Text

Attachment 3: Proposed Changes and Appendix a Technical Specifications Pages
	ML18270A324
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: ML18270A324 (94)
	v • d • e

ATTACHMENT 3 Proposed Changes to Palisades Plant Renewed Facility Operating License DPR*20 and Appendix A Technical Specifications Pages (showing proposed changes; additions are highlighted and deletions are strikethrough) 93 pages follow

ATTACHMENT 3 PNP 2018-025 Proposed Changes to Palisades Plant Renewed Facility Operating License DPR-20 and Appendix A Technical Specifications Pages INSERT 1 In accordance with the Surveillance Frequency Control Program INSERT 2 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.

(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. , 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. ~, 266

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 SOM to be within limits. 24hoUF~

~

Palisades Nuclear Plant 3.1.1-1 Amendment No. 189

Reactivity Balance 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ------------------------------N()TE----------------------------

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. M()DE1 after each fuel loading AND

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

()nly required after initial 60 EFPD 31 EFP ~

~

Palisades Nuclear Plant 3.1.2-2 Amendment No. 189

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 12heuFS~

8 inches of all other control rods in its group.

Insert 1 SR 3.1.4.2 Perform a CHANNEL CHECK of the control rod 12heuFS~

position indication channels.

Insert 1 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 0 is entered for control rod 13.

Verify control rod freedom of movement by moving g2dayS~

each individual full-length control rod that is not fully inserted into the reactor core ~ 6 inches in either Insert 1 direction .

SR 3.1.4.4 Verify the rod position deviation alarm is ~8 Ffl9RtRS OPERABLE.

Insert 1 SR 3.1.4.5 Perform a CHANNEL CALIBRATION of the control ~8 Ffl9RtRS rod position indication channels.

Insert 1 SR 3.1.4.6 Verify each full-length control rod drop time is Prior to reactor

s; 2.5 seconds. criticality, after each reinstallation of the reactor head Palisades Nuclear Plant 3.1.4-3 Amendment No. ~, 260

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 12hour~

withdrawn ~ 128 inches.

~

Palisades Nuclear Plant 3.1.5-1 Amendment No. 189

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 12hour~

withdrawal sequence, overlap, and insertion limits.

~

SR 3.1.6.2 Verify POlL alarm circuit is OPERABLE. 31 days ~

__________________________________________~--~J Insert 1 SR 3.1.6.3 Verify CROOS alarm circuit is OPERABLE. 31 days ~

I Insert 1 Palisades Nuclear Plant 3.1.6-2 Amendment No. 189

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. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ...,

I Insert 1 l SR 3.1.7.2 Verify Tave is ~ 500°F. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ...,

I Insert 1 l SR 3.1.7.3 Verify ~ 1% shutdown reactivity is available for trip 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s~

insertion.

Insert 1 Palisades Nuclear Plant 3.1.7-2 Amendment No. 189

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

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 12hOblF~

COLR.

~

Palisades Nuclear Plant 3.2.1-2 Amendment No. 189

LHR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1 .2 ------------------------------NOT E ----------------------------

Only 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 31 EFPD thereafter ~

r---I-....--.

+----------~! Insert 1 I SR 3.2.1.3 -------------------------------NOTE---------------------------

Only 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 -------------------------------NOT E ---------------------------

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

Verify THERMAL POWER is less than the APL. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ~

~~l Insert 1 Palisades Nuclear Plant 3.2.1-3 Amendment No. 189

LHR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.5 -------------------------------N()TE---------------------------

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

Verify measured ASI is within 0.05 of target AS!. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.2.1.6 -------------------------------N()TE---------------------------

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

Verify Tq ~ 0.03.

Palisades Nuclear Plant 3.2.1-4 Amendment No. 189

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 ~ 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 31 EFPD thereafter Palisades Nuclear Plant 3.2.2-1 Amendment No. 4-89, 205

Tq 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 QUADRANT POWER TILT (Tq)

LCO 3.2.3 Tq shall be ~ O.OS.

APPLICAB ILlTY: MODE 1 with THERMAL POWER> 2S% RTP .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tq> O.OS. 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 < SO% 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 ~ 2S% RTP.

Time not met.

OR Tq> 0.1S.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify Tq is 0 O.OS. 12hour~

~

Palisades Nuclear Plant 3.2.3-1 Amendment No. 489, 20S

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 ~ 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 Verify ASI is within limits specified in the COLR. 12hour~

~

Palisades Nuclear Plant 3.2.4-1 Amendment No. 189

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> 90°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 .

SU RVEI LLANCE FREQUENCY SR 3.3.1.1 Perform a CHANNEL CHECK.

SR 3.3.1 .2 Verify control room temperature is ~ 90°F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.3.1-3 Amendment No. 189

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.3 -----------------------------NOTE-----------------------------

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

Perform calibration (heat balance only) and adjust 24hOUF~

the power range excore and AT power channels to agree with calorimetric calculation if the absolute difference is ~ 1.5%.

~

SR 3.3.1.4 -----------------------------NOTE-----------------------------

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

Calibrate the power range excore channels using 31day~

the incore detectors.

~

SR 3.3.1.5 Perform a CHANNEL FUNCTIONAL TEST and Q2day~

verify the Thermal Margin Monitor Constants.

~

SR 3.3.1.6 Perform a calibration check of the power range 92day~

excore channels with a test signal.

~

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. 189

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1 .8 -----------------------------N()TE-----------------------------

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

Perform a CHANNEL CALIBRATI()N. 18 months Palisades Nuclear Plant 3.3.1-5 Amendment No. 189

RPS Logic and Trip Initiation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform a CHANNEL FUNCTIONAL TEST on 92dayS ~

each RPS Matrix Logic channel and each RPS Trip Initiation Logic channel.

~

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. 189

ESF Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS

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

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

~

I Insert 1 I SR 3.3.3.2 Perform a CHANNEL FUNCTI()NAL TEST. 92 days

~

J Insert 1 I SR 3.3.3.3 Perform a CHANNEL CALIBRATI()N . 18 months ~

I Insert 1 I Palisades Nuclear Plant 3.3.3-3 Amendment No. 189

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 92days ~

channel normal and standby power functions.

~

SR 3.3.4.2 Perform a CHANNEL FUNCTIONAL TEST of each 92days ~

AFAS actuation logic channel.

~

SR 3.3.4.3 Perform a CHANNEL FUNCTIONAL TEST. 18months~

~

Palisades Nuclear Plant 3.3.4-2 Amendment No. 189

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 18 months ~

each DG-UV start logic channel.

~

Palisades Nuclear Plant 3.3.5-1 Amendment No. 189

DG - UV Start 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.2 Perform CHANNEL CALIBRATION on each Loss 18months~

of Voltage and Degraded Voltage channel with setpoints as follows:

~

a. Degraded Voltage Function ~ 2187 V and

2264 V Time delay: ~ 0.5 seconds and

0.8 seconds; and

b. Loss of Voltage Function ~ 1780 V and

1940 V Time delay: ~ 5.45 seconds and

8.15 seconds at 1400 V.

Palisades Nuclear Plant 3.3.5-2 Amendment No. 189

Refueling CHR Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform a CHANNEL CHECK of each refueling 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~

CHR monitor channel.

~

SR 3.3.6.2 Perform a CHANNEL FUNCTIONAL TEST of each J1E1ays ~

refueling CHR monitor channel.

~

SR 3.3.6.3 Perform a CHANNEL FUNCTIONAL TEST of each 1Bmonths~

CHR Manual Initiation channel.

~

SR 3.3.6.4 Perform a CHANNEL CALIBRATION of each 1Bmonths ~

refueling CHR monitor channel.

~

Palisades Nuclear Plant 3.3.6-2 Amendment No. 189

PAM Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS

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

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 31 days ~

instrumentation channel that is normally energized .

~

SR 3.3.7.2 -----------------------------NOTE------------------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18months ~

~

Palisades Nuclear Plant 3.3.7-3 Amendment No. 189

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 18months ~

switch is capable of performing the intended function . ~

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 18months ~

required instrumentation channel.

~

Palisades Nuclear Plant 3.3.8-2 Amendment No. 189

Neutron Flux Monitoring Channels 3.3.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.9.2 -----------------------------N()TE------------------------------

Neutron detectors are excluded from the CHANNEL CALI BRATI ()N .

Perform CHANNEL CALIBRATI()N. 18 months Palisades Nuclear Plant 3.3.9-2 Amendment No. 189

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. 12hoUFS ~

~

SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST. 31days ~

~

SR 3.3.10.3 Perform a CHANNEL CALIBRATION. 1amonths ~

Verify high radiation setpoint on each ESRV Instrumentation radiation monitoring channel is

~

s; 2.2E+5 cpm .

Palisades Nuclear Plant 3.3.10-1 Amendment No. 189

PCS Pressure, Temperature, and Flow ONB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure within the limits 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~

specified in the COLR.

~

SR 3.4.1 .2 Verify PCS cold leg temperature within the limit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~

specified in the COLR.

~

SR 3.4.1.3 ------------------------------NOT E----------------------------

Not required to be performed until 31 EFPO after THERMAL POWER is ;;:: 90% RTP.

Verify PCS total flow rate within the limit specified 18 months in the COLR.

After each plugging of 10 or more steam generator tubes Palisades Nuclear Plant 3.4.1-2 Amendment No. ~,217

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 ;::: 525°F.

APPLICABILITY: MODE 1 MODE 2 with Kelt ~ 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. T ave in one or more PCS A.1 Be in MODE 2 with Kelt 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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.4.2-1 Amendment No. 189

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, or4. operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 ------------------------------- NOT E---------------------------

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

Verify pes pressure, pes temperature, and pes heatup and cooldown rates are within the limits of 30 R1iRutej In~sert 1 I Figure 3.4.3-1 and Figure 3.4.3-2.

Palisades Nuclear Plant 3.4.3-2 Amendment No. 189

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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.4.4-1 Amendment No. 189

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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I Insert 1 r SR 3.4.5.2 Verify secondary side water level in each steam 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months generator ~ -84%.

~

+-----~

I Insert 1 SR 3.4.5.3 Verify correct breaker alignment and indicated 7 days power available to the required primary coolant pump that is not in operation .

Palisades Nuclear Plant 3.4.5-2 Amendment No. 189

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 12hOl:lFS ~

flow through the reactor core, or one PCS loop is in operation.

~

SR 3.4.6 .2 Verify secondary side water level in required SG(s) is 12hOl:lFS ~

~ -84%.

~

SR 3.4.6.3 Verify correct breaker alignment and indicated power 7 days available to the required pump that is not in operation .

Palisades Nuclear Plant 3.4.6-3 Amendment No. 189

PCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4 .7.1 Verify one SDC train is in operation with ~ 2810 gpm 12hours ~

flow through the reactor core.

~

SR 3.4.7.2 Verify required SG secondary side water level is 12hours ~

~ - 84%.

~

SR 3.4.7.3 Verify correct breaker alignment and indicated power 7 days available to the required SDC pump that is not in operation.

Palisades Nuclear Plant 3.4.7-3 Amendment No. 189

PCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SOC train inoperable. A.1 Initiate action to restore Immediately SDC train to OPERABLE status.

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

SOC flow through the AND reactor core not within limits. B.2 Initiate action to restore Immediately one SOC 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 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

~ 2810 gpm flow through the reactor core.

Palisades Nuclear Plant 3.4.8-2 Amendment No. 189

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

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

Verify one SDC train is in operation with 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~

~ 650 gpm flow through the reactor core.

I Insert 1 I SR 3.4.8.3 --------------------------------NOlrE--------------------------

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

Verify two of three charging pumps are incapable 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~

of reducing the boron concentration in the PCS below the minimum value necessary to maintain the required SHUlrDOWN MARGIN.

~

SR 3.4.8.4 Verify correct breaker alignment and indicated 7 days power available to the SDC pump that is not in operation .

Palisades Nuclear Plant 3.4.8-3 Amendment No. 189

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

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

I Insert 1 I SR 3.4.9.2 Verify the capacity of pressurizer heaters from 18months~

electrical bus 1D, and electrical bus 1E is

~ 375 kW.

~

SR 3.4.9.3 Verify the required pressurizer heater capacity 18months~

from electrical bus 1E is capable of being powered from an emergency power supply.

~

Palisades Nuclear Plant 3.4.9-3 Amendment No. 489, 256

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 18month~

average temperature> 200°F.

~

Palisades Nuclear Plant 3.4.11-3 Amendment No. 189

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 -------------------------------NOT E-------------------------

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

Verify both HPSI pumps are incapable of injecting 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~

into the PCS.

Insert 1 SR 3.4.12.2 Verify required PCS vent, capable of relieving 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for z 167 gpm at a PCS pressure of 315 psia, is open. unlocked open vent valve(s) 31 days for locked open vent valve(s) .-,

~----------~! Insert 1 I SR 3.4.12.3 Verify PORV block valve is open for each required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ~

PORV.

Insert 1 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 31days ~

required PORV, excluding actuation.

~

SR 3.4.12.5 Perform CHANNEL CALIBRATION on each 18 months ~

I required PORV actuation channel. ,.....-----'-----,

I Insert 1 Palisades Nuclear Plant 3.4.12-3 Amendment No. 189

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 72 hoUFs .--l--.,

by performance of PCS water inventory balance.

~

SR 3.4.13.2 ------------------------------- 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 establishment of steady state operation.

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

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .--l--., I

~

Palisades Nuclear Plant 3.4.13-2 Amendment No. 4-89, 223

PCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -------------------------------N()TES--------------------------

1. ()nly required to be performed in M()DES 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 18months ~

~ 5 gpm at a PCS pressure of 2060 psia.

AND ~

()nce prior to entering M()DE 2 whenever the plant has been in M()DE 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 18months ~

associated valve from being opened with a simulated or actual PCS pressure signal ~ 280 psia.

~

Palisades Nuclear Plant 3.4.14-3 Amendment No. 189

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

containment sump level indicator.

~

SR 3.4.15.2 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere gaseous activity monitor.

SR 3.4.15.3 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ~

containment atmosphere humidity monitor.

~

SR 3.4.15.4 Perform CHANNEL FUNCTIONAL TEST of the 18 months ~

required containment air cooler condensate level switch .

~

SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required 18months ~

containment sump level indicator.

~

Palisades Nuclear Plant 3.4.15-2 Amendment No. 189

PCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.6 Perform CHANNEL CALIBRATION of the required 18months~

containment atmosphere gaseous activity monitor.

~

SR 3.4.15.7 Perform CHANNEL CALIBRATION of the required 18months~

containment atmosphere humidity monitor.

~

Palisades Nuclear Plant 3.4.15-3 Amendment No. 189

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 j.JCi/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 7 days

1ODIE j.JCi/gm.

Palisades Nuclear Plant 3.4.16-2 Amendment No. 189

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.

14 says Verify primary coolant DOSE EQUIVALENT 1-131 specific activity $; 1.0 IJCi/gm.

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

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 184 says ~

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 .

~

Palisades Nuclear Plant 3.4.16-3 Amendment No. 189

SITs 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each SIT isolation valve is fully open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .-,

! Insert 1 I SR 3.5.1.2 Verify borated water volume in each SIT is 12R."FS ~

~ 1040 ft3 and ::;; 1176 ft3 .

Insert 1 SR 3.5.1.3 Verify nitrogen cover pressure in each SIT is 12R."FS~

~ 200 psig .

Insert 1 SR 3.5.1.4 Verify boron concentration in each SIT is 31dayS ~

~ 1720 ppm and::;; 2500 ppm.

Insert 1 SR 3.5.1.5 Verify power is removed from each SIT isolation 31dayS ~

valve operator.

Insert 1 Palisades Nuclear Plant 3.5.1-2 Amendment No. 189

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves and hand switches are 12hOI:JFS ~

in the open position.

Valve/Hand ~

Switch Number Function CV-3027 SIRWT Recirc Valve HS-3027A Hand Switch For CV-3027 HS-3027B Hand Switch For CV-3027 CV-3056 SIRWT Recirc Valve HS-3056A Hand Switch For CV-3056 HS-3056B Hand Switch For CV-3056 SR 3.5.2.2 Verify each ECCS manual, power operated, and 31days ~

automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position .

~

SR 3.5.2.3 Verify CV-3006, "SOC Flow Control Valve," is open 31 days ~

and its air supply is isolated .

Insert 1 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 18month~

locked, sealed, or otherwise secured in position, in the flow path actuates to the correct position on an actual or simulated actuation signal.

~

Palisades Nuclear Plant 3.5.2-2 Amendment No. 489, 262

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.6 Verify each ECCS pump starts automatically on an 1Bmonths ~

actual or simulated actuation signal.

~

SR 3.5.2.7 Verify each LPSI pump stops on an actual or 1Bmonths ~

simulated actuation signal.

~

SR 3.5.2.8 Verify, for each ECCS throttle valve listed below, 1Bmonths ~

each position stop is in the correct position .

Valve Number Function

~

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 1Bmonths ~

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 .

Palisades Nuclear Plant 3.5.2-3 Amendment No. 489, 228

SIRWT 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Verify SIRWT borated water temperature is ~ 40°F 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ~

and ~ 100°F.

~

SR 3.5.4.2 --------------------------------N()TE--------------------------

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

Verify SIRWT borated water volume is 7 days

~ 250,000 gallons.

SR 3.5.4.3 --------------------------------N()TE--------------------------

()nly required to be met in M()DE 4.

Verify SIRWT borated water volume is 7 days

~ 200,000 gallons.

SR 3.5.4.4 Verify SIRWT boron concentration is ~ 1720 ppm J1days ~

and ~ 2500 ppm.

~

Palisades Nuclear Plant 3.5.4-2 Amendment No. 189

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 S10,553 Ibs of Sodium Tetraborate Decahydrate (STB) Na2B407' 10H20 .

APPLICABI LlTY: 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 1amont~

S10,553 Ibs of equivalent weight sodium tetra borate decahydrate. ~

SR 3.5.5.2 Verify that a sample from the STB baskets provides adequate pH adjustment of borated water.

Palisades Nuclear Plant 3.5.5-1 Amendment No. 48-B; 227

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 24 months ~ I at a time.

Insert 1 Palisades Nuclear Plant 3.6.2-4 Amendment No. 489, 194 I

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 31days ~

room supply valve is locked closed .

~

SR 3.6.3.2 -----------------------------NOT E----------------------------

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

Verify each manual containment isolation valve 31 days ~

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.

SR 3.6.3.3 ----------------------------NO TE-----------------------------

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 MODE 4 from and not locked, sealed, or otherwise secured in MODE 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. 189

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 184dayS ~

12 inch air room supply valve is closed by performance of a leakage rate test.

~

SR 3.6.3.6 Verify each automatic containment isolation valve 18month~

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

~

Palisades Nuclear Plant 3.6.3-5 Amendment No. 439, 262

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be :0:::; 1.0 psig in MODES 1 and 2 and

0:::; 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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Palisades Nuclear Plant 3.6.4-1 Amendment No. 189

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

within limit.

~

Palisades Nuclear Plant 3.6.5-1 Amendment No. 189

Containment Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power a~ says operated, and automatic valve in the flow path that is not locked , sealed , or otherwise secured in position is in the correct position.

~

SR 3.6.6.2 Operate each Containment Air Cooler Fan Unit for 31 days ~

~ 15 minutes.

Insert 1 SR 3.6.6.3 Verify the containment spray piping is full of water a~ says

~

to the 735 ft elevation in the containment spray header.

SR 3.6.6.4 Verify total service water flow rate, when aligned ~8 months for accident conditions, is ~ 4800 gpm to Containment Air Coolers VHX-1, VHX-2, and Insert 1 VHX-3.

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 18m.Rlh~

the flow path that is not locked, sealed, or otherwise secured in position, actuates to its Insert 1 correct position on an actual or simulated actuation signal.

Palisades Nuclear Plant 3.6.6-2 Amendment No. 489, 262

Containment Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.7 Verify each containment spray pump starts 18months ~

automatically on an actual or simulated actuation signal.

~

SR 3.6.6.8 Verify each containment cooling fan starts 18months ~

automatically on an actual or simulated actuation signal. ~

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. 489, 211

MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify closure time of each MSIV is $; 5 seconds on 18months ~

an actual or simulated actuation signal from each train under no flow conditions.

~

Palisades Nuclear Plant 3.7.2-2 Amendment No. 189

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 18month6 ~

bypass valve is s 22 seconds on a actual or simulated actuation signal.

~

Palisades Nuclear Plant 3.7.3-2 Amendment No. 189

ADVs 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ADV. 18 months Palisades Nuclear Plant 3.7.4-2 Amendment No. 189

AFWSystem 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each required AFW manual, power J1 says 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.

SR 3.7.5.2 ------------------------N()TE--------------------------------

Not required to be met for the turbine driven AFW pump in MODE 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----------------------------

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

Verify each AFW automatic valve that is not 18months ~

locked, sealed, or otherwise secured in position ,

actuates to the correct position on an actual or simulated actuation signal.

~

SR 3.7.5.4 ------------------------------N() TE ----------------------------

Only required to be met in M()DES 1, 2, and 3.

Verify each required AFW pump starts 18months ~

automatically on an actual or simulated actuation signal.

~

Palisades Nuclear Plant 3.7.5-3 Amendment No. +QQ, 262

Condensate Storage and Supply 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify condensate useable volume is 12hours ~

~ 100,000 gallons.

~

Palisades Nuclear Plant 3.7.6-2 Amendment No. 189

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 a1 days 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.

SR 3.7.7.2 -----------------------------N() T E-----------------------------

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

Verify each CCW automatic valve in the flow path 18months ~

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

~

SR 3.7.7.3 -----------------------------N()TE-----------------------------

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

Verify each CCW pump starts automatically on an 18months ~

actual or simulated actuation signal in the "with standby power available" mode.

~

Palisades Nuclear Plant 3.7.7-2 Amendment No. 189

SWS 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 -----------------------------N()TE-----------------------------

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

Verify each SWS manual, power operated, and 31 days 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.

SR 3.7.8.2 ----------------------------N() T E------------------------------

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

Verify each SWS automatic valve in the flow path 1Bmonths ~

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

~

SR 3.7.8.3 -----------------------------N() TE -----------------------------

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

Verify each SWS pump starts automatically on an 1Bmonths ~

actual or simulated actuation signal in the "with standby power available" mode.

~

Palisades Nuclear Plant 3.7.8-2 Amendment No. 189

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

mean sea level.

~

SR 3.7.9.2 Verify water temperature of UHS is S 85°F. 24hours ~I

~

Palisades Nuclear Plant 3.7.9-1 Amendment No. 489,202

CRV Filtration 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRV Filtration train for 31E1ays ~

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

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

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 1emonths ~

actual or simulated actuation signal.

~

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. 489,230

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 18 months~

remove the assumed heat load.

Insert 1 Palisades Nuclear Plant 3.7.11-3 Amendment No. 489, 256

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 18months ~

Ventilation System, when aligned to the emergency filter bank, is ~ 5840 cfm and

~ 8760 cfm.

~

Palisades Nuclear Plant 3.7.12-2 Amendment No. 189

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 31 days ~

actual or simulated actuation signal.

~

Palisades Nuclear Plant 3.7.13-1 Amendment No. 189

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. 7 days Palisades Nuclear Plant 3.7.14-1 Amendment No. 189

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.

APPLICABILITY: 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. 7 days Palisades Nuclear Plant 3.7.15-1 Amendment No. 489, 207

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 ::; 0.10 IJCi/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 B

FREQUENCY SR 3.7.17.1 Verify the specific activity of the secondary coolant is 31 days within limit.

Insert 1 Palisades Nuclear Plant 3.7.17-1 Amendment No. 189

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 7 days each offsite circuit.

SR 3.8.1.2 Verify each DG starts from standby conditions and 31 days achieves:

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

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

Palisades Nuclear Plant 3.8.1-4 Amendment No. 189

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 31 days ~

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:$; 2500 kW.

SR 3.8.1.4 Verify each day tank contains ~ 2500 gallons of 31days ~

fuel oil.

~

SR 3.8.1.5 Verify each DG rejects a load greater than or equal 1Bmonths ~

to its associated single largest post-accident load ,

and:

~

a. Following load rejection, the frequency is

$;68 Hz;

b. Within 3 seconds following load rejection, the voltage is ~ 2280 V and:$; 2640 V; and

c. Within 3 seconds following load rejection, the frequency is ~ 59.5 Hz and:$; 61.5 Hz.

Palisades Nuclear Plant 3.8.1-5 Amendment No. 189

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify each DG, operating at a power factor::; 0.9, 1amonths~

does not trip, and voltage is maintained::; 4000 V during and following a load rejection of ~ 2300 kW and::; 2500 kW.

~

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

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

Verify on an actual or simulated loss of offsite 1amonths~

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 ::; 10 seconds,

2. energizes auto-connected shutdown loads through automatic load sequencer,

3. maintains steady state voltage

~ 2280 V and::; 2520 V,

4. maintains steady state frequency

~ 59.5 Hz and::; 61.2 Hz, and

5. supplies permanently connected loads for ~ 5 minutes.

Palisades Nuclear Plant 3.8.1-6 Amendment No. 189

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.8 -----------------------------NOTE-----------------------------

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

18months ~

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.

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

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

Verify each DG:

18months ~

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.

Palisades Nuclear Plant 3.8.1-7 Amendment No. 189

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, or 4.

Verify the time of each sequenced load is within 18month ~

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

~

SR 3.8.1.11 -----------------------------NOTE-----------------------------

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

Verify on an actual or simulated loss of offsite 18months~

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.

Palisades Nuclear Plant 3.8.1-8 Amendment No. 189

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 24

~I

~ A91:1FS 7 day supply of fuel.

Insert 1 SR 3.8.3.2 Verify stored lube oil inventory is ~ a 7 day supply. 31 days

~Insert 1 I 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 31 days

~ 200 psig.

Insert 1 SR 3.8.3.5 Check for and remove excess accumulated water from 92 days the fuel oil storage tank.

Insert 1 SR 3.8.3.6 Verify the fuel oil transfer system operates to transfer 92 days fuel oil from the fuel oil storage tank to each DG day tank and engine mounted tank. Insert 1 Palisades Nuclear Plant 3.8.3-3 Amendment No. 242

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.

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 7 days charge.

SR 3.8.4.2 Verify no visible corrosion at battery terminals and 92 days connectors.

Verify battery connection resistance is

s; 50 1J0hm for inter-cell connections, :s; 360 1J0hm for inter-rack connections, and :s; 360 1J0hm for inter-tier connections.

SR 3.8.4.3 Inspect battery cells, cell plates, and racks for 12months ~

visual indication of physical damage or abnormal deterioration that could degrade battery performance.

~

Palisades Nuclear Plant 3.8.4-2 Amendment No. 189

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.4 Remove visible terminal corrosion and verify 12months~

battery cell to cell and terminal connections are coated with anti-corrosion material.

~

SR 3.8.4.5 Verify battery connection resistance is 12months~

~ 50 jJohm for inter-cell connections, ~ 360 jJohm for inter-rack connections, and ~ 360 jJohm for inter-tier connections.

~

SR 3.8.4.6 Verify each required battery charger supplies 18months~

180 amps at;

:: 125 V for;::: 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

~

SR 3.8.4.7 -----------------------------NOTES---------------------------

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 18month~

emergency loads for the design duty cycle when subjected to a battery service test. ~

Palisades Nuclear Plant 3.8.4-3 Amendment No. 189

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, or 4.

60months ~

Verify battery capacity is ~ 80% of the manufacturer's rating when subjected to a AND ~

performance discharge test or a modified performance discharge test. 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. 189

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°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 31days ~

Category A limits.

~

SR 3.8.6.2 Verify average electrolyte temperature of 31days ~

representative cells is;::: 70°F.

~

SR 3.8.6.3 Verify battery cell parameters meet Table 3.8.6-1 92days ~

Category B limits.

~

Palisades Nuclear Plant 3.8.6-2 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 7 days alignment to Preferred AC buses.

Palisades Nuclear Plant 3.8.7-1 Amendment No. 189

Inverters - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and 7 days alignment to required Preferred AC buses.

Palisades Nuclear Plant 3.8.8-2 Amendment No. 189

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 7 Elays required AC, DC, and Preferred AC bus electrical power distribution subsystems.

Palisades Nuclear Plant 3.8.9-2 Amendment No. 189

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.2.5 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 7 days ~

required AC, DC, and Preferred AC bus electrical power distribution subsystems. Insert 1 Palisades Nuclear Plant 3.8.10-2 Amendment No. 189

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.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not A.1 Suspend CORE Immediately within limit. AL TERA TIONS.

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

BORON CONCENTRATION.

~

Palisades Nuclear Plant 3.9.1-1 Amendment No. 189

Nuclear Instrumentation 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.2.2 -----------------------------NOT E------------------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION . 18 months Palisades Nuclear Plant 3.9.2-2 Amendment No. 189

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 7 days penetration is in the required status.

SR 3.9.3.2 -----------------------------NOTE-----------------------------

Only required to be met for unisolated containment penetrations.

Verify each required automatic isolation valve 1Bmonth ~

closes on an actual or simulated Refueling Containment High Radiation signal.

~

Palisades Nuclear Plant 3.9.3-2 Amendment No. 189

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

primary coolant at a flow rate of ~ 1000 gpm.

~

Palisades Nuclear Plant 3.9.4-2 Amendment No. 189

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 12hours ~

circulating primary coolant at a flow rate of

~ 1000 gpm .

~

SR 3.9.5.2 Verify correct breaker alignment and indicated 7 days ~

power available to the required SDC pump that is not in operation. Insert 1 Palisades Nuclear Plant 3.9.5-2 Amendment No. 189

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 ~ 647ft 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ~

elevation.

~

Palisades Nuclear Plant 3.9.6-1 Amendment No. 189

Programs and Manuals 5.5 5.5 Programs and Manuals This page retained for page numbering Palisades Nuclear Plant 5.0-23 Amendment No. 230

ML18270A324

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