ML18087A742

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Rev 1 to Cold Shutdown to Hot Standby.
ML18087A742
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/07/1983
From: Connor B
Public Service Enterprise Group
To:
Shared Package
ML18087A720 List:
References
IOP-2, NUDOCS 8303160601
Download: ML18087A742 (40)
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Text

SALEM GENERATING STATION OPERATIONS DEPARTMENT DOCUMENT APPROVAL COVER SHEET Cold Shutdown To Hot Standby No.: IOP-2 2 1 Unit: Rev.:

IOP-2 Rev. 1 re laces Rev. b. Changes made; Added note before st~p 5.22, added ste 5.7.2, 5.15.1. Last OTSC P- 8.

Safety Related Review (Ref. AD-13}: S/R yes __ ...__ no

f Author's Checklist Completed: yes x

  • \
  • SRO
  • Ops. Eng._---M~----...........)j.._J

__ ,k

  • Date o~ 0"1 &~

3 SOS+ N jA Date

1 SORC **

General Manager **

  • required for SPM documents only

+ required for EOP validation acceptance only

      • required for safety related documents and fire*

_ protection docum_an~s

  • ("8303160601 830314 '*1 i\tit~-~T}:q ASTE If *c-. :e;.

PDR ADOCK 05000272 S PDR 4

Salem Unit 1/2 AD-1-B-l

  • START TIME

~

INTEGRATED OPERATING PROCEDURE IOP-2 COLD SHUTDO'i"i'N TO HOT STANDBY DA*TE- - - - - - - - BY

~

TERMINATION TIME DATE BY

-------- --------~

COMPLETION TIME- - - - - - - - DATE BY

1. 0 PURPOSE 1.1 This instruction outlines the sequence in which systems

_are placed in service for the plant heatup from Cold Shutdown (Mode 5) to Hot Standby (Mode 3). Specific operating details and valve lineups are found in the referenced Operating Instructions.

2.0 PRECAUTIONS 2.1 Administrative 2 .1.1 In the event plant conditions require a delay during some part of this procedure, the Senior

  • 2 .1. 2 Shift Supervisor/Shift Supervisor shall retain this instruction until the procedure is continued or terminated.

If this instruction is terminated prior to completion, the Senior Shift Supervisor/Shift Supervisor shall note the reason, time, and date of termination on this instruction and file in ~he normal manner. The last completed copy shall remain in the file.

2 .1. 3 Plot on Operations Log No. 4 the RCS Heatup rate at least once per 30 minutes, maintaining the heatup rate less than 100°F/hour and within the limits of the pressure-temperature curve to satisfy Technical Specification Surveillance 4.4.10.1.1.

2 .1. 4 Plot on Operations Log No. 5 the pressurizer Heatup Rate at least once per 30 minutes, maintaining the heatup rate less than 100°F/hour to satisfy Technical Specification Surveillance 4.4.10.2.

2 .1. 5 Shutdown Margin shall be calculated at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> .

Salem Unit 2 1 Rev. 1

IOP-2

  • 2 .1. 6 Criticality must be anticipated anytime the shutdown rods are being withdrawn or boron dilution operations are in progress.

2 .1. 7 If at any point .during the boron dilution, an unexpected increase in count rate by a factor of two(2) occurs, all operations involving positive reactivity insertion must be terminated pending an evaluation.

2 .1. 8 Do not start any Reactor Coolant pumps until a bubble has been formed in the pressurizer.

2 .1. 9 All Shutdown and Control Banks must remain Fully Inserted until temperature is greater than 540°F. IRPI's are calibrated for operation at greater tha~ 540°F. Refer to T. S. 3

  • 1
  • 3 . 2 .* 2
  • 2.2 Equipment
2. 2. 1 The RHR loop must be isolated from the RCS before the Reactor Coolant System temperature
  • 2.2.2 reaches 350°F or the pressure reaches 375 psig.
  • The Reactor Coolant pumps.must not be operated when the RCS pressure is below that required to maintain a differential pressure of 200 PSI across the No. 1 seal or when the VCT pressure is less than 15 psig.
2. 2. 3 The* reactor core shall always be supplied with a flow of water for cooling and reliable temperature indications; therefore, when the RCS temperature is below 250°F, at least one RHR pump or one Reactor Coolant pump shall be in operation. Above 250°F, at least one Reactor Coolant pump shall be in operation.

NOTE Under abnormal conditions, when coolant cannot be supplied to the Reactor Core, a backup means of temperature detection is available in the in-core thermocouples.

2.2.4 The Reactor Coolant pump seal injection water

  • temperature must not exceed 150°F .
  • Salem Unit 2 2 Rev. 1

IOP-2

    • 2.2.5 The pressurizer sprays must not be used if the temperature differential between the pressurizer and the spray fluid is greater than 320°F.
2. 2. 6 Do not exceed the 1600 PSI Delta P limit across the steam generator tube sheets.
2. 2 * .7 While *the RCS temperature is less than 312°F, RCS pressure must be maintained within Tech.

Spec. limits and less than 375 psig to prevent actuation of the POPS system. (2PR47 & 2PR48)

2. 2. 8 Before the Reactor Coolant temperature is allowed to exceed 180°F, the oxygen concentration in the Reactor Coolant must be less than .10 ppm.

2.2.9 The flow rate of the Reactor Coolant shall be greater than 3000 gpm whenever a change in RCS boron concentration is being made.

2.2.10 When changing RCS boron concentration, pressurizer sprays should be utilized to minimize the differential between pressurizer and loop boron concentration. The use of spr~y flow should continue until the difference is less than 50 ppm.*

2.2.11 Mixed bed demineralizers must be bypassed if there is any detectable hydrazin~ in the RCS.

3.0 ATTACHMENTS LIST 3.1 Figures None 3.2 Tables None

____ 3. 3 Check Off Sheets Check Off Sheet 1. Requirements for entering Mode 4. (15 pages) 3.3.2 Check Off Sheet 2. Requirements for entering Mode 3. (5 pag~__s)

Salem Unit 2 3 Rev. 1

IOP-2

  • 3.3.3 Check Off Sheet 3. Requirements to be completed during Mode 3. (1 page) 4.0 PREREQUISITES NOTE: Initial each step after completion.

4.1 The Senior Shift Supervisor/Shift Supervisor has reviewed and verified that the system alignments have been completed on those systems designated by the Operating Engineer.

4.2 The Senior Shift Superviso~/Shift Supervisor ha*s *reviewed maintenance activities to assess imp.act on system lineups and operation ..

4.3 The RCS has been filled and vented and a bubble drawn IAW Operating Instruction II-1.3.4, Filling and Venting the RCS .

  • 4.4 RCS water chemistry is within the Tech ?pee limits and noted below.

Chloride Fluoride

- - - - - - -ppm Chloride less than 0.15 ppm Fluoride less than 0.15 ppm

- - - - - - -ppm_

4.5 RCS temperature is 50-200°F by operation of .RHR pumps and/or Reactor Coolant pumps.

4.6 RCS pressure is 50-350 psig and being maintained by pressurizer heaters and/or spray.

4.7 Pressurizer level is approximately 22% by use of charging and letdown flow.

4.8 The following breakers are closed to energize 2RH1 and 2RH2.

4.8.l 2RH1 on 2B East VMCC 230VCC (Brk Position 4A) 4.8.2 2RH2 on 2A East VMCC 230VCC (Brk Position 4A)

Salem Unit 2 4 Rev. 1

IOP-2

  • 4.9 The following systems are in operation or aligned for operation in accordance with their respective operating instructions.
4. 9. 1 Safety Injection System - Normal Operation (OI II-4.3.1) 4.9.2 Placing CVCS Holdup Tanks In Service (OI II-3.3.4)
4. 9. 3 Boron Concentration Control (OI II-3.3.6) 4.9.4 CVCS Demineralizers ~Normal Operation (OI II-3.3.12) 4.9.5 Component Cooling System - Normal Operation

~* (OI II-7.3.2) 4.9.6 Service Water - Normal Operation (OI V-1.3.1)

4. 9. 7 Service Air System - Normal Operation (OI V-4.3.1) 4.9.8 Control Air System Operation (OI V-5.3.1)

Pressurizer Relief Tank - Normal Operation (OI II-2.3.3)

Reactor Flange Leak Detection and RCS Drain Tank Aligned IAW Reactor Coolant Drain Tank - Normal Operation (OI II-11.3.4) 4.9.12 Contaiminated Drains System Operation (OI II-14.3.1) 4.9.13 Operation of the Nuclear Instrumentation System (QI IV-6.3.1) 4.9.14 Emergency Power - Diesel Operation (OI IV-16.3.1) 4.9.15 Containment Ventilation Ope;i:-at'ion (OI II-16.3.1) 4.9.16 Switchgear and Penetration Areas Ventilation Operation (OI II-16.3.2) 4.9.17 Auxiliary Building Ventilation Operation (OI II-17.3.1) 4.9.18 Control Room Ventilation Operation (OI II-17.3.2)

  • 4.9.19 Salem Unit 2 Sampling System Operation (OI II-10.3.1) 5 Rev. 1

IOP-2

  • 4.9.20 4.9.21 Gas Analyzer Operation (OI II-10.3.2)

Gaseous Waste Disposal System - Normal Operation (OI II-12.3.1) 4.9.22 Nitrogen System - Normal Operation (OI III-17.3.1) 4.9.23 Hydrogen System - Normal Operation (OI III-17.3.2) 4.9.24 Steam Generator Blowdown - Normal Operation (OI III-13.3.2) 4.9.25 Heating Boiler is in Operation IAW OI V-10.3.1, "Heating Boiler Cold Startup"a 4.9.26 Auxiliary Feedwater System Operation (OI III-10.3.1) 4.9.27 The Containment Spray System is ready for Operation IAW OI II-5.3.1, "Filling and Venting the Containment Spray System."

4.10 The Reactor Coolant boron concentration is adequate to

  • maintain a Shutdown Margin greater than 1.6% delta k/k reference Figure 20(A) of the Reactor Engineering Manual, and noted below:

RCS Boron Cone.

- - - - - -ppm.

4 .* 11 At least 50,000 gallons of CVCS Capacity holdup tank capacity is available equivalent to to receive the Reactor Coolant approximately discharged during heatup and one eves holdup dilution. tank.

4.12 The MAKE-UP MODE SELECTOR is in AUTO and adjusted to provide make up water with a boron concentration equal to that in the RCS IAW OI II-3.3.6t "Boron Concentration Control."

4.13 At least 26,000 gallons (greater This is 10,000 than 14%) of primary water gallons above available for the anticipated the low level boron dilution during startup . alarm.

  • Salem Unit 2 6 Rev. 1

IOP-2

  • 4.14 4.15 The VCT level is within 14-80%.

The VCT pressure is 15-65 psig Should be with H2. maintained as close as possible to 15 psig for Maximum RCP Seal Leak Off Flow.

4.16 The CVCS is in Operation IAW OI II-3.3.1, "Establishing Charging, Letdown and Seal Injection Flow."

4.17 The Rod Control System is energized IAW OI IV-8.3.1, Rod Control System - Normal Operations."

4.18 All Shutdown and Control Rods The Shutdown

  • are Fully inserted . Rods may either be fully inserted or

'fully withdrawn depending upon the boron concentration specified in Figure 20(A) of the Reactor Engineering Manual.

- 4.19 The Steam Generators are in

  • If the outage "Wet Layup" IAW OI III-9.3.3, did not require "Filling and Venting the placing the

.*Steam Generators." steam generators in Wet Layup this step may be signed off as N/A .

  • Salem Unit 2 7 Rev. 1

rOP-2

  • 4.20 Both POPS channels are armed and operable.

POPS channels armed and operable if:

2PR47 light is on 2PR48 light is on K 16 Alarm is clear K 40 Alarm is clear 4.21 PLACE the Radiation Monitoring Systems in service* rAW the following or's.

4.21.1 or rv-11.3.1, Radiation Monitoring System - Normal Operation."

4.21.2 or rV-11.3.2, "Operation of Radiation Monitoring

  • 4.22 System Samplers."

A minimum of one Source Range Channel shall be in operation with the Source Range High Flux Level Trip operable.

Trip setT?oint is.lOES CPS 4.23 The SR High Flux at shutdown alarm is operable and not blocked.

4.24 The analog trend recorder located on the control console is indicating the following points:

4.24.1 Pen 1 Delta T SAT 0-120F Delta T SAT U2012 4.24.2 Pen*2 Delta P SAT Delta P SAT 0-lSOOPSrG U2011

  • Salem Unit 2 8 Rev. 1

IOP-2

  • 5.0 NOTE:

PROCEDUF.E Initial each step after completion ..

5.1 INCREASE RCS pressure to Readjtlst No. 23 approximately 340 PSIG and Chargirl'g pump START or MAINTAIN the Reactor low speed stop Coolant Pumps In Service IAW to maintain OI II-1.3.1, "Reactor Coolant minimum Seal Pump Operation." - Injection Flow, as pressure is increased.

5.1.1 OPEN 21-24CV104, Seal Leakoff Valves, when RCS pressure is greater than 100 PSIG. UPOATE TRIS 5.2 After at least 15 minutes of Reactor Tech Spec Coolant Pump Operation, SAMPLE the limits are:

RCS for the following and record: Dissolved oxygen less than 0 .1 ppm

when TAVE greater than 250°F

  • Chlorides less than 0.15ppm Fluorides less Chloride ppm than 0.15ppm Fluoride ppm Also sample the pressurizer for the foilowing and record: '

Boron ppm Dissolved osygen

ppm

  • Salem Unit 2 9 Rev. 1

IOP-2

  • 5.2.l MAINTAIN the RCS temperature less than 180°F if the dissolved oxygen is greater than 0.10 ppm.

Boron differential between the Pressurizer and the loops must be less than 50 ppm.

Lithium must be 0.22-2.2 ppm.

a. If the dissolved oxygen is greater than O.lOpprn:

(1) REMOVE the mixed bed demineralizer from service (2) NOTIFY the Chemistry Department to add Hydrazine to the RCS to reduce the dissolved oxygen.*

  • 5.3 Prior to exceedin~ 200°F the following steps must be completed:

5.3.l Check Off Sheet 1 has been completed and reviewed by the Senior Shtft Supervisor/Shift Supervisor.

5.3.2 The Stearn Generators are drained to a Narrow Range Level of 33% IAW OI III-13.3.1, "Draining th~ Stearn Generators."

5.3.3 RELEASE the tags on each Containment Spray Pump 4KV Breaker.

a. RACK in the breaker and TURN ON the DC Control Power .

.b. PERFORM SP ( 0) 4. 0. 5 if required or run the pump for a functional test to prove operability.

Salem Unit 2 10 Rev. 1

IOP-2

  • 5.3.4 RELEASE the tags on at lest one Centrifugal Charging Pump 4 KV Breaker.
a. RACK in the breaker and turn on the DC Control Power.
b. PERFORM SP(0)4.0.5 if required or run pump for a functional test to prove operability.

5.3.5 SECURE Containment Purge if Containment necessary~ Purge not allowed in Modes 1-4.

5.3.6 VERIFY 21-24 MS 167's are closed.

5.4 When notified by the Chemistry Department 02 is less than 2%,

ESTABLISH a*H2 overpressure in the VCT.

5.5 When informed by the Chemistry Department that the hydrazine and ammonia concentrations in the RCS are non-detectable RETURN the mixed bed demineralizers to service.

5.6 Continue Reactor Coolant Heatup with Reactor Coolant Pumps to 350°F.

5.6.1 PERFORM SP(0)4.4.4.3 PZR Heaters (should be completed after each Refueling Outage) 5.7 When RCS temperature is greater than 200F perform the following:

5.7.1 LOG the time the unit enters Mode 4 .

  • 5.7.2 Salem Unit 2 UPDATE TRIS; change from Mode 5 to Mode 4 11 Rev. 1

IOP-2 5.7.3 SECURE nitrogen to the steam generators if it is valved in.

5.7.4 OPEN all MSlO's 5.7.5. When a full plume of steam is observed, CLOSE all MSlO's 5.7.6 ADJUST all MSlO setpoints to 1035 PSIG.

5.8 When RCS temperature reaches 312°F Pressurizer disarm the POPS system by pressure may DEPRESSING the OFF PB on the now be Bezel, then VERIFY 2PR6 and increased to 2PR7 are open. above 375PSIG~

5.9 Secure and cooldown the RHR Increase RCS pumps IAW OI II-6.3.3, pressure to "Terminating RHR". establish eves letdown thru 2CV3, 4 and 5.

(

\ 5.10 If not performed in the last 92 days then perform:

1. SP(0)4.0.5-V-MD Sheet 4.2
2. SP(0)4.0.5-V-MD Sheet 4.3
3. SP(0)4.0.5-V-CONT Sheet 4.2 5.11 During the RCS heatup the following systems should be placed in service:

5.11.1 VERIFY the gas pressure .Pressure 595.5-and level in each 647.5psig accumulator - Level 60-70%

5.11.2 Place Feed and Condensate Commence Systems in service IAW cleanup of Feed OI III-9.3.1 and Condensate Systems as required .

  • Salem Unit 2 12 Rev. 1

IOP-2

5.11.4 Place Main Turbine on Turning Gear IAW OI III-1.3.4.

5.11.5 Place Turbine Auxiliary Cooling System in service IAW OI III 6.3.1.

5.11.6 Place Circulating Water System in service IAW OI III-7.3.1.

5.11.7 Place Turbine Gland Sealing Stearn in service IAW OI III-4. 3. 1.

5.11.8 Establish condenser vacuum When a 20 inch IAW OI III-8.3.1. vacuum is established, the main steam stop bypass valves (MS18's) may be used for RCS temperature control rather than stopping RCP's.

5.11.S Place Generator Seal Oil System in service IAW OI IV-2. 3. 1.

5.11.10 Place Generator Gas System in service IAW OI IV-2.3.2.

5.11.11 Place the Stator Cooling System in service IAW OI IV-2.3.3.

5.11.12 Place the E/H System in service IAW OI III-1.3.6 .

  • Salem Unit 2 13 Rev;.I 1 I

I!

IOP-2

  • 5.11.13 Place the Main, Reheat System Turbine Bypass Steam Warmup in service IAW
  • OI III-2.3.1.

5.12 Prior to reaching the High Letdown Letdown flow Flow Alarm (130 GPM) ADJUST Letdown will .increase Pressure Controller Valve 2CV18 pressure.

to the Normal Operating Letdown*

pressure of 300 PSIG.

5.13 CLOSE as necessary the Letdown Orifice Valves 2CV3, 4, 5 prior to reaching the High Flow Alarm.

5 .14 Prior to exceeding 350* 0 p (Mode 3) the following conditions must be met:

5.14.1 Ensure the RCS pressure The lockout is greater than the switches are accumulator*pressure located on then perform the following: 2RP4 ..

  • a.

b; OPEN Accumulator Outlet Valves 21,22,23 and 24SJ54.

C & T the 230 Volt ACB of 21,22,23 and 24SJ54.

c. PERFORM SP(0)4.0.5-V-MD Sheet 4.4 if not done in the last 92 days.

5.14.2 MONITOR each Accumulator's A level level after op ning the increase Accumulator Outlet Valves indicates both to verify that the check valves accumulator check valves are leaking.

are not leaking *

  • Salem Unit 2 14 Rev. 1

IOP-2

  • 5.14.3 RELEASE the tags on each Safety Injection Pump 4 KV Breaker.
a. RACK IN the breaker and turn on the DC Control Power.
b. PERFORM SP(0)4.0.5-P if required, or run pumps*

for a functional test to prove operability.

5.14.3.1 ENSURE both Centrifugal Charging Pumps .

are operable and have met the requirements of step 5.3.4.

5.14.4 OPEN 21 & 22SJ134 and 2SJ135, SI pump discharge to Cold Legs *

a. Update TRIS 5.14.5 LOCKOUT the.power on 2SJ135 Lockout for Senior Shift Supervisor switches Shift Supervisor. located on 2RP4.

5.14.6 RELEASE the tags on both Motor Driven AFW Pump 4KV Breakers.

a. RACK in the breaker and turn on the DC Control Power.
b. Perform SP(0)4.0.5-P if required or run pumps for a functional test to prove operability.

5.14.7 RELEASE the tags on the local reset lever for the Steam Driven AFW Pump .

  • Salem Unit 2 15 MA-STER Rev. 1

IOP-2

  • 5.14.8 Check Off Sheet 2, the Technical Specification Requirements, have been completed and reviewed by the Senior Shift

\ Supervisor/Shift Supervisor.

5.15 When the RCS temp is greater than 350°F, LOG the time that the unit has entered Mode 3.

5.15.l UPDATE TRIS; change from Mode 4 to Mode 3.

5.16 VERIFY Steam Generator Level The Condensate is being maintained at Pumps may be approximately 33% by use of used to the AFW System Perform SP(O) maintain Stearn 4.0.5-V-AF Sheet 4.3 if not Generator performed in the last 92 days. levels at approximately 33% with feedwater control on the bypass valves (BF40) until S/G pressure increases to 500 PSIG.

5.17 VERIFY that the Low Pressurizer Manually .

Pressure Safety Injection signal unblock if is automatically unblocked at necessary 1915 PSIG by checking TRAIN "A" (P-11) and TRAIN "B" Pressurizer Pressure SI-unblock pushbuttons energized 5.18 VERIFY the High Steam Flow Manually coincident with Low Stearnline unblock (P-12)

Pressure or Low-Low TAVE Safety Injection signal is automatically unb~ocked when the RCS temperature

  • -*---15 above 543°F by checking the TRAIN "A" and TRAIN "B" STEAMLINE PRESSURE

, SI UNBLOCK pushbuttons energized.

Salem Unit 2 16 Rev. 1

IOP-2

  • 5.19 When the RCS temperature is above 200°F (Mode 4) and normal operating pressure of 2235 PSIG is established, monitor the RCS Do not exceed the 1600 PSI Delta P limit between the RCS for leakage via the installed RCS and the Stearn Leak Detection System, per Generator.

Technical Specification Surveillance Requirement 4.4.6.2 A-E.

5.20 When the RCS temperature reaches If the Main 547°F warrnup of the Main Stearn System is Stearn Lines,rnay begin, if desired, unavailable, IAW OI III-2.3.1,Main, Reheat use .of the Turbine Bypass Steam Warrnup. atmospheric relief valves is authorized.

Use of the MSlO's requires close operator monitoring of the S/G pressure so that S/G Delta P

  • 5.21 When Stearn Generator Pressure inadvertent Safety Injection will not occur ..

is greater than 750 psig:

5. 21. l *-'PERFORM SP (0) 4. 0. 5-V-AF and SP(0)4.0.5-P-AF as required.

5.21.2 PERFORM SP(0)4.0.5-V-MD Sheet 4.5 if not performed in the last 92 days .

  • Salem Unit 2 17 Rev. 1
  • IOP~2
  • NOTE IF Recovering from a Reactor Trip; Form AD-16-A has to he completed, reviewed and approval granted before performing step
5. 22.

5.22 WITHDRAW the Shutdown Rod Banks.

5.22.l Monitor the Source Range Nuclear Instrumentation.

If the countrate increases by a factor of three(3) stop*

rod withdrawal. Reinsert the shutdown rods.

5.22.2 Shutdown Rod Withdrawal must be monitored by an ICRR IAW Reactor Engineer Manual Vol I Part 5. Notify the _Reactor Engineering Department.

5.23 If the unit is to be held in Hot Standby for greater than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ensure the Condensate System is

  • placed in Recirc thru the Condensate Polishing System IAW OI III-9.3.4.

5.24 Prior to entry into Mode 2,

. Check Off Sheet 3, must be completed.

6.0 FINAL CONDITIONS 6.1 RCS Temp @ 547° 6.2 RCS Press @ 2235 PSIG 6.3 Steam Gen. Level @ 33%

6.4 Shutdown Banks Withdrawn END OF PROCEDURE

  • Salem Unit 2 FINAL PAGE 18 Rev. 1

CHECK OFF SHEET 1 REQUIREMENTS FOR ENTERING MODE 4 REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 4.0.5-P-BA (ONE PUMP REQ)

PUMP 21 SHEET 4.1 OD 4.0.5-P-BA M PUMP 22 SHEET 4.1 OD 4.0.5-P-BA M

. 4.0.5-P-CC (TWO PUMPS REQ)

PUMP 21 SHEET 4.. 1 OD 4.0.5-P-CC M PUMP 22 SHEET 4. 1 OD 4.0.5-P-CC M PUMP 23 SHEET 4.1 OD 4.0.5-P-CC M 4.0.5-P-CH (ONE PUMP REQ)

PUMP 21 SHEET 4.1 OD 4.0.5-P-CH M PUMP 22 SHEET 4.1 OD 4.0.5-P-CH M 4.0.5-P-CV ( #21 & 22 PUMP REQ)

PUMP 21 SHEET 4.1 OD 4.0.5-P-CV M

.PUMP 22 SHEET 4.1 OD 4.0.5-P-CV M PUMP 23 SHEET 4. 1 OD 4.0.5-P-CV M 4.0.5-P-RH (BOTH PUMPS REQ)

PUMP 21 SHEET 4.1 OD 4.0.5-P-RH M PUMP 22 SHEET 4. 1 OD 4.0.5-P-RH M Salem Unit 2 MASlFR IOP 2-COS 1-1 Rev. 1

REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE

~

4.0.5-P-CS (BOTH PUMPS REQ)

PUMP 21 SHEET 4.1 OD 4.0.5-P-CS M PUMP 22 SHEET 4.l OD 4.0.5-P-CS M 4.0.5-P-SW HDR 1-21&23 or 22&23 HDR 2-2.5&24 or 26&24 PUMP 21 *sHEET 4.1 OD 4.0.5-P-SW M PUMP 22 SHEET 4.1 OD 4.0.5-P-SW M

.PUMP 23 SHEET 4.1 OD 4.0.5-P-SW M PUMP 24 SHEET 4.1 OD 4.0~5-P-SW. M PUMP 25 SHEET 4.1 OD 4.0.5-P-SW M PUMP 26 SHEET 4.1 OD 4.0.5-P-SW M 4.0.5-V-AF SHEET 4. 1 OD 4.0.5-V-AF Q SHEET 4.2 OD 4.0.5-V-AF Q SHEET 4.3 OD 4.0.5-V-AF Q 4.0.5-V-CC SHEET 4.1 OD 4.0.5-V-CC Q SHEET 4.2 OD. 4.0.5-V-CC Q Salem Unit 2 Ml\~Tt:Jl

.... .,,. .. _.. u -1111:11 IOP 2-COS 1-2 Rev . 1

REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 4.0.5-V-CC SHEE'.1' 4.3 OD 4.0.5-V-CC Q SHEET 4. *4 OD 4.0.5-V-CC Q 4.0.5-V-CS SHEET 4.1 OD 4.0.5-V-CS Q SHEET 4.2 OD 4.0.5-V-CS .Q SHEET 4.3 OD 4.0.5-V-CS Q SHEET 4~4 OD 4.0.5-V-CS Q 4.0.5-V-CV*

SHEET 4.1 OD 4.0.5-V-CV Q SHEET 4.2 OD 4.0.5-V-CV Q SHEET 4.3 OD 4.0.5-V-CV Q SHEET 4.4 OD 4.0.5-V-CV Q SHEET 4.5 OD 4.0.5-V-CV Q 4.0.5-V-RH SHEET 4. 1 OD 4.0.5-V-RH Q SHEET 4.2 OD 4.0.5-V-RH Q SHEET 4.3 OD 4.0.5-V-RH Q Salem Unit 2 IVlt\~\

- - -I~ N

-- IOP 2-COS 1-3 Rev. 1

REFERENCE TECHNICAL SPECIFICATION DEPT OPS 'PROCEDURE FREQ COMPLETION DATE SIGNATURE 4.0.5-V-RH SHEET 4.4 OD 4.0.5-V-RH Q 4.0.5-V-CONT SHEET 4.2 OD 4.0.5-V-CONT Q SHEET 4.3 OD 4.0.5-V-CONT Q SHEET 4.5 OD 4.0.5-V-CONT Q I

4.0.5-V-SJ SHEET 4.1 OD 4 .. 0. 5-V-SJ Q SHEET 4.2 OD 4.0.5-V-SJ Q SHEET 4.3 OD 4.0.5-V-SJ Q SHEET 4.4 *OD

  • 4. 0. 5-V-SJ Q
  • SHEET 4.5 OD 4.0.5-V-SJ Q I

4.0.5-V-SW SHEET 4.1 OD 4.0.5-V-SW Q SHEET 4.2 OD 4.0.5-V-SW

. Q SHEET 4.3 OD 4.0.5-V-SW Q SHE~T 4.4 OD 4.0.5-V-SW Q SHE~T 4.5 OD 4.0.5-V-SW Q ...

Salem Unit 2

\

I I

I r~1 a~ ~ l~.w

- - -- WI - -

r: Jl

~DI tl IOP 2-COS 1-4

,/

_,/Rev. 1

  • i I

REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 4.0.5-V-MISC SHEET 4.1 OD 4.0.5-V-MISC Q SHEET 4.2 OD 4.0.5-V-MISC Q SHEET 4.3 OD 4.0.5-V-MISC Q SHEET 4.4 OD 4.0.5"'.'V-MISC Q SHEET 4.5 OD 4.0.5-V-MISC Q 4.0.5-V-MAINT NOTE #1 OD 4.0.5-V-MAINT M NOTE #1 - This surveillance is SAT if no 4.0.5-V-MAINT Sheets are in file for testing .

. I Salem Unit 2

~1ASTER IOP 2-COS 1-5 Rev 1

REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 3.1.1.1 SHUTDOWN MARGIN DETERMINATION OD D 3.1.2.2 IBORON FLOW PATH OD SP(0)4.l.2.1A w OD SP (0) 4.1. 2. lB M OD SP (0) 4.1. 2. 2D R.

3.1.2.6 BORATED WATER SOURCES OD SP (0) 4.1. 2. 7A w 3.3.2 ENGINEERING SAFETY FEATURES OD SP (0) 4. 3. 2.1. lA R OD SP (0) 4. 3. 2.1. lB R OD SP (0) 4. 3. 2.1. lC R OD SP(0)4.3.2.l.1E-A. 620 OD SP(0)4.3.2.l.1E-B 62D OD SP ( 0) 4. 3. 2. 1. 3 R 3.3.3.6 FIRE DETECTION OD APPX B SA INSTRUMENTATION OD APPX M Q 3.4.1.3 RCP OPERABILITY OD SP (0) 4. 4.1. 2.1 w

  • Signature indicates that all items are Satisfactorily completed with the exception of those items which require RCS pressure to be greate~ than 1000 PSIG and/or the Main Turbine and SGFP to be latched, and/or items requi~ing all 4 RCPs to be in operation.

Salem Unit 2 IOP 2-COS 1-6 R8V l

REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 3.5.3 ECCS SUBSYSTEMS OD SP(0)4.5.2 B** M OD SP(0)4.5.2 c S/U OD 4.5.2 ATTACH 1 M OD SP(0)4.5.2 G R OD SP(0)4.5.2 H

  • 3.6.1.1 CONTAINMENT INTEGRITY OD SP (0) 4. 6. 1. 1 Al M OD SP ( 0) 4. 6. 1. 1 A2 Q 3.6.1.3 CONTAINMENT AIR LOCKS OD SP (0) 4. 6. 1. 3 c SA 3.6.1.7 CONTAINMENT VENTILATION OD SP ( 0) 4. 6. 1. 7 M 3.6.2.1 CONTAINMENT SPRAY OD SP(0)4.6.2.l A M 3.6.2.2 CONTAINMENT SPRAY ADDITIVE OD SP(0)4.6.2.l B R OD SP(0)4.6.2.2 B SA OD SP(0)4.6.2.2 D SY 3.6.3 CONTAINMENT ISOLATION VALVES OD SP (0) 4. 6. 3.1. 2 B R
  • A modification to the ECCS Subsystems require compliance with STS 4.5.2 H. Consult Operating Engin~er. If modification has occurred perform SP(0)4,5,2 H.
    • Requires the following to be operable: One Centrifugal Charging Pump, one RHR Pump, one RHR HX, an operable flow path to the pumps from RWST, and an operable Recirc Flow Path from the Contairw~nt Sump to the RHR System.

Salem Unit 2

. s*-"'- ~. IOP 2-COS 1-7 Rev. 1

REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 3.7.3 COMPONENT COOLING SYSTEM OD SP(0)4.7.3.l M 3.7.4 SERVICE WATER SYSTEM OD SP(0)4.7.4.l A M 3 ** 7. 6 CONTROL ROOM-EMERGENCY OD SP(0)4.7.6.1 A M AIR CONDITIONING OD SP(0)4.7.6.1 D2 R 3.7.7 AUX. BUILDING EXHAUST AIR FILTRATION OD SP(0)4.7.7.1 A M 3.7.10.l FIRE SUPPRESSION OD* SP(0)4.7.10.1.1Bl M OD* SP(0)4.7.10.1.1B2 M OD SP(0)4.7.10.1.l C M OD SP(0)4.7.10.l.1F2 R OD APPX - I y ..

OD SP (0) 4 *. 7. 10. 1. 1F3 R OD APPX - G 3Y 3.7.10.2 SPRINKLER SYSTEM OD APPX - p y OD APPX - Q R

  • on APPX - R 3Y 3.7.10.3 C02 System ' OD SP(0)4.7.10.3 M OD APPX - J R
  • This surveillance done by Unit #1. Verify it is current.

Salem Unit 2 IOP 2-COS 1-8 Rev. 1

~EFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE

3. 7 .. 10.4 FIRE HOSE STATIONS OD .APPX - E M OD APPX - F R 3.7.11 FIRE BARRIER DOORS OD APPX - K R FIRE BARRIER DAMPERS OD SP(0)4.7.11 R 3.8.1.1 ELECTRICAL POWER OD SP (0) 4. 8.1.1. lA w A.C. SOURCES OD SP (0) 4. 8.1.1. lB R 2A D/G OD. SP ( 0) 4. 8. 1. 1. 2
  • 2B D/G OD SP (0) 4. 8 *. 1.1. 2
  • 2C D/G OD SP ( 0) 4. 8. 1. 1. 2
  • 2A D/G * *OD SP(0)4.8.l.l.2Bl. R 2B D/G OD SP(0)4.8.1.l.2Bl R 2c* D/G OD SP(0)4.8.l.1.2Bl R STS 4.8.1.1.2 c OD SP(0)4.9.l.1.2 c lOY **
  • Fre q uenc y varies IAW Tech. s p ec. Tab e 4.8-1
    • Simultaneous start-up of all three Diesel Generators required after any modification which could affect Diesel Generator Interdependence. Consult Operating Engineer.

Perform SP(0)4.8.l.1.2 C if required.

0 Salem Unit 2 IOP 2-COS 1-9 Re 1

REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 3.8.2.1 AC DISTRIBUTION OD SP(0)4.8.2.1 w 3.8.2.3 125 D.C. DISTRIBUTION OD SP(0)4.8.2.3.1 w 3.8.2.5 28VOC DISTRIBUTION OD SP(0)4.8.2.5.1 w Salem Unit 2 IOP 2-COS 1-10 Rev. 1

REFERENCE TECHNICAL SPECIFICATION DEPT SIGNATURE DATE 3.3.2 Engineering Safety Features:

1. Channel Calibrations IC
2. Channel Functional Test IC

\

3. Time:Response Testing IC I

3.3.3.1 Radiation Monitoring ..

.**Instruiuentation IC ..Yl

/

\ ,/

3.4.7.1 RCS Leakage Detection ,~

Systems IC 3.1.2.6 Borated Water Sources CH 3.4.8 RCS Chemistry CH 3 .-4. 9 RCS specific Activity CH

./

3.6.2.2 Containment Spray Additive CH 3.7.1.4 Secondary System Activity CH 3.7.6 Control Room Emergency Air Conditioning CH

~.7.7 Aux Bldg Exhaust Air

Filtration CH Salem Unit 2 IOP 2-COS 1-11 Rev 1

REFERENCE TECHNICAL SPECIFICATION DEPT SIGNATURE DATE 3.7.10.1 Fire Suppression STS 4.7.10.1.2 B CH 3.8.1.1 Electrical Power A.C. Sources I STS 4.8.1.1.3 B CH 3.3.2 Engineering Safety Featur*es:

1. Channel Calibration MD
2. Channel Functional Test MD 3.4.6 Steam Generators MD 3.4.7.1 RCS Leakage Detection Systems MD 3~4.11.1 Structural Integrity MD 3.6.2.2 Containment Spray Additive STS 4.6.2.1 Dl MT 3.6.3 Containment Isolation Valves STS 4.6.3.1 MD 3.7.9 Snubbers MT 3.7.10.1 Fire Suppression STS 4.7.10.1.2 c . MD STS 4.7.10.1.3 MD 3.7.11 Fire Barrier Penetrations MD 3.8.1.1 Electrical Power

--*-- A.C. Sources STS 4.8.1.1.2 Cl .. ~ '"- ...- ...

MD Salem Unit 2 ' MAS

    • -- i l:K IOP 2-COS *1-12 Rev. 1

REFERENCE TECHNICAL SPECIFICATION DEPT SIGNATURE DATE 3.8.2.3 125V DC Distribution STS 4.8.2.3.2 MD 3.8.2.5 28V DC Distribution STS 4.8.2.5.2 MD 3.8.3.1 Electrical Equipment Protective Devices STS 4.8.3.1 MD 3.4.2.1 Pressurizer Safety Valves MT 3.6.1.1 Containment Air Lock STS 4.6.1.1 c MT STS ,4. 6. 1. 2 (A-D) MT STS 4.6.1.2 (F&G) MT STS 4.6.1.3 (B) MT

  • AIR LOCK LEAKAGE. TEST AT DESIGNED PRESSURE REQUIRED:

Prior to establishing Containment Integrity if opened when Integrity was not required or at least once per six months.

Salem Unit 2 MASTER IOP 2-COS 1-13 Rev. 1

  • 1. Verify control console readings taken for Modes 1-4 OPS LOG #3.

Senior Shift Supervisor/Shift Supervisor Date

2. No limiting conditions exist, such as being in an Action Statement, to prevent changing modes.

Senior Shift Supervisor/Shift Supervisor Date

3. All completion dates on the SP(O) 's are within the required frequency.

Senior Shift Supervisor/Shift Supervisor Date

4. Mode Change Sheet document reviewed prior to mode change .
  • 5.

Senior Shift Supervisor/Shift Supervisor Prior to changing modes:

Date 5.1 Change TRIS Operating Mode to the next intended mode (Menu 2 - F2) 5.2 Generate a Components In Off-Normal Position Report (Menu 3 - F2)

NOTE This report will indicate all components not in the required position for the intended mode.

5.3 Position all components as required for the mode change 5.4 Update TRIS using Change/Query Component Current Position (Menu 1 - Fl)

  • Salem Unit 2 IOP 2-COS 1-14
  • 5.5 I have complied with step 5, and all equipment required for changing modes is available.

Shift Supervisor/Senior Shift Supervisor Date

6. I have reviewed the Jumper L*og in the Senior Shi ft Supervisor's office and all equipment and instrumentation required for changing modes is av~ilable.

Shift Supervisor/Senior Shift Supervisor Date Maintenance Department Date I&C Department Date

  • . 7. ~enerate "Equipmant Unavailable List" from TRIS.

reviewed the Equipment Unavailabl~ List from TRIS I have All equipment required for changing modes is available Shift Supervisor/Senior Shift Supervisor Date

8. All design changes required to be completed prior to entry into Mode 4, have been completed.

Station Planning Engineer Date

  • Salem Unit 2 IOP 2-COS 1-15 Rev. 1

CHECK OFF SHEET 2 REQUIREMENTS FOR ENTERING MODE 3

~EFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 4.0.5-P-AF (BOTH PUMPS REQ)

PUMP 21 SHEET 4.1 OD 4.0.5-P-AF M PUMP 22 SHEET 4.1 OD 4.0.5-P-AF M

. 4.0.5-P-SJ (BOTH PUMPS REQ)

PUMP 21 SHEET 4.1 OD 4.0.5-P-SJ M PUMP 22 SHEET 4.1 OD 4.0.5-P-SJ M NOTE: When less than 312°F only one pump may be operable ----

4.0.5-V-MD SHEET 4.2 OD 4.0.5-V-MD S/U SHEET 4. 3 OD 4~0.5-V-MD Q SHEET 4.4 OD 4.0~5-V-MD S/U 3.3.2 Engineering Safety Features OD SP ( 0) 4. 3. 2. 1. 3 R*

3.3.3.5 Remote Shutqown Instrumentation OD SP(0)4.3.3.5 M 3.3.3.7 Post Accident I Instrumentation OD SP ( 0) 4. 3. 3. 7 M 3.4.1.2 RCP Operability OD SP (0) 4. 4. 1. 2. 1 w

3. 4. 4 Pressurizer Heaters OD SP ( 0) 4. 4. 4. 3 R
3. 5. 1 ECCS Accumulators OD SP(0)4.5.l B M OD SP (0) 4. 3. 2 .1. lA R
  • of 23 AFW Pump, 21-24 MS167 Salem Unit 2 IOP 2-COS 2-1 Rev. 1

REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE

. 3.5.2 ECCS Subsystems OD SP(0)4.5.2 B* M OD SP(0)4.5.2 D R 3.5.4.1 Boron Injection System OD SP(0)4.5.4.1 w 3.5.4.2 Heat Tracing OD SP(0)4.5.4.2 A M 3.6.2.3 Containment Cooling System FCU #21 OD SP(0)4.6.2.3A M FCU #22 OD SP(0)4.6.2.3A M FCU #23 OD SP(0)4.6.2.3A M FCU #24 OD SP(0)4.6.2.3A M FCU #25 OD SP(0)4.6.2.3A M t3.7.1.2 Auxiliary Feedwater OD SP(0)4.7.1.2A .M Pumps OD SP(0)4.7.1.2B** R OD SP(0)4.7.l._2C S/U 3.7.1.3 Aux. Feedwater Storage Tanks OD . SP ( 0) 4 . 7 . 1 . 3 . 4 . y Jerify Control Console Readings

.a ken for Mode 1-4 (Log #3) I OD
  • Two ECCS Flow Paths required.
    • SP(0)4.7.l.2B complete with exception of portion for 23 AFW Pump Salem Unit 2 MASTER. IOP 2-COS ~-2 Rev. 1

REFERENCE TECHNICAL SPECIFICATION DEPT SIGNATURE DATE 3.1.1.3 Moderator Temp i Coefficient *RE 3.3.2 ! Engineering Safety* Features i Channel Calibration IC Channel Functional Test IC 3.3.3.5 Remote Shutdown Instrumentation IC*

3.3.3.7 Post Accident Instrumentation IC 3.4.3 PORV Channel Calibration STS 4~4.5.1 IC 3.3.2 Engineering Safety Features Channel Calibration MD Channel Functional Test MD 3.3.3.7 Post Accid.ent Instrumentation MD 3.3.4 Turbine Over speed Protection STS 4.3.4.3 c MD 3.4.4 Pressurizer Heaters STS 4.4.4.2 . MD 3.4.3 Pressurizer Safety Valves MT 3.4.9 RCS Specific Activity CH

3. 5. 1 ECCS Accumulators STS 4.5.1 B CH 3.5.4.1 Boron Injection System STS 4.5.4.1 B (BIT) CH

.R Salem Unit 2 IOP 2-COS 2-3 Rev. 1

    • 1. Verify control console readings taken for Modes 1-4 OPS LOG #3.

Senior Shift Supervisor/Shift Supervisor Date

2. No limiting conditions exist, such a~ being in an Action Statement, to prevent changing modes.

Senior Shift Supervisor/Shift Supervisor Date

3. All completion dates on the SP(O) 's are within the required frequency.

Senior Shift Supervisor/Shift Supervisor Date

4. Mode Change Sheet document reviewed prior to mode change .
  • 5.

Senior Shift Supervisor/Shift Supervisor P~ior to changing modes:

Date 5.1 Change TRIS Operating Mode to the next intended mode (Menu 2- F2) 5.2 Generate a Components In Off-Normal Position Report (Menu 3 - F2)

NOTE This report will indicate all components not in the required position for the intended mode.

5.3 Position all components a required for the mode change 5.4 Update TRIS using Change/Query Component Current Position (Menu 1 - Fl)

  • Salem Unit 2 IOP 2-COS 2-4 MA~itR Rev. 1
  • 5.5 I have complied with the above and all equipment required for changing modes is available.

Shift Supervisor/Senior Shift Supervisor Date

6. I have reviewed the Jumper Log in the Senior Shift Supervisor's office and all equipment and instrumentation required for changing modes is available.

Shift Supervisor/Senior Shift Supervisor Date Maintenance Department Date

  • 7.

I&C Department Generate "Equipment Unavailable List" from TRIS Date I have reviewed th~ Equipment Unavailable List from TRIS All equipment required for changing modes is avqilable.

Shift Supervisor/Senior Shift Supervisor Date

8. All design changes required to be completed prior to entry into Mode 3, have been completed.

Station Planning Engineer Date

  • Salem Unit 2 IOP 2-COS 2-5 MAS1ER Rev. 1

CHECK OFF SHEET 3 REQUIREMENTS TO BE COMPLETED DURING MODE 3 REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 4.0.5-P-AF SHEET 4;1 PUMP 23 OD SP(0)4.0.5-P-AF M 4.0.5-V-MD Sheet 4.5 OD SP(0)4.0.5-V-MD Q 4.0.5-V-AF Sheet 4.3 OD SP(0)4.0.5-V-AF Q 4.0.5-V-MISC Sheet 4.1 OD SP(0)4.0.5-V-MISC Q 3.3.2 Engineering Safety Features OD SP(0)4.3.2.l.1E-A 62D OD SP(0)4.3.2.l.1E-B 620 OD SP(0)4.3.2.l.3 R***

3.4.7.2 RCS Operational OD SP(0)4.4.6.2 c M I

Leakage OD SP(0)4.4.7.2 D 72HRS 3.4.7.2 RCS Check Valve OD SP(0)4.4.7.2.2 R*

Testinq OD SP (0) 4. 4. 7. 2. 2 S/U f<*

3.7.1.2 Aux Feedwater Pumps OD SP(0)4.7.1.2B R 3.7.1.1 Stm Generator Safety Valves MT

~

3.1.3.3 Rod. Drop Times IC 3.1.3.2.2 Rod Position Indicators IC

  • If p lant has been in Cold Shutdown jor 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more , and if leaka g e testin g has not been performed in previous 9 months, SP(0)4.4.7.2.2 must be completed prior to entering Mode 2.
    • If RHR System was in service during shutdown, perfofm SP(0)4.4.7.2.2, sections on 21-24 SJ43, and 21-24 SJ56 valves within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering Mode 3.
      • All time response testing now complete with exception of 21-24 MS167 valves.

Reviewed By-,o----,.~--:o-:--:-=-~-,,--~~--,---~-,--,-~~~~~~~

Senior Shift Supervis?r/Shift Supervisor Salem Unit 2 COS 2-COS 3-1 Rev. 1

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