Text

Attachment 4: Page Change Instructions and Revised Pages, and Appendix a Technical Specifications
	ML18270A325
Person / Time
Site:	Palisades
Issue date:	09/27/2018
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML18270A320	List: ML18270A322; ML18270A323; ML18270A324; ML18270A325; ML18270A326; ML18270A327; ML18270A328; PNP 2018-025, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b;
References
	PNP 2018-025
	Download: ML18270A325 (101)
	v • d • e

ATTACHMENT 4 Page Change Instructions and Revised Pages for the Palisades Plant Renewed Facility Operating License DPR-20 and Appendix A Technical Specifications 100 pages follow

Page Change Instructions ATTACHMENT TO LICENSE AMENDMENT NO. 2xx RENEWED FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Remove the following page of Palisades Plant Renewed Facility Operating License, and replace with the attached revised page. The revised page is identified by amendment number and contains a line in the margin indicating the area of change.

REMOVE INSERT Page 3 Page 3 Remove the following pages of Appendix A, Technical Specifications, and replace with the attached revised pages. The revised pages are identified by amendment number and contain a line in the margin indicating the area of change.

REMOVE Page 3.1.1-1 Page 3.1.2-2 Page 3.1.4-3 Page 3.1.5-1 Page 3.1.6-2 Page 3.1.7-2 Pages 3.2.1 3.2.1-4 Page 3.2.2-1 Page 3.2.3-1 Page 3.2.4-1 Pages 3.3.1 3.3.1-5 Page 3.3.2-2 Page 3.3.3-3 Page 3.3.4-2 Pages 3.3.5 3.3.5-2 INSERT Page 3.1.1-1 Page 3.1.2-2 Pages 3.1.4 3.1.4-4 Page 3.1.5-1 Page 3.1.6-2 Page 3.1.7-2 Pages 3.2.1 3.2.1-4 Page 3.2.2-1 Page 3.2.3-1 Page 3.2.4-1 Pages 3.3.1 3.3.1-5 Page 3.3.2-2 Page 3.3.3-3 Page 3.3.4-2 Pages 3.3.5 3.3.5-2 Page 1 of 4

Page Change Instructions ATTACHMENT TO LICENSE AMENDMENT NO. 2xx RENEWED FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 REMOVE (Continued)

Page 3.3.6-2 Page 3.3.7-3 Page 3.3.8-2 Page 3.3.9-2 Page 3.3.10-1 Page 3.4.1-2 Page 3.4.2-1 Page 3.4.3-2 Page 3.4.4-1 Page 3.4.5-2 Page 3.4.6-3 Page 3.4.7-3 Pages 3.4.8 3.4.8-3 Page 3.4.9-3 Page 3.4.11-3 Page 3.4.12-3 Page 3.4.13-2 Page 3.4.14-3 Pages 3.4.15 3.4.15-3 Pages 3.4.16 3.4.16-3 Page 3.5.1-2 INSERT (Continued)

Page 3.3.6-2 Page 3.3.7-3 Page 3.3.8-2 Page 3.3.9-2 Page 3.3.10-1 Page 3.4.1-2 Page 3.4.2-1 Page 3.4.3-2 Page 3.4.4-1 Pages 3.4.5 3.4.5-3 Page 3.4.6-3 Page 3.4.7-3 Pages 3.4.8 3.4.8-3 Page 3.4.9-3 Page 3.4.11-3 Page 3.4.12-3 Page 3.4.13-2 Page 3.4.14-3 Pages 3.4.15 3.4.15-3 Pages 3.4.16 3.4.16-3 Page 3.5.1-2 Page 2 of4

Page Change Instructions ATTACHMENT TO LICENSE AMENDMENT NO. 2xx RENEWED FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 REMOVE (Continued)

Pages 3.5.2 3.5.2-3 Page 3.5.4-2 Page 3.5.5-1 Page 3.6.2-4 Pages 3.6.3 3.6.3-5 Page 3.6.4-1 Page 3.6.5-1 Pages 3.6.6 3.6.6-3 Page 3.7.2-2 Page 3.7.3-2 Page 3.7.4-2 Page 3.7.5-3 Page 3.7.6-2 Page 3.7.7-2 Page 3.7.8-2 Page 3.7.9-1 Page 3.7.10-4 Page 3.7.11-3 Page 3.7.12-2 Page 3.7.13-1 Page 3.7.14-1 INSERT (Continued)

Pages 3.5.2 3.5.2-3 Page 3.5.4-2 Page 3.5.5-1 Page 3.6.2-4 Pages 3.6.3 3.6.3-5 Page 3.6.4-1 Page 3.6.5-1 Pages 3.6.6 3.6.6-3 Page 3.7.2-2 Page 3.7.3-2 Page 3.7.4-2 Page 3.7.5-3 Page 3.7.6-2 Page 3.7.7-2 Page 3.7.8-2 Page 3.7.9-1 Page 3.7.10-4 Page 3.7.11-3 Page 3.7.12-2 Page 3.7.13-1 Page 3.7.14-1 Page 3 of 4

Page Change Instructions ATTACHMENT TO LICENSE AMENDMENT NO. 2xx RENEWED FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 REMOVE (Continued)

Page 3.7.15-1 Page 3.7.17-1 Pages 3.8.1 3.8.1-8 Page 3.8.3-3 Pages 3.8.4 3.8.4-4 Pages 3.8.6 3.8.6-3 Page 3.8.7-1 Page 3.8.8-2 Page 3.8.9-2 Page 3.8.10-2 Page 3.9.1-1 Page 3.9.2-2 Page 3.9.3-2 Page 3.9.4-2 Page 3.9.5-2 Page 3.9.6-1 Page 5.0-23 INSERT (Continued)

Page 3.7.15-1 Page 3.7.17-1 Pages 3.8.1 3.8.1-8 Page 3.8.3-3 Pages 3.8.4 3.8.4-4 Pages 3.8.6 3.8.6-4 Page 3.8.7-1 Page 3.8.8-2 Page 3.8.9-2 Page 3.8.10-2 Page 3.9.1-1 Page 3.9.2-2 Page 3.9.3-2 Page 3.9.4-2 Page 3.9.5-2 Page 3.9.6-1 Page 5.0-23 Page 4 of 4 (1)

Pursuant to Section 104b of the Act, as amended, and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," (a) ENP to possess and use, and (b) ENO to possess, use and operate, the facility as a utilization facility at the designated location in Van Buren County, Michigan, in accordance with the procedures and limitation set forth in this license; (2)

ENO, pursuant to the Act and 10 CFR Parts 40 and 70, to receive, possess, and use source and special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)

ENO, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use byproduct, source, and special nuclear material as sealed sources for reactor startup, reactor instrumentation, radiation monitoring equipment calibration, and fission detectors in amounts as required; (4)

ENO, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material for sample analysis or instrument calibration, or associated with radioactive apparatus or components; and (5)

ENO, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operations of the facility.

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act; to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

ENO is authorized to operate the facility at steady-state reactor core power levels not in excess of 2565.4 Megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

The Technical Specifications contained in Appendix A, as revised through Amendment No. XXX, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the license amendment request dated December 12, 2012 and November 1,2017, as supplemented by letters dated February 21,2013, September 30,2013, October 24,2013, December 2,2013, April 2, 2014, May 7, Renewed License No. DPR-20 Amendment No. ~, XXX

3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

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

APPLICABILITY:

MODE 3, 4, and 5.

ACTIONS CONDITION A.

SDM not within limit.

A.1 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Initiate boration to restore SDM to within limit.

SURVEILLANCE SR 3.1.1.1 Verify SDM to be within limits.

Palisades Nuclear Plant 3.1.1-1 COMPLETION TIME 15 minutes FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.1.2.1 SURVEILLANCE

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

The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 Effective Full Power Days (EFPD) after each fuel loading.

Verify overall core reactivity balance is within

+/- 1 % ~p of predicted values.

Reactivity Balance 3.1.2 FREQUENCY Prior to entering MODE 1 after each fuel loading AND

NOTE---------

Only required after initial 60 EFPD In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.2-2 Amendment No..:tS9, XXX

SURVEILLANCE REQUIREMENTS SR 3.1.4.1 SR 3.1.4.2 SR 3.1.4.3 SR 3.1.4.4 SR 3.1.4.5 SURVEILLANCE Verify the position of each control rod to be within 8 inches of all other control rods in its group.

Perform a CHANNEL CHECK of the control rod position indication channels.

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

Not required to be performed or met for control rod 13 during cycle 25 provided control rod 13 is administratively declared immovable, but trippable and Condition D is entered for control rod 13.

Verify control rod freedom of movement by moving each individual full-length control rod that is not fully inserted into the reactor core ~ 6 inches in either direction.

Verify the rod position deviation alarm is OPERABLE.

Perform a CHANNEL CALIBRATION of the control rod position indication channels.

Control Rod Alignment 3.1.4 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.4-3 Amendment No. ~, XXX

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1.4.6 Verify each full-length control rod drop time is

~ 2.5 seconds.

Palisades Nuclear Plant 3.1.4-4 Control Rod Alignment 3.1.4 FREQUENCY Prior to reactor criticality, after each reinstallation of the reactor head Amendment No. ~, XXX

Shutdown and Part-Length Rod Group Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown and Part-Length Control Rod Group Insertion Limits LCO 3.1.5 All shutdown and part-length rod groups shall be withdrawn to

?: 128 inches.

APPLICABILITY:

MODE 1, MODE 2 with any regulating rod withdrawn above 5 inches.

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

This LCO is not applicable while performing SR 3.1.4.3 (rod exercise test).

ACTIONS CONDITION REQUIRED ACTION A.

One or more shutdown or A.1 Declare affected control part-length rods not within rod(s) inoperable and limit.

enter the applicable Conditions and Required Actions of LCO 3.1.4.

B.

Required Action and B.1 Be in MODE 3.

associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1.5.1 Verify each shutdown and part-length rod group is withdrawn?: 128 inches.

COMPLETION TIME Immediately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.5-1 Amendment No. 4W, XXX

Regulating Rod Group Position Limits 3.1.6 ACTIONS CONDITION REQUIRED ACTION B.

Regulating rod groups not B.1 Restore regulating rod within sequence or overlap groups to within limits.

appropriate sequence and overlap limits.

C.

POlL or CROOS alarm C.1 Perform SR 3.1.6.1 circuit inoperable.

(group position verification).

D.

Required Action and 0.1 Be in MODE 3.

associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1.6.1 SR 3.1.6.2 SR 3.1.6.3 Verify each regulating rod group is within its withdrawal sequence, overlap, and insertion limits.

Verify POlL alarm circuit is OPERABLE.

Verify CROOS alarm circuit is OPERABLE.

COMPLETION TIME 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Once within 15 minutes following any rod motion 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.6-2 Amendment No. 48Q, XXX

ACTIONS CONDITION D.

Required Action and associated Completion Time not met.

SURVEILLANCE REQUIREMENTS D.1 REQUIRED ACTION Suspend PHYSICS TESTS.

SURVEILLANCE SR 3.1.7.1 Verify THERMAL POWER is ~ 2% RTP.

SR 3.1.7.2 Verify Tave is ~ 500°F.

Special Test Exceptions (STE) 3.1.7 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program SR 3.1.7.3 Verify ~ 1 % shutdown reactivity is available for trip insertion.

In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.7-2 Amendment No. 89, XXX

ACTIONS CONDITION REQUIRED ACTION B.

Incore Alarm and Excore B.1 Reduce THERMAL Monitoring Systems POWER to ~ 85% RTP.

inoperable for monitoring LHR.

AND B.2 Verify LHR is within limits using manual incore readings.

C.

Required Action and C.1 Reduce THERMAL associated Completion POWER to ~ 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SR 3.2.1.1 SURVEILLANCE

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

Only required to be met when the Incore Alarm System is being used to monitor LHR.

Verify LHR is within the limits specified in the COLR.

LHR 3.2.1 COMPLETION TIME 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 4 hours AND Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thereafter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.1-2 Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.2.1.2 SR 3.2.1.3 SR 3.2.1.4 SURVEILLANCE

N()TE----------------------------

()nly required to be met when the Incore Alarm System is being used to monitor LHR.

Adjust incore alarm setpoints based on a measured power distribution.

N () T E ---------------------------

()nly required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify measured ASI has been within 0.05 of target ASI for last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

N () TE ---------------------------

()nly required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify THERMAL P()WER is less than the APL.

LHR 3.2.1 FREQUENCY Prior to operation

> 50% RTP after each fuel loading In accordance with the Surveillance Frequency Control Program Prior to each initial use of Excore Monitoring System to monitor LHR In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.1-3 Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.2.1.5 SR 3.2.1.6 SURVEILLANCE

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

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify measured ASI is within 0.05 of target ASI.

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

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify Tq ::; 0.03.

LHR 3.2.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.1-4 Amendment No. 489, XXX

3.2 POWER DISTRIBUTION LIMITS 3.2.2 TOTAL RADIAL PEAKING FACTOR (FRT)

LCO 3.2.2 FR T shall be within the limits specified in the COLR.

APPLICABILITY:

MODE 1 with THERMAL POWER> 25% RTP.

ACTIONS CONDITION REQUIRED ACTION A.

FRT not within limits A.1 Restore FRT to within specified in the COLR.

limits.

B.

Required Action and B.1 Reduce THERMAL associated Completion POWER to :s; 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.2.1 Verify FR T is within limits specified in the COLR.

Radial Peaking 3.2.2 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 4 hours FREQUENCY Prior to operation

> 50% RTP after each fuel loading In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.2-1 Amendment No. 2Qa, XXX

3.2 POWER DISTRIBUTION LIMITS 3.2.3 QUADRANT POWER TILT (Tq)

LCO 3.2.3 Tq shall be ~ 0.05.

APPLICABILITY:

MODE 1 with THERMAL POWER> 25% RTP.

ACTIONS CONDITION REQUIRED ACTION A.

Tq> 0.05.

A.1 Verify FR T is within the limits of LCO 3.2.2, "TOTAL RADIAL PEAKING FACTOR ".

B.

Tq>0.10.

B.1 Reduce THERMAL POWER to < 50% RTP.

C.

Required Action and C.1 Reduce THERMAL associated Completion POWER to ~ 25% RTP.

Time not met.

OR Tq> 0.15.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.3.1 Verify Tq is ~ 0.05.

Tq 3.2.3 COMPLETION TIME 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4 hours FREQUENCY In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.3-1 Amendment No. ~,XXX

3.2 POWER DISTRIBUTION LIMITS 3.2.4 AXIAL SHAPE INDEX (ASI)

ASI 3.2.4 LCO 3.2.4 The ASI shall be within the limits specified in the COLR.

APPLICABILITY:

MODE 1 with THERMAL POWER> 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

ASI not within limits A.1 Restore ASI to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months specified in COLR.

limits.

B.

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

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.4.1 Verify ASI is within limits specified in the COLR.

Palisades Nuclear Plant 3.2.4-1 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. +89, XXX

ACTIONS CONDITION REQUIRED ACTION G.

Required Action and G.1 Be in MODE 3.

associated Completion Time not met.

AND OR G.2.1 Verify no more than one Control room ambient air full-length control rod is capable of being temperature> gO°F.

withdrawn.

OR G.2.2 Verify PCS boron concentration is at REFUELING BORON CONCENTRATION.

SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 6 hours 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

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

Refer to Table 3.3.1-1 to determine which SR shall be performed for each Function.

SURVEILLANCE SR 3.3.1.1 Perform a CHANNEL CHECK.

SR 3.3.1.2 Verify control room temperature is s; gO°F.

Palisades Nuclear Plant 3.3.1-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7 SURVEILLANCE

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is ~ 15% RTP.

Perform calibration (heat balance only) and adjust the power range excore and AT power channels to agree with calorimetric calculation if the absolute difference is ~ 1.5%.

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

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

Calibrate the power range excore channels using the incore detectors.

Perform a CHANNEL FUNCTIONAL TEST and verify the Thermal Margin Monitor Constants.

Perform a calibration check of the power range excore channels with a test signal.

Perform a CHANNEL FUNCTIONAL TEST of High Startup Rate and Loss of Load Functions.

RPS Instrumentation 3.3.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Once within 7 days prior to each reactor startup Palisades Nuclear Plant 3.3.1-4 Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SURVEILLANCE RPS Instrumentation 3.3.1 FREQUENCY SR 3.3.1.8

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

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform a CHANNEL CALIBRATION.

Palisades Nuclear Plant 3.3.1-5 In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

ACTIONS CONDITION E.

Required Action and associated Completion Time not met.

REQUIRED ACTION E.1 Be in MODE 3.

AND RPS Logic and Trip Initiation 3.3.2 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR E.2.1 Verify no more than one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months One or more Functions full-length control rod is with two or more Manual capable of being Trip, Matrix Logic or Trip withdrawn.

Initiation Logic channels OR inoperable for reasons other than Condition D.

E.2.2 Verify PCS boron concentration is at REFUELING BORON CONCENTRATION.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.3.2.1 Perform a CHANNEL FUNCTIONAL TEST on each RPS Matrix Logic channel and each RPS Trip Initiation Logic channel.

SR 3.3.2.2 Perform a CHANNEL FUNCTIONAL TEST on each RPS Manual Trip channel.

Palisades Nuclear Plant 3.3.2-2 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program Once within 7 days prior to each reactor startup Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS ESF Instrumentation 3.3.3

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

Refer to Table 3.3.3-1 to determine which SR shall be performed for each Function.

SURVEILLANCE SR 3.3.3.1 Perform a CHANNEL CHECK.

SR 3.3.3.2 Perform a CHANNEL FUNCTIONAL TEST.

SR 3.3.3.3 Perform a CHANNEL CALIBRATION.

Palisades Nuclear Plant 3.3.3-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

ESF Logic and Manual Initiation 3.3.4 ACTIONS CONDITION C.

One or more Functions with two Manual Initiation, or Actuation Logic channels inoperable for Functions 5 or 6.

Required Action and associated Completion Time of Condition A not met for Functions 5 or 6.

SURVEILLANCE REQUIREMENTS REQUIRED ACTION C.1 Be in MODE 3.

C.2 Be in MODE 5.

SURVEILLANCE SR 3.3.4.1 SR 3.3.4.2 SR 3.3.4.3 Perform functional test of each SIS actuation channel normal and standby power functions.

Perform a CHANNEL FUNCTIONAL TEST of each AFAS actuation logic channel.

Perform a CHANNEL FUNCTIONAL TEST.

COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.4-2 Amendment No. 489, XXX

3.3 INSTRUMENTATION 3.3.5 Diesel Generator (DG) - Undervoltage Start (UV Start)

DG - UV Start 3.3.5 LCO 3.3.5 Three channels of Loss of Voltage Function and three channels of Degraded Voltage Function auto-initiation instrumentation and associated logic channels for each DG shall be OPERABLE.

APPLICABILITY:

When associated DG is required to be OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions with one channel per DG inoperable.

A.1 Enter applicable Immediately Conditions and Required Actions for the associated DG made inoperable by DG - UV Start instrumentation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.3.5.1 Perform a CHANNEL FUNCTIONAL TEST on each DG-UV start logic channel.

Palisades Nuclear Plant 3.3.5-1 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.3.5.2 SURVEILLANCE Perform CHANNEL CALIBRATION on each Loss of Voltage and Degraded Voltage channel with setpoints as follows:

a.

Degraded Voltage Function ~ 2187 V and

s; 2264 V Time delay: ~ 0.5 seconds and

s; 0.8 seconds; and

b.

Loss of Voltage Function ~ 1780 V and

s; 1940 V Time delay: ~ 5.45 seconds and

s; 8.15 seconds at 1400 V.

Palisades Nuclear Plant 3.3.5-2 DG - UV Start 3.3.5 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. ~,XXX

Refueling CHR Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS SR 3.3.6.1 SR 3.3.6.2 SR 3.3.6.3 SR 3.3.6.4 SURVEILLANCE Perform a CHANNEL CHECK of each refueling CHR monitor channel.

Perform a CHANNEL FUNCTIONAL TEST of each refueling CHR monitor channel.

Perform a CHANNEL FUNCTIONAL TEST of each CHR Manual Initiation channel.

Perform a CHANNEL CALIBRATION of each refueling CHR monitor channel.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.6-2 Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS PAM Instrumentation 3.3.7

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

These SRs apply to each PAM instrumentation Function in Table 3.3.7-1.

SR 3.3.7.1 SR 3.3.7.2 SURVEILLANCE Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

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

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.7-3 Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SR 3.3.8.1 SR 3.3.8.2 SURVEILLANCE Perform CHANNEL FUNCTIONAL TEST of the Source Range Neutron Flux Function.

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

Alternate Shutdown System 3.3.8 FREQUENCY Once within 7 days prior to each reactor startup In accordance with the Surveillance Frequency Control Program SR 3.3.8.3

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

1.

Not required for Functions 16, 17, and 18.

2.

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each required instrumentation channel.

Palisades Nuclear Plant 3.3.8-2 In accordance with the Surveillance Frequency Control Program Amendment No. 4W, XXX

Neutron Flux Monitoring Channels 3.3.9 SURVEILLANCE REQUIREMENTS SR 3.3.9.1 SR 3.3.9.2 SURVEILLANCE Perform CHANNEL CHECK.

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

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.9-2 Amendment No. 489, XXX

3.3 INSTRUMENTATION ESRV Instrumentation 3.3.10 3.3.10 Engineered Safeguards Room Ventilation (ESRV) Instrumentation LCO 3.3.10 Two channels of ESRV Instrumentation shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION A.

One or more channels inoperable.

A.1 Initiate action to isolate the associated ESRV System.

SURVEILLANCE REQUIREMENTS SR 3.3.10.1 SR 3.3.10.2 SR 3.3.10.3 SURVEILLANCE Perform a CHANNEL CHECK.

Perform a CHANNEL FUNCTIONAL TEST.

Perform a CHANNEL CALIBRATION.

Verify high radiation setpoint on each ESRV Instrumentation radiation monitoring channel is s 2.2E+5 cpm.

Palisades Nuclear Plant 3.3.10-1 COMPLETION TIME Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

PCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SR 3.4.1.1 SR 3.4.1.2 SR 3.4.1.3 SURVEILLANCE Verify pressurizer pressure within the limits specified in the COLR.

Verify PCS cold leg temperature within the limit specified in the COLR.

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

Not required to be performed until 31 EFPD after THERMAL POWER is ~ 90% RTP.

Verify PCS total flow rate within the limit specified in the COLR.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program After each plugging of 10 or more steam generator tubes Palisades Nuclear Plant 3.4.1-2 Amendment No. ~,XXX

PCS Minimum Temperature for Criticality 3.4.2 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.2 PCS Minimum Temperature for Criticality LCO 3.4.2 Each PCS loop average temperature (Tave) shall be 2:: 525°F.

APPLICABILITY:

MODE 1 MODE 2 with Keff ~ 1.0.

ACTIONS CONDITION A.

Tave in one or more PCS loops not within limit.

SURVEILLANCE REQUIREMENTS A.1 REQUIRED ACTION Be in MODE 2 with Keff

< 1.0.

SURVEILLANCE SR 3.4.2.1 Verify PCS Tave in each loop ~ 525°F.

Palisades Nuclear Plant 3.4.2-1 COMPLETION TIME 30 minutes FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

ACTIONS CONDITION REQUIRED ACTION C.

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

C.1 Initiate action to restore Required Action C.2 shall parameter(s) to within be completed whenever limits.

this Condition is entered.

AND Requirements of LCO not C.2 Determine PCS is met any time in other than acceptable for continued MODE 1, 2, 3, or 4.

operation.

SURVEILLANCE REQUIREMENTS SR 3.4.3.1 SURVEILLANCE

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

Only required to be performed during PCS heatup and cooldown operations.

Verify PCS pressure, PCS temperature, and PCS heatup and cooldown rates are within the limits of Figure 3.4.3-1 and Figure 3.4.3-2.

PCS PIT Limits 3.4.3 COMPLETION TIME Immediately Prior to entering MODE4 FREQUENCY In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.3-2 Amendment No. 489, XXX

3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.4 PCS Loops - MODES 1 and 2 PCS Loops - MODES 1 and 2 3.4.4 LCO 3.4.4 Two PCS loops shall be OPERABLE and in operation.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION A.

Requirements of LCO not A.1 Be in MODE 3.

met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.4.1 Verify each PCS loop is in operation.

Palisades Nuclear Plant 3.4.4-1 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 89, XXX

ACTIONS CONDITION REQUIRED ACTION B.

Required Action and B.1 Be in MODE 4.

associated Completion Time of Condition A not met.

C.

No PCS loop OPERABLE.

C.1 Suspend all operations involving a reduction of OR PCS boron concentration.

No PCS loop in operation.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.5.1 SR 3.4.5.2 Verify required PCS loop is in operation.

Verify secondary side water level in each steam generator ~ -84%.

PCS Loops - MODE 3 3.4.5 COMPLETION TIME 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.5-2 Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.4.5.3 SURVEILLANCE Verify correct breaker alignment and indicated power available to the required primary coolant pump that is not in operation.

Palisades Nuclear Plant 3.4.5-3 PCS Loops - MODE 3 3.4.5 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 4-89, XXX

SURVEILLANCE REQUIREMENTS SR 3.4.6.1 SR 3.4.6.2 SR 3.4.6.3 SURVEILLANCE Verify one SDC train is in operation with;?: 2810 gpm flow through the reactor core, or one PCS loop is in operation.

Verify secondary side water level in required SG(s) is

?: -84%.

Verify correct breaker alignment and indicated power available to the required pump that is not in operation.

PCS Loops - MODE 4 3.4.6 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.6-3 Amendment No. 4W, XXX

PCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SR 3.4.7.1 SR 3.4.7.2 SR 3.4.7.3 SURVEILLANCE Verify one SOC train is in operation with;;::: 2810 gpm flow through the reactor core.

Verify required SG secondary side water level is

-84%.

Verify correct breaker alignment and indicated power available to the required SOC pump that is not in operation.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.7-3 Amendment No. 489, XXX

PCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS CONDITION REQUIRED ACTION A.

One SDC train inoperable.

A.1 Initiate action to restore SDC train to OPERABLE status.

B.

Two SDC trains B.1 Suspend all operations inoperable.

involving reduction of PCS boron OR concentration.

SDC flow through the AND reactor core not within limits.

B.2 Initiate action to restore one SDC train to OPERABLE status and operation with SDC flow through the reactor core within limit.

SURVEILLANCE REQUIREMENTS SR 3.4.8.1 SURVEILLANCE

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

Only required to be met when complying with LCO 3.4.8.a.

Verify one SDC train is in operation with

~ 2810 gpm flow through the reactor core.

COMPLETION TIME Immediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.8-2 Amendment No. 489-, XXX

SR 3.4.8.2 SR 3.4.8.3 SR 3.4.8.4 PCS Loops - MODE 5, Loops Not Filled 3.4.8 SURVEILLANCE

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

Only required to be met when complying with LCO 3.4.8.b.

Verify one SDC train is in operation with

~ 650 gpm flow through the reactor core.

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

Only required to be met when complying with LCO 3.4.8.b.

Verify two of three charging pumps are incapable of reducing the boron concentration in the PCS below the minimum value necessary to maintain the required SHUTDOWN MARGIN.

Verify correct breaker alignment and indicated power available to the SDC pump that is not in operation.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.8-3 Amendment No. 489, XXX

ACTIONS CONDITION REQUIRED ACTION D.

Required Action and D.1 Be in MODE 3.

associated Completion Time of Condition B or C AND not met.

D.2 Be in MODE 4.

SURVEILLANCE REQUIREMENTS SR 3.4.9.1 SR 3.4.9.2 SR 3.4.9.3 SURVEILLANCE

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

Not required to be met until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after establishing a bubble in the pressurizer and the pressurizer water level has been lowered to within its normal operating band.

Verify pressurizer water level is < 62.8%.

Verify the capacity of pressurizer heaters from electrical bus 1 D, and electrical bus 1 E is

375 kW.

Verify the required pressurizer heater capacity from electrical bus 1 E is capable of being powered from an emergency power supply.

Pressurizer 3.4.9 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 30 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.9-3 Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SR 3.4.11.1 SR 3.4.11.2 SURVEILLANCE Perform a complete cycle of each block valve.

Perform a complete cycle of each PORV with PCS average temperature> 200°F.

Pressurizer PORVs 3.4.11 FREQUENCY Once prior to entering MODE 4 from MODE 5 if not performed within previous 92 days In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.11-3 Amendment No. 4-S9, XXX

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS SR 3.4.12.1 SR 3.4.12.2 SR 3.4.12.3 SR 3.4.12.4 SR 3.4.12.5 SURVEILLANCE

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

Only required to be met when complying with LCO 3.4.12.a.

Verify both HPSI pumps are incapable of injecting into the PCS.

Verify required PCS vent, capable of relieving

167 gpm at a PCS pressure of 315 psia, is open.

Verify PORV block valve is open for each required PORV.

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing any PCS cold leg temperature to

< 430°F.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Perform CHANNEL FUNCTIONAL TEST on each In accordance with required PORV, excluding actuation.

the Surveillance Frequency Control Program Perform CHANNEL CALIBRATION on each required PORV actuation channel.

In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.12-3 Amendment No. 489, XXX

PCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SR 3.4.13.1 SR 3.4.13.2 SURVEILLANCE FREQUENCY

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

NOTE--------

1. Not required to be performed in MODE 3 or 4 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation.

2. Not applicable to primary to secondary LEAKAGE.

Verify PCS operational LEAKAGE is within limits by performance of PCS water inventory balance.

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

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

Verify primary to secondary LEAKAGE is ~ 150 gallons per day through anyone SG.

Only required to be performed during steady state operation In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.13-2 Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SR 3.4.14.1 SR 3.4.14.2 SURVEILLANCE

NOT E S--------------------------

1.

Only required to be performed in MODES 1 and 2.

2.

Leakage rates ~ 5.0 gpm are unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible leakage rate of 5.0 gpm by 50%

or greater.

3.

Minimum test differential pressure shall not be less than 150 psid.

Verify leakage from each PCS PIV is equivalent to

~ 5 gpm at a PCS pressure of 2060 psia.

Verify each SDC suction valve interlock prevents its associated valve from being opened with a simulated or actual PCS pressure signal ~ 280 psia.

PCS PIV Leakage 3.4.14 FREQUENCY In accordance with the Surveillance Frequency Control Program Once prior to entering MODE 2 whenever the plant has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.14-3 Amendment No. 489, XXX

PCS Leakage Detection Instrumentation 3.4.15 ACTIONS CONDITION REQUIRED ACTION C.

All required channels inoperable.

C.1 Enter LCO 3.0.3.

SURVEILLANCE REQUIREMENTS SR 3.4.15.1 SR 3.4.15.2 SR 3.4.15.3 SR 3.4.15.4 SR 3.4.15.5 SURVEILLANCE Perform CHANNEL CHECK of the required containment sump level indicator.

Perform CHANNEL CHECK of the required containment atmosphere gaseous activity monitor.

Perform CHANNEL CHECK of the required containment atmosphere humidity monitor.

Perform CHANNEL FUNCTIONAL TEST of the required containment air cooler condensate level switch.

Perform CHANNEL CALIBRATION of the required containment sump level indicator.

Palisades Nuclear Plant 3.4.15-2 COMPLETION TIME Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

PCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SR 3.4.15.6 SR 3.4.15.7 SURVEILLANCE Perform CHANNEL CALIBRATION of the required containment atmosphere gaseous activity monitor.

Perform CHANNEL CALIBRATION of the required containment atmosphere humidity monitor.

Palisades Nuclear Plant 3.4.15-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control

_ Program Amendment No. 489, XXX

ACTIONS CONDITION B.

Required Action and associated Completion Time of Condition A not met.

OR DOSE EQUIVALENT 1-131

~ 40 IJCi/gm.

Gross specific activity of the primary coolant not within limit.

SURVEILLANCE REQUIREMENTS B.1 REQUIRED ACTION Be in MODE 3 with Tave < 500°F.

SURVEILLANCE SR 3.4.16.1 Verify primary coolant gross specific activity

1 ODIE IJCilgm.

Palisades Nuclear Plant 3.4.16-2 PCS Specific Activity 3.4.16 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 4$9, XXX

SURVEILLANCE REQUIREMENTS SR 3.4.16.2 SR 3.4.16.3 SURVEILLANCE

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

Only required to be performed in MODE 1.

Verify primary coolant DOSE EQUIVALENT 1-131 specific activity ~ 1.0 IJCi/gm.

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

Not required to be performed until 31 days after a minimum of 2 EFPD and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for;::: 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine E from a sample taken in MODE 1 after a minimum of 2 EFPD and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for;::: 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

PCS Specific Activity 3.4.16 FREQUENCY In accordance with the Surveillance Frequency Control Program Once between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after THERMAL POWER change of

15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.16-3 Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SR 3.5.1.1 SR 3.5.1.2 SR 3.5.1.3 SR 3.5.1.4 SR 3.5.1.5 SURVEILLANCE Verify each SIT isolation valve is fully open.

Verify borated water volume in each SIT is

1 040 fe and

::;; 1176 fe.

Verify nitrogen cover pressure in each SIT is

200 psig.

Verify boron concentration in each SIT is

1720 ppm and

::;; 2500 ppm.

Verify power is removed from each SIT isolation valve operator.

Palisades Nuclear Plant 3.5.1-2 SITs 3.5.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.5.2.1 SR 3.5.2.2 SR 3.5.2.3 SR 3.5.2.4 SR 3.5.2.5 SURVEILLANCE Verify the following valves and hand switches are in the open position.

Valve/Hand Switch Number CV-3027 HS-3027A HS-30278 CV-3056 HS-3056A HS-30568 Function SIRWT Recirc Valve Hand Switch For CV-3027 Hand Switch For CV-3027 SIRWT Recirc Valve Hand Switch For CV-3056 Hand Switch For CV-3056 Verify each ECCS 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.

Verify CV-3006, "SOC Flow Control Valve," is open and its air supply is isolated.

Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head.

Verify each ECCS automatic valve that is not locked, sealed, or otherwise secured in position, in the flow path actuates to the correct position on an actual or simulated actuation signal.

ECCS - Operating 3.5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program Palisades Nuciear Plant 3.5.2-2 Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SR 3.5.2.6 SR 3.5.2.7 SR 3.5.2.8 SR 3.5.2.9 SURVEILLANCE Verify each ECCS pump starts automatically on an actual or simulated actuation signal.

Verify each LPSI pump stops on an actual or simulated actuation signal.

Verify, for each ECCS throttle valve listed below, each position stop is in the correct position.

Valve Number MO-3008 MO-3010 MO-3012 MO-3014 MO-3082 MO-3083 Function LPSI to Cold leg 1A LPSI to Cold leg 18 LPSI to Cold leg 2A LPSI to Cold leg 28 HPSI to Hot leg 1 HPSI to Hot leg 1 Verify, by visual inspection, the containment sump passive strainer assemblies are not restricted by debris, and the containment sump passive strainer assemblies and other containment sump entrance pathways show no evidence of structural distress or abnormal corrosion.

ECCS - Operating 3.5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.5.2-3 Amendment No. ~XXX

SURVEILLANCE REQUIREMENTS SR 3.5.4.1 SR 3.5.4.2 SR 3.5.4.3 SR 3.5.4.4 SURVEILLANCE Verify SIRWT borated water temperature is ~ 40°F and ~ 100°F.

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

Only required to be met in MODES 1, 2, and 3.

Verify SIRWT borated water volume is

~ 250,000 gallons.

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

Only required to be met in MODE 4.

Verify SIRWT borated water volume is

~ 200,000 gallons.

Verify SIRWT boron concentration is ~ 1720 ppm and ~ 2500 ppm.

SIRWT 3.5.4 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.5.4-2 Amendment No. 489, XXX

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.5 Containment Sump Buffering Agent and Weight Requirements STB 3.5.5 LCO 3.5.5 Buffer baskets shall contain ~ 8,186 Ibs and :510,553 Ibs of Sodium Tetraborate Decahydrate (STB) Na2B407. 10H20.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION A.

STB not within limits.

A.1 Restore STB to within limits.

B.

Required Action and B.1 Be in MODE 3.

associated Completion Time not met.

AND B.2 Be in MODE 4.

SURVEILLANCE REQUIREMENTS SR 3.5.5.1 SR 3.5.5.2 SURVEILLANCE Verify the STB baskets contain ~ 8,186 Ibs and

510,553 Ibs of equivalent weight sodium tetraborate decahydrate.

Verify that a sample from the STB baskets provides adequate pH adjustment of borated water.

COMPLETION TIME 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 6 hours 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.5.5-1 Amendment No. ~

XXX

SURVEILLANCE REQUIREMENTS SR 3.6.2.1 SR 3.6.2.2 SURVEILLANCE

N()TES---------------------------

1.

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

2.

Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.

Perform required air lock leakage rate testing in accordance with the Containment Leak Rate Testing Program.

Verify only one door in the air lock can be opened at a time.

Containment Air Locks 3.6.2 FREQUENCY In accordance with the Containment Leak Rate Testing Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.6.2-4 Amendment No. 494, XXX

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SR 3.6.3.1 SR 3.6.3.2 SR 3.6.3.3 SURVEILLANCE Verify each 8 inch purge valve and 12 inch air room supply valve is locked closed.

N()TE----------------------------

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

Verify each manual containment isolation valve and blind flange that is located outside containment and not locked, sealed, or otherwise secured in position, and is required to be closed during accident conditions, is closed, except for containment isolation valves that are open under administrative controls.

N () T E -----------------------------

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

Verify each manual containment isolation valve and blind flange that is located inside containment and not locked, sealed, or otherwise secured in position, and required to be closed during accident conditions, is closed, except for containment isolation valves that are open under administrative controls.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Prior to entering M()OE 4 from M()OE 5 if not performed within the previous 92 days Palisades Nuclear Plant 3.6.3-4 Amendment No. 489, XXX

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SR 3.6.3.4 SR 3.6.3.5 SR 3.6.3.6 SURVEILLANCE Verify the isolation time of each automatic power operated containment isolation valve is within limits.

Verify each containment 8 inch purge exhaust and 12 inch air room supply valve is closed by performance of a leakage rate test.

Verify each automatic containment isolation valve that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

FREQUENCY In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.6.3-5 Amendment No. ~,XXX

3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure Containment Pressure 3.6.4 LCO 3.6.4 Containment pressure shall be ~ 1.0 psig in MODES 1 and 2 and

~ 1.5 psig in MODES 3 and 4.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION A.

Containment pressure not A.1 Restore containment within limit.

pressure to within limit.

B.

Required Action and B.1 Be in MODE 3.

associated Completion Time not met.

AND B.2 Be in MODE 5.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.6.4.1 Verify containment pressure is within limit.

Palisades Nuclear Plant 3.6.4-1 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 6 hours 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 4-89, XXX

3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature Containment Air Temperature 3.6.5 LCO 3.6.5 Containment average air temperature shall be ~ 140°F.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

to within limit.

B.

Required Action and B.1 Be in MODE 3.

associated Completion Time not met.

AND B.2 Be in MODE 5.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.6.5.1 Verify containment average air temperature is within limit.

Palisades Nuclear Plant 3.6.5-1 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 4-89, XXX

Containment Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power In accordance with operated, and automatic valve in the flow path the Surveillance that is not locked, sealed, or otherwise secured in Frequency Control position is in the correct position.

Program SR 3.6.6.2 Operate each Containment Air Cooler Fan Unit for In accordance with

~ 15 minutes.

the Surveillance Frequency Control Program SR 3.6.6.3 Verify the containment spray piping is full of water In accordance with to the 735 ft elevation in the containment spray the Surveillance header.

Frequency Control Program SR 3.6.6.4 Verify total service water flow rate, when aligned In accordance with for accident conditions, is ~ 4800 gpm to the Surveillance Containment Air Coolers VHX-1, VHX-2, and Frequency Control VHX-3.

Program SR 3.6.6.5 Verify each containment spray pump's developed In accordance with head at the flow test point is greater than or equal the INSERVICE to the required developed head.

TESTING PROGRAM SR 3.6.6.6 Verify each automatic containment spray valve in In accordance with the flow path that is not locked, sealed, or the Surveillance otherwise secured in position, actuates to its Frequency Control correct position on an actual or simulated Program actuation signal.

Palisades Nuclear Plant 3.6.6-2 Amendment No. ~,XXX

Containment Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SR 3.6.6.7 SR 3.6.6.8 SR 3.6.6.9 SURVEILLANCE Verify each containment spray pump starts automatically on an actual or simulated actuation signal.

Verify each containment cooling fan starts automatically on an actual or simulated actuation signal.

Verify each spray nozzle is unobstructed.

Palisades Nuclear Plant 3.6.6-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Following maintenance which could result in nozzle blockage Amendment No. 2+1-, XXX

SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SURVEILLANCE Verify closure time of each MSIV is :s; 5 seconds on an actual or simulated actuation signal from each train under no flow conditions.

MSIVs 3.7.2 FREQUENCY In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.2-2 Amendment No. 489, XXX

MFRVs and MFRV Bypass Valves 3.7.3 SURVEILLANCE REQUIREMENTS SR 3.7.3.1 SURVEILLANCE Verify the closure time of each MFRV and MFRV bypass valve is :s; 22 seconds on a actual or simulated actuation signal.

Palisades Nuclear Plant 3.7.3-2 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 4$, XXX

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.4.1 Verify one complete cycle of each ADV.

Palisades Nuclear Plant 3.7.4-2 ADVs 3.7.4 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.7.5.1 SR 3.7.5.2 SR 3.7.5.3 SR 3.7.5.4 SURVEILLANCE Verify each required AFW manual, power operated, and automatic valve in each water flow path and in the steam supply flow path to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

N()TE--------------------------------

Not required to be met for the turbine driven AFW pump in M()OE 3 below 800 psig in the steam generators.

Verify the developed head of each required AFW pump at the flow test point is greater than or equal to the required developed head.

N () TE ----------------------------

()nly required to be met in M()OES 1, 2 or 3 when AFW is not in operation.

Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

N () T E ----------------------------

()nly required to be met in M()OES 1, 2, and 3.

Verify each required AFW pump starts automatically on an actual or simulated actuation signal.

AFWSystem 3.7.5 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PR()GRAM In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.5-3 Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS

. SR 3.7.6.1 SURVEILLANCE Verify condensate useable volume is

100,000 gallons.

Palisades Nuclear Plant 3.7.6-2 Condensate Storage and Supply 3.7.6 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.7.7.1 SR 3.7.7.2 SR 3.7.7.3 SURVEILLANCE

N()TE----------------------------

Isolation of CCW flow to individual components does not render the CCW System inoperable.

Verify each CCW manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

N () T E -----------------------------

()nly required to be met in M()OES 1, 2, and 3.

Verify each CCW automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

N () T E -----------------------------

()nly required to be met in M()OES 1, 2, and 3.

Verify each CCW pump starts automatically on an actual or simulated actuation signal in the "with standby power available" mode.

CCWSystem 3.7.7 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.7-2 Amendment No. 439, XXX

SURVEILLANCE REQUIREMENTS SR 3.7.8.1 SR 3.7.8.2 SR 3.7.8.3 SURVEILLANCE

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

Isolation of SWS flow to individual components does not render SWS inoperable.

Verify each SWS manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

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

Only required to be met in MODES 1, 2, and 3.

Verify each SWS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

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

Only required to be met in MODES 1, 2, and 3.

Verify each SWS pump starts automatically on an actual or simulated actuation signal in the "with standby power available" mode.

SWS 3.7.8 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.8-2 Amendment No. 489, XXX

3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION A.

UHS inoperable.

A.1 AND A.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE Be in MODE 3.

Be in MODE 5.

SR 3.7.9.1 Verify water level of UHS is ~ 568.25 ft above mean sea level.

SR 3.7.9.2 Verify water temperature of UHS is:::; 85°F.

Palisades Nuclear Plant 3.7.9-1 UHS 3.7.9 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SR 3.7.10.1 SR 3.7.10.2 SR 3.7.10.3 SR 3.7.10.4 SURVEILLANCE Operate each CRV Filtration train for

10 continuous hours with associated heater (VHX-26A or VHX-268) operating.

Perform required CRV Filtration filter testing in accordance with the Ventilation Filter Testing Program.

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

Only required to be met in MODES 1, 2, 3, and 4, and during movement of irradiated fuel assemblies in containment.

Verify each CRV Filtration train actuates on an actual or simulated actuation signal.

Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.

CRV Filtration 3.7.10 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Ventilation Filter Testing Program In accordance with the Surveillance Frequency Control Program In accordance with the Control Room Envelope Habitability Program Palisades Nuclear Plant 3.7.10-4 Amendment No. ~,XXX

CRVCooling 3.7.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

Two CRV Cooling trains E.1 Suspend CORE Immediately inoperable during CORE ALTERATIONS.

AL TERA TIONS, during movement of irradiated AND fuel assemblies, or movement of a fuel cask in E.2 Suspend movement of Immediately or over the SFP.

irradiated fuel assemblies.

AND E.3 Suspend movement of a Immediately fuel cask in or over the SFP.

SURVEILLANCE REQUIREMENTS SR 3.7.11.1 SURVEILLANCE FREQUENCY Verify each CRV Cooling train has the capability to In accordance with remove the assumed heat load.

the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.11-3 Amendment No. ~,XXX

Fuel Handling Area Ventilation System 3.7.12 SURVEILLANCE REQUIREMENTS SR 3.7.12.1 SR 3.7.12.2 SURVEILLANCE Perform required Fuel Handling Area Ventilation System filter testing in accordance with the Ventilation Filter Testing Program.

Verify the flow rate of the Fuel Handling Area Ventilation System, when aligned to the emergency filter bank, is ~ 5840 cfm and

8760 cfm.

Palisades Nuclear Plant 3.7.12-2 FREQUENCY In accordance with the Ventilation Filter Testing Program In accordance with the Surveillance Frequency Control Program Amendment No. ~, XXX

3.7 PLANT SYSTEMS 3.7.13 Engineered Safeguards Room Ventilation (ESRV) Dampers ESRV Dampers 3.7.13 LCO 3.7.13 Two ESRV Damper trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION A.

One or more ESRV A.1 Damper trains inoperable.

SURVEILLANCE REQUIREMENTS REQUIRED ACTION Initiate action to isolate associated ESRV Damper train(s).

SURVEILLANCE SR 3.7.13.1 Verify each ESRV Damper train closes on an actual or simulated actuation signal.

Palisades Nuclear Plant 3.7.13-1 COMPLETION TIME Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool (SFP) Water Level LCO 3.7.14 The SFP water level shall be ~ 647 ft elevation.

SFP Water Level 3.7.14

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

SFP level may be below the 647 ft elevation to support fuel cask movement, if the displacement of water by the fuel cask when submerged in the SFP, would raise SFP level to ~ 647 ft elevation.

APPLICABILITY:

During movement of irradiated fuel assemblies in the SFP, During movement of a fuel cask in or over the SFP.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION A.

SFP water level not within A.1 limit.

A.2 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Suspend movement of irradiated fuel assemblies in SFP.

Suspend movement of fuel cask in or over the SFP.

SURVEILLANCE SR 3.7.14.1 Verify the SFP water level is ~ 647 ft elevation.

Palisades Nuclear Plant 3.7.14-1 COMPLETION TIME Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool (SFP) Boron Concentration SFP Boron Concentration 3.7.15 LCO 3.7.15 The SFP boron concentration shall be ~ 1720 ppm.

APPLICABI LlTY:

When fuel assemblies are stored in the Spent Fuel Pool.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION A.

SFP boron concentration not within limit.

A.1 REQUIRED ACTION Suspend movement of fuel assemblies in the SFP.

COMPLETION TIME Immediately A.2 Initiate action to restore Immediately SFP boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.15.1 Verify the SFP boron concentration is within limit.

Palisades Nuclear Plant 3.7.15-1 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. ~,XXX

3.7 PLANT SYSTEMS 3.7.17 Secondary Specific Activity Secondary Specific Activity 3.7.17 LCO 3.7.17 The specific activity of the secondary coolant shall be :s; 0.10 jJCi/gm DOSE EQUIVALENT 1-131.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION A.

Specific activity not within A.1 limit.

SURVEILLANCE REQUIREMENTS AND A.2 SURVEILLANCE Be in MODE 3.

Be in MODE 5.

COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours FREQUENCY SR 3.7.17.1 Verify the specific activity of the secondary coolant is In accordance with within limit.

the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.17-1 Amendment No. 489, XXX

ACTIONS CONDITION REQUIRED ACTION F.

Required Action and F.1 Be in MODE 3.

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

F.2 Be in MODE 5.

G.

Three or more AC sources G.1 Enter LCO 3.0.3.

inoperable.

SURVEILLANCE REQUIREMENTS SR 3.8.1.1 SR 3.8.1.2 SURVEILLANCE Verify correct breaker alignment and voltage for each offsite circuit.

Verify each DG starts from standby conditions and achieves:

a.

In :s; 10 seconds, ready-to-Ioad status; and

b.

Steady state voltage;:: 2280 V and :s; 2520 V, and frequency;:: 59.5 Hz and :s; 61.2 Hz.

AC Sources - Operating 3.8.1 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.1-4 Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SR 3.8.1.3 SR 3.8.1.4 SR 3.8.1.5 SURVEILLANCE

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

1.

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

2.

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

3.

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

Verify each DG is synchronized and loaded, and operates for ~ 60 minutes:

a.

For ~ 15 minutes loaded to greater than or equal to peak accident load; and

b.

For the remainder of the test at a load

~ 2300 kW and s 2500 kW.

Verify each day tank contains ~ 2500 gallons of fuel oil.

Verify each DG rejects a load greater than or equal to its associated single largest post-accident load, and:

a.

Following load rejection, the frequency is s 68 Hz;

b.

Within 3 seconds following load rejection, the voltage is ~ 2280 V and s 2640 V; and

c.

Within 3 seconds following load rejection, the frequency is ~ 59.5 Hz and S 61.5 Hz.

AC Sources - Operating 3.8.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.1-5 Amendment No. 4-89, XXX

SURVEILLANCE REQUIREMENTS SR 3.8.1.6 SR 3.8.1.7 SURVEILLANCE Verify each DG, operating at a power factor s 0.9, does not trip, and voltage is maintained s 4000 V during and following a load rejection of ~ 2300 kW and s 2500 kW.

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

This Surveillance shall not be performed in MODE 1,2,3, or 4.

Verify on an actual or simulated loss of offsite power signal:

a.

De-energization of emergency buses;

b.

Load shedding from emergency buses;

c.

DG auto-starts from standby condition and:

1.

energizes permanently connected loads in s 10 seconds,

2.

energizes auto-connected shutdown loads through automatic load sequencer,

3.

maintains steady state voltage

~ 2280 V and s 2520 V,

4.

maintains steady state frequency

~ 59.5 Hz and S 61.2 Hz, and

5.

supplies permanently connected loads for ~ 5 minutes.

AC Sources - Operating 3.8.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.1-6 Amendment No. 439, XXX

SURVEILLANCE REQUIREMENTS SR 3.8.1.8 SR 3.8.1.9 SURVEILLANCE

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

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

Verify each DG, operating at a power factor:S 0.9, operates for ~ 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a.

For ~ 100 minutes loaded ~ its peak accident loading; and

b.

For the remaining hours of the test loaded

~ 2300 kW and :S 2500 kW.

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

This Surveillance shall not be performed in MODE 1, 2, 3, or4.

Verify each DG:

a.

Synchronizes with offsite power source while supplying its associated 2400 V bus upon a simulated restoration of offsite power;

b.

Transfers loads to offsite power source; and

c.

Returns to ready-to-Ioad operation.

AC Sources - Operating 3.8.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.1-7 Amendment No. 489, XXX

SURVEILLANCE REQUIREMENTS SR 3.8.1.10 SR 3.8.1.11 SURVEILLANCE

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

This Surveillance shall not be performed in MODE 1, 2,3, or4.

Verify the time of each sequenced load is within

+/- 0.3 seconds of design timing for each automatic load sequencer.

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

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated safety injection signal:

a.

De-energization of emergency buses;

b.

Load shedding from emergency buses;

c.

DG auto-starts from standby condition and:

1.

energizes permanently connected loads in s 10 seconds,

2.

energizes auto-connected emergency loads through its automatic load sequencer,

3.

achieves steady state voltage

~ 2280 V and s 2520 V,

4.

achieves steady state frequency

~ 59.5 Hz and S 61.2 Hz, and

5.

supplies permanently connected loads for ~ 5 minutes.

AC Sources - Operating 3.8.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.1-8 Amendment No. 489, XXX

Diesel Fuel, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify the fuel oil storage subsystem contains;?: a In accordance with 7 day supply of fuel.

the Surveillance Frequency Control Program SR 3.8.3.2 Verify stored lube oil inventory is;?: a 7 day supply.

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

Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure is In accordance with

?: 200 psig.

the Surveillance Frequency Control Program SR 3.8.3.5 Check for and remove excess accumulated water from In accordance with the fuel oil storage tank.

the Surveillance Frequency Control Program SR 3.8.3.6 Verify the fuel oil transfer system operates to transfer In accordance with fuel oil from the fuel oil storage tank to each DG day the Surveillance tank and engine mounted tank.

Frequency Control Program Palisades Nuclear Plant 3.8.3-3 Amendment No. 242, XXX

ACTIONS CONDITION REQUIRED ACTION C.

Required Action and associated Completion Time not met.

C.1 AND C.2 Be in MODE 3.

Be in MODE 5.

SURVEILLANCE REQUIREMENTS SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 SURVEILLANCE Verify battery terminal voltage is ~ 125 V on float charge.

Verify no visible corrosion at battery terminals and connectors.

Verify battery connection resistance is s 50 lJohm for inter-cell connections, S 360 lJohm for inter-rack connections, and S 360 lJohm for inter-tier connections.

Inspect battery cells, cell plates, and racks for visual indication of physical damage or abnormal deterioration that could degrade battery performance.

DC Sources - Operating 3.8.4 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.4-2 Amendment No. 4-89, XXX

SURVEILLANCE REQUIREMENTS SR 3.8.4.4 SR 3.8.4.5 SR 3.8.4.6 SR 3.8.4.7 SURVEILLANCE Remove visible terminal corrosion and verify battery cell to cell and terminal connections are coated with anti-corrosion material.

Verify battery connection resistance is

s; 50 I-Iohm for inter-cell connections, :s; 360 I-Iohm for inter-rack connections, and :s; 360 I-Iohm for inter-tier connections.

Verify each required battery charger supplies

~ 180 amps at ~ 125 V for ~ 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

NOTE S---------------------------

1.

The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7.

2.

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

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

DC Sources - Operating 3.8.4 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.4-3 Amendment No. 4-89, XXX

SURVEILLANCE REQUIREMENTS SURVEILLANCE DC Sources - Operating 3.8.4 FREQUENCY SR 3.8.4.8

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

This Surveillance shall not be performed in MODE 1, 2,3, or4.

Verify battery capacity is ;;:; 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.

Palisades Nuclear Plant 3.8.4-4 In accordance with the Surveillance Frequency Control Program 12 months when battery shows degradation or has reached 85% of the expected life with capacity < 100% of manufacturer's rating 24 months when battery has reached 85% of the expected life with capacity

100% of manufacturer's rating Amendment No. 489, XXX

ACTIONS CONDITION B.

Required Action and associated Completion Time of Condition A not met.

One or more batteries with average electrolyte temperature of the representative cells

< 70aF.

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

B.1 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Declare associated battery inoperable.

SURVEILLANCE SR 3.8.6.1 SR 3.8.6.2 Verify battery cell parameters meet Table 3.8.6-1 Category A limits.

Verify average electrolyte temperature of representative cells is ~ 70aF.

Palisades Nuclear Plant 3.8.6-2 Battery Cell Parameters 3.8.6 COMPLETION TIME Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 4-89, XXX

SURVEILLANCE REQUIREMENTS SR 3.8.6.3 SURVEILLANCE Verify battery cell parameters meet Table 3.8.6-1 Category B limits.

Palisades Nuclear Plant 3.8.6-3 Battery Cell Parameters 3.8.6 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No..:1-89, XXX

PARAMETER Electrolyte Level Float Voltage Specific Gravity(b)(c)

Table 3.8.6-1 (page 1 of 1)

Battery Surveillance Requirements CATEGORY A:

CATEGORY B:

NORMAL LIMITS NORMAL LIMITS FOR EACH FOR EACH DESIGNATED CONNECTED PILOT CELL CELL

> Minimum level

> Minimum level indication mark, and indication mark, and

s; % inch above

s; % inch above maximum level maximum level indication mark(a) indication mark(a)

~ 2.13 V

~ 1.205

~ 1.200 AND Average of connected cells

~ 1.205 Battery Cell Parameters

3.8.6 CATEGORYC

ALLOWABLE LIMITS FOR EACH CONNECTED CELL Above top of plates, and not overflowing

> 2.07 V Not more than 0.020 below average connected cells AND Average of all connected cells

~ 1.195 (a)

It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overflowing.

(b)

Corrected for electrolyte temperature and level. Level correction is not required, however, when battery charging is < 2 amps when on float charge.

(c)

A battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits.

Palisades Nuclear Plant 3.8.6-4 Amendment No. 189

3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters - Operating LCO 3.8.7 Four inverters shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION A.

One inverter inoperable.

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

Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems -

Inverters - Operating 3.8.7 COMPLETION TIME Operating" with any Preferred AC bus de-energized.

A.1 Restore inverter to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

associated Completion Time not met.

AND B.2 Be in MODE 5.

SURVEILLANCE REQUIREMENTS SR 3.8.7.1 SURVEILLANCE Verify correct inverter voltage, frequency, and alignment to Preferred AC buses.

Palisades Nuclear Plant 3.8.7-1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 6 hours 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 4-89, XXX

SURVEILLANCE REQUIREMENTS SR 3.8.8.1 SURVEILLANCE Verify correct inverter voltage, frequency, and alignment to required Preferred AC buses.

Palisades Nuclear Plant 3.8.8-2 Inverters - Shutdown 3.8.8 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 48S, XXX

Distribution Systems - Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION D.

Required Action and D.1 Be in MODE 3.

associated Completion Time not met.

AND D.2 Be in MODE 5.

E.

Two or more inoperable E.1 Enter LCO 3.0.3.

distribution subsystems that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.9.1 Verify correct breaker alignments and voltage to required AC, DC, and Preferred AC bus electrical power distribution subsystems.

Palisades Nuclear Plant 3.8.9-2 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

ACTIONS Distribution Systems - Shutdown 3.8.10 CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.4 Initiate actions to restore Immediately required AC, DC, and Preferred AC bus electrical power distribution subsystems to OPERABLE status.

A.2.S Declare associated Immediately required shutdown cooling train inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SR 3.8.10.1 SURVEILLANCE Verify correct breaker alignments and voltage to required AC, DC, and Preferred AC bus electrical power distribution subsystems.

Palisades Nuclear Plant 3.8.10-2 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration Boron Concentration 3.9.1 LCO 3.9.1 Boron concentrations of the Primary Coolant System and the refueling cavity shall be maintained at the REFUELING BORON CONCENTRATION.

APPLICABI LlTY:

MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Boron concentration not A.1 Suspend CORE Immediately within limit.

AL TERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.9.1.1 Verify boron concentration is at the REFUELING BORON CONCENTRATION.

Palisades Nuclear Plant 3.9.1-1 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. ~,XXX

SURVEILLANCE REQUIREMENTS SR 3.9.2.1 SR 3.9.2.2 SURVEILLANCE Perform CHANNEL CHECK.

N()TE------------------------------

Neutron detectors are excluded from the CHANNEL CALIBRATI()N.

Perform CHANNEL CALIBRATI()N.

Nuclear Instrumentation 3.9.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.9.2-2 Amendment No. 489, XXX

ACTIONS CONDITION A.

One or more containment penetrations not in required status.

A.1 A.2 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Suspend CORE AL TERATIONS.

Suspend movement of irradiated fuel assemblies within containment.

SURVEILLANCE SR 3.9.3.1 Verify each required to be met containment penetration is in the required status.

Containment Penetrations 3.9.3 COMPLETION TIME Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.9.3.2

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

Only required to be met for unisolated containment penetrations.

Verify each required automatic isolation valve closes on an actual or simulated Refueling Containment High Radiation signal.

In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.9.3-2 Amendment No. 4$, XXX

ACTIONS SDC and Coolant Circulation - High Water Level 3.9.4 CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.3 A.4 Suspend loading irradiated fuel assemblies in the core.

Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SR 3.9.4.1 SURVEILLANCE Verify one SDC train is in operation and circulating primary coolant at a flow rate of ~ 1000 gpm.

Immediately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months FREQUENCY In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.9.4-2 Amendment No. 489, XXX

SDC and Coolant Circulation - Low Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

No SDC train OPERABLE B.1 Suspend operations Immediately or in operation.

involving a reduction in primary coolant boron concentration.

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

AND B.3 Initiate action to close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SR 3.9.5.1 SR 3.9.5.2 SURVEILLANCE Verify one SDC train is in operation and circulating primary coolant at a flow rate of

~ 1000 gpm.

Verify correct breaker alignment and indicated power available to the required SDC pump that is not in operation.

Palisades Nuclear Plant 3.9.5-2 Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

Refueling Cavity Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Cavity Water Level LCO 3.9.6 The refueling cavity water level shall be maintained ~ 647 ft elevation.

APPLICABILITY:

During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION A.

Refueling cavity water level not within limit.

A.1 A.2 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Suspend CORE AL TERATIONS.

Suspend movement of irradiated fuel assemblies within containment.

SURVEILLANCE SR 3.9.6.1 Verify refueling cavity water level is ~ 647 ft elevation.

Palisades Nuclear Plant 3.9.6-1 COMPLETION TIME Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 489, XXX

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a.

The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b.

Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c.

The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

Palisades Nuclear Plant 5.0-23 Amendment No. ~,XXX

ML18270A325

Text

3.8.6 CATEGORYC

Navigation menu

Search