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

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

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

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

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

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

APPLICABILITY: MODE 3, 4, and 5.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limits. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.1-1 Amendment No. 489, XXX

Reactivity Balance 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ------------------------------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 Prior to entering

+/- 1% ~p of predicted values. 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

Control Rod Alignment 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify the position of each control rod to be within In accordance with 8 inches of all other control rods in its group. the Surveillance Frequency Control Program SR 3.1.4.2 Perform a CHANNEL CHECK of the control rod In accordance with position indication channels. the Surveillance Frequency Control Program SR 3.1.4.3 ------------------------------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 In accordance with each individual full-length control rod that is not fully the Surveillance inserted into the reactor core ~ 6 inches in either Frequency Control direction. Program SR 3.1.4.4 Verify the rod position deviation alarm is In accordance with OPERABLE. the Surveillance Frequency Control Program SR 3.1.4.5 Perform a CHANNEL CALIBRATION of the control In accordance with rod position indication channels. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.4-3 Amendment No. ~, XXX

Control Rod Alignment 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.6 Verify each full-length control rod drop time is Prior to reactor

~ 2.5 seconds. criticality, after each reinstallation of the reactor head Palisades Nuclear Plant 3.1.4-4 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 COMPLETION TIME A. One or more shutdown or A.1 Declare affected control Immediately 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. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown and part-length rod group is In accordance with withdrawn?: 128 inches. 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 COMPLETION TIME B. Regulating rod groups not B.1 Restore regulating rod 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 Once within circuit inoperable. (group position 15 minutes following verification) . any rod motion D. Required Action and 0.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify each regulating rod group is within its In accordance with withdrawal sequence, overlap, and insertion limits. the Surveillance Frequency Control Program SR 3.1.6.2 Verify POlL alarm circuit is OPERABLE. In accordance with the Surveillance Frequency Control Program SR 3.1.6.3 Verify CROOS alarm circuit is OPERABLE. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.6-2 Amendment No. 48Q, XXX

Special Test Exceptions (STE) 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Suspend PHYSICS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion TESTS.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify THERMAL POWER is ~ 2% RTP. In accordance with the Surveillance Frequency Control Program SR 3.1.7.2 Verify Tave is ~ 500°F. In accordance with the Surveillance Frequency Control Program SR 3.1.7.3 Verify ~ 1% shutdown reactivity is available for trip In accordance with insertion. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.1.7-2 Amendment No. 89, XXX

LHR 3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Incore Alarm and Excore B.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Monitoring Systems POWER to ~ 85% RTP.

inoperable for monitoring LHR. AND B.2 Verify LHR is within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits using manual incore readings. AND Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thereafter C. Required Action and C.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to ~ 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 -------------------------------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 In accordance with COLR. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.1-2 Amendment No. 489, XXX

LHR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 ------------------------------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 Prior to operation measured power distribution. > 50% RTP after each fuel loading In accordance with the Surveillance Frequency Control Program SR 3.2.1.3 -------------------------------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 Prior to each initial target ASI for last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . use of Excore Monitoring System to monitor LHR SR 3.2.1.4 -------------------------------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. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.1-3 Amendment No. 489, XXX

LHR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.5 -------------------------------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. In accordance with the Surveillance Frequency Control Program SR 3.2.1.6 -------------------------------NOTE ---------------------------

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

Verify Tq ::; 0.03. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.1-4 Amendment No. 489, XXX

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

LCO 3.2.2 FRT shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER> 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. FRT not within limits A.1 Restore FRT to within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months specified in the 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 FREQUENCY SR 3.2.2.1 Verify FRT is within limits specified in the COLR. 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

Tq 3.2.3 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 COMPLETION TIME A. Tq> 0.05. A.1 Verify FRT is within the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits of LCO 3.2.2, "TOTAL RADIAL AND PEAKING FACTOR ".

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter B. Tq>0.10. B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 50% RTP.

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

Time not met.

OR Tq> 0.15.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify Tq is ~ 0.05. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.3-1 Amendment No. ~,XXX

ASI 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 AXIAL SHAPE INDEX (ASI)

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 FREQUENCY SR 3.2.4.1 Verify ASI is within limits specified in the COLR. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.2.4-1 Amendment No. +89, XXX

RPS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR G.2.1 Verify no more than one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months full-length control rod is Control room ambient air capable of being temperature> gO°F. withdrawn.

OR G.2.2 Verify PCS boron 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months concentration is at REFUELING BORON CONCENTRATION.

SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform a CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2 Verify control room temperature is s; gO°F. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.1-3 Amendment No. 489, XXX

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.3 -----------------------------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 In accordance with the power range excore and AT power channels to the Surveillance agree with calorimetric calculation if the absolute Frequency Control difference is ~ 1.5%. Program SR 3.3.1.4 -----------------------------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 In accordance with the incore detectors. the Surveillance Frequency Control Program SR 3.3.1.5 Perform a CHANNEL FUNCTIONAL TEST and In accordance with verify the Thermal Margin Monitor Constants. the Surveillance Frequency Control Program SR 3.3.1.6 Perform a calibration check of the power range In accordance with excore channels with a test signal. the Surveillance Frequency Control Program SR 3.3.1.7 Perform a CHANNEL FUNCTIONAL TEST of High Once within 7 days Startup Rate and Loss of Load Functions. prior to each reactor startup Palisades Nuclear Plant 3.3.1-4 Amendment No. ~,XXX

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.8 -----------------------------NOT E-----------------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

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

RPS Logic and Trip Initiation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND 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 full-length control rod is One or more Functions capable of being with two or more Manual withdrawn.

Trip, Matrix Logic or Trip Initiation Logic channels OR inoperable for reasons other than Condition D.

E.2.2 Verify PCS boron 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months concentration is at REFUELING BORON CONCENTRATION.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform a CHANNEL FUNCTIONAL TEST on In accordance with each RPS Matrix Logic channel and each RPS the Surveillance Trip Initiation Logic channel. Frequency Control Program SR 3.3.2.2 Perform a CHANNEL FUNCTIONAL TEST on Once within 7 days each RPS Manual Trip channel. prior to each reactor startup Palisades Nuclear Plant 3.3.2-2 Amendment No. ~,XXX

ESF Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform a CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.3.2 Perform a CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.3.3 Perform a CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.3-3 Amendment No. 489, XXX

ESF Logic and Manual Initiation 3.3.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions with C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months two Manual Initiation, or Actuation Logic channels inoperable for Functions 5 or 6. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and associated Completion Time of Condition A not met for Functions 5 or 6.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform functional test of each SIS actuation In accordance with channel normal and standby power functions. the Surveillance Frequency Control Program SR 3.3.4.2 Perform a CHANNEL FUNCTIONAL TEST of each In accordance with AFAS actuation logic channel. the Surveillance Frequency Control Program SR 3.3.4.3 Perform a CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.4-2 Amendment No. 489, XXX

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

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform a CHANNEL FUNCTIONAL TEST on In accordance with each DG-UV start logic channel. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.5-1 Amendment No. 489, XXX

DG - UV Start 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.2 Perform CHANNEL CALIBRATION on each Loss In accordance with of Voltage and Degraded Voltage channel with the Surveillance setpoints as follows: Frequency Control Program

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 Amendment No. ~,XXX

Refueling CHR Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform a CHANNEL CHECK of each refueling In accordance with CHR monitor channel. the Surveillance Frequency Control Program SR 3.3.6.2 Perform a CHANNEL FUNCTIONAL TEST of each In accordance with refueling CHR monitor channel. the Surveillance Frequency Control Program SR 3.3.6.3 Perform a CHANNEL FUNCTIONAL TEST of each In accordance with CHR Manual Initiation channel. the Surveillance Frequency Control Program SR 3.3.6.4 Perform a CHANNEL CALIBRATION of each In accordance with refueling CHR monitor channel. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.6-2 Amendment No. 489, XXX

PAM Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK for each required In accordance with instrumentation channel that is normally energized. the Surveillance Frequency Control Program SR 3.3.7.2 -----------------------------NOT E------------------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

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

Alternate Shutdown System 3.3.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL FUNCTIONAL TEST of the Once within 7 days Source Range Neutron Flux Function. prior to each reactor startup SR 3.3.8.2 Verify each required control circuit and transfer In accordance with switch is capable of performing the intended the Surveillance function. 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 In accordance with required instrumentation channel. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.3.8-2 Amendment No. 4W, XXX

Neutron Flux Monitoring Channels 3.3.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.9.2 -----------------------------NOT E------------------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

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

ESRV Instrumentation 3.3.10 3.3 INSTRUMENTATION 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 COMPLETION TIME A. One or more channels A.1 Initiate action to isolate Immediately inoperable. the associated ESRV System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.10.1 Perform a CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.10.3 Perform a CHANNEL CALIBRATION. In accordance with the Surveillance Verify high radiation setpoint on each ESRV Frequency Control Instrumentation radiation monitoring channel is Program s 2.2E+5 cpm.

Palisades Nuclear Plant 3.3.10-1 Amendment No. 489, XXX

PCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure within the limits In accordance with specified in the COLR. the Surveillance Frequency Control Program SR 3.4.1.2 Verify PCS cold leg temperature within the limit In accordance with specified in the COLR. the Surveillance Frequency Control Program SR 3.4.1.3 ------------------------------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 accordance with in the COLR. 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 REQUIRED ACTION COMPLETION TIME A. Tave in one or more PCS A.1 Be in MODE 2 with Keff 30 minutes loops not within limit. < 1.0.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify PCS Tave in each loop ~ 525°F. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.2-1 Amendment No. 489, XXX

PCS PIT Limits 3.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. --------------NOTE------------- C.1 Initiate action to restore Immediately 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 Prior to entering met any time in other than acceptable for continued MODE4 MODE 1, 2, 3, or 4. operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 -------------------------------NOTE---------------------------

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

Verify PCS pressure, PCS temperature, and PCS In accordance with heatup and cooldown rates are within the limits of the Surveillance Figure 3.4.3-1 and Figure 3.4.3-2. Frequency Control Program Palisades Nuclear Plant 3.4.3-2 Amendment No. 489, XXX

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

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCO not A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each PCS loop is in operation. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.4-1 Amendment No. 89, XXX

PCS Loops - MODE 3 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 4. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition A not met.

C. No PCS loop OPERABLE. C.1 Suspend all operations Immediately involving a reduction of OR PCS boron concentration.

No PCS loop in operation.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required PCS loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.5.2 Verify secondary side water level in each steam In accordance with generator ~ -84%. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.5-2 Amendment No. 489, XXX

PCS Loops - MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.3 Verify correct breaker alignment and indicated In accordance with power available to the required primary coolant the Surveillance pump that is not in operation. Frequency Control Program Palisades Nuclear Plant 3.4.5-3 Amendment No. 4-89, XXX

PCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one SDC train is in operation with;?: 2810 gpm In accordance with flow through the reactor core, or one PCS loop is in the Surveillance operation. Frequency Control Program SR 3.4.6.2 Verify secondary side water level in required SG(s) is In accordance with

?: -84%. the Surveillance Frequency Control Program SR 3.4.6.3 Verify correct breaker alignment and indicated power In accordance with available to the required pump that is not in the Surveillance operation. 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 SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one SOC train is in operation with;;::: 2810 gpm In accordance with flow through the reactor core. the Surveillance Frequency Control Program SR 3.4.7.2 Verify required SG secondary side water level is In accordance with

-84%. the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and indicated power In accordance with available to the required SOC pump that is not in the Surveillance operation. 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 COMPLETION TIME A. One SDC train inoperable. A.1 Initiate action to restore Immediately SDC train to OPERABLE status.

B. Two SDC trains B.1 Suspend all operations Immediately inoperable. involving reduction of PCS boron OR concentration.

SDC flow through the AND reactor core not within limits. B.2 Initiate action to restore Immediately one SDC train to OPERABLE status and operation with SDC flow through the reactor core within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 -------------------------------NOTE ---------------------------

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

Verify one SDC train is in operation with In accordance with

~ 2810 gpm flow through the reactor core. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.8-2 Amendment No. 489-, XXX

PCS Loops - MODE 5, Loops Not Filled 3.4.8 SURVEILLANCE FREQUENCY SR 3.4.8.2 -------------------------------NOT E---------------------------

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

Verify one SDC train is in operation with In accordance with

~ 650 gpm flow through the reactor core. the Surveillance Frequency Control Program SR 3.4.8.3 --------------------------------NOT E--------------------------

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

Verify two of three charging pumps are incapable In accordance with of reducing the boron concentration in the PCS the Surveillance below the minimum value necessary to maintain Frequency Control the required SHUTDOWN MARGIN. Program SR 3.4.8.4 Verify correct breaker alignment and indicated In accordance with power available to the SDC pump that is not in the Surveillance operation. Frequency Control Program Palisades Nuclear Plant 3.4.8-3 Amendment No. 489, XXX

Pressurizer 3.4.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B or C AND not met.

D.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -------------------------------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%. In accordance with the Surveillance Frequency Control Program SR 3.4.9.2 Verify the capacity of pressurizer heaters from In accordance with electrical bus 1D, and electrical bus 1E is the Surveillance

375 kW. Frequency Control Program SR 3.4.9.3 Verify the required pressurizer heater capacity In accordance with from electrical bus 1E is capable of being powered the Surveillance from an emergency power supply. Frequency Control Program Palisades Nuclear Plant 3.4.9-3 Amendment No. ~,XXX

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 Perform a complete cycle of each block valve. Once prior to entering MODE 4 from MODE 5 if not performed within previous 92 days SR 3.4.11.2 Perform a complete cycle of each PORV with PCS In accordance with average temperature> 200°F. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.11-3 Amendment No. 4-S9, XXX

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 -------------------------------NOTE-------------------------

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

Verify both HPSI pumps are incapable of injecting In accordance with into the PCS. the Surveillance Frequency Control Program SR 3.4.12.2 Verify required PCS vent, capable of relieving In accordance with

167 gpm at a PCS pressure of 315 psia, is open. the Surveillance Frequency Control Program SR 3.4.12.3 Verify PORV block valve is open for each required In accordance with PORV. the Surveillance Frequency Control Program SR 3.4.12.4 -------------------------------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.

Perform CHANNEL FUNCTIONAL TEST on each In accordance with required PORV, excluding actuation. the Surveillance Frequency Control Program SR 3.4.12.5 Perform CHANNEL CALIBRATION on each In accordance with required PORV actuation channel. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.12-3 Amendment No. 489, XXX

PCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 -------------------------------NOTES------------------------- ----------NOTE--------

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

2. Not applicable to primary to secondary operation LEAKAGE.

Verify PCS operational LEAKAGE is within limits In accordance with by performance of PCS water inventory balance. the Surveillance Frequency Control Program SR 3.4.13.2 ------------------------------- NOTE ---------------------------

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

Verify primary to secondary LEAKAGE is ~ 150 In accordance with gallons per day through anyone SG. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.13-2 Amendment No. ~,XXX

PCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -------------------------------NOT ES--------------------------

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 In accordance with

~ 5 gpm at a PCS pressure of 2060 psia. 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 SR 3.4.14.2 Verify each SDC suction valve interlock prevents its In accordance with associated valve from being opened with a the Surveillance simulated or actual PCS pressure signal ~ 280 psia. 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 COMPLETION TIME C. All required channels C.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required In accordance with containment sump level indicator. the Surveillance Frequency Control Program SR 3.4.15.2 Perform CHANNEL CHECK of the required In accordance with containment atmosphere gaseous activity monitor. the Surveillance Frequency Control Program SR 3.4.15.3 Perform CHANNEL CHECK of the required In accordance with containment atmosphere humidity monitor. the Surveillance Frequency Control Program SR 3.4.15.4 Perform CHANNEL FUNCTIONAL TEST of the In accordance with required containment air cooler condensate level the Surveillance switch. Frequency Control Program SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required In accordance with containment sump level indicator. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.15-2 Amendment No. 489, XXX

PCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.6 Perform CHANNEL CALIBRATION of the required In accordance with containment atmosphere gaseous activity monitor. the Surveillance Frequency Control Program SR 3.4.15.7 Perform CHANNEL CALIBRATION of the required In accordance with containment atmosphere humidity monitor. the Surveillance Frequency Control

_Program Palisades Nuclear Plant 3.4.15-3 Amendment No. 489, XXX

PCS Specific Activity 3.4.16 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tave < 500°F.

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 SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify primary coolant gross specific activity In accordance with

1ODIE IJCilgm. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.4.16-2 Amendment No. 4$9, XXX

PCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.2 -------------------------------NOT E---------------------------

Only required to be performed in MODE 1.

In accordance with Verify primary coolant DOSE EQUIVALENT 1-131 the Surveillance specific activity ~ 1.0 IJCi/gm. 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 SR 3.4.16.3 -------------------------------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 In accordance with a minimum of 2 EFPD and 20 days of MODE 1 the Surveillance operation have elapsed since the reactor was last Frequency Control subcritical for;::: 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . Program Palisades Nuclear Plant 3.4.16-3 Amendment No. ~,XXX

SITs 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each SIT isolation valve is fully open. In accordance with the Surveillance Frequency Control Program SR 3.5.1.2 Verify borated water volume in each SIT is In accordance with

1040 fe and

::;; 1176 fe. the Surveillance Frequency Control Program SR 3.5.1.3 Verify nitrogen cover pressure in each SIT is In accordance with

200 psig. the Surveillance Frequency Control Program SR 3.5.1.4 Verify boron concentration in each SIT is In accordance with

1720 ppm and

::;; 2500 ppm. the Surveillance Frequency Control Program SR 3.5.1.5 Verify power is removed from each SIT isolation In accordance with valve operator. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.5.1-2 Amendment No. 489, XXX

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves and hand switches are In accordance with in the open position. the Surveillance Frequency Control Valve/Hand Program Switch Number Function CV-3027 SIRWT Recirc Valve HS-3027A Hand Switch For CV-3027 HS-30278 Hand Switch For CV-3027 CV-3056 SIRWT Recirc Valve HS-3056A Hand Switch For CV-3056 HS-30568 Hand Switch For CV-3056 SR 3.5.2.2 Verify each ECCS manual, power operated, and In accordance with automatic valve in the flow path, that is not locked, the Surveillance sealed, or otherwise secured in position, is in the Frequency Control correct position. Program SR 3.5.2.3 Verify CV-3006, "SOC Flow Control Valve," is open In accordance with and its air supply is isolated. the Surveillance Frequency Control Program SR 3.5.2.4 Verify each ECCS pump's developed head at the In accordance with test flow point is greater than or equal to the the INSERVICE required developed head. TESTING PROGRAM SR 3.5.2.5 Verify each ECCS automatic valve that is not In accordance with locked, sealed, or otherwise secured in position, in the Surveillance the flow path actuates to the correct position on an Frequency Control actual or simulated actuation signal. Program Palisades Nuciear Plant 3.5.2-2 Amendment No. ~,XXX

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.6 Verify each ECCS pump starts automatically on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program SR 3.5.2.7 Verify each LPSI pump stops on an actual or In accordance with simulated actuation signal. the Surveillance Frequency Control Program SR 3.5.2.8 Verify, for each ECCS throttle valve listed below, In accordance with each position stop is in the correct position. the Surveillance Frequency Control Valve Number Function Program MO-3008 LPSI to Cold leg 1A MO-3010 LPSI to Cold leg 18 MO-3012 LPSI to Cold leg 2A MO-3014 LPSI to Cold leg 28 MO-3082 HPSI to Hot leg 1 MO-3083 HPSI to Hot leg 1 SR 3.5.2.9 Verify, by visual inspection, the containment sump In accordance with passive strainer assemblies are not restricted by the Surveillance debris, and the containment sump passive strainer Frequency Control assemblies and other containment sump entrance Program pathways show no evidence of structural distress or abnormal corrosion.

Palisades Nuclear Plant 3.5.2-3 Amendment No. ~XXX

SIRWT 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Verify SIRWT borated water temperature is ~ 40°F In accordance with and ~ 100°F. the Surveillance Frequency Control Program SR 3.5.4.2 --------------------------------NOT E--------------------------

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

Verify SIRWT borated water volume is In accordance with

~ 250,000 gallons. the Surveillance Frequency Control Program SR 3.5.4.3 --------------------------------NOT E--------------------------

Only required to be met in MODE 4.

Verify SIRWT borated water volume is In accordance with

~ 200,000 gallons. the Surveillance Frequency Control Program SR 3.5.4.4 Verify SIRWT boron concentration is ~ 1720 ppm In accordance with and ~ 2500 ppm. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.5.4-2 Amendment No. 489, XXX

STB 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.5 Containment Sump Buffering Agent and Weight Requirements 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 COMPLETION CONDITION REQUIRED ACTION TIME A. STB not within limits. A.1 Restore STB to within limits. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.5.1 Verify the STB baskets contain ~ 8,186 Ibs and In accordance with

510,553 Ibs of equivalent weight sodium tetraborate the Surveillance decahydrate. Frequency Control Program SR 3.5.5.2 Verify that a sample from the STB baskets provides In accordance with adequate pH adjustment of borated water. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.5.5-1 Amendment No. ~ XXX

Containment Air Locks 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 ----------------------------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.

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

SR 3.6.2.2 Verify only one door in the air lock can be opened In accordance with at a time. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.6.2-4 Amendment No. 494, XXX

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 8 inch purge valve and 12 inch air In accordance with room supply valve is locked closed. the Surveillance Frequency Control Program SR 3.6.3.2 -----------------------------N()TE----------------------------

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

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

SR 3.6.3.3 ----------------------------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 Prior to entering and blind flange that is located inside containment M()OE 4 from and not locked, sealed, or otherwise secured in M()OE 5 if not position, and required to be closed during performed within the accident conditions, is closed, except for previous 92 days containment isolation valves that are open under administrative controls.

Palisades Nuclear Plant 3.6.3-4 Amendment No. 489, XXX

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.4 Verify the isolation time of each automatic power In accordance with operated containment isolation valve is within the INSERVICE limits. TESTING PROGRAM SR 3.6.3.5 Verify each containment 8 inch purge exhaust and In accordance with 12 inch air room supply valve is closed by the Surveillance performance of a leakage rate test. Frequency Control Program SR 3.6.3.6 Verify each automatic containment isolation valve In accordance with that is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the isolation position on an Frequency Control actual or simulated actuation signal. Program Palisades Nuclear Plant 3.6.3-5 Amendment No. ~,XXX

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure 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 COMPLETION TIME A. Containment pressure not A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within limit. pressure to within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limit. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.6.4-1 Amendment No. 4-89, XXX

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be ~ 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. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature is In accordance with within limit. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.6.5-1 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 SURVEILLANCE FREQUENCY SR 3.6.6.7 Verify each containment spray pump starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.6.6.8 Verify each containment cooling fan starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.6.6.9 Verify each spray nozzle is unobstructed. Following maintenance which could result in nozzle blockage Palisades Nuclear Plant 3.6.6-3 Amendment No. 2+1-, XXX

MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify closure time of each MSIV is :s; 5 seconds on In accordance with an actual or simulated actuation signal from each the Surveillance train under no flow conditions. Frequency Control Program Palisades Nuclear Plant 3.7.2-2 Amendment No. 489, XXX

MFRVs and MFRV Bypass Valves 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each MFRV and MFRV In accordance with bypass valve is :s; 22 seconds on a actual or the Surveillance simulated actuation signal. Frequency Control Program Palisades Nuclear Plant 3.7.3-2 Amendment No. 4$, XXX

ADVs 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ADV. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.4-2 Amendment No. 489, XXX

AFWSystem 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each required AFW manual, power In accordance with operated, and automatic valve in each water flow the Surveillance path and in the steam supply flow path to the Frequency Control steam turbine driven pump, that is not locked, Program sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 ------------------------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 In accordance with pump at the flow test point is greater than or equal the INSERVICE to the required developed head. TESTING PR()GRAM SR 3.7.5.3 ----------------------------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 In accordance with locked, sealed, or otherwise secured in position, the Surveillance actuates to the correct position on an actual or Frequency Control simulated actuation signal. Program SR 3.7.5.4 ------------------------------N() T E----------------------------

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

Verify each required AFW pump starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program Palisades Nuclear Plant 3.7.5-3 Amendment No. ~,XXX

Condensate Storage and Supply 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

. SR 3.7.6.1 Verify condensate useable volume is In accordance with

100,000 gallons. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.6-2 Amendment No. 489, XXX

CCWSystem 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 ------------------------------N()TE----------------------------

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

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

SR 3.7.7.2 -----------------------------N() TE-----------------------------

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

Verify each CCW automatic valve in the flow path In accordance with that is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the correct position on an Frequency Control actual or simulated actuation signal. Program SR 3.7.7.3 -----------------------------N() T E-----------------------------

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

Verify each CCW pump starts automatically on an In accordance with actual or simulated actuation signal in the "with the Surveillance standby power available" mode. Frequency Control Program Palisades Nuclear Plant 3.7.7-2 Amendment No. 439, XXX

SWS 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 -----------------------------NOTE -----------------------------

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

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

SR 3.7.8.2 ----------------------------NOTE------------------------------

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

Verify each SWS automatic valve in the flow path In accordance with that is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the correct position on an Frequency Control actual or simulated actuation signal. Program SR 3.7.8.3 -----------------------------NOT E-----------------------------

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

Verify each SWS pump starts automatically on an In accordance with actual or simulated actuation signal in the "with the Surveillance standby power available" mode. Frequency Control Program Palisades Nuclear Plant 3.7.8-2 Amendment No. 489, XXX

UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS inoperable. A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is ~ 568.25 ft above In accordance with mean sea level. the Surveillance Frequency Control Program SR 3.7.9.2 Verify water temperature of UHS is:::; 85°F. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.9-1 Amendment No. ~,XXX

CRV Filtration 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRV Filtration train for In accordance with

10 continuous hours with associated heater the Surveillance (VHX-26A or VHX-268) operating. Frequency Control Program SR 3.7.10.2 Perform required CRV Filtration filter testing in In accordance with accordance with the Ventilation Filter Testing the Ventilation Filter Program. Testing Program SR 3.7.10.3 -----------------------------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 In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program SR 3.7.10.4 Perform required CRE unfiltered air inleakage In accordance with testing in accordance with the Control Room the Control Room Envelope Habitability Program. 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 TERATIONS, 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 SURVEILLANCE FREQUENCY SR 3.7.11.1 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 SURVEILLANCE FREQUENCY SR 3.7.12.1 Perform required Fuel Handling Area Ventilation In accordance with System filter testing in accordance with the the Ventilation Filter Ventilation Filter Testing Program. Testing Program SR 3.7.12.2 Verify the flow rate of the Fuel Handling Area In accordance with Ventilation System, when aligned to the the Surveillance emergency filter bank, is ~ 5840 cfm and Frequency Control

8760 cfm. Program Palisades Nuclear Plant 3.7.12-2 Amendment No. ~, XXX

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

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more ESRV A.1 Initiate action to isolate Immediately Damper trains inoperable. associated ESRV Damper train(s).

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify each ESRV Damper train closes on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.13-1 Amendment No. 489, XXX

SFP Water Level 3.7.14 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.

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 REQUIRED ACTION COMPLETION TIME A. SFP water level not within A.1 Suspend movement of Immediately limit. irradiated fuel assemblies in SFP.

A.2 Suspend movement of Immediately fuel cask in or over the SFP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the SFP water level is ~ 647 ft elevation. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.14-1 Amendment No. 489, XXX

SFP Boron Concentration 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool (SFP) Boron Concentration 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 REQUIRED ACTION COMPLETION TIME A. SFP boron concentration A.1 Suspend movement of Immediately not within limit. fuel assemblies in the SFP.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the SFP boron concentration is within limit. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.15-1 Amendment No. ~,XXX

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

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not within A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months limit.

AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify the specific activity of the secondary coolant is In accordance with within limit. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.7.17-1 Amendment No. 489, XXX

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A, B, C, AND D, or E not met.

F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Three or more AC sources G.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and voltage for In accordance with each offsite circuit. the Surveillance Frequency Control Program SR 3.8.1.2 Verify each DG starts from standby conditions and In accordance with achieves: the Surveillance Frequency Control

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

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

Palisades Nuclear Plant 3.8.1-4 Amendment No. ~,XXX

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.3 -----------------------------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 In accordance with operates for ~ 60 minutes: the Surveillance Frequency Control

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

b. For the remainder of the test at a load

~ 2300 kW and s 2500 kW.

SR 3.8.1.4 Verify each day tank contains ~ 2500 gallons of In accordance with fuel oil. the Surveillance Frequency Control Program SR 3.8.1.5 Verify each DG rejects a load greater than or equal In accordance with to its associated single largest post-accident load, the Surveillance and: Frequency Control Program

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.

Palisades Nuclear Plant 3.8.1-5 Amendment No. 4-89, XXX

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify each DG, operating at a power factor s 0.9, In accordance with does not trip, and voltage is maintained s 4000 V the Surveillance during and following a load rejection of ~ 2300 kW Frequency Control and s 2500 kW. Program SR 3.8.1.7 -----------------------------NOT E-----------------------------

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

Verify on an actual or simulated loss of offsite In accordance with power signal: the Surveillance Frequency Control

a. De-energization of emergency buses; Program

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.

Palisades Nuclear Plant 3.8.1-6 Amendment No. 439, XXX

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.8 -----------------------------NOT E-----------------------------

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

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

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.

SR 3.8.1.9 -----------------------------NOTE----------------------------

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

Verify each DG:

In accordance with

a. Synchronizes with offsite power source while the Surveillance supplying its associated 2400 V bus upon a Frequency Control simulated restoration of offsite power; Program

b. Transfers loads to offsite power source; and

c. Returns to ready-to-Ioad operation.

Palisades Nuclear Plant 3.8.1-7 Amendment No. 489, XXX

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.10 -----------------------------NOT E-----------------------------

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

Verify the time of each sequenced load is within In accordance with

+/- 0.3 seconds of design timing for each automatic the Surveillance load sequencer. Frequency Control Program SR 3.8.1.11 -----------------------------NOTE-----------------------------

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

Verify on an actual or simulated loss of offsite In accordance with power signal in conjunction with an actual or the Surveillance simulated safety injection signal: Frequency Control Program

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.

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

DC Sources - Operating 3.8.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is ~ 125 V on float In accordance with charge. the Surveillance Frequency Control Program SR 3.8.4.2 Verify no visible corrosion at battery terminals and In accordance with connectors. the Surveillance Frequency Control Program 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.

SR 3.8.4.3 Inspect battery cells, cell plates, and racks for In accordance with visual indication of physical damage or abnormal the Surveillance deterioration that could degrade battery Frequency Control performance. Program Palisades Nuclear Plant 3.8.4-2 Amendment No. 4-89, XXX

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.4 Remove visible terminal corrosion and verify In accordance with battery cell to cell and terminal connections are the Surveillance coated with anti-corrosion material. Frequency Control Program SR 3.8.4.5 Verify battery connection resistance is In accordance with

s; 50 I-Iohm for inter-cell connections, :s; 360 I-Iohm the Surveillance for inter-rack connections, and :s; 360 I-Iohm for Frequency Control inter-tier connections. Program SR 3.8.4.6 Verify each required battery charger supplies In accordance with

~ 180 amps at ~ 125 V for ~ 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . the Surveillance Frequency Control Program SR 3.8.4.7 -----------------------------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 In accordance with emergency loads for the design duty cycle when the Surveillance subjected to a battery service test. Frequency Control Program Palisades Nuclear Plant 3.8.4-3 Amendment No. 4-89, XXX

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE 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 In accordance with manufacturer's rating when subjected to a the Surveillance performance discharge test or a modified Frequency Control performance discharge test. 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 Palisades Nuclear Plant 3.8.4-4 Amendment No. 489, XXX

Battery Cell Parameters 3.8.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A not met.

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

< 70 a F.

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 Table 3.8.6-1 In accordance with Category A limits. the Surveillance Frequency Control Program SR 3.8.6.2 Verify average electrolyte temperature of In accordance with representative cells is ~ 70 a F. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.6-2 Amendment No. 4-89, XXX

Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.3 Verify battery cell parameters meet Table 3.8.6-1 In accordance with Category B limits. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.6-3 Amendment No. .:1-89, XXX

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

Battery Surveillance Requirements CATEGORY A: CATEGORY B: CATEGORYC:

NORMAL LIMITS NORMAL LIMITS ALLOWABLE FOR EACH FOR EACH LIMITS FOR EACH DESIGNATED CONNECTED CONNECTED PARAMETER PILOT CELL CELL CELL Electrolyte Level > Minimum level > Minimum level Above top of plates, indication mark, and indication mark, and and not overflowing

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

Float Voltage ~ 2.13 V ~ 2.13 V > 2.07 V Specific Gravity(b)(c) ~ 1.205 ~ 1.200 Not more than 0.020 below AND average connected cells Average of connected cells AND

~ 1.205 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

Inverters - Operating 3.8.7 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 COMPLETION TIME A. One inverter inoperable. -----------------NOTE------------------

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

Operating" with any Preferred AC bus de-energized.

A.1 Restore inverter to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and In accordance with alignment to Preferred AC buses. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.7-1 Amendment No. 4-89, XXX

Inverters - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and In accordance with alignment to required Preferred AC buses. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.8.8-2 Amendment No. 48S, XXX

Distribution Systems - Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Two or more inoperable E.1 Enter LCO 3.0.3. Immediately distribution subsystems that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance with required AC, DC, and Preferred AC bus electrical the Surveillance power distribution subsystems. Frequency Control Program Palisades Nuclear Plant 3.8.9-2 Amendment No. 489, XXX

Distribution Systems - Shutdown 3.8.10 ACTIONS 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 SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to In accordance with required AC, DC, and Preferred AC bus electrical the Surveillance power distribution subsystems. Frequency Control Program Palisades Nuclear Plant 3.8.10-2 Amendment No. 489, XXX

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration 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. ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is at the REFUELING In accordance with BORON CONCENTRATION. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.9.1-1 Amendment No. ~,XXX

Nuclear Instrumentation 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.9.2.2 -----------------------------N()TE------------------------------

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

Perform CHANNEL CALIBRATI()N. In accordance with the Surveillance Frequency Control Program Palisades Nuclear Plant 3.9.2-2 Amendment No. 489, XXX

Containment Penetrations 3.9.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Suspend CORE Immediately penetrations not in ALTERATIONS.

required status.

A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify each required to be met containment In accordance with penetration is in the required status. 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 In accordance with closes on an actual or simulated Refueling the Surveillance Containment High Radiation signal. Frequency Control Program Palisades Nuclear Plant 3.9.3-2 Amendment No. 4$, XXX

SDC and Coolant Circulation - High Water Level 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Suspend loading Immediately irradiated fuel assemblies in the core.

A.4 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one SDC train is in operation and circulating In accordance with primary coolant at a flow rate of ~ 1000 gpm. 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 Immediately all containment penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one SDC train is in operation and In accordance with circulating primary coolant at a flow rate of the Surveillance

~ 1000 gpm. Frequency Control Program SR 3.9.5.2 Verify correct breaker alignment and indicated In accordance with power available to the required SDC pump that is the Surveillance not in operation. Frequency Control Program Palisades Nuclear Plant 3.9.5-2 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 REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.1 Suspend CORE Immediately level not within limit. AL TERATIONS.

A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling cavity water level is ~ 647 ft In accordance with elevation. the Surveillance Frequency Control Program Palisades Nuclear Plant 3.9.6-1 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

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