 3.4.7-1 3.4.8-1 3.4.9-1 3.5.1-1 3.5.2-1 3.5.3-1 3.6.1.1-1 3.6.1.2-1 3.6.1.3-1 3.6.1.4-1 3.6.1.5-1 3.6.1.6-1 3.6.1.7-1 3.6.1.8-1 3.6.1.9-1 3.6.2.1-1 3.6.2.2-1 3.6.2.3-1 3.6.2.4-1 3.6.3.1-1 3.6.3.2-1 3.6.4.1-1 3.6.4.2-1 3.6.4.3-1 3.7.1-1 3.7.2-1 (continued)

Amendment 274 3.4.1-1 3.4.2-1 3.4.3-1 3.4.4-1 3.4.5-1 3.4.6-1 3.7 3.7.1 3.7.2 i i JAFNPP

TABLE OF CONTENTS 3.7 PLANT SYSTEMS (continued) 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS)

System 3.7.3-1 3.7.4 Control Room Air Conditioning (AC)

System.......

3.7.4-1 3.7.5 Main Condenser Steam Jet Air Ejector (SJAE) Offgas 3.7.5-1 3.7.6 Main Turbine Bypass System....................

3.7.6-1 3.7.7 Spent Fuel Storage Pool Water Level..............

3.7.7-1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating........

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-Operating........

3.8.4-1 3.8.5 DC Sources-Shutdown........................

3.8.5-1 3.8.6 Battery Cell Parameters........

3.8.6-1 3.8.7 Distribution Systems-Operating.....

3.8.7-1 3.8.8 Distribution Systems-Shutdown................

3.8.8-1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks................

3.9.1-1 3.9.2 Refuel Position One-Rod-Out Interlock...........

3.9.2-1 3.9.3 Control Rod Position....

3.9.3-1 3.9.4 Control Rod Position Indication.....

3.9.4-1 3.9.5 Control Rod OPERABILITY -Refueling.............

3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV)

Water Level........

3.9.6-1 3.9.7 Residual Heat Removal (RHR) -High Water Level 3.9.7-1 3.9.8 Residual Heat Removal (RHR) -Low Water Level........

3.9.8-1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation 3.10.1-1 3.10.2 Reactor Mode Switch Interlock Testing...........

3.10.2-1 3.10.3 Single Control Rod Withdrawal -Hot Shutdown........

3.10.3-1 3.10.4 Single Control Rod Withdrawal -Cold Shutdown........

3.10.4-1 3.10.5 Single Control Rod Drive (CRD) Removal-Refueling 3.10.5-1 3.10.6 Multiple Control Rod Withdrawal-Refueling.........

3.10.6-1 3.10.7 Control Rod Testing-Operating................

3.10.7-1 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling...........

3.10.8-1 4.0 DESIGN FEATURES 4.1 Site Location........

4.0-1 4.2 Reactor Core............................

4.0-1 4.3 Fuel Storage............................

4.0-2 (continued)

Amendment 274 JAFNPP iii

TABLE OF CONTENTS (continued) 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility.........

5.1-1 5.2 Organization.....

5.2-1 5.3 Plant Staff Qualifications....................

5.3-1 5.4 Procedures..........

5.4-1 5.5 Programs and Manuals........................

5.5-1 5.6 Reporting Requirements.......................

5.6-1 5.7 High Radiation Area........

5.7-1 Amendment 274 JAFNPP iv

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

---N O T E OTE..

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

Term Definition ACTIONS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

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

The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.

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.

A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation.

This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

(con-t-i-nued)

Amendment 274 JAFNPP 1.1-1

Definitions 1.1 1.1 Definitions (continued)

CHANNEL FUNCTIONAL TEST CORE ALTERATION 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 channel steps.

CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a.

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

and

b.

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

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

The COLR is the plant specific document that provides cycle specific parameter limits for the current reload cycle.

These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5.

Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 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 International Commission on Radiological Protection Publication 30 (ICRP-30),

"Limits for Intake by Workers," or in NRC Regulatory Guide 1.109, Rev. 1, 1977.

CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT 1-131 (continued)

Amendment 274 1.1-2 JAFNPP

Definitions 1.1 1.1 Definitions (continued)

ISOLATION INSTRUMENTATION RESPONSE TIME LEAKAGE The ISOLATION INSTRUMENTATION RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valve receives the isolation signal (e.g., de energization of the main steam isolation valve solenoids).

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

In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

LEAKAGE shall be:

a.

Identified LEAKAGE

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

2.

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

b.

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

c.

Total LEAKAGE Sum of the identified and unidentified LEAKAGE;

d.

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

(conti-nued)T Amendment 274 1.1-3 JAFNPP

Definitions 1.1 1.1 Definitions (continued)

LINEAR HEAT GENERATION RATE (LHGR)

LOGIC SYSTEM FUNCTIONAL TEST MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD)

MINIMUM CRITICAL POWER RATIO (MCPR)

MODE OPERABLE - OPERABILITY The LHGR shall be the heat generation rate per unit length of fuel rod.

It is the integral of the heat flux over the heat transfer area associated with the unit length.

A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

The MFLPD shall be the largest value of the fraction of limiting power density in the core.

The fraction of limiting power density shall be the LHGR existing at a given location divided by the specified LHGR limit for that bundle type.

The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each type of fuel.

The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

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

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

(continued)

Amendment 274 1.1-4 JAFNPP

Definitions 1.1 1.1 Definitions (continued)

RATED THERMAL POWER (RTP)

REACTOR PROTECTION SYSTEM (RPS)

RESPONSE

TIME SHUTDOWN MARGIN (SDM)

STAGGERED TEST BASIS THERMAL POWER RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2536 MWt.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.

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

In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

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

a.

The reactor is xenon free;

b.

The moderator temperature is 68 0 F; and

c.

All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

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

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

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

core heat (continued)

Amendment 274 JAFNPP 1.1-5

Definitions 1.1 1.1 Definitions (continued)

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

RESPONSE TIME consists

a.

The time from initial movement of the main turbine stop valve or control valve until 80%

of the assumed turbine bypass capacity is established; and

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

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

Amendment 274 JAFNPP 1.1-6

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

MODES REACTOR MODE AVERAGE REACTOR MODE TITLE SWITCH POSITION COOLANT TEMPERATURE (OF) 1 Power Operation Run NA 2

Startup Refuel(a) or Startup/Hot NA Standby 3

Hot Shutdown(a)

Shutdown

> 212 4

Cold Shutdown(a)

Shutdown

212 5

Refueling(b)

Shutdown or Refuel NA (a)

All reactor vessel head closure bolts fully tensioned.

(b)

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

Amendment 274 1.1-7 JAFNPP

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 con-stitutes-logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions.

These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action.

The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

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

When logical connectors are used to state a 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.

(continued)

Amendment 274 JAFNPP 1.2-1

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, botfi-equired Actions A.1 and A.2 must be completed.

(continued)

Amendment 274 1.2-2 JAFNPP

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 thFree 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 c--oices, only one of which must be performed.

Amendment 274 1.2-3 JAFNPP

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 plant.

The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met.

Specified with each stated Condition are Required Action(s) and Completion Times(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action.

It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the plant 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 plant 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 divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated.

The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

(continued)

Amendment 274 JAFNPP 1.3-1

Completion Times 1.3 1.3 Completion Times DESCRIPTION However, when a subsequent division, subsystem, component, (continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.

To apply this Completion Time extension, two criteria must first be met.

The subsequent inoperability:

a.

Must exist concurrent with the first inoperability; and

b.

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

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

a.

The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 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 extension does not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry.

These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero."

This modified "time zero" may be expressed as a repetitive time (i.e.,

"once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery.

Example 1.3-3 illustrates one use of this type of Completion Time.

The 10 day Completion Time specified for Condition A and B in Example 1.3-3 may not be extended.

(continued)

Amendment 274 Completion Times JAFNPP 1.3-2

Completion Times 1.3 1.3 Completion Times (continued)

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

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

Condition B has two Required Actions.

Each Required Action has its own separate Completion Time.

Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-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 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B was entered.

If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching MODE 4 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 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

Amendment 274 JAFNPP 1.3-3

Completion 1.3 Completion Times EXAMPLES (continued)

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.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

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

If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start.

If the inoperable pump is restored to OPERABLE status after Condition B is entered, 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.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

(continued)

Amendment 274 Times 1.3 JAFNPP 1.3-4

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (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.

(continued)

Amendment 274 JAFNPP 1.3-5

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 7 days Function X Function X subsystem subsystem to AND inoperable.

OPERABLE status.

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

OPERABLE status.

10 days from discovery of failure to meet the LCO C. One C.1 Restore 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Function X Function X subsystem subsystem to inoperable.

OPERABLE status.

AND OR One C.2 Restore 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Function Y Function Y subsystem subsystem to inoperable.

OPERABLE status.

(continued)

Amendment 274 JAFNPP 1.3-6

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

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable.

The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered.

A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited.

If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A.

The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met.

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

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

This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock".

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

(continued)

Amendment 274 JAFNPP 1.3-7

Completion 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) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves to OPERABLE inoperable, status.

B. Required B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

A single Completion Time is used for any number of valves inoperable at the same time.

The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis.

Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable.

The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve.

The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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

(continued)

Amendment 274 Times 1.3 JAFNPP 1.3-8

Completion 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-5 ACTIONS NOTE O

TE--------------

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.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked.

If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis.

When a valve is declared inoperable, Condition A is entered and its Completion Time starts.

If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

(continued)

Amendment 274 Times 1.3 1.3-9 JAFNPP

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

If the Completion Time associated with a valve in Condition A expires. Condition B is entered for that valve.

If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve.

If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

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

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per inoperable.

SR 3.x.x.x.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR A.2 Place channel in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months trip.

B. Required B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated Completion Time not met.

(continued)

Amendment 274 JAFNPP 1.3-10

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

Entry into Condition A offers a choice between Required Action A.1 or A.2.

Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance.

The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval.

If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2), Condition B is entered.

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

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

(continued)

Amendment 274 JAFNPP 1.3-11

Completion 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 inoperable, isolated.

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

B. Required B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

Required Action A.1 has two Completion Completion Time begins at the time the and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" performance of Required Action A.1.

Times.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Condition is entered interval begins upon 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 (continued)

Amendment 274 Times 1.3 1.3-12 JAFNPP

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued) and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

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

Amendment 274 JAFNPP 1.3-13

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 Limiting Condition for Operation (LCO).

An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

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

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

Sometimes special situations dictate when the requirements of a Surveillance are to be met.

They are "otherwise stated" conditions allowed by SR 3.0.1.

They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts.

To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed.

With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings.

A Surveillance is "met" only when the acceptance criteria are satisfied.

Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met."

"Performance" refers only to the requirement to specifically determine the ability to meet the acceptance (continued)

Amendment 274 JAFNPP 1.4-1

Frequency 1.4 1.4 Frequency DESCRIPTION (continued) criteria.

Some Surveillances contain notes that modify the Frequency of performance of the conditions during which the acceptance criteria must be satisfied.

For these Surveillances, the MODE entry restrictions of SR 3.0.4 may not apply.

Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

a.

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

b.

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

c.

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

(continued)

Amendment 274 JAFNPP 1.4-2

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS).

The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time.

Performance of the Surveillance initiates the subsequent interval.

Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility.

The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the plant is outside the Applicability of the LCO).

If the interval specified by SR 3.0.2 is exceeded while the plant is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the plant is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition.

Failure to do so would result in a violation of SR 3.0.4.

(continued)

Amendment 274 JAFNPP 1.4-3

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

Ž 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies.

The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1.

The logical connector "AND" indicates that both Frequency requirements must be met__

Each time reactor power is increased from a power level < 25% RTP to 2 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 exten-Ton allowed by SR 3.0.2.

"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example).

If reactor power decreases to < 25% RTP, the measurement of both intervals stops.

New intervals start upon reactor power reaching 25% RTP.

(continued)

Amendment 274 JAFNPP 1.4-4

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 Ž 25% RTP.

Perform channel adjustment.

7 days The interval continues whether or not the

< 25% RTP between performances.

plant operation is 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 within the "specified Frequency."

Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by SR 3.0.2), but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO.

Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power

, 25% RTP.

Once the plant 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 were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

(continued)

Amendment 274 1.4-5 JAFNPP

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 plant is in MODE 1.

The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1.

However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance.

Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2),

but the plant 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 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met),

SR 3.0.4 would require satisfying the SR.

(continued)

Amendment 274 JAFNPP 1.4-6

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 plant is in MODE 1, 2, or 3 (the assumed Applicability associated LCO) between performances.

operation of the As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency."

Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance.

The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1.

Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a 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 plant reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed.

If the Surveillance were not performed prior to entering MODE 1. there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

(continued)

Amendment 274 JAFNPP 1.4-7

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-6 (continued)

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 plant is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3).

The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1.

However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance.

Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the 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 were not met),

SR 3.0.4 would require satisfying the SR.

Amendment 274 JAFNPP 1.4-8

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be

25% RTP.

2.1.1.2 With the reactor steam dome pressure ; 785 psig and core flow 2 10% rated core flow:

MCPR shall be 2 1.09 for two recirculation loop operation or ; 1.10 for single recirculation loop operation.

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

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

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

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

Amendment 274 JAFNPP 2.0-1

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO)

APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

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

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

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the plant 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 plant, as applicable, in:

a.

MODE 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b.

MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c.

MODE 4 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, and 3.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time.

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

(continued)

Amendment 274 3.0-1 JAFNPP

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 Exceptions to this Specification are stated in the (continued) individual Specifications.

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

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 5.5.12, "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 Special Operations LCOs in Section 3.10 allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations.

Unless otherwise specified, all other TS requirements remain unchanged.

Compliance with Special Operations LCOs is optional.

When a Special Operations LCO is desired to be met but is not met, the ACTIONS of the Special Operations LCO shall be met.

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

Amendment 274 JAFNPP 3.0-2

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.

(continued)

Amendment 274 JAFNPP 3.0-3

SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.4 (continued)

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

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

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

Amendment 274 3.0-4 JAFNPP

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

LCO

3.1.1 APPLICABILITY

SDM shall be i 0.38% Ak/k, with the highest worth control rod analytically determined.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits A.1 Restore SDM to within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in MODE 1 or 2.

limits.

B.

Required Action and B.1 Be in MODE 3.

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.

SDM not within limits C.1 Initiate action to Immediately in MODE 3.

fully insert all insertable control rods.

D.

SDM not within limits D.1 Initiate action to Immediately in MODE 4.

fully insert all insertable control rods.

AND (continued)

Amendment 274 JAFNPP 3.1.1-1

SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

(continued)

D.2 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore secondary containment to OPERABLE status.

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

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

E.

SDM not within limits E.1 Suspend CORE Immediately in MODE 5.

ALTERATIONS except for control rod insertion and fuel assembly removal.

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

AND (continued)

Amendment 274 JAFNPP 3.1.1-2

SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. (continued)

E.3 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore secondary containment to OPERABLE status.

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

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

Amendment 274 JAFNPP 3.1.1-3

SDM 3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is 2 0.38% Ak/k with the highest Prior to each worth control rod analytically determined, in vessel fuel movement during fuel loading sequence AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after criticality following fuel movement within the reactor pressure vessel or control rod replacement Amendment 274 JAFNPP 3.1.1-4

Reactivity Anomalies 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Anomalies LCO

3.1.2 APPLICABILITY

The reactivity difference between the measured rod density and the predicted rod density shall be within +/- 1% Ak/k.

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity A.1 Restore core 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months difference not within reactivity difference

limit, to within limit.

B. Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

Amendment 274 JAFNPP 3.1.2-1

Reactivity Anomalies 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1.2.1 Verify core reactivity difference between the measured rod density and the predicted rod density is within +/- 1% Ak/k.

FREQUENCY Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AND 1000 MWD/T thereafter during operations in MODE 1 Amendment 274 3.1.2-2 JAFNPP

Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO

3.1.3 APPLICABILITY

Each control rod shall be OPERABLE.

MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each control rod.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One withdrawn control NOTE ------------

rod stuck.

Rod worth minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation," if required, to allow continued operation.

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

AND A.2 Disarm the associated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months control rod drive (CRD).

AND (continued)

Amendment 274 JAFNPP 3.1.3-1

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3 Perform SR 3.1.3.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from and SR 3.1.3.3 for discovery of each withdrawn Condition A OPERABLE control rod.

concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM AND A.4 Perform SR 3.1.1.1.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

Two or more withdrawn B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months control rods stuck.

C.

One or more control C.1

NOTE.........

rods inoperable for RWM may be bypassed reasons other than as allowed by Condition A or B.

LCO 3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.

Fully insert 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months inoperable control rod.

AND C.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

(continued)

Amendment 274 JAFNPP 3.1.3-2

Control Rod OPERABILITY 3.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

NOTE --------- D.1 Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Not applicable when with BPWS.

THERMAL POWER

> 10% RTP.

OR D.2 Restore control rod 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Two or more inoperable to OPERABLE status.

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

E.

Required Action and E.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, C, or D not met.

OR Nine or more control rods inoperable.

Amendment 274 JAFNPP 3.1.3-3

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.1.3.2 NOTE -------------------

Not required to be performed until 7 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

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

SR 3.1.3.3

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

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

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

SR 3.1.3.4 Verify each control rod scram time from In accordance fully withdrawn to notch position 04 is with S7 seconds.

SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3. and SR 3.1.4.4 (continued)

Amendment 274 JAFNPP 3.1.3-4

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.1.3.5 Verify each control rod does not go to the withdrawn overtravel position.

FREQUENCY Each time the control rod is withdrawn to "full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling Amendment 274 3.1.3-5 JAFNPP

Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4

a.

No more than 10 OPERABLE control rods in accordance with Table 3.1.4-1; and shall be "slow,"

b.

No more than 2 OPERABLE control rods shall occupy adjacent locations.

APPLICABILITY:

that are "slow" MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months LCO not met.

SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is Prior to within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure Ž 800 psig.

40% RTP after each reactor shutdown days (continued)

Amendment 274 JAFNPP 3.1.4-1

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each 120 days tested control rod scram time is within cumulative the limits of Table 3.1.4-1 with reactor operation in steam dome pressure ; 800 psig.

MODE 1 SR 3.1.4.3 Verify each affected control rod scram Prior to time is within the limits of declaring Table 3.1.4-1 with any reactor steam dome control rod pressure.

OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram Prior to time is within the limits of exceeding Table 3.1.4-1 with reactor steam dome 40% RTP after pressure Ž 800 psig.

fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Amendment 274 3.1.4-2 JAFNPP

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

Control Rod Scram Times

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

1.

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

2.

Enter applicable Conditions and Required Actions of LCO 3.1.3. "Control Rod OPERABILITY," for control rods with scram times > 7 seconds to notch position 04.

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

SCRAM TIMES(a)(b) when REACTOR STEAM DOME NOTCH POSITION PRESSURE ; 800 psig (seconds) 46 0.44 36 1.08 26 1.83 06 3.35 (a)

Maximum scram time from fully withdrawn position, based on de-energization of scram pilot valve solenoids at time zero.

(b)

Scram times as a function of reactor steam dome

< 800 psig, are within established limits.

pressure, when Amendment 274 3.1.4-3 JAFNPP

Control Rod Scram Accumulators 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Control Rod Scram Accumulators LCO

3.1.5 APPLICABILITY

Each control rod scram accumulator shall be OPERABLE.

MODES 1 and 2.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One control rod scram A.1 -

NOTE --------

accumulator inoperable Only applicable if with reactor steam the associated dome pressure control rod scram 2 900 psig.

time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated control rod scram time "slow."

OR A.2 Declare the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated control rod inoperable.

(continued)

Amendment 274 JAFNPP 3.1.5-1

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

CONDITION IREQUIRED ACTION

[COMPLETION TIME B.

Two or more control rod scram accumulators inoperable with reactor steam dome pressure 2 900 psig.

B.1 AND B.2.1 OR B.2.2 Restore charging water header pressure to > 940 psig.

NOTE --------

Only applicable if the associated control rod scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the associated control rod scram time "slow."

Decl are the associated control rod inoperable.

C. One or more control C.1 Verify all control Immediately upon rod scram accumulators rods associated with discovery of inoperable with inoperable charging water reactor steam dome accumulators are header pressure pressure < 900 psig.

fully inserted.

< 940 psig AND (continued)

Amendment 274 20 minutes from discovery of Condition B concurrent with charging water header pressure

< 940 psig 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour 3.1.5-2 JAFNPP

Control Rod Scram Accumulators 3.1.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

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

D. Required Action B.1 or D.1

NOTE --------

C.1 and associated Not applicable if all Completion Time not inoperable control met.

rod scram accumulators are associated with fully inserted control rods.

Place the reactor Immediately mode switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator 7 days pressure is

! 940 psig.

Amendment 274 JAFNPP 3.1.5-3

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO

3.1.6 APPLICABILITY

OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

MODES 1 and 2 with THERMAL POWER

10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more OPERABLE A.1

NOTE --------

control rods not in Rod worth minimizer compliance with BPWS.

(RWM) may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation."

Move associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod(s) to correct position.

OR A.2 Declare associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod(s) inoperable.

(continued)

Amendment 274 JAFNPP 3.1.6-1

Rod Pattern Control 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Nine or more OPERABLE B.1

NOTE------

control rods not in Rod worth minimizer compliance with BPWS.

(RWM) may be bypassed as allowed by LCO 3.3.2.1.

Suspend withdrawal of Immediately control rods.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with BPWS.

Amendment 274 JAFNPP 3.1.6-2

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO

3.1.7 APPLICABILITY

Two SLC subsystems shall be OPERABLE.

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One SLC subsystem A.1 Restore SLC subsystem 7 days inoperable, to OPERABLE status.

B.

Two SLC subsystems B.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

subsystem to OPERABLE status.

C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

Amendment 274 JAFNPP 3.1.7-1

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months pentaborate solution is within the limits of Figure 3.1.7-1.

SR 3.1.7.2 Verify temperature of sodium pentaborate 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months solution is within the limits of Figure 3.1.7-2.

SR 3.1.7.3 Verify temperature of pump suction piping 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is within the limits of Figure 3.1.7-2.

SR 3.1.7.4 Verify continuity of explosive charge.

31 days SR 3.1.7.5 Verify the concentration of sodium 31 days pentaborate in solution is within the limits of Figure 3.1.7-1.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or sodium pentaborate is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 (continued)

Amendment 274 JAFNPP 3.1.7-2

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual valve in 31 days the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

SR 3.1.7.7 Verify each pump develops a flow rate In accordance 2 50 gpm at a discharge pressure with the 2 1275 psig.

Inservice Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem from 24 months on a pump into reactor pressure vessel.

STAGGERED TEST BASIS SR 3.1.7.9 Verify all heat traced piping between 24 months storage tank and pump suction is unblocked.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after piping temperature is restored within the limits of Figure 3.1.7-2 SR 3.1.7.10 Verify sodium pentaborate enrichment is Prior to S34.7 atom percent B-10.

addition to SLC tank (continued)

Amendment 274 3.1.7-3 JAFNPP

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.11 Verify sodium pentaborate enrichment in 24 months solution in the SLC tank is Ž 34.7 atom percent B-1O.

Amendment 274 JAFNPP 3.1.7-4

SLC System 3.1.7 (4724gal, 13%)

0

0.

LU "4

0 0.

(4724gal, 10%)

I I

3000 4000 Net Volume of Solution in Tank (gal)

Figure 3.1.7-1 (page 1 of 1)

Sodium Pentaborate Solution Volume Versus Concentration Requirements Amendment 274 14-(2200gal, 13%)

(2850gal, 10%)

0 0., 0 13 12 11 10 9.

2 2000 5000 R

3.1.7-5 JAFNPP

SLC System 3.1.7 6

8 10 12 14 16 18 20 Concentration (Weight Percent Enriched Sodium Pentaborate)

Figure 3.1.7-2 (page 1 of 1)

Sodium Pentaborate Solution Temperature Versus Concentration Requirements Amendment 274 100 90 U,i,

0.

01 1..

80 70 60 50 40 JAFNPP 3.1.7-6

SDV Vent and Drain 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV)

Vent and Drain Valves LCO

3.1.8 APPLICABILITY

Each SDV vent and drain valve shall be OPERABLE.

MODES 1 and 2.

ACTIONS

-NOTE NOTES........................

1.

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

2.

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more SDV vent A.1 Isolate the 7 days or drain lines with associated line.

one valve inoperable.

B.

One or more SDV vent B.1 Isolate the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or drain lines with associated line.

both valves inoperable.

C. Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

Amendment 274 Valves 3.1.8 JAFNPP 3.1.8-1

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

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

Verify each SDV vent and drain valve is 31 days open.

SR 3.1.8.2 Cycle each SDV vent and drain valve to the In accordance fully closed and fully open position.

with the Inservice Testing Program SR 3.1.8.3 Verify each SDV vent and drain valve:

24 months

a.

Closes in g 30 seconds after receipt of an actual or simulated scram signal; and

b.

Opens when the actual or simulated scram signal is reset.

Amendment 274 3.1.8-2 JAFNPP

3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

LCO

3.2.1 APPLICABILITY

All APLHGRs shall be less than or equal to the limits specified in the COLR.

THERMAL POWER 2 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

limits, within limits.

B.

Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal Once within to the limits specified in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment 274 APLHGR 3.2.1 JAFNPP 3.2.1-1

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

LCO

3.2.2 APPLICABILITY

All MCPRs shall be greater operating limits specified THERMAL POWER Ž 25% RTP.

than or equal to the MCPR in the COLR.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Any MCPR not within A.1 Restore MCPR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

limits, within limits.

B.

Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal Once within to the limits specified in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

> 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

Amendment 274 MCPR 3.2.2 3.2.2-1 JAFNPP

MCPR 3.2.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.2.2.2 Determine the MCPR limits.

FREQUENCY 1

Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.1 AND Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.2 AND Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.4 Amendment 274 3.2.2-2 JAFNPP

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

LCO

3.2.3 APPLICABILITY

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

THERMAL POWER

Ž 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Any LHGR not within A.1 Restore LHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

limits, within limits.

B.

Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to Once within the limits specified in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 2 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment 274 LHGR 3.2.3 3.2.3-1 JAFNPP

APRM Gain and Setpoint 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 Average Power Range Monitor (APRM)

Gain and Setpoint LCO

3.2.4 APPLICABILITY

a.

MFLPD shall be less than or equal to Fraction of RTP;

b.

Each required APRM Neutron Flux-High (Flow Biased)

Function Allowable Value specified in the COLR shall be made applicable; or

c.

Each required APRM gain shall be adjusted as specified in the COLR.

THERMAL POWER Ž 25% RTP.

ACTIONS.

CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months LCO not met.

requirements of the LCO.

B.

Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

Amendment 274 JAFNPP 3.2.4-1

APRM Gain and Setpoint 3.2.4 SURVE I LLANCE REQU I REMENTS SURVEILLANCE SR 3.2.4.1

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

Not required to be met if SR 3.2.4.2 is satisfied for LCO 3.2.4.b or LCO 3.2.4.c requirements.

Verify MFLPD is within limits.

FREQUENCY Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 2 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter SR 3.2.4.2 NOTE ------------------

Not required to be met if SR 3.2.4.1 is satisfied for LCO 3.2.4.a requirements.

Verify required APRM Neutron Flux-High 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (Flow Biased) Function Allowable Value or ARPM gains are adjusted for the calculated MFLPD.

Amendment 274 I

3.2.4-2 JAFNPP

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS)

Instrumentation LCO 3.3.1.1 APPLICABILITY:

The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

According to Table 3.3.1.1-1.

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable, trip.

OR A.2 Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

B.

One or more Functions B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more trip system in trip.

required channels inoperable in both OR trip systems.

B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

(continued)

Amendment 274 ACTIONS JAFNPP 3.3.1.1-1

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

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

capability not maintained.

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

the channel.

E.

As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 to < 29% RTP.

and referenced in Table 3.3.1.1-1.

F.

As required by F.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

G. As required by G.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

H.

As required by H.1 Initiate action to Immediately Required Action D.1 fully insert all and referenced in insertable control Table 3.3.1.1-1.

rods in core cells containing one or more fuel assemblies.

Amendment 274 3.3.1.1-2 JAFNPP

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

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

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

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

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.1.2 NOTE ------------------

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

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

2% RTP plus any gain adjustment required by LCO 3.2.4, "Average Power Range Monitor (APRM)

Gain and Setpoint,"

while operating at 2 25% RTP.

SR 3.3.1.1.3 NOTE ------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

7 days SR 3.3.1.1.4 Perform a functional test of each RPS 7 days automatic scram contactor.

(continued)

Amendment 274 JAFNPP 3.3.1.1-3

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Verify the source range monitor (SRM) and Prior to fully intermediate range monitor (IRM) channels withdrawing overlap.

SRMs SR 3.3.1.1.6 NOTE ------------------

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

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.7 Calibrate the local power range monitors.

1000 MWD/T average core exposure SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.1.1.9 NOTES -----------------

1.

Neutron detectors are excluded.

2.

For Functions l.a and 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

3.

For Function 2.b, the recirculation loop flow signal portion of the channel is excluded.

Perform CHANNEL CALIBRATION.

92 days (continued)

Amendment 274 JAFNPP 3.3.1.1-4

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Calibrate the trip units.

184 days SR 3.3.1.1.11 Perform CHANNEL FUNCTIONAL TEST.

24 months SR 3.3.1.1.12 ------------------

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

For Function 2.b, all portions of the channel except the recirculation loop flow signal portion are excluded.

Perform CHANNEL CALIBRATION.

24 months SR 3.3.1.1.13 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months SR 3.3.1.1.14 Verify Turbine Stop Valve-Closure and 24 months Turbine Control Valve Fast Closure, EHC Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 29% RTP.

SR 3.3.1.1.15 ------------------

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

1.

Neutron detectors are excluded.

2.

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

Verify the RPS RESPONSE TIME is within 24 months on a limits.

STAGGERED TEST BASIS Amendment 274 3.3.1.1-5 JAFNPP

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

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

1.

Intermediate Range Monitors

a.

Neutron Flux-High 2

3 G

SR 3.3.1.1.1

< 120/125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.4 full scale SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1.9 SR 3.3.1.1.13 5 (a) 3 H

SR 3.3.1.1.1

< 120/125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.4 full scale SR 3.3.1.1.9 SR 3.3.1.1.13

b.

Inop 2

3 G

SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13 5 (a) 3 H

SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13

2.

Average Power Range Monitors

a.

Neutron Flux-High.

2 2

G SR 3.3.1.1.1

< 15% RTP (Startup)

SR 3.3.1.1.3 SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.13

b.

Neutron Flux-High 1

2 F

SR 3.3.1.1.1 As specified (Flow Biased)

SR 3.3.1.1.2 in the COLR SR 3.3.1.1.4 and < 117% RTP SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 (continued)

(a)

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

Amendment 274 3.3.1.1-6 JAFNPP

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

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

2.

Average Power Range Monitors (continued)

c.

Neutron Flux-High (Fixed)

d.

Inop

3.

Reactor Pressure - High

4.

Reactor Vessel Water Level - Low (Level 3)

5.

Main Steam Isolation Valve - Closure

6.

Drywell Pressure-High 1

2 1.2 1.2 1,2 1

1.2 F

SR SR SR SR SR SR SR SR G

SR SR SR SR G

SR SR SR SR SR SR SR G

SR SR SR SR SR SR SR F

SR SR SR SR SR G

SR SR SR SR SR SR SR 3.3.1.1.1 3.3.1.1.2 3.3.1.1.4 3.3.1.1.7 3.3.1.1.8 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.4 3.3.1.1.7 3.3.1.1.8 3.3.1.1.13 3.3.1.1.1 3.3.1.1.4 3.3.1.1.8 3.3.1.1.10 3.3.1.1.12 3.3.1.1.13 3.3.1.1.15 3.3.1.1.1 3.3.1.1.4 3.3.1.1.8 3.3.1.1.10 3.3.1.1.12 3.3.1.1.13 3.3.1.1.15 3.3.1.1.4 3.3.1.1.8 3.3.1.1.12 3.3.1.1.13 3.3.1.1.15 3.3.1.1.1 3.3.1.1.4 3.3.1.1.8 3.3.1.1.10 3.3.1.1.12 3.3.1.1.13 3.3.1.1.15

< 120% RTP NA g 1080 psig

Ž 177 inches 5 15% closed g 2.7 psig (continued)

Amendment 274 3.3.1.1-7 JAFNPP

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

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

7.

Scram Discharge Volume Water Level - High

a.

Differential Pressure Transmitter/Trip Unit

b.

Level Switch

8.

Turbine Stop Valve - Closure

9.

Turbine Control Valve Fast Closure, EHC Oil Pressure - Low

10.

Reactor Mode Switch Shutdown Position

11.

Manual Scram 1,2 5 (a) 1,2 5 (a) 2 2

2 2

> 29X RTP 4

29% RTP 1,2 5 (a) 1,2 5 (a)

G SR SR SR SR H

SR SR SR SR G

SR SR SR SR H

SR SR SR SR E

SR SR SR SR SR SR SR SR E

SR SR SR SR SR SR SR SR G

SR SR H

SR SR G

SR SR H

SR SR 2

1 1

1 3.3.1.1.1 3.3.1.1.4 3.3.1.1.9 3.3.1.1.13 3.3.1.1.1 3.3.1.1.4 3.3.1.1.9 3.3.1.1.13 3.3.1.1.4 3.3.1.1.8 3.3.1.1.12 3.3.1.1.13 3.3.1.1.4 3.3.1.1.8 3.3.1.1.12 3.3.1.1.13 3.3.1.1.1 3.3.1.1.4 3.3.1.1.8 3.3.1.1.10 3.3.1.1.12 3.3.1.1.13 3.3.1.1.14 3.3.1.1.15 3.3.1.1.1 3.3.1.1.4 3.3.1.1.8 3.3.1.1.10 3.3.1.1.12 3.3.1.1.13 3.3.1.1.14 3.3.1.1.15 3.3.1.1.11 3.3.1.1.13 3.3.1.1.11 3.3.1.1.13 3.3.1.1.8 3.3.1.1.13 3.3.1.1.8 3.3.1.1.13 S34.5 gallons S34.5 gallons

34.5 gallons S34.5 gallons S15% closed S500 psig and S850 psig NA NA NA NA Amendment 274 (a)

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

3.3.1.1-8 JAFNPP

SRM Instrumentation 3.3.1.2 3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor (SRM)

Instrumentation LCO 3.3.1.2 APPLICABILITY:

The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

According to Table 3.3.1.2-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Restore required SRMs 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SRMs inoperable in to OPERABLE status.

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

B.

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

with IRMs on Range 2 or below.

C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B not met.

(continued)

Amendment 274 JAFNPP 3.3.1.2-1

SRM Instrumentation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more required D.1 Fully insert all 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SRMs inoperable in insertable control MODE 3 or 4.

rods.

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

E.

One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except MODE 5.

for control rod insertion.

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

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified condition.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Amendment 274 JAFNPP 3.3.1.2-2

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.1.2.2 NOTES..................

1. Only required to be met during CORE ALTERATIONS.

2.

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

Verify an OPERABLE SRM detector is located in:

a.

The fueled region;

b.

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

c.

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

+

FREQUENCY 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2.3 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.2.4 NOTE ------------------

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

Verify count rate is

Ž 3.0 cps with a 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during signal to noise ratio ; 2:1.

CORE ALTERATIONS AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

Amendment 274 (continued)

JAFNPP 3.3.1.2-3

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.1.2.5

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

The determination of signal to noise ratio is not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

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

FREQUENCY 7 days SR 3.3.1.2.6 NOTE ------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

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

SR 3.3.1.2.7 NOTES..................

1.

Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION.

92 days Amendment 274 3.3.1.2-4 i

JAFNPP

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

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

1.

Source Range Monitor 2 (a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3.4 2

SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5

2 (b)(c)

SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a)

With IRMs on Range 2 or below.

(b)

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

(c)

Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.

Amendment 274 3.3.1.2-5 JAFNPP

Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation LCO 3.3.2.1 APPLICABILITY:

The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

According to Table 3.3.2.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One rod block monitor A.1 Restore RBM channel 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (RBM) channel to OPERABLE status.

inoperable.

B.

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

Time of Condition A not met.

OR Two RBM channels inoperable.

C.

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

startup.

OR (continued)

Amendment 274 3.3.2.1-1 JAFNPP

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2.1.1 Verify ; 12 rods Immediately withdrawn.

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

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

D.

RWM inoperable during D.1 Verify movement of During control reactor shutdown.

control rods is in rod movement compliance with BPWS by a second licensed operator or other qualified member of the technical staff.

(continued)

Amendment 274 JAFNPP 3.3.2.1-2

Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

One or more Reactor E.1 Suspend control rod Immediately Mode Switch -Shutdown withdrawal.

Position channels inoperable.

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

SURVEILLANCE REQUIREMENTS

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

1.

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

2.

When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.2.1.2 NOTE ----------------

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

10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

92 days (continued)

Amendment 274 JAFNPP 3.3.2.1-3

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE 4

SR 3.3.2.1.3

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

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

Perform CHANNEL FUNCTIONAL TEST.

4.

SR 3.3.2.1.4 NOTE ------------------

Neutron detectors are excluded.

Verify the RBM is not bypassed:

a. When THERMAL POWER is Ž 30% RTP; and

b.

When a peripheral control rod is not selected.

I1 SR 3.3.2.1.5

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

1.

Neutron detectors are excluded.

2.

For Function 1.a, the recirculation loop flow signal portion of the channel is excluded.

Perform CHANNEL CALIBRATION.

FREQUENCY 92 days 92 days 92 days SR 3.3.2.1.6 Verify the RWM is not bypassed when 24 months THERMAL POWER is

10% RTP.

(continued)

Amendment 274 3.3.2.1-4 JAFNPP

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.7 NOTE ------------------

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

Perform CHANNEL FUNCTIONAL TEST.

24 months SR 3.3.2.1.8

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

For Function 1.a, all portions of the channel except the recirculation loop flow signal portion are excluded.

Perform CHANNEL CALIBRATION.

24 months SR 3.3.2.1.9 Verify control rod sequences input to the Prior to RWM are in conformance with BPWS.

declaring RWM OPERABLE following loading of sequence into RWM Amendment 274 3.3.2.1-5 JAFNPP

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

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

1.

Rod Block Monitor

a.

Upscale (a) 2 SR 3.3.2.1.4 As specified in SR 3.3.2.1.5 the COLR SR 3.3.2.1.8

b.

Inop (a) 2 SR 3.3.2.1.1 NA SR 3.3.2.1.4

c. Downscale (a) 2 SR 3.3.2.1.4

ý 2.5/125 SR 3.3.2.1.5 divisions of full scale

2.

Rod Worth Minimizer 1 (b), 2 (b)

I SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.6 SR 3.3.2.1.9

3.

Reactor Mode Switch-Shutdown (c) 2 SR 3.3.2.1.7 NA Position (a)

(b)

(c)

THERMAL POWER

Ž 30% RTP and no peripheral control rod selected.

With THERMAL POWER

1OX RTP.

Reactor mode switch in the shutdown position.

Amendment 274 3.3.2.1-6 JAFNPP

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 APPLICABILITY:

Three channels of feedwater and main turbine high water level trip instrumentation shall be OPERABLE.

THERMAL POWER ; 25% RTP.

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One feedwater and main A.1 Place channel in 7 days turbine high water trip.

level trip channel inoperable.

B.

Two or more feedwater B.1 Restore feedwater and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and main turbine high main turbine high water level trip water level trip channels inoperable, capability.

(continued)

Amendment 274 ACTIONS JAFNPP 3.3.2.2-1

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and C.1

NOTE --------

associated Completion Only applicable if Time not met.

inoperable channel is the result of inoperable feedwater pump turbine or main turbine stop valve.

Remove affected stop 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valve(s) from service.

OR C.2 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to < 25% RTP.

SURVEILLANCE REQUIREMENTS

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

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided feedwater and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

Amendment 274 3.3.2.2-2 JAFNPP

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

SURVEILLANCE FREQUENCY SR 3.3.2.2.2 NOTE ------------------

Only required to be performed when in MODE 4 for > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.2.2.3 Perform CHANNEL CALIBRATION.

The 24 months Allowable Value shall be

222.5 inches.

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

Amendment 274 JAFNPP 3.3.2.2-3

PAM Instrumentation 3.3.3.1 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM)

Instrumentation LCO 3.3.3.1 APPLICABILITY:

The PAM instrumentation for each Function in Table 3.3.3.1-1 shall be OPERABLE.

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

Function 8 may be inoperable for up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period during Post Accident Sampling System operation.

MODES 1 and 2.

ACTIONS

-NOTE NOTES........................

1.

LCO 3.0.4 is not applicable.

2.

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE channel inoperable, status.

B.

Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.6.

not met.

C.

One or more Functions C.1 Restore one required 7 days with two required channel to OPERABLE channels inoperable, status.

(continued)

Amendment 274 JAFNPP 3.3.3.1-1

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3.1-1 for not met.

the channel.

E.

As required by E.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by F.1 Initiate action in Immediately Required Action D.1 accordance with and referenced in Specification 5.6.6.

Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK of each required 31 days PAM instrument channel.

(continued)

Amendment 274 JAFNPP 3.3.3.1-2

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.3.1.2 Perform CHANNEL CALIBRATION of each 92 days required PAM Primary Containment H2 and 02 Concentration Function channel.

SR 3.3.3.1.3 Perform CHANNEL CALIBRATION of each 24 months required PAM instrumentation channel except for the Primary Containment H2 and 02 Concentration Function channels.

Amendment 274 JAFNPP 3.3.3.1-3

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

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

1.

Reactor Vessel Pressure 2

E

2.

Reactor Vessel Water Level

a.

Fuel Zone 2

E

b.

Wide Range 2

E

3.

Suppression Pool Water Level (Wide Range) 2 E

4.

Drywell Pressure

a.

Narrow Range 2

E

b.

Wide Range 2

E

5.

Containment High Range Radiation 2

F

6.

Drywell Temperature 2

E

7.

Penetration Flow Path PCIV Position 2 per penet~a~t(& n flow E

8.

Primary Containment H2 & 02 Concentration 2

E

9.

Suppression Chamber Pressure 2

E

10.

Suppression Pool Water Temperature 2

E

11.

Drywell Water Level 2

E (a)

Not required for isolation valves whose associated penetration flow path 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.

Amendment 274 3.3.3.1-4 JAFNPP

Remote Shutdown System 3.3.3.2 3.3 INSTRUMENTATION 3.3.3.2 Remote Shutdown System LCO 3.3.3.2 APPLICABILITY:

The Remote Shutdown System Functions shall be OPERABLE.

MODES 1 and 2.

ACTIONS NOTES OTES....................

1. LCO 3.0.4 is not applicable.

2.

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Restore required 30 days Functions inoperable.

Function to OPERABLE status.

B. Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

Amendment 274 JAFNPP 3.3.3.2-1

Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2.2 Verify each required control circuit and 24 months transfer switch is capable of performing the intended function.

SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each 24 months required instrumentation channel.

Amendment 274 JAFNPP 3.3.3.2-2

ATWS-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)

Instrumentation LCO 3.3.4.1 APPLICABILITY:

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

a. Reactor Vessel Water Level-Low Low (Level 2); and

b.

Reactor Pressure-High.

MODE 1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Restore channel to 14 days inoperable.

OPERABLE status.

OR A.2

NOTE --------

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

Place channel in 14 days trip.

(continued)

Amendment 274 3.3.4.1-1 JAFNPP

ATWS-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One Function with B.1 Restore ATWS-RPT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ATWS-RPT trip capability.

capability not maintained.

C.

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

maintained.

D. Required Action and D.1

NOTE ---------

associated Completion Only applicable if Time not met.

inoperable channel is the result of an inoperable RPT breaker.

Remove the affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months recirculation pump from service.

OR D.2 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Amendment 274 JAFNPP 3.3.4.1-2

ATWS-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.4.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.4.1.3 Calibrate the trip units.

184 days SR 3.3.4.1.4 Perform CHANNEL CALIBRATION.

The 24 months Allowable Values shall be:

a.

Reactor Vessel Water Level - Low Low (Level 2): 2 105.4 inches; and

b.

Reactor Pressure-High: ! 1153 psig.

SR 3.3.4.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including breaker actuation.

Amendment 274 3.3.4.1-3 JAFNPP

ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS)

Instrumentation LCO 3.3.5.1 APPLICABILITY:

The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.

According to Table 3.3.5.1-1.

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Enter the Condition Immediately inoperable, referenced in Table 3.3.5.1-1 for the channel.

B.

As required by B.1 -

NOTES -------

Required Action A.1

1. Only applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1.

and 3.

2.

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

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

Amendment 274 ACTIONS 3.3.5.1-1 JAFNPP

ECCS Instrumentation 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.2

NOTE --------

Only applicable for Functions 3.a and 3.b.

Declare High Pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Coolant Injection discovery of (HPCI)

System loss of HPCI inoperable.

initiation capability AND B.3 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

C.

As required by C.1

NOTES -------

Required Action A.1

1. Only applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1.

and 3.

2.

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

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable, feature(s) in both divisions AND C.2 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

Amendment 274 3.3.5.1-2 JAFNPP

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1

NOTE------

Required Action A.1 Only applicable if and referenced in HPCI pump suction is Table 3.3.5.1-1.

not aligned to the suppression pool.

Declare HPCI System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable, discovery of loss of HPCI initiation capability AND D.2.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

OR D.2.2 Align the HPCI pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months suction to the suppression pool.

(continued)

Amendment 274 3.3.5.1-3 JAFNPP

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

As required by E.1

NOTES -------

Required Action A.1

1. Only applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1.

and 3.

2.

Only applicable for Functions i.el.f.

and 2.g.

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

(continued)

Amendment 274 JAFNPP 3.3.5.1-4

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

As required by F.1 Declare Automatic 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 Depressurization discovery of and referenced in System (ADS) valves loss of ADS Table 3.3.5.1-1.

inoperable, initiation capability in both trip systems AND F.2 Place channel in 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from trip.

discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days G.

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

initiation capability in both trip systems AND (continued)

Amendment 274 JAFNPP 3.3.5.1-5

ECCS Instrumentation 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G.

(continued)

G.2 Restore channel to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from OPERABLE status.

discovery of i noperabl e channel concurrent with HPCI or RCIC inoperable AND 8 days H. Required Action and H.1 Declare associated Immediately associated Completion supported feature(s)

Time of Condition B, inoperable.

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

Amendment 274 JAFNPP 3.3.5.1-6

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

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

1.

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

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c, 3.f, and 3.g; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c, 3.f, and 3.g provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.1.4 Calibrate the trip units.

184 days SR 3.3.5.1.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months Amendment 274 JAFNPP 3.3.5.1-7

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

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

1.

Core Spray System

a.

Reactor Vessel Water Level - Low Low Low (Level 1)

b.

Drywell Pressure - High

c.

Reactor Pressure-Low (Injection Permissive)

d.

Core Spray Pump Start -Time Delay Relay

e.

Core Spray Pump Discharge Flow - Low (Bypass)

f.

Core Spray Pump Discharge Pressure - High (Bypass)

2.

Low Pressure Coolant Injection (LPCI) System

a.

Reactor Vessel Water Level - Low Low Low (Level 1) 1,2,3, 4 (a) 5 (a) 1,2,3 1,2,3 4 (a),

5 (a) 1,2.3, 4 (a),

5 (a) 1,2,3, 4 (a),

5 (a) 4 (b) 4 (b) 4 4

1 per pump 1 per pump 1 per pump 4 (b)

B SR SR SR SR SR B

SR SR SR SR SR C

SR SR SR SR SR B

SR SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 C

SR 3.3.5.1.5 SR 3.3.5.1.6 E

SR 3.3.5.1.3 SR 3.3.5.1.6 B

SR SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 inches

2.7 psig 2 410 psig and s 490 psig

Ž 410 psig and psig seconds 2 510 gpm and

! 980 gpm

Ž 90 psig and

110 psig S18 inches (continued)

(a)

When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2. ECCS - Shutdown.

(b)

Also required to initiate the associated emergency diesel generator subsystem.

Amendment 274 3.3.5.1-8 JAFNPP

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

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

2.

LPCI System (continued)

b.

Drywell Pressure - High

c.

Reactor Pressure - Low (Injection Permissive)

d.

Reactor Pressure - Low (Recirculation Discharge Valve Permissive)

e.

Reactor Vessel Shroud Level (Level 0)

f.

Low Pressure Coolant Injection Pump Start -Time Delay Relay Pumps A, D 1.2.3 1.2,3 4 (a) 5 (a) 1 (c) 2 (c),

3 (c) 1,2,3 1,2,3, 4 (a),

5 (a) 4 (b) 4 4

4 2

1 per pump B

SR SR SR SR SR C

SR SR SR SR SR B

SR SR SR SR SR C

SR SR SR SR SR B

SR SR SR SR SR C

SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 33.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.5 3.3.5.1.6 S2.7 psig S410 psig and

! 490 psig 2 410 psig and

! 490 psig a 295 psig

ý 1.0 inches

1.51 seconds

! 6.73 seconds Pumps B, C (conti nued)

(a)

When (b)

Also (c)

With associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.

required to initiate the associated emergency diesel generator subsystem.

associated recirculation pump discharge valve open.

Amendment 274 3.3.5.1-9 JAFNPP

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)

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

2.

LPCI System (continued)

g.

Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass)

h.

Containment Pressure - High 1.2,3, 4 (a),

5 (a) 1.2,3 1 per subsystem 4

E SR 3.3.5.1.5 SR 3.3.5.1.6 B

SR 3.3.5.1.3 SR 3.3.5.1.6

3.

High Pressure Coolant Injection (HPCI) System

a.

Reactor Vessel Water Level - Low Low (Level 2)

b.

Drywell Pressure - High

c.

Reactor Vessel Water Level - High (Level 8)

d.

Condensate Storage Tank Level - Low

e.

Suppression Pool Water Level - High

f.

High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass)

g.

High Pressure Coolant Injection Pump Discharge Pressure - High (Bypass) 1, 2 (d),

3 (d) 1, 2(d) 3 (d) 1I 2 (d) 3 (d) 1, 2 (d),

3 (d) 1, 2 (d),

3 (d) 4 4

B SR SR SR SR SR B

SR SR SR SR SR C

SR SR SR SR SR 2

4 2

3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 D

SR 3.3.5.1.3 SR 3.3.5.1.6 D

SR 3.3.5.1.3 SR 3.3.5.1.6 E

SR 3.3.5.1.5 SR 3.3.5.1.6 E

SR 3.3.5.1.3 SR 3.3.5.1.6 1

1 2 126.5 inches

2.7 psig 5 222.5 inches z 59.5 inches

14.5 ft S475 gpm and

800 gpm 2 25 psig and

80 psig (continued)

Amendment 274

- 1040 gpm and

. 1665 gpm z 1 psig and

2.7 psig (a)

When the associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.

(d)

With reactor steam dome pressure > 150 psig.

3.3.5.1-10 JAFNPP

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)

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

4.

Automatic Depressurization System (ADS) Trip System A

a.

Reactor Vessel Water Level - Low Low Low (Level 1)

b.

Automatic Depressurization System Initiation Timer

c.

Reactor Vessel Water Level - Low (Level 3)

d.

Core Spray Pump Discharge Pressure - High

e.

Low Pressure Coolant Injection Pump Discharge Pressure - High

5.

ADS Trip System B

a.

Reactor Vessel Water Level - Low Low Low (Level 1)

b.

Automatic Depressurization System Initiation Timer 1,

2 (d) 3 (d) 1, 2 (d),

3 (d)

1.

2 (d),

3 (d)

1.

2 (d),

3 (d) 1, 2(d),

3(d) 1, 2 (d),

3 (d) 1, 2 (d), 3 (d) 2 1

1 F

SR SR SR SR SR G

SR SR F

SR SR SR SR SR 2

3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 G

SR 3.3.5.1.3 SR 3.3.5.1.6 G

SR 3.3.5.1.3 SR 3.3.5.1.6 4

2 1

F SR SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 G

SR 3.3.5.1.5 SR 3.3.5.1.6 18 inches S134 seconds S177 inches 2 90 psig and S110 psig S105 psig and

! 145 psig

> 18 inches g 134 seconds (continued)

(d)

With reactor steam dome pressure > 150 psig.

Amendment 274 3.3.5.1-11 JAFNPP

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

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

5.

ADS Trip System B (continued)

c.

Reactor Vessel Water 1,

1 F

SR 3.3.5.1.1 2 177 inches Level - Low (Level 3) 2(d)

(d)

SR 3.3.5.1.2 S3(d SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6

d.

Core Spray Pump 1,

2 G

SR 3.3.5.1.3

Ž 90 psig Discharge 2 (d)

(d)

SR 3.3.5.1.6 and Pressure - High Co, 3l a

110 psig

e.

Low Pressure Coolant 1,G SR 3.3.5.1.3

ý 105 psig Injection Pump SR 3.3.5.1.6 and Discharge 2 (d),

3 (d) g 145 psig Pressure - High (d)

With reactor steam dome pressure > 150 psig.

Amendment 274 3.3.5.1-12 JAFNPP

RCIC System Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.2 APPLICABILITY:

ACTIONS The RCIC System instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

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

....................................N O T E ------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Enter the Condition Immediately inoperable, referenced in Table 3.3.5.2-1 for the channel.

B.

As required by B.1 Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 inoperable, discovery of and referenced in loss of RCIC Table 3.3.5.2-1.

initiation capability AND B.2 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

C. As required by C.1 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action A.1 OPERABLE status.

and referenced in Table 3.3.5.2-1.

(continued)

Amendment 274 JAFNPP 3.3.5.2-1

RCIC System Instrumentation 3.3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1

NOTE --------

Required Action A.1 Only applicable if and referenced in RCIC pump suction is Table 3.3.5.2-1.

not aligned to the suppression pool.

Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable, discovery of loss of automatic RCIC initiation capability AND D.2.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

OR D.2.2 Align RCIC pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months suction to the suppression pool.

E.

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

Time of Condition B, C, or D not met.

Amendment 274 3.3.5.2-2 JAFNPP

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

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

1.

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

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 2 and 4; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.5.2.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.2.4 Calibrate the trip units.

184 days SR 3.3.5.2.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.5.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months Amendment 274 JAFNPP 3.3.5.2-3

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

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

1.

Reactor Vessel Water 4

B SR 3.3.5.2.1

126.5 inches Level - Low Low (Level 2)

SR 3.3.5.2.2 SR 3.3.5.2.4 SR 3.3.5.2.5 SR 3.3.5.2.6

2.

Reactor Vessel Water 2

C SR 3.3.5.2.1

222.5 inches Level -High (Level 8)

SR 3.3.5.2.2 SR 3.3.5.2.4 SR 3.3.5.2.5 SR 3.3.5.2.6

3.

Condensate Storage Tank 4

D SR 3.3.5.2.3 k 59.5 inches Level-Low SR 3.3.5.2.6

4.

Manual Initiation 1

C SR 3.3.5.2.6 NA Amendment 274 3.3.5.2-4 JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 APPLICABILITY:

The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

According to Table 3.3.6.1-1.

NOTES OTES-----------------------

1.

Penetration flow paths may be unisolated intermittently under administrative controls.

2.

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable, trip.

Functions 2.a, 2.b, 2.d, 2.g, 5.e, 5.f, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 2.a, 2.b, 2.d, 2.g, 5.e, 5.f, 6.b, 7.a, and 7.b B.

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

capability not maintained.

(continued)

Amendment 274 ACTIONS JAFNPP 3.3.6.1-1

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A Table 3.3.6.1-1 for or B not met.

the channel.

D. As required by D.1 Isolate associated 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action C.1 main steam line and referenced in (MSL).

Table 3.3.6.1-1.

OR D.2.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E.

As required by E.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action C.1 and referenced in Table 3.3.6.1-1.

F.

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

Table 3.3.6.1-1.

G. As required by G.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action C.1 penetration flow and referenced in path(s).

Table 3.3.6.1-1.

(continued)

Amendment 274 JAFNPP 3.3.6.1-2

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

Required Action and H.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition F or AND G not met.

H.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR As required by Required Action C.1 and referenced in Table 3.3.6.1-1.

I.

As required by 1.1 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action C.1 standby liquid and referenced in control subsystem Table 3.3.6.1-1.

(SLC) inoperable.

OR 1.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup System.

J.

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

Table 3.3.6.1-1.

OR J.2 Initiate action to Immediately isolate the Residual Heat Removal (RHR)

Shutdown Cooling System.

Amendment 274 3.3.6.1-3 JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

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

1.

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

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows:

(a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 2.d, 2.g, 7.a, and 7.b; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 2.d, 2.g, 7.a, and 7.b provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.1.3 NOTE -----------------

For Functions 1.f and 2.f, radiation detectors are excluded.

Perform CHANNEL CALIBRATION.

92 days SR 3.3.6.1.4 Calibrate the trip units.

184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.6.1.6 Calibrate the radiation detectors.

24 months SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months (continued)

Amendment 274 3.3.6.1-4 JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEI LLANCE REQU IREMENTS (continued)

Amendment 274 3.3.6.1-5 SURVEILLANCE FREQUENCY SR 3.3.6.1.8

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

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

Verify the ISOLATION INSTRUMENTATION 24 months on a RESPONSE TIME is within limits.

STAGGERED TEST BASIS JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 6)

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

1.

Main Steam Line Isolation

a.

Reactor Vessel Water 1,2,3 2

D SR 3.3.6.1.1

> 18 inches Level - Low Low Low SR 3.3.6.1.2 (Level 1)

SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8

b.

Main Steam Line 1

2 E

SR 3.3.6.1.1

> 825 psig Pressure-Low SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8

c.

Main Steam Line 1,2,3 2 per D

SR 3.3.6.1.1

< 125.9 psid Flow-High MSL SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8

d.

Condenser Vacuum-Low 1,

2 D

SR 3.3.6.1.1

> 8 inches SR 3.3.6.1.2 Hg vacuum 2 (a),

3 (a)

SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

e.

Main Steam Tunnel Area 1,2.3 8

D SR 3.3.6.1.1

< 195°F Temperature-High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

f.

Main Steam Line 1.2,3 2

F SR 3.3.6.1.1

3 times Radiation-High SR 3.3.6.1.3 Normal Full SR 3.3.6.1.6 Power SR 3.3.6.1.7

Background

(continued)

(a)

With any turbine stop valve not closed.

(b) Not used.

Amendment 274 3.3.6.1-6 JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 6)

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

2.

Primary Containment Isol ati on

a.

Reactor Vessel Water 1,2,3 2

H SR 3.3.6.1.1 2 177 inches Level - Low (Level 3)

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

b.

Drywell Pressure-High 1,2,3 2

H SR 3.3.6.1.1

< 2.7 psig SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

c.

Containment 1,2,3 1

F SR 3.3.6.1.1

< 450 R/hr Radiation-High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

d.

Drywell Pressure-High 1,2,3 2 (c)

F SR 3.3.6.1.1

< 2.7 psig SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

e.

Reactor Vessel Water 1,2,3 2

F SR 3.3.6.1.1

> 18 inches Level - Low Low Low SR 3.3.6.1.2 (Level 1)

SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

f.

Main Steam Line 1,2,3 2

F SR 3.3.6.1.1

< 3 times Radiation-High SR 3.3.6.1.3 Normal Full SR 3.3.6.1.6 Power SR 3.3.6.1.7

Background

g.

Reactor Vessel Water 1,2,3 2 (c)

F SR 3.3.6.1.1

> 177 inches Level - Low (Level 3)

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)

(b)

Not used.

(c)

Only one trip system provided for each associated penetration.

Amendment 274 3.3.6.1-7 JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 6)

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

3.

High Pressure Coolant Injection (HPCI)

System Isolation

a.

HPCI Steam Line Flow-High

b.

HPCI Steam Supply Line Pressure - Low

c.

HPCI Turbine Exhaust Diaphragm Pressure - High

d.

HPCI Steam Line Penetration (Drywell Entrance) Area Temperature - High

e.

HPCI Steam Line Torus Room Area Temperature - High

f.

RHR Heat Exchanger A Area Temperature - High

g.

RHR Heat Exchanger B Area Temperature - High

h.

RB Southwest Area of Elevation 272' Temperature - High

i.

RB Southeast Area of Elevation 272' Temperature - High 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1.2,3 1,2,3 1.2,3 1.2,3 1

2 2

1 F

SR SR SR SR SR F

SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 F

SR 3.3.6.1.3 SR 3.3.6.1.7 F

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 F

SR SR SR SR SR F

SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 Amendment 274

168.24 inches of water dP 2 61 psig and S90 psig S9.9 psig S160°F S160°F S170°F S170°F S144°F S144°F (continued) 3.3.6.1-8 JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 6)

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

3.

HPCI System Isolation (continued)

j.

HPCI Equipment Area Temperature - High

4.

Reactor Core Isolation Cooling (RCIC) System Isolation

a.

RCIC Steam Line Flow - High

b.

RCIC Steam Supply Line Pressure - Low

c.

RCIC Turbine Exhaust Diaphragm Pressure - High

d.

RCIC Steam Line Penetration (Drywell Entrance) Area Temperature - High

e.

RCIC Steam Line Torus Room Area Temperature - High

f.

RCIC Equipment Area Temperature - High 1,2,3 1.2,3 1,2,3 1,2,3 1,2,3 1.2.3 1,2,3 2

1 2

2 2

F SR SR SR SR SR F

SR SR SR SR SR F

SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 F

SR 3.3.6.1.3 SR 3.3.6.1.7 F

SR SR SR SR SR F

SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 5 144°F

272.26 inches of water dP 2 58 psig and

93 psig psig g 160°F S160°F S144°F (continued)

Amendment 274 3.3.6.1-9 JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 6)

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

5.

Reactor Water Cleanup (RWCU)

System Isolation

a.

RWCU Suction Line 1,2,3 1

F SR 3.3.6.1.3

144°F Penetration Area SR 3.3.6.1.7 Temperature - High

b.

RWCU Pump Area 1,2,3 1 per F

SR 3.3.6.1.3

165°F for Temperature-High room SR 3.3.6.1.7 Pump Room A and

175°F for Pump Room B

c.

RWCU Heat 1,2,3 1

F SR 3.3.6.1.3

155°F Exchanger Room Area SR 3.3.6.1.7 Temperature - High

d.

SLC System Initiation 1,2 2 (d)

I SR 3.3.6.1.7 NA

e.

Reactor Vessel Water 1,2,3 2

F SR 3.3.6.1.1

Ž 177 inches Level - Low (Level 3)

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

f.

Drywell 1,2,3 2

F SR 3.3.6.1.1 g 2.7 psig Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

6.

Shutdown Cooling System Isolation

a.

Reactor 1,2,3 1

F SR 3.3.6.1.3 g 74 psig Pressure-High SR 3.3.6.1.7

b.

Reactor Vessel Water 3,4,5 2 (e)

J SR 3.3.6.1.1

ý 177 inches Level - Low (Level 3)

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)

(d)

SLC System Initiation only inputs into one of the two trip systems and only isolates one valve in the RWCU suction and return line.

(e)

Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

Amendment 274 3.3.6.1-10 JAFNPP

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 6 of 6)

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

7.

Traversing Incore Probe System Isolation

a.

Reactor Vessel Water 1,2,3 2

G SR 3.3.6.1.1

> 177 inches Level - Low (Level 3)

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

b.

Drywell 1,2,3 2

G SR 3.3.6.1.1

< 2.7 psig Pressure-High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 Amendment 274 3.3.6.1-11 JAFNPP

Secondary Containment Isolation Instrumentation 3.3.6.2 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 APPLICABILITY:

The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.

According to Table 3.3.6.2-1.

N O T E ------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for inoperable.

trip.

Functions 1 and 2 AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions 3 and 4

B.

One or more Functions B.1 Restore secondary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with secondary containment isolation containment isolation capability.

capability not maintained.

C.

Required Action and C.1.1 Isolate the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion associated secondary Time of Condition A containment or B not met.

penetration flow path(s).

OR (continued)

Amendment 274 ACTIONS JAFNPP 3.3.6.2-1

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

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

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

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

SURVEILLANCE REQUIREMENTS

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

1.

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

2.

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

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Amendment 274 3.3.6.2-2 JAFNPP

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.2.3 Perform CHANNEL CALIBRATION 92 days SR 3.3.6.2.4 Calibrate the trip units.

184 days SR 3.3.6.2.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.6.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months Amendment 274 JAFNPP 3.3.6.2-3

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

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

1.

Reactor Vessel Water 1,2.3, 2

SR 3.3.6.2.1 k 177 inches Level -Low (Level 3)

(a)

SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6

2.

Drywell Pressure-High 1,2.3 2

SR 3.3.6.2.1

< 2.7 psig SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6

3.

Reactor Building Exhaust 1.2.3, 1

SR 3.3.6.2.1

< 24,800 cpm Radiation-High (a),(b)

SR 3.3.6.2.3 SR 3.3.6.2.6

4.

Refueling Floor Exhaust 1,2,3, 1

SR 3.3.6.2.1

< 24.800 cpm Radiation-High (a).(b)

SR 3.3.6.2.3 SR 3.3.6.2.6 (a)

During operations with a potential for draining the reactor vessel.

(b)

During CORE ALTERATIONS and during movement of irradiated fuel assemblies in secondary containment.

Amendment 274 3.3.6.2-4 JAFNPP

CREVAS System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS)

System Instrumentation LCO 3.3.7.1 The Control Room Air Inlet Radiation-High channel shall be OPERABLE.

MODES 1, 2 and 3, During movement of irradiated fuel secondary containment, During CORE ALTERATIONS, During operations with a potential vessel.

assemblies in the for draining the reactor ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Channel inoperable.

A.1 Place the CREVAS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months System in the isolate mode of operation.

OR A.2 Declare both CREVAS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystems inoperable.

Amendment 274 APPLICABILITY:

JAFNPP 3.3.7.1-1

CREVAS System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.7.1.2 Perform CHANNEL CALIBRATION.

The 92 days Allowable Value shall be < 4000 cpm.

Amendment 274 3.3.7.1-2 JAFNPP

Condenser Air Removal Pump Isolation Instrumentation 3.3.7.2 3.3 INSTRUMENTATION 3.3.7.2 Condenser Air Removal Pump Isolation Instrumentation LCO 3.3.7.2 APPLICABILITY:

Four channels of the Main Steam Line Radiation-High Function for the condenser air removal pump isolation shall be OPERABLE.

MODES 1 and 2 with any condenser air removal pump not isolated and any main steam line not isolated.

ACTIONS

-NOTE--

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months channels inoperable.

OPERABLE status.

OR A.2

NOTE --------

Not applicable if inoperable channel is the result of an inoperable isolation valve.

Place channel or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated trip system in trip.

(continued)

Amendment 274 JAFNPP 3.3.7.2-1

Condenser Air Removal Pump Isolation Instrumentation 3.3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Condenser air removal B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months pump isolation capability.

capability not maintained.

C.

Required Action and C.1 Isolate the condenser 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion air removal pumps.

Time of Condition A or B not met.

OR C.2 Isolate the main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months steam lines.

OR C.3 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS

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

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains condenser air removal pump isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Amendment 274 3.3.7.2-2 JAFNPP

Condenser Air Removal Pump Isolation Instrumentation 3.3.7.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.7.2.2

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

Radiation detectors are excluded.

Perform CHANNEL CALIBRATION.

The 92 days Allowable Value shall be ! 3 times Normal Full Power Background.

SR 3.3.7.2.3 Calibrate the radiation detectors.

24 months SR 3.3.7.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including isolation valve actuation.

Amendment 274 JAFNPP 3.3.7.2-3

Emergency Service Water (ESW)

System Instrumentation 3.3.7.3 3.3 INSTRUMENTATION 3.3.7.3 Emergency Service Water (ESW)

System Instrumentation LCO 3.3.7.3 APPLICABILITY:

Four channels of ESW pressure instrumentation shall be OPERABLE.

MODES 1, 2 and 3.

N O T E ------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable, trip.

B. Initiation capability B.1 Restore initiation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not maintained in both capability.

logic systems.

C.

Required Action and C.1 Declare associated Immediately associated Completion ESW subsystem(s)

Time of Condition A inoperable.

or B not met.

Amendment 274 ACTIONS JAFNPP 3.3.7.3-1

Emergency Service Water (ESW)

System Instrumentation 3.3.7.3 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.7.3.1 Perform CHANNEL CALIBRATION.

The Allowable 92 days Value shall be ! 40 psig and

50 psig.

SR 3.3.7.3.2 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months Amendment 274 3.3.7.3-2 JAFNPP

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP)

Instrumentation LCO 3.3.8.1 APPLICABILITY:

The LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.

MODES 1, 2, and 3, When the associated emergency diesel generator (EDG) subsystem is required to be OPERABLE by LCO 3.8.2, "AC Sources - Shutdown."

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Place channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, trip.

B.

Required Action and B.1 Declare associated Immediately associated Completion EDG(s) inoperable.

Time not met.

Amendment 274 JAFNPP 3.3.8.1-1

LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CALIBRATION.

24 months SR 3.3.8.1.2 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months Amendment 274 3.3.8.1-2 JAFNPP

LOP Instrumentation 3.3.8.1 Table 3.3.8.1-1 (page 1 of 1)

Loss of Power Instrumentation REQUIRED CHANNELS SURVEILLANCE ALLOWABLE FUNCTION PER BUS REQUIREMENTS VALUE

1.

4.16 kV Emergency Bus Undervoltage (Loss of Voltage)

a.

Bus Undervoltage 2

SR 3.3.8.1.1

Ž 80.2 V and : 89.8 V SR 3.3.8.1.2

b.

Time Delay 1

SR 3.3.8.1.1 k 2.4 seconds and SR 3.3.8.1.2 5 2.6 seconds

2.

4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

a.

Bus Undervoltage 2

SR 3.3.8.1.1

Ž 109.8 V and SR 3.3.8.1.2

111.4 V

b.

Time Delay (LOCA) 1 SR 3.3.8.1.1

Ž 8.4 seconds and SR 3.3.8.1.2

! 9.5 seconds

c.

Time Delay (non-LOCA) 1 SR 3.3.8.1.1

Ž 41.0 seconds and SR 3.3.8.1.2

46.6 seconds Amendment 274 3.3.8.1-3 JAFNPP

RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 APPLICABILITY:

Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply.

MODES 1 and 2.

MODES 3, 4, and 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or both inservice A.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power supplies with inservice power one electric power supply(s) from monitoring assembly service.

inoperable.

B.

One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power supplies with inservice power both electric power supply(s) from monitoring assemblies service.

inoperable.

C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B not met in MODE 1 or 2.

(continued)

Amendment 274 JAFNPP 3.3.8.2-1

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to Immediately associated Completion fully insert all Time of Condition A insertable control or B not met in rods in core cells MODE 3, 4, or 5 with containing one or any control rod more fuel assemblies.

withdrawn from a core cell containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 NOTE ------------------

Only required to be performed prior to entering MODE 2 from MODE 3 or 4, when in MODE 4 for ; 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Perform CHANNEL FUNCTIONAL TEST.

184 days (continued)

Amendment 274 JAFNPP 3.3.8.2-2

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.8.2.2 SR 3.3.8.2.3 Perform CHANNEL CALIBRATION of the electric power monitoring assemblies associated with the inservice RPS motor generator sets.

The Allowable Values shall be:

a.

Overvoltage

132 V, with time delay set to

4 seconds.

b.

Undervoltage Ž 112.5 V for RPS bus A and 2 113.9 V for RPS bus B, with time delay set to

4 seconds.

c.

Underfrequency 2 57 Hz, with time delay set to : 4 seconds.

Perform CHANNEL CALIBRATION of the electric power monitoring assemblies associated with the inservice alternate power supplies.

The Allowable Values shall be:

a.

Overvoltage

132 V, with time delay set to

4 seconds.

b.

Undervoltage Ž 109.9 V, with time delay set to g 4 seconds.

c.

Underfrequency Ž 57 Hz, with time delay set to g 4 seconds.

Amendment 274 FREQUENCY 24 months 24 months SR 3.3.8.2.4 Perform a system functional test.

24 months JAFNPP 3.3.8.2-3

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating Two recirculation loops with matched flows shall operation and the reactor operating at core flow POWER conditions outside the Exclusion Region of to-flow map specified in the COLR.

be in and THERMAL the power-OR One recirculation loop shall be in operation and the reactor operating at core flow and THERMAL POWER conditions outside the Exclusion Region of the power-to-flow map specified in the COLR with the following limits applied when the associated LCO is applicable:

a.

LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR),"

single loop operation limits specified in the COLR;

b.

LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," single loop operation limits specified in the COLR;

c.

LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitors Neutron Flux-High (Flow Biased)), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation; and

d.

LCO 3.3.2.1, "Control Rod Block Instrumentation,"

Function l.a (Rod Block Monitor-Upscale), Allowable Value of Table 3.3.2.1-1 is reset for single loop operation.

APPLICABILITY:

MODES 1 and 2.

Amendment 274 LCO 3.4.1 JAFNPP 3.4.1-1

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two A.1 Initiate action to Immediately recirculation loops in exit the Exclusion operation with core Region.

flow and THERMAL POWER conditions within the Exclusion Region of the power-to-flow map.

B.

Requirements of the B.1 Satisfy the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO not met for requirements of the reasons other than LCO.

Condition A.

C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B not met.

OR No recirculation loops in operation.

Amendment 274 JAFNPP 3.4.1-2

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 NOTE --------------------

Only required to be performed in MODE 1.

Verify reactor operating at core flow and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months THERMAL POWER conditions outside the Exclusion Region of the power-to-flow map specified in the COLR.

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

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mismatch with both recirculation loops in operation is:

a.

10% of rated core flow when operating at < 70% of rated core flow; and

b.

5% of rated core flow when operating at 2 70% of rated core flow.

Amendment 274 JAFNPP 3.4.1-3

Jet Pumps 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 Jet Pumps LCO

3.4.2 APPLICABILITY

All jet pumps shall be OPERABLE.

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more jet pumps A.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

Amendment 274 JAFNPP 3.4.2-1

Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1

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

1. Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

2.

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 25% RTP.

Verify at least one of the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months criteria (a or b) is satisfied for each operating recirculation loop:

a.

Recirculation pump flow to speed ratio differs by

5% from established patterns, and recirculation loop jet pump flow to recirculation pump speed ratio differs by ! 5% from established patterns.

b.

Each jet pump diffuser to lower plenum differential pressure differs by : 20%

from established patterns.

Amendment 274 JAFNPP 3.4.2-2

S/RVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (S/RVs)

LCO 3.4.3 The safety function of 9 S/RVs shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months S/RVs inoperable.

AND A.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Amendment 274 JAFNPP 3.4.3-1

S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoint of In accordance the required S/RVs is 1145 +/- 34.3 psig.

with the Following testing, lift settings shall be Inservice within +/- 1%.

Testing Program SR 3.4.3.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify each required S/RV opens when 24 months on a manually actuated.

STAGGERED TEST BASIS for each valve solenoid Amendment 274 JAFNPP 3.4.3-2

RCS Operational LEAKAGE 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to:

a.

No pressure boundary LEAKAGE;

b.

! 5 gpm unidentified LEAKAGE;

c.

25 gpm total LEAKAGE averaged over the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period; and

d.

! 2 gpm increase in unidentified LEAKAGE previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period in MODE 1.

APPLICABILITY:

within the MODES 1, 2, and 3.

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

within limits.

OR Total LEAKAGE not within limit.

B. Unidentified LEAKAGE B.1 Reduce unidentified 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months increase not within LEAKAGE increase to limit.

within limits.

OR (continued)

Amendment 274 JAFNPP 3.4.4-1

RCS Operational LEAKAGE 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.2 Verify source of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

C. Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met.

C.2 Be in MODE 4.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and unidentified LEAKAGE increase are within limits.

Amendment 274 JAFNPP 3.4.4-2

RCS Leakage Detection Instrumentation 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Leakage Detection Instrumentation LCO 3.4.5 The following RCS leakage detection instrumentation shall OPERABLE:

a. Drywell floor drain sump monitoring system;

b. One channel of the drywell continuous particulate monitoring system; and

c.

One channel of the drywell continuous gaseous monitoring system.

APPLICABILITY:

be atmospheric atmospheric MODES 1, 2. and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell floor drain

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

sump monitoring system LCO 3.0.4 is not applicable.

inoperable.

A.1 Restore drywell floor 30 days drain sump monitoring system to OPERABLE status.

B. One drywell continuous B.1

NOTE.........

atmospheric monitoring Not applicable when system inoperable, both drywell continuous atmospheric monitoring systems are inoperable.

Perform SR 3.4.5.1.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (continued)

Amendment 274 JAFNPP 3.4.5-1

RCS Leakage Detection Instrumentation 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Both drywell

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

continuous atmospheric LCO 3.0.4 is not applicable.

monitoring systems inoperable.

C.1 Analyze grab samples Once per of drywell 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months atmosphere.

AND C.2 Restore one drywell 30 days continuous atmospheric monitoring system to OPERABLE status.

D. Required Action and D.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, AND B, or C not met.

D.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. All required leakage E.1 Enter LCO 3.0.3.

Immediately detection systems inoperable.

Amendment 274 JAFNPP 3.4.5-2

RCS Leakage Detection Instrumentation 3.4.5 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.4.5.1 Perform a CHANNEL CHECK of drywell 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months continuous atmospheric monitoring systems.

SR 3.4.5.2 Perform a CHANNEL FUNCTIONAL TEST of 31 days required leakage detection instrumentation.

SR 3.4.5.3 Perform a CHANNEL CALIBRATION of required 92 days leakage detection instrumentation.

Amendment 274 JAFNPP 3.4.5-3

RCS Specific Activity 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Specific Activity LCO 3.4.6 APPLICABILITY:

The specific activity of the reactor coolant shall be limited to DOSE EQUIVALENT 1-131 specific activity g 0.2 pCi/gm.

MODE 1, MODES 2 and 3 with any main steam line not isolated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor coolant

NOTE ----------

specific activity LCO 3.0.4 is not applicable.

> 0.2 pCi/gm and

2.0 pCi/gm DOSE EQUIVALENT 1-131.

A.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131.

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 limits.

B.

Required Action and B.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion EQUIVALENT 1-131.

Time of Condition A not met.

AND OR B.2.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months steam lines.

Reactor coolant specific activity OR

> 2.0 pCi/gm DOSE EQUIVALENT 1-131.

(continued)

Amendment 274 JAFNPP 3.4.6-1

RCS Specific Activity 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.2.2.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.2.2.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 NOTE -------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 7 days 1-131 specific activity is a 0.2 pCi/gm.

Amendment 274 JAFNPP 3.4.6-2

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR)

Shutdown Cooling System-Hot Shutdown LCO 3.4.7 APPLICABILITY:

Two RHR shutdown cooling subsystems shall be OPERABLE.

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

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

MODE 3, with reactor steam dome pressure less than the RHR cut in permissive pressure.

ACTIONS NOTES............

ES.......... ----------

1.

LCO 3.0.4 is not applicable.

2.

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two RHR A.1 Initiate action to Immediately shutdown cooling restore RHR shutdown subsystems inoperable, cooling subsystem(s) to OPERABLE status.

AND A.2 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

AND A.3 Be in MODE 4.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Amendment 274 JAFNPP 3.4.7-1

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.7.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify each required RHR shutdown cooling subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.

Amendment 274 FREQUENCY 4.

31 days JAFNPP 3.4.7-2

RHR Shutdown Cooling System-Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR)

Shutdown Cooling System-Cold Shutdown LCO

3.4.8 APPLICABILITY

Two RHR shutdown cooling subsystems shall be OPERABLE.

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

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

MODE 4.

ACTIONS

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

Separate Condition entry is allowed for each shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two RHR A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months shutdown cooling method of decay heat subsystems inoperable, removal is available AND for each inoperable RHR shutdown cooling Once per subsystem.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment 274 JAFNPP 3.4.8-1

RHR Shutdown Cooling System-Cold Shutdown 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify each RHR shutdown cooling subsystem 31 days

manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.

Amendment 274 JAFNPP 3.4.8-2

RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (P/T) Limits LCO

3.4.9 APPLICABILITY

RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within limits.

At all times.

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

NOTE --------- A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed if this Condition is AND entered.

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

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

B. Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

Amendment 274 JAFNPP 3.4.9-1

RCS P/T Limits 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

NOTE --------- C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed if to within limits.

this Condition is entered.

AND C.2 Determine RCS is Prior to Requirements of the acceptable for entering MODE 2 LCO not met in other operation.

or 3 than MODES 1, 2, and 3.

Amendment 274 JAFNPP 3.4.9-2

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.9.1

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

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

Verify:

a.

RCS pressure and RCS temperature are within the limits specified in Figure 3.4.9-1 or Figure 3.4.9-2, as applicable; and

b.

RCS temperature change averaged over a one hour period is:

1.

100'F when the RCS pressure and RCS temperature are on or to the right of curve C of Figure 3.4.9-1 or Figure 3.4.9-2, as applicable, during inservice leak and hydrostatic testing;

2.

20°F when the RCS pressure and RCS temperature are to the left of curve C of Figure 3.4.9-1 or Figure 3.4.9-2, as applicable, during inservice leak and hydrostatic testing; and

3.

. 1007F during other cooldown operations.

heatup and (continued)

Amendment 274 FREQUENCY 30 minutes JAFNPP 3.4.9-3

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in 15 minutes Figure 3.4.9-1 or Figure 3.4.9-2, as prior to applicable.

control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3

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

1.

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump startup.

2.

Not required to be performed if SR 3.4.9.4 is satisfied.

Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes pressure vessel (RPV) coolant temperature prior to each is

145 0F.

startup of a reci rcul ation pump SR 3.4.9.4 NOTES -------------------

1.

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump startup.

2.

Not required to be met if SR 3.4.9.3 is satisfied.

Verify the active recirculation pump flow Once within exceeds 40% of rated pump flow or the 15 minutes active recirculation pump has been prior to each operating below 40% rated flow for a period startup of a no longer than 30 minutes.

recirculation pump (continued)

Amendment 274 3.4.9-4 JAFNPP

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.4.9.5

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump startup.

Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is g 50 0F.

SR 3.4.9.6 NOTE -------------------

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify, when the reactor vessel head bolting studs are under tension, reactor vessel flange and head flange temperatures are

90°F.

SR 3.4.9.7 NOTE -------------------

Not required to be performed until 30 minutes after RCS temperature

100'F with any reactor vessel head bolting stud tensioned.

Verify, when the reactor vessel head bolting studs are under tension, reactor vessel flange and head flange temperatures are Ž 90'F.

FREQUENCY Once within 15 minutes prior to each startup of a recirculation pump 30 minutes 30 minutes (continued)

Amendment 274 JAFNPP 3.4.9-5

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.8

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature : 120'F with any reactor vessel head bolting stud tensioned.

Verify, when the reactor vessel head 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months bolting studs are under tension, reactor vessel flange and head flange temperatures are ; 90'F.

Amendment 274 JAFNPP 3.4.9-6

RCS P/T Limits 3.4.9 1600 1400 1200

0.

CL loo

""1000 CL 0

I 0

0 800 C

A 600 00

h.

0 I

0.

400 200 0

ABH AN8 BBH A

B C

VALID TO 24 EFPY A - System Hydrotest Limit with Fuel in Vessel B - Non-Nuclear Heating Limit C - Nuclear (Core Critical) Limit ABH - System Hydrotest Limit with Fuel in Vessel - Bottom Head ANB - System Hydrotest Limit with Fuel in Vessel - Non Beltline BBH - Non-Nuclear Heating Limit I

II

~~~BELTLINiE_____

ART =95OF i

I I

I

~NON-BELTLINE 1

RTNo-r=30 *F' (90.312.0)

(195,312.5)I

-t I

I I

I (90.3 ~

~120)I{9,312.5)"

SATURATION 0

50 100 150 200 250 300 350 Minimum Reactor Vessel Metal Temperature (OF)

Figure 3.4.9-1 (page 1 of 1)

Reactor Coolant System Pressure and Temperature Limits through 24 Effective Full Power Years (EFPY)

Amendment 274 K

Bottom Head

'/1/ /f'K 3.4.9-7 JAFNPP D I J

t

f

RCS P/T Limits 3.4.9 VALID TO 32 EFPY A - System Hydrotest Limit with Fuel in Vessel B - Non-Nuclear Heating Limit C - Nuclear (Core Critical) Limit NH - System Hydrotest Limit with Fuel in Vessel - Bottom Head ANB - System Hydrotest Limit with Fuel in Vessel - Non Beltline B8H - Non-Nuclear Heating Limit

- Bottom Head 50 100 A1H ANB BB" A

B C

_T1U i 150 200 250 300 350 Minimum Reactor Vessel Metal Temperature (OF)

Figure 3.4.9-2 (page 1 of 1)

Reactor Coolant System Pressure and Temperature Limits through 32 Effective Full Power Years (EFPY)

Amendment 274 1600 1400 1200 1000 800 600 400 P

U)

CL CL 0

U S

I U,9 U,

a..

200 0

0 JAFNPP 3.4.9-8

ML021750467

Contents

Text

Subject:

References:

Dear Sir,

Subject:

Subject:

References:

RESPONSE

3.1.1 APPLICABILITY

3.1.2 APPLICABILITY

3.1.3 APPLICABILITY

3.1.5 APPLICABILITY

3.1.6 APPLICABILITY

3.1.7 APPLICABILITY

3.1.8 APPLICABILITY

3.2.1 APPLICABILITY

3.2.2 APPLICABILITY

3.2.3 APPLICABILITY

3.2.4 APPLICABILITY

Background

Background

3.4.2 APPLICABILITY

3.4.8 APPLICABILITY

3.4.9 APPLICABILITY

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ML021750467

Text

Subject:

References:

Dear Sir,

Subject:

Subject:

References:

RESPONSE

3.1.1 APPLICABILITY

3.1.2 APPLICABILITY

3.1.3 APPLICABILITY

3.1.5 APPLICABILITY

3.1.6 APPLICABILITY

3.1.7 APPLICABILITY

3.1.8 APPLICABILITY

3.2.1 APPLICABILITY

3.2.2 APPLICABILITY

3.2.3 APPLICABILITY

3.2.4 APPLICABILITY

Background

Background

3.4.2 APPLICABILITY

3.4.8 APPLICABILITY

3.4.9 APPLICABILITY

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