Text

Part 1 of 1 - James A. FitzPatrick Nuclear Power Plant, Technical Specifications (License Amendment) as Part of Conversion to Improved Standard Technical Specifications
	ML021750479
Person / Time
Site:	FitzPatrick
Issue date:	06/12/2002
From:	; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML021750479 (176)
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ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS -Operating LCO

3.5.1 APPLICABILITY

Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.

MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure

150 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable, subsystem(s) to OPERABLE status.

OR One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.

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 3.5.1-1

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. HPCI System C.1 Verify by Immediately inoperable, administrative means RCIC System is OPERABLE.

AND C.2 Restore HPCI System 14 days to OPERABLE status.

D. HPCI System D.1 Restore HPCI System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable, to OPERABLE status.

AND OR Condition A entered.

D.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ECCS injection/spray subsystem(s) to OPERABLE status.

E.

One required ADS valve E.1 Restore required ADS 14 days inoperable, valve to OPERABLE status.

F.

One required ADS valve F.1 Restore required ADS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable, valve to OPERABLE status.

AND OR Condition A entered.

F.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ECCS injection/spray subsystem(s) to OPERABLE status.

(continued)

Amendment 274 JAFNPP 3.5.1-2

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.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 C, AND D. E, or F not met.

G.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR dome pressure to

150 psig.

Two or more required ADS valves inoperable.

H.

Two or more low H.1 Enter LCO 3.0.3.

Immediately pressure ECCS injection/spray subsystems inoperable for reasons other than Condition A.

OR HPCI System and one or more required ADS valves inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

(continued)

Amendment 274 JAFNPP 3.5.1-3

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.5.1.2

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

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray 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.

FREQUENCY

+

31 days SR 3.5.1.3 Verify ADS pneumatic supply header pressure 31 days is Ž 95 psig.

SR 3.5.1.4 Verify the RHR System cross tie valves are 31 days closed and power is removed from the electrical valve operator.

SR 3.5.1.5 Cycle open and closed each LPCI motor 31 days operated valve independent power supply battery charger AC input breaker and verify each LPCI inverter output voltage is

576 V and

624 V while supplying the respective bus.

(continued)

Amendment 274 3.5.1-4 JAFNPP

ECCS -Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.5.1.6

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

Not required to be performed if performed within the previous 31 days.

Verify each recirculation pump discharge valve cycles through one complete cycle of full travel or is de-energized in the closed position.

SR 3.5.1.7 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure above primary containment pressure.

SYSTEM FLOW RATE Core Spray LPCI SR 3.5.1.8 S4265 gpm S7700 gpm NO.

OF PUMPS 1

1 SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE ABOVE PRIMARY CONTAINMENT PRESSURE OF

> 113 psi

Ž 20 psi 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, with reactor pressure

1040 psig and ; 970 psig, the HPCI pump can develop a flow rate ; 3400 gpm against a system head corresponding to reactor pressure.

FREQUENCY Once each startup prior to exceeding 25% RTP In accordance with the Inservice Testing Program 4.

In accordance with the Inservice Testing Program (continued)

Amendment 274 JAFNPP 3.5.1-5

ECCS -Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9 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, with reactor pressure

165 psig, 24 months the HPCI pump can develop a flow rate

3400 gpm against a system head corresponding to reactor pressure.

SR 3.5.1.10 ------------------- NOTES--------------

1. For the HPCI System, 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.

2. Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem 24 months actuates on an actual or simulated automatic initiation signal.

SR 3.5.1.11

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

Valve actuation may be excluded.

Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.

SR 3.5.1.12 Verify each LPCI motor operated valve 24 months independent power supply inverter capacity is adequate to supply and maintain in OPERABLE status the required emergency loads for the design duty cycle.

(continued)

Amendment 274 JAFNPP 3.5.1-6

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.13 ------------------- 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 ADS valve opens when 24 months on a manually actuated.

STAGGERED TEST BASIS for each valve solenoid Amendment 274 JAFNPP 3.5.1-7

ECCS - Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.2 ECCS-Shutdown LCO

3.5.2 APPLICABILITY

Two low pressure ECCS injection/spray subsystems shall be OPERABLE.

MODE 4, MODE 5, except with the spent fuel storage pool gates removed and water level 2 22 ft 2 inches over the top of the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required low A.1 Restore required low 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pressure ECCS pressure ECCS injection/spray injection/spray subsystem inoperable.

subsystem to OPERABLE status.

B.

Required Action and B.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A with a potential for not met.

draining the reactor vessel (OPDRVs).

C.

Two required low C.1 Initiate action to Immediately pressure ECCS suspend OPDRVs.

injection/spray subsystems inoperable.

AND C.2 Restore one required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months low pressure ECCS injection/spray subsystem to OPERABLE status.

(continued)

Amendment 274 JAFNPP 3.5.2-1

ECCS - Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary Completion Time not containment to met.

OPERABLE status.

AND D.2 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.

AND D.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months coolant injection (LPCI) subsystem, the suppression pool water level is 2 10.33 ft.

(continued)

Amendment 274 3.5.2-2 JAFNPP

ECCS - Shutdown 3.5.2 SURVE I LLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.5.2.2 Verify, for each required core spray (CS) subsystem, the:

a.

Suppression

10.33 ft; pool water level is or

b................

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

Only one required CS subsystem may take credit for this option during OPDRVs.

The water level in each condensate storage tank is 2 324 inches.

FREQUENCY 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.2.3 Verify, for each required ECCS injection/

31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.2.4 NOTE -------------------

One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued)

Amendment 274 3.5.2-3 JAFNPP

ECCS -Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.5.2.5 Verify each required ECCS pump develops the specified flow rate against a system head corresponding to the specified reactor pressure above primary containment pressure.

SYSTEM FLOW RATE CS 2 4265 gpm LPCI

7700 gpm NO.

OF PUMPS 1

1 SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE ABOVE PRIMARY CONTAINMENT PRESSURE OF S113 psi S20 psi FREQUENCY In accordance with the Inservice Testing Program SR 3.5.2.6 NOTE -------------------

Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray 24 months subsystem actuates on an actual or simulated automatic initiation signal.

Amendment 274 JAFNPP 3.5.2-4

RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.3 RCIC System LCO

3.5.3 APPLICABILITY

The RCIC System shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RCIC System A.1 Verify by Immediately inoperable, administrative means High Pressure Coolant Injection System is OPERABLE.

AND A.2 Restore RCIC System 14 days 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.

AND B.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months dome pressure to S150 psig.

Amendment 274 3.5.3-1 JAFNPP

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with water from the pump discharge valve to the injection valve.

SR 3.5.3.2 Verify each RCIC System manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.3.3 NOTE -------------------

Not required to be performed until 12 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, with reactor pressure

1040 psig 92 days and 2 970 psig, the RCIC pump can develop a flow rate 2 400 gpm against a system head corresponding to reactor pressure.

SR 3.5.3.4

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, with reactor pressure

165 psig, 24 months the RCIC pump can develop a flow rate

Ž 400 gpm against a system head corresponding to reactor pressure.

(continued)

Amendment 274 JAFNPP 3.5.3-2

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5 NOTES ------------------

1.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

2.

Vessel injection may be excluded.

Verify the RCIC System actuates on an 24 months actual or simulated automatic initiation signal.

Amendment 274 JAFNPP 3.5.3-3

Primary Containment 3.6.1.1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment LCO 3.6.1.1 APPLICABILITY:

Primary containment shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Primary containment A.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, containment to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

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

AND B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Amendment 274 JAFNPP 3.6.1.1-1

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and In accordance leakage rate testing except for primary with the containment air lock testing, in Primary accordance with the Primary Containment Containment Leakage Rate Testing Program.

Leakage Rate Testing Program SR 3.6.1.1.2 Verify suppression chamber pressure 24 months increase is g 0.25 in. water gauge per minute over a 10 minute period with a AND drywell to suppression chamber differential pressure of Ž 1 psi.

.NOTE -----

Only required after two consecutive tests fail and continues until two consecutive tests pass 12 months Amendment 274 JAFNPP 3.6.1.1-2

Primary Containment Air Locks 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2 APPLICABILITY:

Two primary containment air locks shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS

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

1.

Entry and exit is permissible to perform repairs of the affected air lock components.

2.

Separate Condition entry is allowed for each air lock.

3.

Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when air lock leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more primary NOTES -----------

containment air locks

1.

Required Actions A.1, with one primary A.2, and A.3 are not containment air lock applicable if both doors door inoperable, in the same air lock are inoperable and Condition C is entered.

2.

Entry and exit is permissible for 7 days under administrative control s.

A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND (continued)

Amendment 274 3.6.1.2-1 JAFNPP

Primary Containment Air Locks 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2 Lock the OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed in the affected air lock.

AND A.3

NOTE --------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.

B.

One or more primary

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

containment air locks

1.

Required Actions B.1, with primary B.2, and B.3 are not containment air lock applicable if both doors interlock mechanism in the same air lock are inoperable, inoperable and Condition C is entered.

2.

Entry into and exit from primary containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND (continued)

Amendment 274 JAFNPP 3.6.1.2-2

Primary Containment Air Locks 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock.

AND B.3

NOTE --------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify an OPERABLE Once per 31 days door is locked closed in the affected air lock.

C.

One or more primary C.1 Initiate action to Immediately containment air locks evaluate primary inoperable for reasons containment overall other than Condition A leakage rate per or B.

LCO 3.6.1.1, using current air lock test results.

AND C.2 Verify a door is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months closed in the affected air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

Amendment 274 JAFNPP 3.6.1.2-3

Primary Containment Air Locks 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 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 not met.

AND D.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 3.6.1.2.1 NOTES ----------------

1.

An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2.

Results shall be evaluated against criteria applicable to SR 3.6.1.1.1.

Perform required primary containment air In accordance lock leakage rate testing in accordance with the with the Primary Containment Leakage Rate Primary Testing Program.

Containment Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary 24 months containment air lock can be opened at a time.

Amendment 274 JAFNPP 3.6.1.2-4

PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 APPLICABILITY:

Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.

MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."

Amendment 274 3.6.1.3-1 JAFNPP

PCIVs 3.6.1.3 ACTIONS

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

1.

Penetration flow paths may be unisolated intermittently under administrative controls.

2.

Separate Condition entry is allowed for each penetration flow path.

3.

Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4.

Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A.

NOTE --------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except Only applicable to penetration flow path for main steam penetration flow paths by use of at least line with two or more one closed and PCIVs.

de-activated AND automatic valve, closed manual valve, 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main One or more blind flange, or steam line penetration flow paths check valve with flow with one PCIV through the valve inoperable for reasons secured.

other than Conditions D and E.

AND (continued)

Amendment 274 3.6.1.3-2 JAFNPP

PCIVS 3.6.1.3 ACTIONS CONDITION IREQUIRED ACTION COMPLETION TIME A.

(continued)

A.2 NOTES -------

1.

Isolation devices in high radiation areas may be verified by use of administrative means.

2.

Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4, if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment (continued)

Amendment 274 JAFNPP 3.6.1.3-3

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ---------NOTE --------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path penetration flow paths by use of at least with two or more one closed and PCIVs.

de-activated automatic valve, closed manual valve, One or more or blind flange.

penetration flow paths with two or more PCIVs inoperable for reasons other than Conditions D and E.

C.

NOTE --------- C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except Only applicable to penetration flow path for excess flow penetration flow paths by use of at least check valves with only one PCIV.

one closed and (EFCVs) and de-activated penetrations automatic valve, with a closed One or more closed manual valve, system penetration flow paths or blind flange.

with one PCIV AND inoperable for reasons other than Conditions 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for D and E.

EFCVs and penetrations with a closed system AND (continued)

Amendment 274 JAFNPP 3.6.1.3-4

PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2

NOTES -------

1.

Isolation devices in high radiation areas may be verified by use of administrative means.

2.

Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

D. One or more D.1 Restore leakage rate 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months penetration flow paths to within limit.

with one or more MSIVs not within leakage rate limit.

E.

One or more E.1 Restore leakage rate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months penetration flow paths to within limit.

with LPCI System or CS System testable check valve leakage limit not met.

(continued)

Amendment 274 JAFNPP 3.6.1.3-5

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

Required Action and F.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, C, D, or E not met in MODE 1, 2, or 3.

F.2 Be in MODE 4.

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

Required Action and G.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A or with a potential for B not met for PCIV(s) draining the reactor required to be vessel.

OPERABLE during MODE 4 or 5.

OR G.2 Initiate action to Immediately restore valve(s) to OPERABLE status.

Amendment 274 3.6.1.3-6 JAFNPP

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.6.1.3.1 SR 3.6.1.3.2

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

Not required to be met when the 20 inch and 24 inch primary containment vent and purge valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open, provided the full-flow line to Standby Gas Treatment (SGT)

System is closed and one or more SGT System reactor building suction valves are open.

Verify each 20 inch and 24 inch primary containment vent and purge valve is closed.

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

1.

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2.

Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual valve and blind flange that is located outside primary containment and not locked, sealed or otherwise secured and is required to be closed during accident conditions is closed.

(continued)

Amendment 274 PCIVs 3.6.1.3 FREQUENCY 31 days 31 days JAFNPP 3.6.1.3-7

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.6.1.3.3 NOTES -----------------

1.

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2.

Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual isolation valve and blind flange that is located inside primary containment and not locked, sealed or otherwise secured and is required to be closed during accident conditions is closed.

FREQUENCY Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing 31 days incore probe (TIP) shear isolation valve explosive charge.

SR 3.6.1.3.5 Verify the isolation time of each power In accordance operated, automatic PCIV, except for with the MSIVs, is within limits.

Inservice Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV is In accordance

3 seconds and

5 seconds.

with the Inservice Testing Program (continued)

Amendment 274 I

JAFNPP 3.6.1.3-8

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.7 Verify each automatic PCIV actuates to 24 months the isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify each reactor instrumentation line In accordance EFCV actuates to the isolation position with the on a simulated instrument line break.

Inservice Testing Program SR 3.6.1.3.9 Remove and test the explosive squib from 24 months on a each shear isolation valve of the TIP STAGGERED TEST System.

BASIS SR 3.6.1.3.10 Verify leakage rate through each MSIV is In accordance g 11.5 scfh when tested at > 25 psig.

with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.11 Verify the leakage rate of each air In accordance operated testable check valve associated with the with the LPCI and CS Systems vessel Primary injection penetrations is within limits.

Containment Leakage Rate Testing Program Amendment 274 JAFNPP 3.6.1.3-9

Drywell Pressure 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Drywell Pressure LCO 3.6.1.4 APPLICABILITY:

Drywell pressure shall be g 1.95 psig.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell pressure not A.1 Restore drywell 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within limit, pressure 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.

AND B.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 3.6.1.4.1 Verify drywell pressure is within limit.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Amendment 274 JAFNPP 3.6.1.4-1

Drywell Air Temperature 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Drywell Air Temperature LCO 3.6.1.5 APPLICABILITY:

Drywell average air temperature shall be g 135 0 F.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Drywell average air A.1 Restore drywell 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within average air

limit, temperature 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.

AND B.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 3.6.1.5.1 Verify drywell average air temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limit.

Amendment 274 3.6.1.5-1 JAFNPP

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers LCO 3.6.1.6 APPLICABILITY:

Each reactor building-to-suppression chamber vacuum breaker shall be OPERABLE.

MODES 1, 2, and 3.

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

Separate Condition entry is allowed for each line.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more lines with A.1 Close the open vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months one reactor building-breaker.

to-suppression chamber vacuum breaker not closed.

B.

One or more lines with B.1 Close one open vacuum I hour two reactor building-breaker.

to-suppression chamber vacuum breakers not closed.

C.

One line with one or C.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months more reactor building-breaker(s) to to-suppression chamber OPERABLE status.

vacuum breakers inoperable for opening.

(continued)

Amendment 274 ACTIONS JAFNPP 3.6.1.6-1

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Two lines with one or D.1 Restore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months more reactor building-breakers in one line to-suppression chamber to OPERABLE status.

vacuum breakers inoperable for opening.

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 not met.

AND E.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 3.6.1.6.1 NOTES -----------------

1.

Not required to be met for vacuum breakers that are open during Surveillances.

2.

Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed.

14 days SR 3.6.1.6.2 Perform a functional test of each vacuum In accordance breaker.

with the Inservice Testing Program (continued)

Amendment 274 3.6.1.6-2 JAFNPP

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.6.3 Perform a CHANNEL CALIBRATION of each air 92 days operated vacuum breaker differential pressure instrument channel and verify the setpoint is < 0.5 psid.

SR 3.6.1.6.4 Verify the opening setpoint of each self 24 months actuating vacuum breaker is : 0.5 psid.

Amendment 274 3.6.1.6-3 JAFNPP

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 3.6 CONTAINMENT SYSTEMS 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers LCO 3.6.1.7 APPLICABILITY:

Each suppression chamber-to-drywell vacuum breaker shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One suppression A.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months chamber-to-drywell breaker to OPERABLE vacuum breaker status.

inoperable for opening.

B.

One suppression B.1 Close the open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months chamber-to-drywell breaker.

vacuum breaker not closed.

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.

AND C.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Amendment 274 JAFNPP 3.6.1.7-1

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.6.1.7.1 NOTES -----------------

1.

Not required to be met for vacuum breakers that are open during Surveillances.

2.

Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed.

.7 FREQUENCY 14 days SR 3.6.1.7.2 Perform a functional test of each vacuum In accordance breaker.

with the Inservice Testing Program SR 3.6.1.7.3 Verify the opening setpoint of each 24 months vacuum breaker is

0.5 psid.

Amendment 274 3.6.1.7-2 JAFNPP

MSLC System 3.6.1.8 3.6 CONTAINMENT SYSTEMS 3.6.1.8 Main Steam Leakage Collection (MSLC)

System LCO 3.6.1.8 APPLICABILITY:

Two MSLC subsystems shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One MSLC subsystem A.1 Restore MSLC 30 days inoperable, subsystem to OPERABLE status.

B.

Two MSLC subsystems B.1 Restore one MSLC 7 days 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.

AND C.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Amendment 274 JAFNPP 3.6.1.8-1

MSLC System 3.6.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.8.1 Verify each MSLC subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

SR 3.6.1.8.2 Perform a system functional test of each 24 months MSLC subsystem.

Amendment 274 JAFNPP 3.6.1.8-2

RHR Containment Spray System 3.6.1.9 3.6 CONTAINMENT SYSTEMS 3.6.1.9 Residual Heat Removal (RHR)

Containment Spray System LCO 3.6.1.9 APPLICABILITY:

Two RHR containment spray subsystems shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR containment A.1 Restore RHR 7 days spray subsystem containment spray inoperable, subsystem to OPERABLE status.

B.

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

AND C.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Amendment 274 3.6.1.9-1 JAFNPP

RHR Containment Spray System 3.6.1.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.9.1 Verify each RHR containment spray 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

SR 3.6.1.9.2 Verify each required RHR pump develops a In accordance flow rate of ; 7750 gpm through the with the associated heat exchanger while operating Inservice in the suppression pool cooling mode.

Testing Program SR 3.6.1.9.3 Verify each spray nozzle is unobstructed.

10 years Amendment 274 JAFNPP 3.6.1.9-2

Suppression Pool Average Temperature 3.6.2.1 3.6 CONTAINMENT SYSTEMS 3.6.2.1 Suppression Pool Average Temperature LCO 3.6.2.1 Suppression pool average temperature shall be:

a.

95 0F with THERMAL POWER > 1% RTP and no testing that adds heat to the suppression pool is being performed;

b.

105'F with THERMAL POWER >

adds heat to the suppression and 1% RTP and testing that pool is being performed;

c.

110°F with THERMAL POWER g 1% RTP.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool A.1 Verify suppression Once per hour average temperature pool average

> 95 0F but ! 110 0F.

temperature : 1107F.

AND AND THERMAL POWER A.2 Restore suppression 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> 1% RTP.

pool average temperature to AND

957F.

Not performing testing that adds heat to the suppression pool.

(continued)

Amendment 274 JAFNPP 3.6.2.1-1

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and B.1 Reduce THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion to

1% RTP.

Time of Condition A not met.

C. Suppression pool C.1 Suspend all testing Immediately average temperature that adds heat to the

> 105 0 F.

suppression pool.

AND THERMAL POWER

> 1% RTP.

AND Performing testing that adds heat to the suppression pool.

D. Suppression pool D.1 Place the reactor Immediately average temperature mode switch in the

> 110°F but g 1200F.

shutdown position.

AND D.2 Verify suppression Once per pool average 30 minutes temperature s 120 0 F.

AND D.3 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

Amendment 274 JAFNPP 3.6.2.1-2

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

Suppression pool E.1 Depressurize the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months average temperature reactor vessel to

> 120 0F.

< 200 psig.

AND E.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 3.6.2.1.1 Verify suppression pool average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months temperature is within the applicable limits.

AND 5 minutes when performing testing that adds heat to the suppression pool Amendment 274 JAFNPP 3.6.2.1-3

Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 APPLICABILITY:

Suppression pool water level shall be 2 13.88 ft and

14 ft.

NOTE.............................

Not required to be met for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during Surveillances that cause suppression pool water level to be outside the limit.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within pool water level to

limits, within 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 not met.

AND B.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 3.6.2.2.1 Verify suppression pool water level is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limits.

Amendment 274 JAFNPP 3.6.2.2-1

RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 Two RHR suppression OPERABLE.

pool cooling subsystems shall be APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR suppression A.1 Restore RHR 7 days pool cooling subsystem suppression pool inoperable, cooling subsystem to OPERABLE status.

B.

Two RHR suppression B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pool cooling suppression pool subsystems inoperable, cooling 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.

AND C.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Amendment 274 3.6.2.3-1 JAFNPP

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each required RHR pump develops a In accordance flow rate 2 7700 gpm through the with the associated heat exchanger while operating Inservice in the suppression pool cooling mode.

Testing Program Amendment 274 3.6.2.3-2 JAFNPP

Drywell -to-Suppression Chamber Differential Pressure 3.6.2.4 3.6 CONTAINMENT SYSTEMS 3.6.2.4 Drywell-to-Suppression Chamber Differential Pressure LCO 3.6.2.4 APPLICABILITY:

The drywell pressure shall be maintained 2 1.7 psi above the pressure of the suppression chamber.

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

Not required to be met for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during Surveillances that cause or require the drywell-to-suppression chamber differential pressure to be outside the limit.

MODE 1 during the time period:

a.

From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell-to-suppression A.1 Restore differential 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months chamber differential pressure to within pressure not within limit.

limit.

B.

Required Action and B.1 Reduce THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion to

15% RTP.

Time not met.

Amendment 274 3.6.2.4-1 JAFNPP

Drywell-to-Suppression Chamber Differential Pressure 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify drywell-to-suppression chamber 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months differential pressure is within limit.

Amendment 274 JAFNPP 3.6.2.4-2

Primary Containment Oxygen Concentration 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Oxygen Concentration LCO 3.6.3.1 APPLICABILITY:

The primary containment oxygen concentration shall be

< 4.0 volume percent.

MODE 1 during the time period:

a.

From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Primary containment A.1 Restore oxygen 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months oxygen concentration concentration to not within limit, within limit.

B. Required Action and B.1 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion to ! 15% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify primary containment oxygen 7 days concentration is within limits.

Amendment 274 JAFNPP 3.6.3.1-1

CAD System 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Containment Atmosphere Dilution (CAD) System LCO 3.6.3.2 APPLICABILITY:

Two CAD subsystems shall be OPERABLE.

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CAD subsystem A.1

NOTE------

inoperable.

LCO 3.0.4 is not applicable.

Restore CAD subsystem 30 days to OPERABLE status.

B.

Two CAD subsystems B.1 Verify by 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, administrative means that the hydrogen AND control function is maintained.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Restore one CAD 7 days subsystem to OPERABLE status.

C.

Required Action and C.1 Be in MODE 3.

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

Amendment 274 JAFNPP 3.6.3.2-1

CAD System 3.6.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Verify Ž 1400 gal of liquid nitrogen are 31 days contained in each CAD subsystem.

SR 3.6.3.2.2 Verify each CAD subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

Amendment 274 JAFNPP 3.6.3.2-2

Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

MODES 1, 2, and 3, During movement of irradiated fuel secondary containment, During CORE ALTERATIONS, During operations with a potential vessel (OPDRVs).

assemblies in the for draining the reactor ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable in MODE 1, containment to 2, or 3.

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 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 C.

Secondary containment C.1

NOTE --------

inoperable during LCO 3.0.3 is not movement of irradiated applicable.

fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel OPDRVs.

assemblies in the secondary containment.

AND (continued)

Amendment 274 APPLICABILITY:

3.6.4.1-1 JAFNPP

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Ž 0.25 inch of vacuum water gauge.

SR 3.6.4.1.2 Verify all secondary containment 31 days equipment hatches are closed and sealed.

SR 3.6.4.1.3 Verify one secondary containment access 31 days door in each access opening is closed.

SR 3.6.4.1.4 Verify the secondary containment can be 24 months on a maintained > 0.25 inch of vacuum water STAGGERED TEST gauge for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months using one SGT subsystem BASIS for each at a flow rate < 6000 cfm.

SGT subsystem Amendment 274 JAFNPP 3.6.4.1-2

SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

MODES 1, 2, and 3, During movement of irradiated fuel secondary containment, During CORE ALTERATIONS, During operations with a potential vessel (OPDRVs).

assemblies in the for draining the reactor ACTIONS NOTES -------

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

1.

Penetration flow paths may be unisolated intermittently under administrative control s.

2.

Separate Condition entry is allowed for each penetration flow path.

3.

Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months penetration flow paths penetration flow path with one SCIV by use of at least inoperable, one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND (continued)

Amendment 274 APPLICABILITY:

JAFNPP 3.6.4.2-1

SCIVs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2

NOTES -------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

B.

NOTE --------- B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path penetration flow paths by use of at least with two isolation one closed and valves.

de-activated automatic valve, closed manual valve, One or more or blind flange.

penetration flow paths with two SCIVs 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 AND or B not met in MODE 1, 2, or 3.

C.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 3.6.4.2-2

SCIVs 3.6.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1

NOTE --------

associated Completion LCO 3.0.3 is not Time of Condition A applicable.

or B not met during movement of irradiated fuel assemblies in the Suspend movement of Immediately secondary containment, irradiated fuel during CORE assemblies in the ALTERATIONS, or during secondary OPDRVs.

containment.

AND D.2 Suspend CORE Immediately ALTERATIONS.

AND D.3 Initiate action to Immediately suspend OPDRVs.

Amendment 274 JAFNPP 3.6.4.2-3

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.6.4.2.1

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

1.

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2.

Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment isolation manual valve and blind flange that is not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

FREQUENCY 31 days SR 3.6.4.2.2 Verify the isolation time of each power 92 days operated, automatic SCIV is within limits.

SR 3.6.4.2.3 Verify each automatic SCIV actuates to 24 months the isolation position on an actual or simulated actuation signal.

Amendment 274 JAFNPP 3.6.4.2-4

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT)

System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

MODES 1, 2, and 3, During movement of irradiated fuel secondary containment, During CORE ALTERATIONS, During operations with a potential vessel (OPDRVs).

assemblies in the for draining the reactor ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

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

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2, or 3.

B.2 Be in MODE 4.

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

Required Action and

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

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated C.1 Place OPERABLE SGT Immediately fuel assemblies in the subsystem in secondary containment, operation.

during CORE ALTERATIONS, or during OR OPDRVs.

(continued)

Amendment 274 APPLICABILITY:

3.6.4.3-1 JAFNPP

SGT System 3.6.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2.1 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

AND C.2.3 Initiate action to Immediately suspend OPDRVs.

D.

Two SGT subsystems D.1 Enter LCO 3.0.3.

Immediately inoperable in MODE 1, 2, or 3.

E.

Two SGT subsystems E.1

NOTE --------

inoperable during LCO 3.0.3 is not movement of irradiated applicable.

fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel OPDRVs.

assemblies in secondary containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to Immediately suspend OPDRVs.

Amendment 274 JAFNPP 3.6.4.3-2

SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 31 days

10 continuous hours with heaters operating.

SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an 24 months actual or simulated initiation signal.

SR 3.6.4.3.4 Manually cycle each SGT subsystem filter 24 months cooling cross-tie valve.

Amendment 274 JAFNPP 3.6.4.3-3

RHRSW System 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW)

System LCO

3.7.1 APPLICABILITY

Two RHRSW subsystems shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHRSW pump A.1 Restore RHRSW pump to 30 days inoperable.

OPERABLE status.

B.

One RHRSW pump in each B.1 Restore one RHRSW 7 days subsystem inoperable, pump to OPERABLE status.

C.

One RHRSW subsystem

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

inoperable for reasons Enter applicable Conditions other than and Required Actions of LCO Condition A.

3.4.7, "Residual Heat Removal (RHR)

Shutdown Cooling System-Hot Shutdown," for RHR shutdown cooling made inoperable by RHRSW System.

C.1 Restore RHRSW 7 days subsystem to OPERABLE status.

(continued)

Amendment 274 3.7.1-1 JAFNPP

RHRSW System 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Both RHRSW subsystems

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

inoperable for reasons Enter applicable Conditions other than and Required Actions of LCO Condition B.

3.4.7 for RHR shutdown cooling made inoperable by RHRSW System.

D.1 Restore one RHRSW 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months subsystem to OPERABLE status.

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 not met.

AND E.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 3.7.1.1 Verify each RHRSW manual, power operated, 31 days and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

Amendment 274 3.7.1-2 JAFNPP

ESW System and UHS 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Emergency Service Water (ESW)

System and Ultimate Heat Sink (UHS)

LCO

3.7.2 APPLICABILITY

Two ESW subsystems and UHS shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One ESW subsystem

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

inoperable.

Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources Operating," for emergency diesel generator subsystem made inoperable by ESW.

A.1 Restore the ESW 7 days subsystem to OPERABLE status.

B.

One division of B.1 Restore the division of 7 days required deicing deicing heaters to heaters inoperable.

OPERABLE status.

AND UHS temperature S37°F.

(continued)

Amendment 274 3.7.2-1 JAFNPP

ESW System and UHS 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 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.

AND OR C.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Both ESW subsystems inoperable for reasons other than Condition A.

OR UHS inoperable for reasons other than Condition B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in the ESW pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months screenwell is k 236.5 ft mean sea level.

SR 3.7.2.2 Verify the average water temperature of UHS 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is

85°F.

(continued)

Amendment 274 3.7.2-2 JAFNPP

ESW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.2.3 NOTE -------------------

Not required to be met if UHS temperature is > 37 0F.

Verify the required deicing heater feeder 7 days current is within limits for each division of deicing heaters.

SR 3.7.2.4 NOTE -------------------

Isolation of flow to individual components does not necessarily render ESW System inoperable.

Verify each ESW subsystem manual, power 31 days operated, and automatic valve in the flow paths servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.2.5 NOTE -------------------

Not required to be met if UHS temperature is > 37 0F.

Verify the required deicing heater power is 6 months within limits for each division of deicing heaters.

(continued)

Amendment 274 JAFNPP 3.7.2-3

ESW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.2.6 NOTE -------------------

Not required to be met if UHS temperature is > 370F.

Verify the required deicing heater 12 months resistance to ground is within limits for each division of deicing heaters.

SR 3.7.2.7 Verify each ESW subsystem actuates on an 24 months actual or simulated initiation signal.

Amendment 274 JAFNPP 3.7.2-4

CREVAS System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS)

System LCO 3.7.3 Two CREVAS subsystems shall be OPERABLE.

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

The control room boundary may be opened intermittently under administrative control.

MODES 1, 2, and 3, During movement of irradiated fuel secondary containment, During CORE ALTERATIONS, During operations with a potential vessel (OPDRVs).

assemblies in the for draining the reactor ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

B.

Two CREVAS subsystems B.1 Restore control room 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable due to boundary to OPERABLE inoperable control status.

room boundary in MODE 1, 2. or 3.

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 AND B not met in MODE 1,

2. or 3.

C.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

Amendment 274 APPLICABILITY:

JAFNPP 3.7.3-1

CREVAS System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and

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

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated D.1 Place OPERABLE CREVAS Immediately fuel assemblies in the subsystem in isolate secondary containment, mode.

during CORE ALTERATIONS, or during OR OPDRVs.

D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.

E.

Two CREVAS subsystems E.1 Enter LCO 3.0.3.

Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

Amendment 274 JAFNPP 3.7.3-2

CREVAS System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREVAS subsystems

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

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel assemblies in the secondary containment, F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS, or during assemblies in the OPDRVs.

secondary containment.

AND F.2 Suspend CORE Immediately ALTERATIONS.

AND F.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREVAS subsystem for 92 days

Ž 15 minutes.

SR 3.7.3.2 Perform required CREVAS filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

(continued)

Amendment 274 3.7.3-3 JAFNPP

CREVAS System 3.7.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.3.3 Verify each CREVAS subsystem can maintain a 18 months on a positive pressure of e 0.125 inches water STAGGERED TEST gauge relative to atmosphere and turbine BASIS building during the isolate mode of operation at a flow rate of ; 900 scfm and scfm.

Amendment 274 JAFNPP 3.7.3-4

Control Room AC 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC)

System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.

MODES 1, 2, and 3, During movement of irradiated fuel secondary containment, During CORE ALTERATIONS, During operations with a potential vessel (OPDRVs).

assemblies in the for draining the reactor ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One control room AC A.1 Restore control room 30 days subsystem inoperable.

AC subsystem 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 of Condition A AND not met in MODE 1, 2, or 3.

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 System

3.7.4 APPLICABILITY

3.7.4-1 JAFNPP

Control Room ACSystem 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and

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

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated C.1 Place OPERABLE Immediately fuel assemblies in the control room AC secondary containment, subsystem in during CORE operation.

ALTERATIONS, or during OPDRVs.

OR C.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

AND C.2.3 Initiate action to Immediately suspend OPDRVs.

D.

Two control room AC D.1 Enter LCO 3.0.3.

Immediately subsystems inoperable in MODE 1, 2, or 3.

(continued)

Amendment 274 3.7.4-2 JAFNPP

Control Room AC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

Two control room AC

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

subsystems inoperable LCO 3.0.3 is not applicable.

during movement of irradiated fuel assemblies in the E.1 Suspend movement of Immediately secondary containment, irradiated fuel during CORE assemblies in the ALTERATIONS, or during secondary OPDRVs.

containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has 24 months the capability to remove the assumed heat load.

Amendment 274 JAFNPP 3.7.4-3

Main Condenser SJAE Offgas 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Main Condenser Steam Jet Air Ejector (SJAE) Offgas LCO 3.7.5 The gross gamma activity rate of the noble gases measured at the discharge of the SJAE (prior to dilution and/or discharge) shall be g 600,000 pCi/second.

APPLICABILITY:

MODE 1.

MODES 2 and 3 with steam jet air any main steam line not isolated and ejector (SJAE) in operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross gamma activity A.1 Restore gross gamma 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months rate of the noble activity rate of the gases not within noble gases to within

limit, limit.

B. Required Action and B.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion steam lines.

Time not met.

OR B.2 Isolate SJAE.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR B.3.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.3.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Amendment 274 3.7.5-1 JAFNPP

Main Condenser SJAE Offgas 3.7.5 SURVEI LLANCE REQUIREMENTS SURVEILLANCE SR 3.7.5.1 NOTE -------------------

Not required to be performed until 31 days after any main steam line not isolated and SJAE in operation.

Verify the gross gamma activity rate of the noble gases is

600,000 pCi/second.

T FREQUENCY 1*

31 days AND NOTE ----

Only required when gross gamma activity rate is

Ž 5,000 pCi/second Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a 2 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level Amendment 274 JAFNPP 3.7.5-2

Main Turbine Bypass 3.7 PLANT SYSTEMS 3.7.6 Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.

OR The following limits are made applicable:

a.

LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and

b.

LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR.

APPLICABILITY:

THERMAL POWER

Ž 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1 Satisfy the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 System 3.7.6 3.7.6-1 JAFNPP

Main Turbine Bypass System 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each required Prior to main turbine bypass valve, entering MODE 2 or 3 from MODE 4 SR 3.7.6.2 Perform a system functional test.

24 months SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM RESPONSE 24 months TIME is within limits.

Amendment 274 3.7.6-2 JAFNPP

Spent Fuel Storage Pool Water 3.7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LCO 3.7.7 The spent fuel storage pool water level shall be 2 21 ft 7 inches over the top of irradiated fuel seated in the spent fuel storage pool racks.

assemblies APPLICABILITY:

During movement of irradiated fuel assemblies in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Spent fuel storage A.1

NOTE --------

pool water level not LCO 3.0.3 is not within limit, applicable.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water 7 days level is

Ž 21 ft 7 inches over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

Amendment 274 Level 3.7.7 3.7.7-1 JAFNPP

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO

3.8.1 APPLICABILITY

The following AC electrical power sources shall be OPERABLE:

a.

Two qualified circuits between the offsite transmission network and the plant Class 1E AC Electrical Power Distribution System; and

b.

Two emergency diesel generator (EDG) subsystems.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One offsite circuit A.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

for OPERABLE offsite circuit.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from feature(s) with no discovery of no offsite power offsite power to available inoperable one division when the redundant concurrent with required feature(s) inoperability of are inoperable, redundant required feature(s)

AND (continued)

Amendment 274 3.8.1-1 JAFNPP

AC Sources-Operating 3.8.1 CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3 Restore offsite 7 days circuit to OPERABLE status.

AND 21 days from discovery of failure to meet LCO B.

One EDG subsystem inoperable.

Perform SR 3.8.1.1 for OPERABLE offsite circuit(s).

Declare required feature(s), supported by the inoperable EDG subsystem, inoperable when the redundant required feature(s) are inoperable.

AND B.3.1 Determine OPERABLE EDG subsystem is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for OPERABLE EDG subsystem.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours (continued)

Amendment 274 ACTIONS B.1 AND B.2 3.8.1-2 JAFNPP

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.4 Restore EDG subsystem 14 days to OPERABLE status.

AND 21 days from discovery of failure to meet LCO C.

Two offsite circuits C.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable, feature(s) inoperable discovery of when the redundant Condition C required feature(s) concurrent with are inoperable.

inoperability of redundant required feature(s)

AND C.2 Restore one offsite 7 days circuit to OPERABLE status.

D.

One offsite circuit

NOTE---------

inoperable.

Enter applicable Conditions and Required Actions of AND LCO 3.8.7, "Distribution Systems -Operating,"

when One EDG subsystem Condition D is entered with inoperable, no AC power source to any division.

D.1 Restore offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status.

OR (continued)

Amendment 274 JAFNPP 3.8.1-3

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

(continued)

D.2 Restore EDG subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to OPERABLE status.

E.

Two EDG subsystems E.1 Restore one EDG 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable, subsystem to OPERABLE status.

F.

Required Action and F.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, C, D, or E not met.

F.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Three or more AC G.1 Enter LCO 3.0.3.

Immediately sources inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days indicated power availability for each offsite circuit.

(continued)

Amendment 274 JAFNPP 3.8.1-4

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.2

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

All EDG subsystem starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

Verify each EDG subsystem starts from 31 days standby conditions, force parallels, and achieves:

a.

In

10 seconds, voltage 2 3900 V and frequency ; 58.8 Hz; and

b.

Steady state voltage 2 3900 V and

, 4400 V and frequency 2 58.8 Hz and

61.2 Hz.

SR 3.8.1.3

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

1.

EDG loadings may include gradual loading as recommended by the manufacturer.

2.

Momentary transients outside the load range do not invalidate this test.

3.

This Surveillance shall be conducted on only one EDG subsystem at a time.

4.

This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2.

Verify each EDG subsystem is paralleled 31 days with normal, reserve, or backfeed power and each EDG is loaded and operates for 2 60 minutes at a load ; 2340 kW and S2600 kW.

(continued)

Amendment 274 JAFNPP 3.8.1-5

AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains > 327 gal of 31 days fuel oil.

SR 3.8.1.5 Check for and remove accumulated water from 31 days each day tank.

SR 3.8.1.6 Verify that each EDG fuel oil transfer 31 days system operates to automatically transfer fuel oil from its storage tank to the associated day tank.

SR 3.8.1.7 NOTE --------------------

Only required to be met for each offsite circuit that is not energizing its respective 4.16 kV emergency bus.

Verify automatic and manual transfer of 24 months plant power supply from the normal station service transformer to each offsite circuit.

(continued)

Amendment 274 JAFNPP 3.8.1-6

AC Sources - Operating 3.8.1 SURVE I LLANCE REQU I REMENTS (continued)

SURVEILLANCE SR 3.8.1.8 NOTE --------------------

If performed with the EDG subsystem paralleled with normal, reserve, or backfeed power, it shall be performed within the power factor limit.

However, if grid conditions do not permit, the power factor limit is not required to be met.

Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each EDX greater than or single largest following load

66.75 Hz.

subsystem rejects a load equal to its associated post-accident load, and rejection, the frequency is FREQUENCY 24 months (continued)

Amendment 274 JAFNPP 3.8.1-7

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.8.1.9

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

All EDG subsystem starts may be preceded by an engine prelube period.

Verify on an actual or simulated loss of power signal:

a.

De-energization of emergency buses;

b.

Load shedding from emergency buses; and

c.

EDG subsystem auto-starts from standby condition, force parallels, and:

1.

energizes permanently connected loads in

11 seconds,

2.

energizes auto-connected shutdown

loads,

3.

maintains steady state voltage

Ž 3900 V and ! 4400 V,

4.

maintains steady state frequency 2 58.8 Hz and : 61.2 Hz, and

5.

supplies permanently connected and auto-connected shutdown loads for 2 5 minutes.

FREQUENCY 24 months (continued)

Amendment 274 3.8.1-8 JAFNPP

AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.10 ------------------- NOTE -------------------

All EDG subsystem starts may be preceded by an engine prelube period.

Verify on an actual or simulated Emergency 24 months Core Cooling System (ECCS) initiation signal each EDG subsystem auto-starts from standby condition, force parallels, and:

a.

In. 10 seconds after auto-start and during tests, achieves voltage

> 3900 V, frequency 2 58.8 Hz;

b.

Achieves steady state voltage Ž 3900 V and g 4400 V and frequency Ž 58.8 Hz and : 61.2 Hz;

c.

Operates for 2 5 minutes;

d.

Permanently connected loads remain energized from the offsite power system; and

e.

Emergency loads are auto-connected in the prescribed sequence from the offsite power system.

(continued)

Amendment 274 3.8.1-9 JAFNPP

AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 ------------------- NOTES ------------------

1.

Momentary transients outside the load and power factor ranges do not invalidate this test.

2.

If grid conditions do not permit, the power factor limit is not required to be met.

Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each EDG subsystem operating within 24 months the power factor limit operates for S8 hours:

a.

For 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months each EDG loaded

Ž 2730 kW and

2860 kW; and

b.

For the remaining hours of the test each EDG loaded ; 2340 kW and

2600 kW.

(continued)

Amendment 274 JAFNPP 3.8.1-10

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.8.1.12 ------------------- NOTE -------------------

All EDG subsystem starts may be preceded by an engine prelube period.

Verify, on an actual or simulated loss of power signal in conjunction with an actual or simulated ECCS initiation signal:

a.

De-energization of emergency buses;

b.

Load shedding from emergency buses; and

c.

EDG subsystem auto-starts from standby condition, force parallels, and:

1.

energizes permanently connected loads in

11 seconds,

2.

energizes auto-connected emergency loads in the prescribed

sequence,

3.

achieves steady state voltage k 3900 V and : 4400 V,

4.

achieves steady state frequency 2 58.8 Hz and ! 61.2 Hz, and

5.

supplies permanently connected and auto-connected emergency loads for 2 5 minutes.

FREQUENCY 24 months SR 3.8.1.13 Verify interval between each sequenced load 24 months block is greater than or equal to the minimum design load interval.

Amendment 274 JAFNPP 3.8.1-11

AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a.

One qualified circuit between the offsite transmission network and one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown";

b.

One qualified circuit, which maybe the same circuit required by LCO 3.8.2.a, between the offsite transmission network and the other division of the plant Class 1E AC electrical power distribution subsystem(s),

when a second division is required by LCO 3.8.8; and

c.

One emergency diesel generator (EDG) subsystem capable of supplying one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY:

MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

Amendment 274 JAFNPP 3.8.2-1

AC Sources - Shutdown 3.8.2 ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION IREQUIRED ACTION COMPLETION TIME A.

One or both required offsite circuits inoperable.

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

Enter applicable Condition and Required Actions of LCO 3.8.8, when any required division is de-energized as a result of Condition A.

Declare affected required feature(s),

with no offsite power available, inoperable.

Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).

AND Immediately Immediately Immediately Immediately (continued)

Amendment 274 A.1 OR A.2.1 3.8.2-2 JAFNPP

AC Sources -Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.4 Initiate action to Immediately restore required offsite power circuit(s) to OPERABLE status.

B.

One required EDG B.1 Suspend CORE Immediately subsystem inoperable.

ALTERATIONS.

AND B.2 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND B.3 Initiate action to Immediately suspend OPDRVs.

AND B.4 Initiate action to Immediately restore required EDG subsystem to OPERABLE status.

Amendment 274 JAFNPP 3.8.2-3

AC Sources-Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS NOTES ------------------

1.

The following SRs are not required to be performed:

SR 3.8.1.3, SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11, SR 3.8.1.12, and SR 3.8.1.13.

2.

SR 3.8.1.10 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown."

For AC sources required to be OPERABLE the SRs of Specification 3.8.1, except SR 3.8.1.7, are applicable.

FREQUENCY In accordance with applicable SRs Amendment 274 SURVEILLANCE SR 3.8.2.1 3.8.2-4 JAFNPP

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air LCO

3.8.3 APPLICABILITY

The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits for each required emergency diesel generator (EDG).

When associated EDG subsystem is required to be OPERABLE.

ACTIONS NOTE OTE.......................

Separate Condition entry is allowed for each EDG.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more EDGs with A.1 Restore fuel oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months fuel oil level level to within

< 32,000 gal and limits.

> 28,000 gal in storage tank.

B.

One or more EDGs with B.1 Restore lube oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months lube oil inventory inventory to within

< 168 gal and limits.

> 144 gal.

C.

One or more EDGs with C.1 Restore stored fuel 7 days stored fuel oil total oil total particulates not particulates to within limit, within limit.

(continued)

Amendment 274 3.8.3-1 JAFNPP

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

One or more EDGs with D.1 Restore stored fuel 30 days new fuel oil oil properties to properties not within within limits.

limits.

E.

One or more EDGs with E.1 Restore required 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months required starting air starting air receiver receiver pressure pressure to within

< 150 psig and limits.

2 110 psig.

F.

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

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

OR One or more EDGs with diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains 31 days 2 32,000 gal of fuel.

(continued)

Amendment 274 3.8.3-2 JAFNPP

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.3.2 Verify lube oil inventory of each EDG is 31 days 2 168 gal.

SR 3.8.3.3 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel with, and maintained within the limits of, Fuel Oil the Diesel Fuel Oil Testing Program.

Testing Program SR 3.8.3.4 Verify each EDG required air start receiver 31 days pressure is 2 150 psig.

SR 3.8.3.5 Check for and remove accumulated water from 31 days each fuel oil storage tank.

Amendment 274 JAFNPP 3.8.3-3

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCO 3.8.4 The following DC OPERABLE:

electrical power subsystems shall be

a.

Two 125 VDC subsystems; and

b.

Two 419 VDC low pressure coolant injection (LPCI)

MOV independent power supply subsystems.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One 125 VDC electrical A.1 Restore 125 VDC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power subsystem electrical power inoperable, subsystem 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 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 C.

One or both 419 VDC C.1 Declare associated Immediately LPCI MOV independent LPCI subsystem(s) power supply inoperable.

subsystems inoperable.

Amendment 274 JAFNPP 3.8.4-1

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage on float 7 days charge is:

a.

Ž 127.8 VDC for 125 VDC batteries, and

b.

2 396.2 VDC for 419 VDC LPCI MOV independent power supply batteries.

SR 3.8.4.2 Verify each 125 VDC battery charger 24 months supplies 2 270 amps at Ž 128 VDC for

Ž 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SR 3.8.4.3 NOTE -------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3 for the 125 VDC batteries.

However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to 24 months supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test or a modified performance discharge test.

(continued)

Amendment 274 JAFNPP 3.8.4-2

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.4

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

This Surveillance shall not normally be performed in MODE 1, 2, or 3 for the 125 VDC batteries.

However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is

Ž 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.

60 months AND 12 months when battery shows degradation or has reached 85%

of expected life with capacity < 100%

of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity 2 100%

of manufacturer's rating Amendment 274 JAFNPP 3.8.4-3

DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown LCO

3.8.5 APPLICABILITY

One 125 VDC electrical power subsystem shall be OPERABLE to support one division of the plant Class IE DC Electrical Power Distribution System required by LCO 3.8.8, "Distribution Systems - Shutdown."

MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS NOT E ------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical A.1 Declare affected Immediately power subsystem required feature(s) inoperable.

inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND (continued)

Amendment 274 JAFNPP 3.8.5-1

DC Sources - Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate action to Immediately restore required DC electrical power subsystem to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 NOTE -------------------

The following SRs are not required to be performed:

SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.

For DC electrical power subsystem required In accordance to be OPERABLE the following SRs are with applicable applicable:

SRs SR 3.8.4.1, SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.

Amendment 274 3.8.5-2 JAFNPP

Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 APPLICABILITY:

ACTIONS Battery cell parameters for the 125 VDC and 419 VDC LPCI MOV independent power supply batteries shall be within the limits of Table 3.8.6-1.

AND Battery cell average electrolyte temperature for the 125 VDC and 419 VDC LPCI MOV independent power supply batteries shall be within required limits.

When associated DC electrical power subsystems are required to be OPERABLE.

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

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more batteries A.1 Verify pilot cells 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one or more electrolyte level and battery cell float voltage meet parameters not within Table 3.8.6-1 Category A or B Category C limits.

limits.

AND A.2 Verify battery cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters meet Table 3.8.6-1 AND Category C limits.

Once per 7 days thereafter AND (continued)

Amendment 274 JAFNPP 3.8.6-1

Battery Cell Parameters 3.8.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.

B.

Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A not met.

OR One or more batteries with average electrolyte temperature of the representative cells not within limits.

OR One or more batteries with one or more battery cell parameters not within Category C limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days Table 3.8.6-1 Category A limits.

(continued)

Amendment 274 JAFNPP 3.8.6-2

Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify battery cell parameters meet 92 days Table 3.8.6-1 Category B limits.

SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells is a 65 0 F for each 125 VDC battery, and > 50°F for each 419 VDC LPCI MOV independent power supply battery.

Amendment 274 3.8.6-3 JAFNPP

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Cell Parameter Requirements CATEGORY A:

LIMITS FOR EACH CATEGORY B:

CATEGORY C:

DESIGNATED PILOT LIMITS FOR EACH LIMITS FOR EACH PARAMETER CELL CONNECTED CELL CONNECTED CELL Electrolyte

> Minimum level

> Minimum level Above top of Level indication mark, indication mark, plates, and not and ! 3 inch above and :

inch above overflowing maximum level maximum level indication mark(a) indication mark(a)

Float Voltage

Ž 2.13 V

> 2.07 V Specific

Ž 1.195

Ž 1.195 Not more than Gravity(b)(c) 0.020 below AND average of all connected cells Average of all connected cells AND

> 1.205 Average of all connected cells S1.195 (a)

It is acceptable for the electrolyte level to temporarily increase above the specified maximum level during and, for a limited time, following equalizing charges provided it is not overflowing.

(b)

Corrected for electrolyte temperature and level.

Level correction is not required, however, when on float charge and battery charging current is < 2 amps for 125 VDC batteries and < 1 amp for 419 VDC LPCI MOV independent power supply batteries.

(c)

A battery charging current of < 2 amps for 125 VDC batteries and < 1 amp for 419 VDC LPCI MOV independent power supply batteries when on float charge is acceptable for meeting specific gravity limits following a battery recharge, for a maximum of 7 days.

When charging current is used to satisfy specific gravity requirements, specific gravity of each connected cell shall be measured prior to expiration of the 7 day allowance.

Amendment 274 3.8.6-4 JAFNPP

Distribution Systems -Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating LCO 3.8.7 APPLICABILITY:

The Division 1 and Division 2 AC and 125 VDC electrical power distribution subsystems shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more AC A.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months electrical power power distribution distribution subsystems to AND subsystems inoperable.

OPERABLE status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO B.

One 125 VDC electrical B.1 Restore 125 VDC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution electrical power subsystem inoperable, distribution AND subsystem to OPERABLE status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 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 AND 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 (continued)

Amendment 274 JAFNPP 3.8.7-1

Distribution Systems -Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two or more electrical D.1 Enter LCO 3.0.3.

Immediately power distribution subsystems inoperable that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and 7 days voltage to required AC and 125 VDC electrical power distribution subsystems.

Amendment 274 JAFNPP 3.8.7-2

Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems -Shutdown LCO

3.8.8 APPLICABILITY

ACTIONS The necessary portions of the AC and 125 VDC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

MODES 4 and 5, During movement of irradiated fuel assemblies in the secondary containment.

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Declare associated Immediately AC or 125 VDC supported required electrical power feature(s) distribution inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND (continued)

Amendment 274 3.8.8-1 JAFNPP

Distribution Systems - Shutdown 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate actions to Immediately restore required AC and 125 VDC electrical power distribution subsystems to OPERABLE status.

AND Immediately A.2.5 Declare associated required shutdown cooling subsystem(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and 7 days voltage to required AC and 125 VDC electrical power distribution subsystems.

Amendment 274 3.8.8-2 JAFNPP

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO

3.9.1 APPLICABILITY

The refueling equipment interlocks associated with the reactor mode switch in the refuel position shall be OPERABLE.

During in-vessel fuel movement with equipment associated with the interlocks when the reactor mode switch is in the refuel position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Suspend in-vessel Immediately refueling equipment fuel movement with interlocks inoperable, equipment associated with the inoperable interlock(s).

OR A.2.1 Insert a control rod Immediately withdrawal block.

AND A.2.2 Verify all control Immediately rods are fully inserted.

Amendment 274 3.9.1-1 JAFNPP

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQU I REMENTS SURVEILLANCE SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of the following required refueling equipment interlock inputs:

a.

All-rods-in,

b.

Refuel platform position,

c.

Refuel platform

loaded,

d.

Refuel platform up, fuel grapple, fuel fuel grapple not fully

e.

Refuel platform frame mounted hoist, fuel loaded, and

f.

Refuel platform trolley mounted (monorail) hoist, fuel loaded.

FREQUENCY 7 days Amendment 274 JAFNPP 3.9.1-2

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY:

MODE 5 with the reactor mode switch in the and any control rod withdrawn.

refuel position ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one-A.1 Suspend control rod Immediately rod-out interlock withdrawal.

inoperable.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position.

(continued)

Amendment 274 JAFNPP 3.9.2-1

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.2.2 NOTE -------------------

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

Perform CHANNEL FUNCTIONAL TEST.

7 days Amendment 274 JAFNPP 3.9.2-2

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO

3.9.3 APPLICABILITY

All control rods shall be fully inserted.

When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more control A.1 Suspend loading fuel Immediately rods not fully assemblies into the

inserted, core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Amendment 274 JAFNPP 3.9.3-1

ACTIONS Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO

3.9.4 APPLICABILITY

The control rod "full-in" position indication channel for each control rod shall be OPERABLE.

MODE 5.

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more control A.1.1 Suspend in-vessel Immediately rod position fuel movement.

indication channels inoperable.

AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to Immediately fully insert all insertabl e control rods in core cells containing one or more fuel assemblies.

OR (continued)

Amendment 274 3.9.4-1 JAFNPP

Control Rod Position Indication 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.1 Initiate action to Immediately fully insert the control rod associated with the inoperable position indicator.

AND A.2.2 Initiate action to Immediately disarm the control rod drive associated with the fully inserted control rod.

SURVEILLANCE REQUIREMENT SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the channel has no "full-in" Each time the indication on each control rod that is not control rod is "full-in."

withdrawn from the "full-in" position Amendment 274 JAFNPP 3.9.4-2

Control Rod OPERABILITY-Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY-Refueling LCO

3.9.5 APPLICABILITY

Each withdrawn control rod shall be OPERABLE.

MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more withdrawn A.1 Initiate action to Immediately control rods fully insert inoperable, inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1

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

Not required to be performed until 7 days after the control rod is withdrawn.

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

SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is ; 940 psig.

Amendment 274 JAFNPP 3.9.5-1

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO

3.9.6 APPLICABILITY

RPV water level shall be - 22 ft 2 inches above the top of the RPV flange.

During movement of irradiated fuel assemblies within the

RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RPV water level not A.1 Suspend movement of Immediately within limit, fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is

Ž 22 ft 2 inches 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months above the top of the RPV flange.

Amendment 274 JAFNPP 3.9.6-1

RHR-High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR)-High Water Level LCO

3.9.7 APPLICABILITY

One RHR shutdown cooling subsystem shall be OPERABLE.

MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level 2 22 ft 2 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat inoperable, removal is available.

AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel Time of Condition A assemblies into the not met.

RPV.

AND B.2 Initiate action to Immediately restore secondary containment to OPERABLE status.

AND (continued)

Amendment 274 JAFNPP 3.9.7-1

RHR-High Water Level 3.9.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.3 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.

AND B.4 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify each required RHR shutdown cooling 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.

Amendment 274 3.9.7-2 JAFNPP

RHR-Low Water 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR)-Low Water Level LCO

3.9.8 APPLICABILITY

Two RHR shutdown cooling subsystems shall be OPERABLE.

MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft 2 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RHR shutdown cooling method of decay heat subsystems inoperable, removal is available AND for each inoperable required RHR shutdown Once per cooling subsystem.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Initiate action to Immediately associated Completion restore secondary Time of Condition A containment to not met.

OPERABLE status.

AND B.2 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.

AND (continued)

Amendment 274 Level 3.9.8 JAFNPP 3.9.8-1

RHR-Low Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 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 3.9.8-2 JAFNPP

Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1 APPLICABILITY:

The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA,"

and operation considered not to be in MODE 3; and the requirements of LCO 3.4.8. "Residual Heat Removal (RHR)

Shutdown Cooling System-Cold Shutdown," may be suspended, to allow performance of an inservice leak or hydrostatic test provided the following MODE 3 LCOs are met:

a.

LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," Functions 1, 3, and 4 of Table 3.3.6.2-1;

b.

LCO 3.6.4.1, "Secondary Containment";

c.

LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)"; and

d.

LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."

MODE 4 with average reactor coolant temperature > 212 0F.

Amendment 274 3.10.1-1 JAFNPP

Inservice Leak and Hydrostatic Testing Operation 3.10.1 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more of the A.1

NOTE --------

above requirements not Required Actions to met.

be in MODE 4 include reducing average reactor coolant temperature to

212'F.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Suspend activities Immediately that could increase the average reactor coolant temperature or pressure.

AND A.2.2 Reduce average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reactor coolant temperature to

- 212'F.

Amendment 274 JAFNPP 3.10.1-2

Inservice Leak and Hydrostatic Testing Operation 3.10.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.1.1 Perform the applicable SRs for the required According to MODE 3 LCOs.

the applicable SRs Amendment 274 JAFNPP 3.10.1-3

Reactor Mode Switch Interlock Testing 3.10.2 3.10 SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testing LCO 3.10.2 The reactor mode switch position specified in Table 1.1-1 for MODES 3, 4, and 5 may be changed to include the run, startup/hot standby, and refuel position, and operation considered not to be in MODE 1 or 2, to allow testing of instrumentation associated with the reactor mode switch interlock functions, provided:

a.

All control rods remain ful containing one or more fuel ly inserted in core cells assemblies; and

b.

No CORE ALTERATIONS are in progress.

APPLICABILITY:

MODES 3 and 4 with the reactor mode startup/hot standby, or refuel MODE 5 with the reactor mode switch startup/hot standby position.

switch in the run,

position, in the run or ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more of the A.1 Suspend CORE Immediately above requirements not ALTERATIONS except met.

for control rod insertion.

AND A.2 Fully insert all 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months insertable control rods in core cells containing one or more fuel assemblies.

AND (continued)

Amendment 274 JAFNPP 3.10.2-1

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3.1 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.

OR A.3.2 -------- NOTE --------

Only applicable in MODE 5.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in core cells containing one or more fuel assemblies.

SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Amendment 274 JAFNPP 3.10.2-2

Single Control Rod Withdrawal -Hot Shutdown 3.10.3 3.10 SPECIAL OPERATIONS 3.10.3 Single Control Rod Withdrawal -Hot Shutdown LCO 3.10.3 APPLICABILITY:

The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, provided the following requirements are met:

a.

LCO 3.9.2, "Refuel Position One-Rod-Out Interlock";

b.

LCO 3.9.4, "Control Rod Position Indication";

c.

All other control rods are fully inserted; and

d.

1.

LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions l.a, 1.b, 7.a, 7.b, 10, and 11 of Table 3.3.1.1-1, and LCO 3.9.5, "Control Rod OPERABILITY-Refueling,"

OR

2.

All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM),"

MODE 3 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

MODE 3 with the reactor mode switch in the refuel position.

Amendment 274 3.10.3-1 JAFNPP

Single Control Rod Withdrawal -Hot Shutdown 3.10.3 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION I COMPLETION TIME A.

One or more of the above requirements not met.

A.1 NOTES -------

1. Required Actions to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.

2.

Only applicable if the requirement not met is a required LCO.

Enter the applicable Condition of the affected LCO.

OR A.2.1 Initiate action to fully insert all insertable control rods.

AND A.2.2 Place the reactor mode switch in the shutdown position.

Immediately Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Amendment 274 JAFNPP 3.10.3-2

Single Control Rod Withdrawal -Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required According to LCOs.

the applicable SRs SR 3.10.3.2 ------------------- NOTE -------------------

Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.

Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.

SR 3.10.3.3 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, are fully inserted.

Amendment 274 JAFNPP 3.10.3-3

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Single Control Rod Withdrawal -Cold Shutdown LCO 3.10.4 APPLICABILITY:

The reactor mode switch position specified in Table 1.1-1 for MODE 4 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, and subsequent removal of the associated control rod drive (CRD) if desired, provided the following requirements are met:

a.

All other control rods are fully inserted:

b.

1.

LCO 3.9.2, "Refuel Position One-Rod-Out Interlock,"

and LCO 3.9.4, "Control Rod Position Indication,"

OR

2.

A control rod withdrawal block is inserted:

c.

1.

LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," MODE 5 requirements for Functions l.a, 1.b, 7.a, 7.b, 10, and 11 of Table 3.3.1.1-1, and LCO 3.9.5, "Control Rod OPERABILITY-Refueling,"

OR

2.

All other control rods in a five by five array centered on the control rod being withdrawn are disarmed: at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM),"

MODE 4 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

MODE 4 with the reactor mode switch in the refuel position.

Amendment 274 JAFNPP 3.10.4-1

Single Control Rod Withdrawal -Cold Shutdown 3.10.4 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more of the above requirements not met with the affected control rod insertable.

NOTES -------

1.

Required Actions to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.

2.

Only applicable if the requirement not met is a required LCO.

Enter the applicable Condition of the affected LCO.

.1 AND A.2.2 Initiate action to fully insert all insertable control rods.

Place the reactor mode switch in the shutdown position.

Immediately Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (continued)

Amendment 274 A.1 OR A.2 JAFNPP 3.10.4-2

Single Control Rod Withdrawal -Cold Shutdown 3.10.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more of the B.1 Suspend withdrawal of Immediately above requirements not the control rod and met with the affected removal of associated control rod not CRD.

insertable.

AND B.2.1 Initiate action to Immediately fully insert all control rods.

OR B.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required According to LCOs.

the applicable SRs SR 3.10.4.2...................

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

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.

(continued)

Amendment 274 JAFNPP 3.10.4-3

Single Control Rod Withdrawal -Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.4.3 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, are fully inserted.

SR 3.10.4.4 ------------------- NOTE -------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

Amendment 274 3.10.4-4 JAFNPP

Single CRD Removal -Refueling 3.10.5 3.10 SPECIAL OPERATIONS 3.10.5 Single Control Rod Drive (CRD)

Removal -Refueling LCO 3.10.5 APPLICABILITY:

The requirements of LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation"; LCO 3.3.8.2, "Reactor Protection System (RPS) Electric Power Monitoring"; LCO 3.9.1, "Refueling Equipment Interlocks"; LCO 3.9.2, "Refuel Position One-Rod-Out Interlock"; LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY-Refueling,"

may be suspended in MODE 5 to allow the removal of a single CRD associated with a control rod withdrawn from a core cell containing one or more fuel assemblies, provided the following requirements are met:

a.

All other control rods are fully inserted;

b.

All other control rods in a five by five array centered on the withdrawn control rod are disarmed;

c.

A control rod withdrawal block is inserted and LCO 3.1.1, "SHUTDOWN MARGIN (SDM),"

MODE 5 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod; and

d.

No other CORE ALTERATIONS are in progress.

MODE 5 with LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more of the A.1 Suspend removal of Immediately above requirements not the CRD.

met.

AND (continued)

Amendment 274 JAFNPP 3.10.5-1

Single CRD Removal -Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.1 Initiate action to Immediately fully insert all control rods.

OR A.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD, are fully inserted.

SR 3.10.5.2 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD. in a five by five array centered on the control rod withdrawn for the removal of the associated CRD, are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

SR 3.10.5.4 Perform SR 3.1.1.1.

According to SR 3.1.1.1 (continued)

Amendment 274 JAFNPP 3.10.5-2

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months progress.

Amendment 274 Single CRD Removal -Refueling 3.10.5 JAFNPP 3.10.5-3

Multiple Control Rod Withdrawal -Refueling 3.10.6 3.10 SPECIAL OPERATIONS 3.10.6 Multiple Control Rod Withdrawal - Refueling LCO 3.10.6 APPLICABILITY:

The requirements of LCO 3.9.3, "Control Rod Position";

LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY-Refueling,"

may be suspended, and the "full-in" position indicators may be bypassed for any number of control rods in MODE 5, to allow withdrawal and removal of these control rods, removal of associated control rod drives (CRDs),

or both, provided the following requirements are met:

a.

The four fuel assemblies are removed from the core cells associated with each control rod or CRD to be removed;

b.

All other control rods in core cells containing one or more fuel assemblies are fully inserted; and

c.

Fuel assemblies shall only be loaded in compliance with an approved spiral reload sequence.

MODE 5 with LCO 3.9.3, LCO 3.9.4, or LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more of the A.1 Suspend withdrawal of Immediately above requirements not control rods and met.

removal of associated CRDs.

AND A.2 Suspend loading fuel Immediately assemblies.

AND (continued)

Amendment 274 JAFNPP 3.10.6-1

Multiple Control Rod Withdrawal -Refueling 3.10.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3.1 Initiate action to Immediately fully insert all control rods in core cells containing one or more fuel assemblies.

OR A.3.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from core cells associated with each control rod or CRD removed.

SR 3.10.6.2 Verify all other control rods in core cells 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months containing one or more fuel assemblies are fully inserted.

SR 3.10.6.3 ------------------- NOTE -------------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months compliance with an approved spiral reload sequence.

Amendment 274 JAFNPP 3.10.6-2

Control Rod Testing-Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing-Operating LCO 3.10.7 APPLICABILITY:

The requirements of LCO 3.1.6, "Rod Pattern Control," may be suspended to allow performance of SDM testing, control rod scram time testing, and control rod friction testing, provided:

a.

The banked position withdrawal sequence requirements of SR 3.3.2.1.8 are changed to require the control rod sequence to conform to the specified test sequence.

OR

b.

The RWM is bypassed; the requirements of LCO 3.3.2.1, "Control Rod Block Instrumentation," Function 2 are suspended; and conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.

MODES 1 and 2 with LCO 3.1.6 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1 Suspend performance Immediately LCO not met.

of the test and exception to LCO 3.1.6.

Amendment 274 JAFNPP 3.10.7-1

Control Rod Testing-Operating 3.10.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.10.7.1

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

Not required to be met if SR 3.10.7.2 satisfied.

Verify movement of control rods is in compliance with the approved control rod sequence for the specified test by a second licensed operator or other qualified member of the technical staff.

FREQUENCY 4

During control rod movement SR 3.10.7.2 ------------------- NOTE -------------------

Not required to be met if SR 3.10.7.1 satisfied.

Verify control rod sequence input to the Prior to RWM is in conformance with the approved control rod control rod sequence for the specified movement test.

Amendment 274 3.10.7-2 JAFNPP

SDM Test - Refuel i ng 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling LCO 3.10.8 APPLICABILITY:

The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a.

LCO 3.3.1.1. "Reactor Protection System Instrumentation,"

MODE 2 requirements for Functions 2.a and 2.d of Table 3.3.1.1-1;

b.

1.

LCO 3.3.2.1, "Control Rod Block Instrumentation,"

MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence, OR

2.

Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c.

Each withdrawn control rod shall be coupled to the associated CRD;

d.

All control rod withdrawals during out of sequence control rod moves shall be made in notch out mode;

e.

No other CORE ALTERATIONS are in progress; and

f.

CRD charging water header pressure k 940 psig.

MODE 5 with the reactor mode switch in startup/hot standby position.

Amendment 274 JAFNPP 3.10.8-1

SDM Test -Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----------- NOTE -------- ----------- NOTE -----------

Separate Condition Rod worth minimizer may be entry is allowed for bypassed as allowed by each control rod.

LCO 3.3.2.1, "Control Rod Block Instrumentation," if required, to allow insertion One or more of inoperable control rod and control rods not continued operation.

coupled to its associated CRD.

A.1 Fully insert 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months inoperable control rod.

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

B.

One or more of the B.1 Place the reactor Immediately above requirements not mode switch in the met for reasons other shutdown or refuel than Condition A.

position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for LCO According to 3.3.1.1, Functions 2.a and 2.d of Table the applicable 3.3.1.1-1.

SRs (continued)

Amendment 274 JAFNPP 3.10.8-2

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.2 ------------------- NOTE -------------------

Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for According to LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1.

the applicable SRs SR 3.10.8.3 ------------------- NOTE -------------------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the SDM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months progress.

(continued)

Amendment 274 JAFNPP 3.10.8-3

SDM Test-Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.10.8.5 Verify each withdrawn 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 satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days S940 psig.

Amendment 274 JAFNPP 3.10.8-4

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location 4.1.1 Site and Exclusion Area Boundaries The Site and Exclusion Area Boundaries coincide with each other and shall be as shown on Figure 4.1-1.

4.1.2 Low Population Zone (LPZ)

The LPZ shall be a 4 mile radius around the Nine Mile Point Nuclear Station Unit 1 stack.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 560 fuel assemblies.

Each assembly shall consist of a matrix of Zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U02) as fuel material, and water rods.

Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used.

Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases.

A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 137 cruciform shaped control rod assemblies.

The control material shall be boron carbide or hafnium metal as approved by the NRC.

(continued)

Amendment 274 JAFNPP 4.0-1

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum k-infinity of 1.32 in the normal reactor core configuration at cold conditions (20'C);

b.

kff

0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.3 of the UFSAR; and

c.

A nominal 6.625 inch center to center distance between fuel assemblies placed in the aluminum high density storage racks, and a nominal 6.355 inch center to center distance between fuel assemblies placed in the stainless steel high density storage racks.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum k-infinity of 1.31 in the normal reactor core configuration at cold conditions (20 0C);

b.

keff : 0.90 if dry;

c.

keff : 0.95 if fully flooded with unborated water; and

d.

A nominal 6.625 inch center to center distance between fuel assemblies placed in storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 344 ft 6 inches.

(continued)

Amendment 274 4.0-2 JAFNPP

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3239 fuel assemblies.

Amendment 274 JAFNPP 4.0-3

Design Features 4.0 LAKE ONTARIO Figure 4.1-1 (page 1 of 1)

Site and Exclusion Area Boundaries Amendment 274 I I SE& EXCLUJSO SAREA BOUNDARY 4.0-4 JAFNPP

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall plant operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment, and modification to systems or equipment that affect nuclear safety.

5.1.2 The shift supervisor (SS) shall be responsible for the control room command function.

During any absence of the SS from the control room while the plant is in MODE 1, 2, or 3, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function.

During any absence of the SS from the control room while the plant is in MODE 4 or 5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

JAFNPP 5.1-1 Amendment 274

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for plant operation and corporate management, respectively.

The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions.

These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the UFSAR;

b.

The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;

c.

The chief nuclear officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d.

The individuals who train the operating staff, carry out radiation protection, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Plant Staff The plant staff organization shall include the following:

a.

At least one non-licensed operator shall be on site when the plant is in MODE 4 or 5.

At least two non-licensed operators shall be on site when the plant is in MODE 1, 2, or 3.

(continued)

Amendment 274 5.2-1 JAFNPP

Organization 5.2 5.2 Organization 5.2.2 Plant Staff (continued)

b.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c.

A radiation protection technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d.

Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g., licensed Senior Reactor Operators (SROs),

licensed Reactor Operators (ROs),

radiation protection technicians, auxiliary operators, and key maintenance personnel).

The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.

Any deviation from the working hour guidelines shall be authorized in advance by the plant manager or the plant manager's designee, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation.

Routine deviation from the working hour guidelines shall not be authorized.

Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.

e.

The operations manager or assistant operations manager shall hold an SRO license.

f.

When the plant is in MODE 1, 2, or 3, an individual shall provide advisory technical support to the shift supervisor (SS) in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the plant.

This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift, published in the October 28, 1985 Federal Register (50 FR 43621).

Amendment 274 JAFNPP 5.2-2

Plant Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Plant Staff Qualifications 5.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the radiation protection manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, September 1975.

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

Amendment 274 5.3-1 JAFNPP

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a.

The applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 1972;

b.

The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c.

Quality assurance program for radioactive effluent and radiological environmental monitoring;

d.

Fire Protection Program implementation; and

e.

All programs specified in Specification 5.5.

Amendment 274 JAFNPP 5.4-1

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs and manuals shall be established, implemented and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a.

The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b.

The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3.

c.

Licensee initiated changes to the ODCM:

1.

Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

(a) sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s),

and (b) a determination that the change(s) maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

2.

Shall become effective after the approval of the plant manager; and

3.

Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made.

Each change shall be identified by (continued)

Amendment 274 JAFNPP 5.5-1

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM)

(continued) markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.

The systems include the Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, Reactor Water Cleanup, process sampling, and Standby Gas Treatment.

The program shall include the following:

a.

Preventive maintenance and periodic visual inspection requirements; and

b.

Integrated leak test requirements for each system at 24 month intervals or less.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the 24 month Frequency for performing integrated leak test activities.

5.5.3 Post Accident Sampling This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive iodines, and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the following:

a.

Training of personnel;

b.

Procedures for sampling and analysis; and

c.

Provisions for maintenance of sampling and analysis equipment.

(continued)

Amendment 274 5.5-2 JAFNPP

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.

The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b.

Limitations on the concentrations of radioactive material released in liquid effluents from the site to unrestricted areas, conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;

c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the site to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e.

Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

f.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; (continued)

Amendment 274 JAFNPP 5.5-3

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

g.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1.

For noble gases:

a dose rate

500 mrem/yr to the whole body and a dose rate

3000 mrem/yr to the skin, and

2.

For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:

a dose rate

1500 mrem/yr to any organ;

h.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the site to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I:

i.

Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives > 8 days in gaseous effluents released from the site to areas at or beyond the site boundary, conforming to 10 CFR 50, Appendix I;

j.

Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190; and

k.

Limitations on venting and purging of the primary containment through the Standby Gas Treatment System to maintain releases as low as reasonably achievable.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program Surveillance Frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR Section 4.2, cyclic and transient occurrences to ensure that components are maintained within the design limits.

(continued)

Amendment 274 JAFNPP 5.5-4

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.6 Primary Containment Leakage Rate Testing Program This program implements the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program,"

dated September 1995, as modified by the following exception:

Type C testing of valves not isolable from the containment free air space may be accomplished by pressurization in the reverse direction, provided that testing in this manner provides equivalent or more conservative results than testing in the accident direction.

If potential atmospheric leakage paths (e.g.,

valve stem packing) are not subjected to test pressure, the portions of the valve not exposed to test pressure shall be subjected to leakage rate measurement during regularly scheduled Type A testing.

A list of these valves, the leakage rate measurement method, and the acceptance criteria, shall be contained in the Program.

a.

The peak primary containment internal pressure for the design basis loss of coolant accident, Pa, is 45 psig.

b.

The maximum allowable primary containment leakage rate, La, at Pa, shall be 1.5% of containment air weight per day.

c.

The leakage rate acceptance criteria are:

1.

Primary containment leakage rate acceptance criteria is

1.0 La.

During plant startup following testing in accordance with this program, the leakage rate acceptance criteria are ! 0.60 La for the Type B and Type C tests, and. 0.75 La for the Type A tests.

2.

Air lock testing acceptance criteria are:

(a)

Overall air lock leakage rate is ! 0.05 L. when tested at ; Pa; and (b)

For each door seal, leakage rate is ! 120 scfd when tested at ; Pa.

(continued)

Amendment 274 5.5-5 JAFNPP

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice testing activities Required Frequencies for performing inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years

b.

The provisions of SR required Frequencies activities; At least once At least once per 7 days per 31 days At least once per 92 days At At At least least least once once once per 184 days per 276 days per 366 days At least once per 731 days 3.0.2 are applicable to the above for performing inservice testing

c.

The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued)

Amendment 274 Primary Containment Leakage Rate Testing Program (continued)

d.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

e.

Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.

Inservice Testing Program This program provides controls for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves.

The program shall include the following:

a.

Testing Frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda are as follows:

5.5.7 5.5-6 JAFNPP

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Inservice Testing Program (continued)

d.

Nothing in the ASME Boiler and Pressure Vessel code shall be construed to supersede the requirements of any TS.

5.5.8 Ventilation Filter Testing Program (VFTP)

This program implements the following required testing of Engineered Safeguards filter ventilation systems.

The tests described in Specifications 5.5.8.a and 5.5.8.b shall be performed:

Once per 24 months:

After each complete or partial replacement of the HEPA filter train or charcoal adsorber filter or after removal of a charcoal sample; After any structural maintenance on the HEPA filter or charcoal adsorber housing that could affect the filter system efficiency; and Following painting, fire, or chemical release that could adversely affect the ability of the filter system to perform the intended function in any ventilation zone communicating with the system.

The tests described in Specification 5.5.8.c shall be performed:

Once per 24 months; After 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation; After any structural maintenance on the charcoal adsorber housing that could affect the filter system efficiency; and Following painting, fire, or chemical release that could adversely affect the ability of the charcoal filter system to perform the intended function in any ventilation zone communicating with the system.

The tests described in Specifications 5.5.8.d and 5.5.8.e shall be performed once per 24 months.

(continued)

Amendment 274 JAFNPP 5.5-7

Programs and Manuals 5.5 5.5 Programs and Manuals Ventilation Filter Testing Program (VFTP)

(continued)

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test Frequencies.

a.

Demonstrate for each of the Engineered Safeguards systems that an inplace test of the HEPA filters shows a penetration and system bypass less than the value specified below when tested in accordance with Sections C.5.a and C.5.c of Regulatory Guide 1.52, Revision 2, and ASME N510-1980 at the system flowrate specified below.

Engineered Safeguards Ventilation System Standby Gas Treatment System Control Room Emergency Ventilation Air Supply System Penetration and System Bypass 1.0%

1.0%

Flowrate (scfm) 5,400 to 6,600 900 to 1,100

b.

Demonstrate for each of the Engineered Safeguards systems that an inplace test of the charcoal adsorber shows a penetration and system bypass less than the value specified below when tested in accordance with Sections C.5.a and C.5.d of Regulatory Guide 1.52, Revision 2, and ASME N510 1980 at the system flowrate specified below.

Engineered Safeguards Ventilation System Standby Gas Treatment System Control Room Emergency Ventilation Air Supply System Penetration and System Bypass 1.0%

0.5%

Flowrate (scfm) 5,400 to 6,600 900 to 1,100 (continued)

Amendment 274 5.5.8 JAFNPP 5.5-8

Programs and Manuals 5.5 5.5 Programs and Manuals Ventilation Filter Testing Program (VFTP)

(continued)

c.

Demonstrate for each of the Engineered Safeguards systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Section C.6.b of Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of

300C (86°F) and the relative humidity specified below.

Engineered Safeguards Ventilation System Penetration Standby Gas Treatment System Control Room Emergency Ventilation Air Supply System RH

> 70%

Ž 95%

d.

Demonstrate for each of the Engineered Safeguards systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below:

Engineered Safeguards Ventilation System Standby Gas Treatment System Control Room Emergency Ventilation Air Supply System

e.

Demonstrate that th*

System dissipate >

ASME N510-1975.

Delta P (inches wg) 5.7 5.8 Flowrate (scfm) 5,400 to 6,600 900 to 1,100 e heaters for the Standby Gas Treatment 29 kW when tested in accordance with (continued)

Amendment 274 5.5.8 JAFNPP 5.5-9

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.9 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Main Condenser Offgas Treatment System and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

a.

The limits for concentrations of hydrogen and oxygen in the Main Condenser Offgas Treatment System and a surveillance program to ensure the limits are maintained.

Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion); and

b.

A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste System is less than the amount that would result in a concentration that is 10 times the concentration values in Appendix B, Table 2, Column 2, to 10 CFR 20.1001-20.2402 (excluding tritium and dissolved or entrained noble gases) at the nearest potable water supply and the nearest surface water supply beyond the site boundary, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program Surveillance Frequencies.

5.5.10 Diesel Fuel Oil Testing Program This program implements required testing of both new fuel oil and stored fuel oil.

The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards.

The purpose of the program is to establish the following:

(continued)

Amendment 274 JAFNPP 5.5-10

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Diesel Fuel Oil Testing Program (continued)

a.

Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. An API gravity or an absolute specific gravity within

limits,

2.

A flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and

3.

A clear and bright appearance with proper color;

b.

Within 31 days following addition of the new fuel oil to storage tanks verify that the properties of the new fuel oil, other than those addressed in Specification 5.5.10.a above, are within limits for ASTM 2D fuel oil; and

c.

Total particulate concentration of the fuel oil is

10 mg/l when tested every 31 days in accordance with the applicable ASTM Standard, except that the specified filters may be replaced with filters up to 3.0 microns.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test Frequencies.

5.5.11 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a.

Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1.

A change in the TS incorporated in the license; or

2.

A change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

(continued)

Amendment 274 JAFNPP 5.5-11

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Technical Specifications (TS)

Bases Control Program (continued)

c.

The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d.

Proposed changes that meet the criteria of Specification 5.5.11.b above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.12 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken.

Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists.

Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.

a.

The SFDP shall contain the following:

1.

Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

2.

Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

3.

Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

4.

Other appropriate limitations and remedial or compensatory actions.

b.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of emergency diesel generator (continued)

Amendment 274 JAFNPP 5.5-12

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Safety Function Determination Program (SFDP)

(continued) subsystems, a safety function assumed in the accident analysis cannot be performed.

For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

1.

A required system redundant to system(s) supported by the inoperable support system is also inoperable; or

2.

A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or

3.

A required system redundant to support system(s) for the supported systems (1) and (2) above is also inoperable.

The SFDP identifies where a loss of safety function exists.

If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.13 Configuration Risk Management Program (CRMP)

The CRMP provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability.

The program applies to technical specification structures, systems, or components for which a risk-informed allowed outage time has been granted.

The program is to include the following:

a.

Provisions for the control and implementation of a Level 1 at-power internal events PRA-informed methodology.

The assessment is to be capable of evaluating the applicable plant configuration.

b.

Provisions for performing an assessment prior to entering the plant configuration described by the Limiting Condition for Operation (LCO)

Condition(s) for preplanned activities.

c.

Provisions for performing an assessment after entering the plant configuration described by the LCO Condition(s) for unplanned entry into the LCO Condition(s).

(continued)

Amendment 274 5.5-13 JAFNPP

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Configuration Risk Management Program (CRMP)

(continued)

d.

Provisions for assessing the need for additional actions after the discovery of additional equipment-out-of-service conditions while in the plant configuration described by the LCO Condition(s).

e.

Provisions for considering other applicable risk-significant contributors such as Level 2 issues and external events, qualitatively or quantitatively.

Amendment 274 JAFNPP 5.5-14

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Occupational Radiation Exposure Report A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors), for whom monitoring was performed, receiving an annual deep dose equivalent

> 100 mrems and the associated collective deep dose equivalent (reported in person-rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling).

This tabulation supplements the requirements of 10 CFR 20.2206.

The dose assignments to various duty functions may be estimated based on pocket ionization chamber, thermoluminescent dosimeter (TLD),

electronic dosimeter, or film badge measurements.

Small exposures totalling < 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total deep dose equivalent received from external sources should be assigned to specific major work functions.

The report, covering the previous calendar year shall be submitted by April 30 of each year.

5.6.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the plant during the previous calendar year shall be submitted by May 15 of each year.

The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM),

and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period at the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some individual results are not available for inclusion with the report, the report shall be (continued)

Amendment 274 JAFNPP 5.6-1

Reporting Requirements 5.6 5.6 Reporting Requirements Annual Radiological Environmental Operating Report (continued) submitted results.

report as noting and explaining the reasons for the missing The missing data shall be submitted in a supplementary soon as possible.

Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the plant during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.

The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

Monthly Operating Reports Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1.

The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) of Specification 3.2.1;

2. The MINIMUM CRITICAL POWER Specification 3.2.2;

3.

The LINEAR HEAT GENERATION Specification 3.2.3; RATIO (MCPR) of RATE (LHGR) of (continued)

Amendment 274 5.6.2 5.6.3 5.6.4 5.6.5 JAFNPP 5.6-2

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

(continued)

4.

The Reactor Protection System (RPS)

APRM Neutron Flux-High (Flow Biased) Function Allowable Value of Table 3.3.1.1-1;

5.

The Rod Block Monitor-Upscale Function Allowable Value of Table 3.3.2.1-1; and

6.

The Power/Flow Exclusion Region of Specification 3.4.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

1.

NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel;

2.

NEDC-31317P, James A. FitzPatrick Nuclear Power Plant SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis; and

3.

NEDO-31960-A, BWR Owners' Group Long-Term Stability Solutions Licensing Methodology.

The COLR will contain the complete identification for each of the Technical Specification referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

Amendment 274 5.6-3 JAFNPP

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.6 PAM Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days.

The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

Amendment 274 5.6-4 JAFNPP

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with dose rates not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation:

a.

Each entrance or access point to such an area shall be barricaded (e.g., roped off) and conspicuously posted as a high radiation area, or be continuously guarded to prevent unauthorized personnel entry.

Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b.

Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided they are following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1.

A radiation monitoring device that continuously displays radiation dose rates in the area; or

2.

A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with a pre-set alarm setpoint, or

3.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued)

Amendment 274 JAFNPP 5.7-1

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with dose rates not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation:

(continued)

4.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (a)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (b)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.

These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas.

This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 meter from the radiation source or from any surface penetrated by the radiation:

a.

Each entrance or access point to such an area shall be conspicuously posted as a high radiation area and shall be (continued)

Amendment 274 5.7-2 JAFNPP

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 meter from the radiation source or from any surface penetrated by the radiation:

(continued) provided with a locked door or gate that prevents unauthorized entry, or be continuously guarded to prevent unauthorized personnel entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift manager, radiation protection manager, or designee.

2.

Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b.

Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided they are following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with a pre-set alarm setpoint, or

2.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (continued)

Amendment 274 5.7-3 JAFNPP

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 meter from the radiation source or from any surface penetrated by the radiation:

(continued)

3.

A self reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (a)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (b)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area, or,

4.

In those cases where options 2 and 3, above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area may be used.

e.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.

These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas.

This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to entry.

f.

Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonable be constructed around the individual area need not be controlled by a locked door or gate, nor conspicuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

Amendment 274 JAFNPP 5.7-4

ML021750479

Contents

Text

3.5.1 APPLICABILITY

3.5.2 APPLICABILITY

3.5.3 APPLICABILITY

3.7.1 APPLICABILITY

3.7.2 APPLICABILITY

3.7.4 APPLICABILITY

3.8.1 APPLICABILITY

3.8.3 APPLICABILITY

3.8.5 APPLICABILITY

3.8.8 APPLICABILITY

3.9.1 APPLICABILITY

3.9.3 APPLICABILITY

3.9.4 APPLICABILITY

3.9.5 APPLICABILITY

3.9.6 APPLICABILITY

3.9.7 APPLICABILITY

3.9.8 APPLICABILITY

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ML021750479

Text

3.5.1 APPLICABILITY

3.5.2 APPLICABILITY

3.5.3 APPLICABILITY

3.7.1 APPLICABILITY

3.7.2 APPLICABILITY

3.7.4 APPLICABILITY

3.8.1 APPLICABILITY

3.8.3 APPLICABILITY

3.8.5 APPLICABILITY

3.8.8 APPLICABILITY

3.9.1 APPLICABILITY

3.9.3 APPLICABILITY

3.9.4 APPLICABILITY

3.9.5 APPLICABILITY

3.9.6 APPLICABILITY

3.9.7 APPLICABILITY

3.9.8 APPLICABILITY

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