ML021970095

From kanterella
Jump to navigation Jump to search

Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), 3.6 Containment Systems
ML021970095
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 07/03/2002
From: Vissing G
NRC/NRR/DLPM/LPD1
To: Kansler M
Entergy Nuclear Operations
Vissing G, NRR/DLPM, 415-1441
Shared Package
ML021980178 List:
References
NUREG-1433, Rev 1, NUREG-1434, Rev 1, TAC MA5049
Download: ML021970095 (136)
v • d • e


Text

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 0 F with THERMAL POWER > 1% RTP and no testing that adds heat to the suppression pool is being performed;
b. g 105'F with THERMAL POWER > 1%RTP and testing that adds heat to the suppression pool is being performed; and
c.  : 110'F with THERMAL POWER
  • 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 0 F but - 110 0F. temperature

  • 110'F.

AND AND THERMAL POWER A.2 Restore suppression 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />

> 1%RTP. pool average temperature to AND 0

  • 95 F.

Not performing testing that adds heat to the suppression pool.

(continued)

JAFNPP 3.6.2.1-1 Amendment 274

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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion to

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

  • 120'F. shutdown position.

AND D.2 Verify suppression Once per pool average 30 minutes temperature g 1207F.

AND D.3 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> (continued)

JAFNPP 3.6.2.1-2 Amendment 274

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool E.1 Depressurize the 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> average temperature reactor vessel to

> 120 0 F. < 200 psig.

AND E.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> temperature is within the applicable limits. AND 5 minutes when performing testing that adds heat to the suppression pool JAFNPP 3.6.2.1-3 Amendment 274

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 Suppression pool water level shall be 2 13.88 ft and S14 ft.

NOTE Not required to be met for up to 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> during Surveillances that cause suppression pool water level to be outside the limit.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> level not within pool water level to limits, within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> within limits.

JAFNPP 3.6.2.2-1 Amendment 274

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 pool cooling subsystems shall be OPERABLE.

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 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> pool cooling suppression pool subsystems inoperable, cooling subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> JAFNPP 3.6.2.3-1 Amendment 274

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 JAFNPP 3.6.2.3-2 Amendment 274

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 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 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> during Surveillances that cause or require the drywell-to-suppression chamber differential pressure to be outside the limit.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> after THERMAL POWER is > 15% RTP following startup, to
b. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell-to-suppression A.1 Restore differential 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> chamber differential pressure to within pressure not within limit.

limit.

B. Required Action and B.1 Reduce THERMAL POWER 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion to . 15% RTP.

Time not met.

JAFNPP 3.6.2.4-1 Amendment 274

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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> differential pressure is within limit.

3.6.2.4-2 Amendment 274 JAFNPP

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 The primary containment oxygen concentration shall be

< 4.0 volume percent.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> after THERMAL POWER is > 15% RTP following startup, to
b. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> oxygen concentration concentration to not within limit, within limit.

B. Required Action and B.1 Reduce THERMAL POWER 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> associated Completion to

Time not met.

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

JAFNPP 3.6.3.1-1 Amendment 274

CAD System 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Containment Atmosphere Dilution (CAD) System LCO 3.6.3.2 Two CAD subsystems shall be OPERABLE.

APPLICABILITY: 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable, administrative means that the hydrogen AND control function is maintained. Once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> thereafter AND B.2 Restore one CAD 7 days subsystem to OPERABLE status.

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

JAFNPP 3.6.3.2-1 Amendment 274

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.

JAFNPP 3.6.3.2-2 Amendment 274

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

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> inoperable in MODE 1, containment to 2, or 3. OPERABLE status.

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

B.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> 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)

JAFNPP 3.6.4.1-1 Amendment 274

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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 2 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using one SGT subsystem BASIS for each at a flow rate

  • 6000 cfm. SGT subsystem JAFNPP 3.6.4.1-2 Amendment 274

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.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

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

. . OTES.. --------

1. Penetration flow paths may be unisolated intermittently under administrative controls.
2. Separate Condition entry is allowed for each penetration flow path.
3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Isolate the affected 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> 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)

JAFNPP 3.6.4.2-1 Amendment 274

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 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> 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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time of Condition A AND or B not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> (continued)

JAFNPP 3.6.4.2-2 Amendment 274

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.

JAFNPP 3.6.4.2-3 Amendment 274

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS_

SURVEILLANCE FREQUENCY 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 31 days 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.

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.

JAFNPP 3.6.4.2-4 Amendment 274

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.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

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

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time of Condition A AND not met in MODE 1, 2, or 3. B.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> 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)

JAFNPP 3.6.4.3-1 Amendment 274

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.

JAFNPP 3.6.4.3-2 Amendment 274

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.

JAFNPP 3.6.4.3-3 Amendment 274

RHRSW System 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LCO 3.7.1 Two RHRSW subsystems shall be OPERABLE.

APPLICABILITY: 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)

JAFNPP 3.7.1-1 Amendment 274

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 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> subsystem to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> 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.

JAFNPP 3.7.1-2 Amendment 274

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 Two ESW subsystems and UHS shall be OPERABLE.

APPLICABILITY: 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

  • 37°F.

(continued)

JAFNPP 3.7.2-1 Amendment 274

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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time not met. AND OR C.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> screenwell is 2 236.5 ft mean sea level.

SR 3.7.2.2 Verify the average water temperature of UHS 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> is

  • 85 0 F.

(continued)

JAFNPP 3.7.2-2 Amendment 274

ESW System and UHS 3.7.2 SURVE ILLANCE REQUIREMENTS (continued)

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

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

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 0 F.

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

(continued)

JAFNPP 3.7.2-3 Amendment 274

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 > 370 F.

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.

JAFNPP 3.7.2-4 Amendment 274

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.

--- -NOT E ---------------------------

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

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time of Condition A or AND B not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> (continued)

JAFNPP 3.7.3-1 Amendment 274

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)

JAFNPP 3.7.3-2 Amendment 274

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)

JAFNPP 3.7.3-3 Amendment 274

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 ? 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 2 900 scfm and scfm. S1100 JAFNPP 3.7.3-4 Amendment 274

Control Room AC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION 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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time of Condition A AND not met in MODE 1, 2, or 3. B.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> (continued)

JAFNPP 3.7.4-1 Amendment 274

Control Room AC System 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)

JAFNPP 3.7.4-2 Amendment 274

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.

JAFNPP 3.7.4-3 Amendment 274

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

  • 600,000 pCi/second.

APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated and steam jet air ejector (SJAE) in operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross gamma activity A.1 Restore gross gamma 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> 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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion steam lines.

Time not met.

OR B.2 Isolate SJAE. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> OR B.3.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> AND B.3.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> JAFNPP 3.7.5-1 Amendment 274

Main Condenser SJAE Offgas 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 31 days noble gases is

  • 600,000 pCi/second.

AND NOTE ----

Only required when gross gamma activity rate is ; 5,000 pCi/second Once within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> after a 2 50X increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level JAFNPP 3.7.5-2 Amendment 274

Main Turbine Bypass System 3.7.6 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 2 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> LCO not met. requirements of the LCO.

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

Time not met.

JAFNPP 3.7.6-1 Amendment 274

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.

JAFNPP 3.7.6-2 Amendment 274

Spent Fuel Storage Pool Water Level 3.7.7 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 assemblies seated in the spent fuel storage pool racks.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage 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 2 21 ft 7 inches over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

JAFNPP 3.7.7-1 Amendment 274

AC Sources- Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the plant Class 1E AC Electrical Power Distribution System: and
b. Two emergency diesel generator (EDG) subsystems.

APPLICABILITY: 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable, for OPERABLE offsite circuit. AND Once per 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> thereafter AND A.2 Declare required 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 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)

JAFNPP 3.8.1-1 Amendment 274

AC Sources- Operating 3.8.1 ACT TAM 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 B.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. for OPERABLE offsite circuit(s). AND Once per 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> thereafter AND B.2 Declare required 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> from feature(s), supported discovery of by the inoperable EDG Condition B subsystem, inoperable concurrent with when the redundant inoperability of required feature(s) redundant are inoperable. required feature(s)

AND B.3.1 Determine OPERABLE 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> EDG subsystem is not inoperable due to common cause failure.

OR Perform SR 3.8.1.2 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> B.3.2 for OPERABLE EDG subsystem.

AND (continued)

______________________ J________________________ I ______________

3.8.1-2 Amendment 274 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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> 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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> circuit to OPERABLE status.

OR (continued)

JAFNPP 3.8.1-3 Amendment 274

AC Sources- Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) D.2 Restore EDG subsystem 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> to OPERABLE status.

E. Two EDG subsystems E.1 Restore one EDG 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> inoperable, subsystem to OPERABLE status.

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

F.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> 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)

JAFNPP 3.8.1-4 Amendment 274

AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

.4 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 - 3900 V and frequency ; 58.8 Hz; and
b. Steady state voltage Ž 3900 V and S4400 V and frequency 2 58.8 Hz and S61.2 Hz.

.4 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

> 60 minutes at a load > 2340 kW and

< 2600 kW.

(continued)

JAFNPP 3.8.1-5 Amendment 274

AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains 2 327 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) 3.8.1-6 Amendment 274 JAFNPP

AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 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 EDG subsystem rejects a load 24 months greater than or equal to its associated single largest post-accident load, and following load rejection, the frequency is S66.75 Hz.

(continued)

JAFNPP 3.8.1-7 Amendment 274

AC Sources -Operating 3.8.1 ZIllVFTI IANCP PFOHTRFMFNTS (continued' (ZHPVPT1iAmrP PFnUIREMENTS (continued) I SURVEILLANCE FREQUENCY I

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 24 months 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 S3900 V and
  • 4400 V,
4. maintains steady state frequency
58.8 Hz and < 61.2 Hz, and
5. supplies permanently connected and auto-connected shutdown loads for

Ž 5 minutes.

(continued) 3.8.1-8 Amendment 274 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 g 10 seconds after auto-start and during tests, achieves voltage 2 3900 V, frequency 2 58.8 Hz;
b. Achieves steady state voltage ; 3900 V and : 4400 V and frequency ; 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)

JAFNPP 3.8.1-9 Amendment 274

AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY t

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

8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />:
a. For ? 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> each EDG loaded 2 2730 kW and : 2860 kW; and
b. For the remaining hours of the test each EDG loaded ; 2340 kW and
  • 2600 kW.

(continued)

JAFNPP 3.8.1-10 Amendment 274

AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) I SURVEILLANCE FREQUENCY i

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 24 months 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 2 3900 V and g 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 ; 5 minutes.

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.

JAFNPP 3.8.1-11 Amendment 274

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.

3.8.2-1 Amendment 274 JAFNPP

AC Sources -Shutdown 3.8.2 ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION I REQUIRED ACTION COMPLETION TIME A. One or both required ------------- NOTE ------------

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

A.1 Declare affected Immediately required feature(s),

with no offsite power available, 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 A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel (OPDRVs).

AND (continued)

______________________________ .1__________________________________ A JAFNPP 3.8.2-2 Amendment 274

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.

JAFNPP 3.8.2-3 Amendment 274

AC Sources -Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4

SR 3.8.2.1 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 In accordance SRs of Specification 3.8.1, except with applicable SR 3.8.1.7, are applicable. SRs I __________________________________________________________

JAFNPP 3.8.2-4 Amendment 274

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits for each required emergency diesel generator (EDG).

APPLICABILITY: When associated EDG subsystem is required to be OPERABLE.

ACTIONS

. NOT E ------------------------------------

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 hours2 days <br />0.286 weeks <br />0.0658 months <br /> 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 hours2 days <br />0.286 weeks <br />0.0658 months <br /> 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) 3.8.3-1 Amendment 274 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 hours2 days <br />0.286 weeks <br />0.0658 months <br /> 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 S32,000 gal of fuel.

(continued)

JAFNPP 3.8.3-2 Amendment 274

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 e 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.

JAFNPP 3.8.3-3 Amendment 274

DC Sources- Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCO 3.8.4 The following DC electrical power subsystems shall be OPERABLE:

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 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> power subsystem electrical power inoperable, subsystem to OPERABLE status.

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

B.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> C. One or both 419 VDC C.1 Declare associated Immediately LPCI MOV independent LPCI subsystem(s) power supply inoperable.

subsystems inoperable.

JAFNPP 3.8.4-1 Amendment 274

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. Ž 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 2 128 VDC for 2 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />.

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)

JAFNPP 3.8.4-2 Amendment 274

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 2 80% of the 60 months manufacturer's rating when subjected to a performance discharge test or a modified AND performance discharge test.

12 months when battery shows degradation or has reached 85%

of expected life with capacity < 100%

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

of manufacturer's rating JAFNPP 3.8.4-3 Amendment 274

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

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

ACTIONS

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

-NOTE-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) 3.8.5-1 Amendment 274 JAFNPP

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.

JAFNPP 3.8.5-2 Amendment 274

Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for 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.

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

ACTIONS

--.------. ----. --.----. ----. ---- -NOTENOTE ....................... ------------

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> parameters meet Table 3.8.6-1 AND Category C limits.

Once per 7 days thereafter AND (continued)

JAFNPP 3.8.6-1 Amendment 274

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)

JAFNPP 3.8.6-2 Amendment 274

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 ; 65 0 F for each 125 VDC battery, and Ž 50°F for each 419 VDC LPCI MOV independent power supply battery.

JAFNPP 3.8.6-3 Amendment 274

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 * %,inch above and ! %, inch above overflowing maximum level maximum level indication mark(a) indication mark(a)

Float Voltage 2 2.13 V 2 2.13 V > 2.07 V Specific Ž 1.195 2 1.195 Not more than Gravityb) (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.

JAFNPP 3.8.6-4 Amendment 274

Distribution Systems- Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems -Operating LCO 3.8.7 The Division 1 and Division 2 AC and 125 VDC electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC A.1 Restore AC electrical 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> electrical power power distribution distribution subsystems to AND subsystems inoperable. OPERABLE status. 16 hours0.667 days <br />0.0952 weeks <br />0.0219 months <br /> from discovery of failure to meet LCO B. One 125 VDC electrical B.1 Restore 125 VDC 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> power distribution electrical power subsystem inoperable, distribution AND subsystem to OPERABLE status. 16 hours0.667 days <br />0.0952 weeks <br />0.0219 months <br /> from discovery of failure to meet LCO C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time of Condition A or AND

.B not met.

C.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> (continued)

JAFNPP 3.8.7-1 Amendment 274

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.

JAFNPP 3.8.7-2 Amendment 274

Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems- Shutdown LCO 3.8.8 The necessary portions of the AC and 125 VDC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

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

ACTIONS

. NOT 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)

JAFNPP 3.8.8-1 Amendment 274

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.

JAFNPP 3.8.8-2 Amendment 274

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks associated with the reactor mode switch in the refuel position shall be OPERABLE.

APPLICABILITY: 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.

JAFNPP 3.9.1-1 Amendment 274

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of 7 days the following required refueling equipment interlock inputs:

a. All-rods-in,
b. Refuel platform position,
c. Refuel platform fuel grapple, fuel loaded,
d. Refuel platform fuel grapple not fully up,
e. Refuel platform frame mounted hoist, fuel loaded, and
f. Refuel platform trolley mounted (monorail) hoist, fuel loaded.

JAFNPP 3.9.1-2 Amendment 274

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 refuel position and any control rod withdrawn.

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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> position.

(continued)

JAFNPP 3.9.2-1 Amendment 274

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. 7 days JAFNPP 3.9.2-2 Amendment 274

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control 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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> JAFNPP 3.9.3-1 Amendment 274

Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 The control rod "full-in" position indication channel for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS

-----NOTE OTE------------------------- --------

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

OR (continued)

JAFNPP 3.9.4-1 Amendment 274

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 JAFNPP 3.9.4-2 Amendment 274

Control Rod OPERABILITY- Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY-Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to 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.

JAFNPP 3.9.5-1 Amendment 274

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be Ž 22 ft 2 inches above the top of the RPV flange.

APPLICABILITY: 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 ; 22 ft 2 inches 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> above the top of the RPV flange.

JAFNPP 3.9.6-1 Amendment 274

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 One RHR shutdown cooling subsystem shall be OPERABLE.

APPLICABILITY: 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystem method of decay heat inoperable, removal is available. AND Once per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 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)

JAFNPP 3.9.7-1 Amendment 274

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.

JAFNPP 3.9.7-2 Amendment 274

RHR- Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR)-Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE.

APPLICABILITY: 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> RHR shutdown cooling method of decay heat subsystems inoperable, removal is available AND for each inoperable required RHR shutdown Once per cooling subsystem. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 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)

JAFNPP 3.9.8-1 Amendment 274

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.

JAFNPP 3.9.8-2 Amendment 274

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 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."

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

JAFNPP 3.10.1-1 Amendment 274

Inservice Leak and Hydrostatic Testing Operation 3.10.1 ACTIONS

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

the LCO.

Separate Condition entry is allowed for each requirement . of---------

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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> reactor coolant temperature to S212'F.

3.10.1-2 Amendment 274 JAFNPP

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 JAFNPP 3.10.1-3 Amendment 274

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 fully inserted in core cells containing one or more fuel assemblies: and
b. No CORE ALTERATIONS are in progress.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> insertable control rods in core cells containing one or more fuel assemblies.

AND (continued) 3.10.2-1 Amendment 274 JAFNPP

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> mode switch in the shutdown position.

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

Only applicable in MODE 5.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> in core cells containing one or more fuel assemblies.

SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> JAFNPP 3.10.2-2 Amendment 274

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 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.

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

JAFNPP 3.10.3-1 Amendment 274

Single Control Rod Withdrawal -Hot Shutdown 3.10.3 ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 --------

- NOTES -------

above requirements not 1. Required Actions met. to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.

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

Enter the applicable Immediately Condition of the affected LCO.

OR A.2. 1 Initiate action to Immediately fully insert all insertable control rods.

AND A.2.2 Place the reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> mode switch in the shutdown position.

______________________ I _____________

JAFNPP 3.10.3-2 Amendment 274

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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> control rod being withdrawn, are fully inserted.

JAFNPP 3.10.3-3 Amendment 274

Single Control Rod Withdrawal -Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Single Control Rod Withdrawal -Cold Shutdown LCO 3.10.4 The reactor mode switch position specified in Table 1.1-1 for MODE 4 may be changed to include the refuel position, 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.

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

3.10.4-1 Amendment 274 JAFNPP

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 A.1 - -------- NOTES -------

above requirements not 1. Required Actions met with the affected to fully insert control rod all insertable insertable. control rods include placing the reactor mode switch in the shutdown position.

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

Enter the applicable Immediately Condition of the affected LCO.

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

AND Place the reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> A.2.2 mode switch in the shutdown position.

____________________ I ______________________

(continued)

JAFNPP 3.10.4-2 Amendment 274

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.

i nsertabl e.

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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.

(continued) 3.10.4-3 Amendment 274 JAFNPP

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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> inserted.

JAFNPP 3.10.4-4 Amendment 274

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 The requirements of LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation"; LCO 3.3.8.2, "Reactor Protection System (RPS) Electric Power Monitoring"; LCO 3.9.1, "Refueling Equipment Interlocks"; LCO 3.9.2, "Refuel Position One-Rod-Out Interlock"; LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY-Refueling," may be suspended in MODE 5 to allow the removal of a single CRD associated with a control rod withdrawn from a core cell containing one or more fuel assemblies, provided the following requirements are met:

a. All other control rods are fully inserted;
b. All other control rods in a five by five array centered on the withdrawn control rod are disarmed;
c. A control rod withdrawal block is inserted and LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 5 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod; and
d. No other CORE ALTERATIONS are in progress.

APPLICABILITY: MODE 5 with LCO 3.9.5 not met.

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) 3.10.5-1 Amendment 274 JAFNPP

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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> inserted.

SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 (continued)

JAFNPP 3.10.5-2 Amendment 274

Single CRD Removal -Refueling 3.10.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> progress.

3.10.5-3 Amendment 274 JAFNPP

Multiple Control Rod Withdrawal -Refueling 3.10.6 3.10 SPECIAL OPERATIONS 3.10.6 Multiple Control Rod Withdrawal-Refueling LCO 3.10.6 The requirements of LCO 3.9.3, "Control Rod Position";

LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY-Refueling," may be suspended, and the "full-in" position indicators may be bypassed for any number of control rods in MODE 5, to allow withdrawal 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.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the 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)

JAFNPP 3.10.6-1 Amendment 274

Multiple Control Rod Withdrawal -Refueling 3.10.6

^*T*kl*

MUI ivili r CONDITION REQUIRED ACTION COMPLETION TIME A.3.1 Initiate action to Immediately A. (continued) fully insert all control rods in core cells containing one or more fuel assemblies.

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

L _____________________________________________________________

CIIflIICTI I AMP DrAIITDMMTcZ C Q *nIFREQ'UENCY SURVEILLANCE FREQUENCY I

Verify the four fuel assemblies are removed 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.10.6.1 from core cells associated with each control rod or CRD removed.

I--r Verify all other control rods in core cells 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> SR 3.10.6.2 containing one or more fuel assemblies are fully inserted.

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

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> compliance with an approved spiral reload sequence.

.1 ____________________________

3.10.6-2 Amendment 274 JAFNPP

Control Rod Testing-Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing-Operating LCO 3.10.7 The requirements of LCO 3.1.6, "Rod Pattern Control," may be suspended to allow performance of SDM 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.

APPLICABILITY: 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.

JAFNPP 3.10.7-1 Amendment 274

Control Rod Testing-Operating 3.10.7 SURVEILLANCE REOUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.7.1 ------------------ NOTE -------------------

Not required to be met if SR 3.10.7.2 satisfied.

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

SR 3.10.7.2 -------------------NOTE -------------------

Not required to be met if SR 3.10.7.1 satisfied.

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

JAFNPP 3.10.7-2 Amendment 274

SDM Test- Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a. LCO 3.3.1.1, "Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a 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 2 940 psig.

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

JAFNPP 3.10.8-1 Amendment 274

SDM Test -Refueling 3.10.8 AIJ i IUNb AL; I1UNZ _ _ _ __ _ _ _ _ __ _ _ _ _

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

Separate Condition Rod worth minimizer may be bypassed as allowed by entry is allowed for 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. 3 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> A. 1 Fully insert inoperable control rod.

AND 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> A.2 Disarm the associated CRD.

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

than Condition A.

., r-,uITkAr#dTC SURVEILLANUt K_.u1KrMN1 3 SURVEILLANCE FREQUENCY According to SR 3.10.8.1 Perform the MODE 2 applicable SRs for LCO the applicable 3.3.1.1, Functions 2.a and 2.d of Table SRs 3.3.1.1-1.

(continued) 3.10.8-2 Amendment 274 JAFNPP

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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> progress.

(continued)

JAFNPP 3.10.8-3 Amendment 274

SDM Test-Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.5 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position. control rod is withdrawn to "full-out" position AND Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days t 940 psig.

3.10.8-4 Amendment 274 JAFNPP

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)

JAFNPP 4.0-1 Amendment 274

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. k f
  • 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 0 C);
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)

JAFNPP 4.0-2 Amendment 274

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.

JAFNPP 4.0-3 Amendment 274

Design Features 4.0 LAKE ONTARIO SI-E &D1Cc1UjSO AREA SM14DARY Figure 4.1-1 (page 1 of 1)

Site and Exclusion Area Boundaries 4.0-4 Amendment 274 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) 5.2-1 Amendment 274 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 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> 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 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />, 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).

JAFNPP 5.2-2 Amendment 274

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).

5.3-1 Amendment 274 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.

JAFNPP 5.4-1 Amendment 274

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)

JAFNPP 5.5-1 Amendment 274

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) 5.5-2 Amendment 274 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)

JAFNPP 5.5-3 Amendment 274

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)

JAFNPP 5.5-4 Amendment 274

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, L,,

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 La when tested at 2 Pa; and (b) For each door seal, leakage rate is
  • 120 scfd when tested at ? Pa.

(continued)

JAFNPP 5.5-5 Amendment 274

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 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.

5.5.7 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:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities;
c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and (continued)

JAFNPP 5.5-6 Amendment 274

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 hours30 days <br />4.286 weeks <br />0.986 months <br /> 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)

JAFNPP 5.5-7 Amendment 274

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 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 Penetration and Flowrate (scfm)

Ventilation System System Bypass Standby Gas 1.0% 5,400 to 6,600 Treatment System Control Room 1.0% 900 to 1,100 Emergency Ventilation Air Supply System

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 Penetration and Flowrate (scfm)

Ventilation System System Bypass Standby Gas 1.0% 5,400 to 6,600 Treatment System Control Room 0.5% 900 to 1,100 Emergency Ventilation Air Supply System (continued)

JAFNPP 5.5-8 Amendment 274

Manuals and Programs and Manuals 5.5 Programs 5.5 5.5 Programs and Manuals 5.5.8 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 0 accordance with ASTM D3803-1989 at a temperature of
  • 30 C (86°F) and the relative humidity specified below.

Engineered Safeguards Penetration RH Ventilation System 5% > 70%

Standby Gas Treatment System 2 95%

Control Room Emergency Ventilation Air Supply System

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 Delta P Flowrate (scfm)

Ventilation System (inches wg) 5.7 5,400 to 6,600 Standby Gas Treatment System 5.8 900 to 1,100 Control Room Emergency Ventilation Air Supply System

e. Demonstrate that th e heaters for the Standby Gas Treatment System dissipate > 29 kW when tested in accordance with ASME N510-1975.

(continued)

JAFNPP 5.5-9 Amendment 274

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)

JAFNPP 5.5-10 Amendment 274

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)

JAFNPP 5.5-11 Amendment 274

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)

JAFNPP 5.5-12 Amendment 274

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)

JAFNPP 5.5-13 Amendment 274

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.

JAFNPP 5.5-14 Amendment 274

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) 5.6-1 Amendment 274 JAFNPP

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued) submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the 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.

5.6.4 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.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
1. The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) of Specification 3.2.1;
2. The MINIMUM CRITICAL POWER RATIO (MCPR) of Specification 3.2.2:
3. The LINEAR HEAT GENERATION RATE (LHGR) of Specification 3.2.3:

(continued)

JAFNPP 5.6-2 Amendment 274

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)

JAFNPP 5.6-3 Amendment 274

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.

JAFNPP 5.6-4 Amendment 274

High Radiation Area5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls required by shall be applied to high radiation areas in place of the controls paragraph 20.1601(a) and (b) of 10 CFR Part 20:

at 5.7.1 High Radiation Areas with dose rates not exceeding 1.0 rem/hour from any surface 30 centimeters from the radiation source or 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.

and

c. Individuals qualified in radiation protection procedures by such individuals may be personnel continuously escorted while exempted from the requirement for an RWP or equivalent 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) 5.7-1 Amendment 274 JAFNPP

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)

JAFNPP 5.7-2 Amendment 274

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) 5.7-3 Amendment 274 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.

JAFNPP 5.7-4 Amendment 274

Retrieved from "https://kanterella.com/w/index.php?title=ML021970095&oldid=2699662"