ML18087A743

Rev 1 to Hot Standby to Min Load.

ML18087A743
Person / Time
Site:	Salem
Issue date:	03/08/1983
From:	CONNOR B Public Service Enterprise Group
To:
Shared Package
ML18087A720	List: ML18087A719 ML18087A721 ML18087A722 ML18087A723 ML18087A724 ML18087A726 ML18087A727 ML18087A728 ML18087A729 ML18087A730 ML18087A732 ML18087A733 ML18087A734 ML18087A735 ML18087A736 ML18087A737 ML18087A738 ML18087A739 ML18087A740 ML18087A741 ML18087A742 ML18087A743 ML18087A745 ML18087A746 ML18087A747 ML18087A748 ML18087A749 ML18087A750 ML18087A751 ML18087A752 ML18087A753
References
IOP-3, NUDOCS 8303160603
Download: ML18087A743 (30)

Text

-,. SALEM GENERATING STATION

• OPERATIONS DEPARTMENT DOCUMENT APPROVAL COVER SHEET Title: Hot Standbv To.Minimum Load No.: IOP-3 Unit: 1 Rev.: 1 -**.**-* Remarks: 17 pages of text, 1 figure, 2 Check Off Sheets. Rev. 1 replaces Rev. 0. Changes *made; Step 4.5 was rewritten due -to -implementation of AD-16. Added step 5.11.2, 5.15.1 Last OTSC P-6. Safety Related Review (Ref. AD-13) : S/R yes x no A Author's Checklist Completed:

yes x Date 3/,/<('? I * * (2 )\t\ o..<...iW Date \0"1 \ SRO . -Ops. Eng. F );J Date 3fa/-63 SOS+ N\A <<... Date Ops. Mgr. :y !Vjf Date 3k/r?'3 . -** b fi Date ;;?4-53 QA J! , r.M **

Date. :3/?' ,/f3 SORC F / .. **

General Manager I /

• required for Sl?M documents only + required for EOP validation acceptance only ** required for safety related documents and fire

• protection documents MaSTFR il\6" .. -ii ' I MASTER Salem Unit 1/2 I AD-1-B-l Rev. 4 I 03160603 830314 ADOCK 05000272 I I PDR . . ---.........

-...

..........

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• *

• TERMINATION TIME COMPLETION TIME INTEGRATED OPERATIHG PROCEDURE IOP-3 HOT STANDBY TO MINIMUM LOAD DATE --------DATE DATE BY BY ---------------

1.0 PURPOSE

1.1 This instruction outlines the sequence in which systems are placed in service for a plant startup from Hot Standby (Mode 3) to Power Operation (Mode 1). Specific operating details and valve lineups are found in referenced 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 Shift Supervisor/Shift Supervisor shall retain this instruction until the*procedure is continued or terminated.

If this instructton is terminated prior to completion, the Senior Shift Supervisor/Shift Supervisor shall note the reason, time and. date of termination on this instruction.

The last completed IOP will be maintained in the Control Room file. 2. 1. 3 Criticality must be anticipated any time the. Control Rods are being withdrawn or boron dilution operations are in progress.

2.1.4 An Inverse Count Rate Ratio (ICRR) Plot shall be maintained during Control Rod withdrawal on a reactor startup when the estimated critical configuration differs from a known critical configuration by more than 650 PCM differential due to rods or a 1000 PCM differential due to Xenon. 2.1.5 Do not exceed a stable start up rate of one decade per minute . Salem Unit 1 1 MASlER Rev.

• 3.0

• Salem IOP-3 2.1.6 The critical position shall be no less than described in Technical Specification 3.1.3.5 and tigure 14 of the Reactor Engineering Manual. 2.1.7 In Modes 1 and 2, the Group Step Counters and Rod Position Indicators for that bank must be within +/-12.steps as specified by Technical Specification 3.1.3.2. 2.1.8 Refer to Emergency Plan Procedure, Part 4 for the appropriate event classification and reporting requirements.

2.2 EQUIPMENT

When changing the RCS boron concentration, sprays should be utilized to minimize the differential between pressurizer and loop boron concentration to less than 50 ppm by placing heaters in MANUAL-ON and leaving spray control in AUTO. 2.2.2 The pressurizer spray must not be used if the temperature between the pressurizer and the spray fluid is greater than 320F . 2.2.3 Reactor Coolant Pumps a. With less than 4 RCP's in service; be in Hot Standby within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. b. Power operation above P-7 is not permitted with less than 4 RCP's in service. ' c. The reactor should not be brought critical with less than 4 RCP's in service. 2.2.4 Stearn Generator pH must be maintained between 8.5 and 9.2. Steam Generator Blowdown after the ion exchange conductivity must be less than .8 rnicrornhos.

If unable to achieve chemistry specifications, refer to EI-I-4.21, "Condenser Tube Leak," Table 1. ATTACHMENTS LIST 3.1 Figures 3 .1. 1 Figure 1 -Feedwater Differential Pressure vs. Total Feedwater Flow Unit 1 2 Rev.

• I

• I I

• IOP-3 3.2 Tables None 3.3 Check Off Sheets 3.3.l Check Off Sheet 1 -Requirements to Enter Mode 2 3.3.2 Check Off Sheet 2 -Requirements to Enter Mode 1 4.0 PREREQUISITES NOTE Initial each step after completion 4.1 The plant is in the Hot Standby Mode IAW IOP-2 "Cold Shutdown to Hot Standby." 4.2 The Full Length Control Rods are inserted; the.Shutdown Banks are fully withdrawn.

4.3 4.4 4.5 Final inspection and closure of the containment has been made and signed off IAW SP(0)4.5.2(c), ECCS Subsystems and SP(0)4.6.1.3(a),

Systems -Air Locks. Containment integrity is established.

Permission has been granted to take the Reactor Critical, in accordance with AD-16 "Post Reactor Trip/ Safety Injection Review and Unit Startup Approval Requirements" section 4.0 -Approval Requirements for Reactor Startup. *

• 4.6 The estimated critical boron concentration for the desired critical control rod bank position has been determined, IAW Reactor Engineering Manual, Part I . Salem Unit 1 3 MASTER Rev.

• **

• 4.7 Check Off Sheet 1, Requirements to Enter Mode 2 has been reviewed and signed by the Senior Shift Supervisor.

4.7.1 PERFORM

SP(0)4.3.l.l.l Instrumentation-Reactor Trip Breakers if not done in last 7 days (satisfies item 1 of STS Table 4.3-1) 4.7.2 VERIFY IC Department Weekly Surveillances are current to satisfy item 5; 6, 18 and 21 Salem Unit 1 of Tech Spec Surv 4.3.1.1.1 Table 4.3-1 (COSl-2 IC Sign Off) . 4 IOP-3 IF st:artup is being made to recover from a reactor trip and: 1. Control Rod withdrawal is started within *24 hours of the trip AND 2. RCS temperature has not decreased below 500°F since the trip occurred AND 3. The cause of the trip is known and corr.ected.

Then Check Off Sheet is not required.

Rev. J

• *

• 4.8 All RCP's are in service. 4.9-Both Source Range Channels are operable.

4.10 Prior to starting the Main Feedwater System, permission must be obtained from the Chemistry Department to feed the Stearn Generator from the Condenser hotwells.

5.0 PROCEDURE

NOTE Initial the indicated steps after completion.

5.1 ADJUST

the RCS boron concentration to the Estimated Critical Boron Concentratioh IAWi OI II-3.3.6 Boron Concentration Control. 5.2 DEFEAT the Source Range HIGH FLUX AT SHUTDOWN ALARM and verify the .SR HIGH FLUX AT SHUTDOWN BLOCKED annunciator alarm energizes.

5.3 With 15 minutes prior to withdrawal of any Control Rod Bank, DETERMINE that each Shutdown Rod is fully withdrawn . Tech Spec 3.4.1.1 Tech Spec 3. 3. 1 IOP-3 If the plant is being restarted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after last shutdown, due to either a reactor trip or a controlled shutdown, and the plant "chemistry was within specifications at the time of the shutdown, Chemistry Department permission is not required . Block switches are on NIS rack. Tech Spec 4.l.3.4(a)

Salem Unit 1 I 5 Rev.

• *

• 5.4 MAKE the following announcement twice on the plant PA-System. "ATTENTION ALL PERSONNEL", Commencing Unit #1 Reactor Startup. 5.5 Within 15 minutes prior to Criticality, VERIFY RCS Tavg to be greater than or equal to 541°F. 5.6 SELECT both Source Range Channels on the recorder for the Nuclear Instrumentation System until the Intermediate Range is approached.

At this time one pen must be switched to an Intermediate Range Channel. 5.7 OBTAIN APPROVAL of the Senior Shift Supervisor and withdraw the Control Rod Banks in Manual and begin the approach to Criticality.

5.7.1 MONITOR

Nuclear Instrumentation and expect Criticality at any time. 5.8 STOP Rod Withdrawal at every 50 steps and check for proper Rod Alignment (individual rod position indicators versus step counters) and overlap. 5.8.1 If an ICRR is required, PLOT the Count Rate versus rod position at every 50 step stop point . Salem Unit 1 6 Tech Spec 4.1.1.5(a)

IOP-3 The licensed operator making the startup mav at his discretion, use the NR-45 recorder differently, as required by the situation.

Rev. J

• *

• 5.9 *IF any of the following conditions occur while trying to achieve criticality, PROCEED as specified.

5.9.1 The Bank height at Criticality is below the Rod Insertion Limit for zero power. a. NOTIFY the Senior Shift Supervisor/Shift Supervisor.

b. INSERT all control rod banks. c. CALCULATE a Shutdown margin d. RECALCULATE the ECP e. DETERMINE AND CORRECT the error 5.9.2 The Control Bank height at Criticality is 500 PCM the ECP but above the Rod Insertion limit. a. NOTIFY the Senior Shift Supervisor/Shift Supervisor.

b. INSERT all Control Rod Banks . IOP-3 A detailed description should be entered in Operations Log #1 and all copies of the ECP shall be retained.

The Operations Manager or Operating Engineer should be notified and an Incident Report should be in,itiated.

'I'ech Spe.c 3.1.1.l Salem Unit 1 7 MASTER. Rev. 1

• *

• c. RECALCULATE the ECP d. DETERMINE AND CORRECT the error 5.9.3 Criticality has not been achieved with the rods withdrawn to an equivalent of 500 PCM past the ECP. a. NOTIFY the Senior Shift Supervisor/Shift Supervisor.

b. INSERT control banks the position for 500 PCM below criticality

c. RECALCULATE the ECP d. DETERMINE AND CORRECT the error. If no error was 1. 2. 3. 4. *found, REQUEST confirming boron sample NOTIFY Reactor Engineering FULLY INSERT all control rod banks PULL rods for criticality using an ICCR plot 5.10 When the P-6 (Source Range Permissive) light is energized, BLOCK the Source Range High Flux Trip by depressing both BLOCK SOURCE RANGE "A" and BLOCK SOURCE RANGE "B" pushbuttons on the console. 5.10.1 VERIFY the Source Range Trains A&B TRIP BLOCKED light on RP4 and the SR Detector Voltage Trouble Overhead Annunciator alarm are energized . IOP-3 MarkN/A the steps not required.

Salem Unit 1 8 MASTER Rev. J

• *

• 5. 10. 2

• When P-6 is exceeded and the Source Range Channels are the Becond Pen should be switched to the other Range Channel. \ 5.11 LEVEL off the Reactor Neutron level at lXl0-8 amps in the Intermediate Range.

VERIFY Critical Rod Position is not less than the limits of Tech Spec 3.1.3.5 and 14 of the Reactor Engineering Manual within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of achieving criticality.

5.11.2 UPDATE TRIS; change from Mode 3 to Mode 2. 5.12 COMPLEJTE the ECP FORM. 5.13 INCREASE Reactor Power to 1% to 2% and complete the following:

5.13.1 COMPLETE warmup of the Main Steam System by performing the following:

a. Check Off Sheet 4.1 OI Irr-2.3.1 Main Steam b. Check Off Sheet 4.2 or rrr-2.3.1 Reheat Steam c. Check Off Sheet 4.3 or rrr-2.3.l Reheat Drains d. OPEN OR CYCLE the Warm Up Valves, ll-14MS18, to maintain RCS temperature constant.

• • --*-----* ------1. During warmup of Steam System, FEED the steam generators as necessary to maintain their normal no load level . Salem Unit 1 9 MA S TEP ** I

• t 'it IOP-3 Rev. 1

• *

• Salem Unit 1 e. OPEN the following:

1. Drain valves11-14MS7 2. Drain valves 11&12MS26

f. When less than 50 PSID between steam generator and lines downstream of stop valves, OPEN steam generator stop valves, ll-14MS167. . g. VERIFY 11-14MS18's are open, then VERIFY ll-14MS167's valve closure times are less than 5 seconds. PERFORM SP(0)4.7.1.5 if not performed in last 9.2 days. h. CLOSE the following:

1. Warmup Valves ll-14MS18

2. Drain Valves11-14MS7 3. Drain Valves 11&12MS26

i. PERFORM SP(0)4.0.5-V-MISC Check Off Sheet 4.1 Page 3 of 3 if not performed in the previous 92 days. j. SECURE Condensate System Recirc Flow IAW OI III-9.3.4 Placing Condensate System in Recirc for Cleanup . Tech Spec 4.7.1.5 IOP-3 10 MASTER Rev. 1

• *

• k. OBTAIN PERMISSION from Chemistry Department to feed Steam Generators from the Condenser hotwells.

1. BEGIN Feed Pump Turbine Warmup IAW OI III-9.3.2 Feed Pump Operation

• m. CHANGE Sealing Steam over to #1 or #2 Unit Main Steam IAW OI III-4.3.1.

Turbine Gland Sealing Steam Normal Operation.

n. ESTABLISH S/G Blowdown IAW OI III-13.3.2 Steam Generator Blowdown Normal Operation.

o. OPEN 11-14 MS167 5.14 Prior to exceeding 5% Power, ENSURE Check Off Sheet 2 Requirements to Enter Mode 1 has been completed and signed off by the Senior Shift Supervisor.

Salem Unit 1 11 IOP-3 If the plant is being restarted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the last shutdown, due to either a reactor trip or a controlled shutdown and the plant chemistry was within specifications at the time of shutdown, Chemistry Department permission is not required.

Chemistry Department shall specify the amount of blowdown.

Check Off Sheet 2 is not required when the Startup is being made to recover from a reactor trip and: Rev. 1

• • *

• 5.15 INCREASE Reactor power to 8%

When Reactor power is greater than 5% power UPDATE TRIS; change from Mode 2 to Mode 1. 5.16 MAINTAIN Steam Generator water level with the Auxiliary Feed System. 5.16.1 COORDINATE all changes in feed water or steam flow with the reactor while rod control is in manual . Salem Unit 1 12 IOP-3 1. Control Rod Withdrawal is started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the trip AND 2. RCS __ temperature has not dropped below 500°F, since the trip AND 3. The cause of the trip is known and corrected.

Remain below P-10 for turbine roll. At this point Steam Generator Level Control becomes very critical sudden increases or decreases in feedwater or steam flow are to be avoided. MASTER Rev. 1 __ -_* ._*-*_._,._-,__.:-**_*

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• • --* -* ----.-.---*---. -

___ ___:____:..:...._-'-__:_

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___ .;..._ ____________

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--! 5.17 PLACE Main Feed System in service IAW OI III-9.3.2 Feed Pump Operation.

5.18 Once Steam Generator Feedwater Control Valves are in automatic and controlling S/G level adequately, ALIGN the AFWS for power operation as follows: 5.18.1 OPEN OR CHECK OPEN ll-14AF11 SG AF level control valves Update TRIS 5.18.2 VERIFY that the Auxiliary Feed System Controls are adjusted to conform to the standby conditions IAW OI III-10.3.1, Auxiliary Feedwater System Operation.

5.19 PLACE the Turbine Generator on the line IAW OI III-1.3.1 Turbine Generator Operation.

5.20 INCREASE Turbine load until the steam dump valves have fully closed. 5.21 NOTIFY the .Load Dispatcher that the unit has been synchronized.

5.22 CONTINUE INCREASING Turbine Load while maintaining TAVE at the programmed value .. 5.23 VERIFY that permissive P-10 signals have*actuated (P-10 light energized) then _perform the following:

5.23.1 MANUALLY BLOCK Intermediate Range A&B low power trips by depressing both BLOCK IR "A" and BLOCK IR "B" pushbuttons on the console. IOP-3 2/4 Power Range greater than 10.% Salem Unit 1 13 MASTER Rev. 1 5.23.2. MANUALLY BLOCK Power Range "A" and Power Range "B" Low Power trips by depressing both BLOCK PWR RANGE "A" and BLOCK PWR RANGE "B" pushbuttons on the console. 5.24 VERIFY that Permissive Signal P-7 has actuated (below P-7 light de-energized) . 5.25 If manual MSR control is to be used, BEGIN WARMUP of the MSR's I.AW OI III-2.3.3, Moisture Separator Reheaters Manual Operation.

5.26 When the P-2 Interlock has been actuated, ADJUST TAVE to within +/- 1°F of TREF and PLACE Rod Control System in AUTO. IOP-3 This makes the following

• reactor trips operable.

A. Pressurizer Low Pressure B. Pressurizer High Water Level c. Loss of Two Lpop Logic D. Turbine Trip *p-7 Setpoint greater than 10% Power Reactor Power (2/ 4) or TURB PWR ( 1 / 2) Turbine Power greater-than 15% Salem Unit 1 l 4a ASTER Rev. 1 5.27 ALIGN Steam Dump Valves for Power Operations as follows: 5.27.1 ENSURE the Loss of Load Interlock is reset by pushing the Reset Load Rejection pushbutton and observing the Turbine Impulse Chamber Pressure Permissive light on the Status Panel is out. 5.27.2 PLACE the Steam Dump.Valve Controller in Average Temp. Cont. Mode. 5.27.3 VERIFY that the Block Cooldown and the* Block Non-Cooldown lights are On. 5.28 PERFORM the following to place the Steam Generator Feed Pump Speed Controls to Automatic.

5.28.1 MANUALLY ADJUST the Master Controller Speed Demand to match the speed of .the pump 5.28.2 PLACE the Feed Pump Individual Controller in AUTO. 5.28.3 ADJUST the Speed Demand of the Master.Controller to maintain proper dp shown on Figure No. 1. 5.28.4 PLACE the Master Controller in AUTO. IOP-3 0-100% of the Master Controller is equal to 1100-5550 RPM on the individual pump controller.

Salem Unit 1 *15 MASTER Rev. 1

\ \ \ \ 5.29 At approximately 20%

VERIFY the steam generator pH between 8.5-9.2 and steam generator blowdown after the ion exchanger conductivity is less than .8 micromhos.

a. If recorders indicate an out of specification condition, NOTIFY the Chemistry Department to verify by analysis.

b. If an out of specification condition is verified, REFER to EI-I-4.21 Condenser Tube Leak. c. If* analysis .indicates faulty control room indication, ENSURE analysis is performed every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 5.3Q SELECT IMP in Mode on the E/H Control Panel. 5.31 RESET Auxiliary Power Transformer Isolation Trip_. 5.32 TRANSFER the Group Buses from the Station Power Transformer to the Auxiliary Power Transformer by selecting on the Mimic Panel

• and closing the following breakers:

5.32.1 lAHGD CLOSED 5.32.2 lAEGD CLOSED 5.32.3 lBFGD CLOSED 5.32.4 lBGGD CLOSED 5.33 VERIFY the Station Power Breaker open. UPDATE TRIS for steps 5.32 and 5.33 5.34 NOTIFY the Load Dispatcher that the unit is ready for additional load. -*---Salem Unit 1 16 IOP-3 Reset pushbutton on console. Rev. 1 IOP-3 6.0 FINAL CONDITIONS 6.1 The 4KV Group Buses are being supplied by the Auxiliary Power Transformer.

6.2 The generator is synchronized and is supplying the grid. END OF PROCEDURE FINAL PAGE Salem Unit 1 17 AS'lER Rev. 1 200 175 150 125 FW Press 100 . vs S/G d/p 75 (psi l 50 25 *Salem Unit 1 FIGURE 1 FEEDWATER DIFFERENTIAL PRESSURE 2 4 vs TOTAL FEEDWATER FLOW 6 I I I J 8 10 12 14 16 IOP-3 14.44=100%

stm./feed flow TOTAL FEED FLOW (XlOE6 lbs/hr) IOP 3-FIG 1-1 Rev. 1

1.0 TECHNICAL

SPECIFICATIONS CHECK OFF SHEET 1 REQUIREMENTS TO ENTER MODE 2 REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ 3.1.3.l Rod Control Assemblies OD SP(0)4.l.3.l.2 M 3.3.1.l Reactor Trip OD SP (0) 4. 3. 1.1. 1 w Instrumentation OD SP (0) 4. 3. 2.1. lA R Verify Control Console Prior Readings taken for Complete to Modes 1-4 OD Ops Log #3 Mode 3.3.1.l Reactr)r Trip Instr,1mentation Channel Calibration RE 3.3.1.l Reactor Trip Instrumentation Channel Calibration MD Channel Functional Test MD 3.6.4.2 Hydrogen Re combiners MD Salem Unit 1 IOP-3-COSl-l

• *

• COMPLETION DATE SIGNATURE 2 MASTER Rev. 1 *

• 1. 0 TECHNICAL SPECIFICATIONS REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 3.3.1.l Reactor Trip Instrumentation Channel Calibration IC Channel Functional Test IC* 3.6.4.1 Hydrogen Analyzers CH * *lA. Items 5,6,18 and 21 of Tech. Spec. Surveillance*Requirement 4.3.1.1 (Table 4.3.1) .must have been completed within seven days of the Reactor Startup. All design changes required to be completed prior to entry into Mode 2 have been completed.

Date Station Planning Engineer Reviewed By Senior Shift Supervisor MASTER Salem Unit 1 IOP-3-COSl-2 Rev. 1 * * *

• 2.0 Prior to changing modes: 2.1 Change TRIS Operating Mode to the next intended mode {Menu 2-F2) 2.2 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. 2.3 Position all components as required for the mode change. 2.4 Update TRIS using Change/Query Component Current Position {Menu 2-Fl) 2.5 I have *complied with steps 2.1-2.4, and all equipment required for changing modes is available.

DATE Shift Supervisor/Senior Shift Supervisor

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

DATE Shift Supervisor/Senior Shift Supervi9or DATE Maintenance Department DATE I&C Department

4.0 Generate

"Equipment Unavailable List" from TRIS 3: I have reviewed the Equipment Unavailable list from TRIS All equipment required for changing modes is available

):D DATE

• Shift Supervisor/Senior Shift Supervisor

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f ::a Salem Unit 1 IOP 3-COS 1-3 Rev. 1

1.0 TECHNICAL

SPECIFICATIONS CHECK OFF SHEET 2 REQUIREMENTS TO ENTER MODE 1 !REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE

!FREQ* 3.7.1.5 Mn. Stm Stop Valves OD SP (0) 4. 7. 1. 5 S/U 4.0.5-V-MISC SHEET 4.1 PAGE 3 OD SP(0)4.0.5-V-MISC Q 3.1.3.1 Rod Control Assemblies OD *sP (O) 4.1. 3. i. 2 M 3.3.2.l Engineer Safety OD SP (O) 4. 3. 2. 1. lD R I Features OD SP (0) 4. 3. 2. 1. 3 *R Verify Control Console* Prior Readings taken for Modes OD Complete to 1-4 Ops Log #3 Mode 3.2.2 Hot Channel Factor Heat Flux STS 4.2.2.2 RE i ./ i STS 4.2.2.3 RE ' '. 3.2.3 Hot Chanrlel Enthalpy i STS 4.2.3.1 RE STS 4.2.3.2 RE 3.2.5 D N B Parameters STS 4.2.5.2 RE MASTER ! Salem Unit 1 IOP 3-COS 2-1 . I COMPLETION DATE SIGNATURE 1 I .;;}' *' , ,,,.,,,....,-

... * ..-Rev. 1

1.0 TECHNICAL

SPECIFICATIONS REFERENCE TECHNICAL SPECIFICATION DEPT OPS PROCEDURE FREQ COMPLETION DATE SIGNATURE 3.3.1.1 Reactor Trip Instrumentation Channel Calibration MD' Channel Functional Test MD 3.3.1.1 Reactor Trip Instrumentation Channel Calbiration IC Channel Functional Test IC Reviewed By Senior Shift Supervisor DATE *lA All design changes required to be completed prior to entry into Mode 1, have been completed.

Date Station Planning Engineer MASTER Salem Unit 1

• IOP 3-COS 2-2 * *

• L__ _________________________________ -----------------'----------------

2.0 Prior

to changing modes: 2.1 Change TRIS Operating Mode to the next .intended mode (Menu 2-F2) 2.2 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. 2.3 Position all components as required for the mode change. 2.4 Update TRIS using Change/Query Component Current Position (Menu 2-Fl) 2.5 I have complied with steps 2.1-2.4, and all equipment required for changing modes is available.

DATE Shift Supervisor/Senior Shift Supervisor 3.0 I have reviewed the Jumper Log in the Senior Shift Supervisor's office and all equipment and instrumentation required for changing modes is available.

DATE Shift Supervisor/Senior Shift Supervisor DATE ----Maintenance Department DATE I&C Dep.artment

4.0 Generate

"Equipment Unavailable List" from TRIS I have reviewed the Equipment Unavailable List from TRIS All equipment required for changing modes is available DATE Shift Supervisor/Senior Shift Supervisor Salem Unit 1 IOP 3-COS 2-3 MASTtt\ Rev. 1

• *

• Appendix F Administrative Directives AD-13, Independent Review of Operations Department Documents AD-16, Post Reactor Trip/Safety Injection Review . ; 'l ;

• . ... -"'*---'* *. , . -..:..*-------------------------------------------------------------------------, SALEM GENERATING STATION OPERATIONS DEPARTMENT DOCUMENT APPROVAL COVER SHEET Title: Independent Review of Operations Department Documents

____________________________________

...;;.. ______________________ No.: AD-13 Unit: 1/2 Rev.: 4 ----------

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Remarks: three pages of text, no forms, revised page 3 -ODM ------------------------------------------------------------

table Safety Related Review (Ref. AD-13): S/R yes ___ _ Author's Checklist Completed:

yes _ __.x......__

Author SRO * ,,.sAf fJil j Ops.

___ _ Ops. Mgr. _____________

......, ___________________________

_ SORC *

• jt '1V4.5 ** _J General Manager

• required for SPM documents only ** required for safety related documents only Salem Unit 1/2 AD-1-B-l no_ ..... x ____ _ no ----Date 3 -¥2-Date Date Date Date 1J<1-'3-<fr.1..-

Date Date I Rev. 2 .._ ____________________________

...,.._....

___ ..,,_,,;;;::

• . *-=\

ADMINISTRATIVE DIRECTIVE

-13 INDEPENDENT REVIEW OF OPERATIONS DEPARTMENT DOCUMENTS Regulatory guides from various agencies have established a need to have an independent review performed of nuclear power plant procedures.

This independent review has been established only for safety related procedures.

Public Service Electric an.d Gas has committed to these guides in order to get a construction permit and later an operating license for Salem. These independent reviewers have been defined to be the Station Operations Review Committee (SORC) and the Station Quality Assurance Engineer {SQAE). The following depicts the regulatory sequence that has established the two groups as independent reviewers.

ANSI 18.7 NRC Reg. Guide 1.33 FSAR section D.5-14 Tech Spec section 6.5.1 AP-4 10CFR50 App B & ANSI 45.2 Corporate QA Policy Salem Unit 1/2 SORC 1 established and defined the need for and of an independent reviewer defined safety related procedures stated safety related procedures shall be reviewed by SORC further defined SORC requirements, very similar wording to ANSI 18.7 Administrative Procedure established SORC requirements for station established general criteria for QA program required for licenses of 1;SE&G that lS I Rev. 4

_-. ..

/ I AD-13

• FSAR section D.5-14 AP-17 (now deleted) and Quality Assurance Instructions (QAI's) required before licenses stated safety related procedures shall be reviewed by SQAE established tion QA program using Corporate QA as reference The following is a list of the Operations Department documents that have been be safety related and therefore, shall be sent to SORC and the SQAE for review prior to implementation.

Any document not contained in this list shall be reviewed by the author to determine the safety related status, using Reg. Guide 1.33 as a reference.

If document is determined to be safety related it shall be added to this list. Station Plant Manual (SPM) VOLUME II VOLUME III VOLUME IV. VOLUME V Salem Unit 1/2 UNIT 1 ALL* ALL or III-1. 3.1 QI III-1. 3. 2 OI III-1. 3. 3 QI III-1. 3. 5 or III-1.3.7 OI III-2.3.1 or III-2.3.4 QI III-7.3.2 or III-9.3.1 OI III-9.3.2 OI III-9.3.3 QI III-10.3.1 or III-11. 3.1 OI III-11. 3. 2 QI III-13.3.1 QI III-13.3.2 or III-15.3.1 QI IV-1. 3 .1 or rv-3.3.1 UNIT 2 ALL ALL same as Unit 1 same except delete: 'IV-4.3.6 2 MASTER I Rev. 4

,*

• VOLUME VI VOLUME VII or rv-4.3.1 OIIV-4.3.2 or IV-4.3.4 OI IV-4.3.6 or rv-s.3.1 or rv-s.3.2 or rv-s.3.3 OI IV-6.3.1 or rv-8.3.1 or rv-10.3.1 OI IV-11.3.1 OI IV-11. 3. 2 or rv-11. 3. 3 QI IV-12.3.1 or rv-12.3.2 OI IV-16.3.1 OI V-1. 3.1 or v-3.3.1 or v-3.3.2 QI V-3.3.3 i-or v-3.3.4 QI V-4.3.1 OI V-5.3.1 or v-s.3.2 or v-9.3.1 OI V-13.3.1 OI V-15.3.2 Annunciator A-K Console Back Panels

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... *** ,._ .. : ..... IV-11. 3 .-3 IV-12.3.1 V-5.3.2 V-13.3.1 V-15.3.2

• AD-13 Add: IV-4 ... 3.5 same Auxilary Annunciator Local Panels ALL ALL OPERATIONS DEPARTMENT MANUAL (ODM) OD-3 OD-8 OD-9 OD-10 OD-11 OD-12 OD-13 OD-15 OD-18 OD-20 OD-28 Salem Unit 1/2 OD-29 OD-33 OD-36 OD-37 OD-38 OD-40 OD-41 OD-42 OD-43 END OF PROCEDURE FINAL PAGE 3 OD-44 OD-45 OD-46 OD-47 oD-so* OD-51 OD-52 OD-55 OD-62 MASTER I Rev. 4