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Operating Procedure 1102-11,Revision 21, Plant Cooldown.
	ML19209B636
Person / Time
Site:	Three Mile Island
Issue date:	09/06/1979
From:	; METROPOLITAN EDISON CO.
To:	;
References
	1102-11, NUDOCS 7910100258
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  >                                                                                                       Revision 21 09/06/79 THREE MILE ISLAND NUCLEAR STATION                                               l      i UNIT #1 OPERATING PROCEDURE 1102-11 PLANT C00LDOWN yN'] -]

Table of Effective Pages CONTROLLED COPY Pace Date Revision Pace Date Revision Pace Date R evision 1.0 06/23/76 11 2.0 05/17/78 17 3.0 07/07/79 20 4.0 09/06/79 21 5.0 09/06/79 21 6.0 09/06/79 21 7.0 09/06/79 21 8.0 09/06/79 21 9.0 09/06/79 21 10.0 09/06/79 21 11.0 09/0s/79 21 12.0 09/06/79 ' 21 - 13.0 09/06/79 21 14.0 09/06/79 21 15.0 07/07/79 20 16.0 07/07/79 20 17.0 07/07/79 20 , 18.0 07/07/79 20 Unit 1 Staff Recommend Approval Unit 2 Staff Recommends Approval Approval Date Approval Date Cognizant dapt.hised Ccgr/zaltlD6pt.\Head Unit 1 P RC Recommends Approval Unit 2 PORC Recom n Approval

           \                                Date S/77
                                                                                         /                 Date s/ Chairrnen of PORC                                             Chairmin of'P0h C' Unit 1 Superintendent Approval                                 Unit 2 Superintendent         roval u        ,>   f      x    .9-/      Date         '

79 Date f' d* '/ LI SUPERVISOR OUALITY CONTROL N Date - TMt $$ A AewAr/7 7910100 cl N 1123 !46 jJ

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    '                                                                 1102-11 Revision 11 06/23/76 THREE MILE ISLAND NUCLEAR STATION UNIT #1 OPERATING PROCEDURE #1102-11 PLANT C00LDOWN TABLE OF CONTENTS 11.1   References 11.1.1 Drawings 11.1.2 Applicable Operating Procedures 11.1.3 Curves. Tables 11.2    Limits and Precautions 11.2.1  Equipment 11.2.2  Administrative 11.3    Operating Procedure 11.3.1  Prerequisites for Cooldown 11.3.2  Cooldown Procedure -

1.0 1 1 <^. 3 ! 4 7

1102-11 Revision 17 05/17/78 11.1 References 11.1.1 Drawings

1. Reactor Coolant System, GAI-C-302-650; B&W 27617F

2. Makeup and Purification System GAI-C-302-60/661; B&W 27551F

3. Decay Heat Removal System GAH-C-302-640; B&W 27554F

4. RCP Motor Process & Inst. B&W-20702F 11.1.2 Applicable Operating Procedures

1. OP-1103-5 Pressurizer Operation

2. OP-1103-6 Reactor Coolant Pump Operation

3. OP-1104-4 Decay Heat Removal Operation 4 OP-1202-16 R.C. Pump & Motor Emergencies

5. OP-1104-2 Makeup and Purification Operation

6. OP-1105-2 Reactor Protection System

7. OP-1106-5 Turbine Bypass Operation

8. OP-1102-13 Decay Heat Removal by OTSG

9. OP-1106-16 OTSG Secondary Fill, Drain and Layup

10. OP-1101 Plant Limits and Precautions 11.1.3 Curves

1. Figure 1 Heat-Up and Cooldown Limitations - Wide Range

2. Figure 1 A Heat-Up and Cooldown Limitations - Narrow Range

3. Figure 2 OTSG Level Control

4. Figure 3 Boron Shutdown Curve 11.2 Limits & Precautions CAUTION: If plant cooldown is in preparation.for the refueling I outage, RCS boration should be in progress towards the refueling boron concentration. DO NOT FLOOD THE FEEDWATER !

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1102-11

 .-                                                                         Revision 20 07/07/79 N0ZZLES UNTIL the RCS boron concentration is greater than the cold shutdown boron concentration on Figure 3.

Regard all other sections of the following plant cooldown procedure. 11.2.1 Equipment

1. Reactor Coolant Temperature, Pressure and Cooldown Rates-shall be maintained within limits specified in Figure 1.

2. Pressurizer Maximum Cooldown Rate is 100U F in any one hour.

3. The pressurizer to loop differential temperature shall be maintained less than 410UF.

4. Secondary side of the steam generator shall not be pres-surized above 200 PSIG if the temperature of the steam U

generator shell is below 100 F.

5. Seal water injection flow is required to all reactor coolant pumps when reactor coolant temperature is above 190U F and pressure is above 100 PSIG.

6. During cooldown and depressurization, the number one seal bypass valve should remain closed unless RCP bearing temperature (seal inlet temp.) or #1 seal leak-off temperature approaches their alarm levels. It should only be used then if #1 seal leakoff is < 1 gpm and RCS pressure is <

1000 psig. Do not open #1 seal bypass unless #1 leak off valve is open. [

7. Do not operate RCP with less than .2 GPM seal leak off.

8. The DHR cooler t2T shall not exceed 200 F between inlet and outlet shell.

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1102-11 Revision 21 09/06/79

9. Af ter borating to 5% AK/K subcritical at 532 F, fill the OTSG's and maintain the main feedwater nozzles submerged.

At the same time, open the bypass line around the feedwater control valves (FW-V85A/B), and control OTSG level by the lower tubesheet drains (FW-V-86A/B), OR by opening turbine bypass valves as necessary to lower 0TSG level.

10. Borate to the 70 0F,1% aK/K shutdown concentration prior to cooling down below 525 F.

11. When cooling down the Reactor Coolant System under other than normal conditions (normal - two operating OTSG's),

the maximum allowable temperature difference between the average OTSG shell and its associated reactor coolant loop average temperature is 100U F.

12. If either RC-V2 and/or RC-V3 are closed, the valves shall 0

be cycled every 100 F during the cooldown unt' jou have 0 reached % 140 F. CAUTION: If cycled by use of their handwheel do not over torque the valve. CAUTION: Valve may have to be cycled more frequently to maintain proper pressure / temperature relat nship. 11.2.2 Administrative

1. When the reactor coolant system has been shutdown and depressurized, isolate the borated water storage tank from decay heat removal system by checking closed or closing DHV-5A & 58. Also isolate the sodium hydroxide storage tank from the decay heat removal system by checking as closed or close BS-V2A & B.

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1102-11

 .-                                                                Reviston 21 09/06/79

2. The active means of decay heat removal may be interrupted providing the following limits are not exceeded.

A. Reactor coolant temp. and pressure are within limits of cooldown curve Figure 1. B. Pressurizer level above 100". C. OTSG average shell temperature may be a maximum of U 60 F above or below RC system water temp.

3. Verify that MU-V16 A,C,C, and D are closed and their respective breakers open prior to placing the DHR system in operation to prevent overpressurization of DHR system in event of inadvertent activation of E.S.

4. Ensure cooldown, rates are limited those specified in heatup and cooldown curve. In the temp range of 2600F to 0

175 F as read by the wide range temp. indicator (RC 5A-TI-l and RC 58-TI-1) on console center, a max, step temp. 0 change of 75 F is allowable followed by a one hour minimum hold of temp. If the step change is taken below 250 F P.C temp., the maximum allowable step change shall be that which yeilds a final temp. of 175UF.

5. When the DHR system is in operation without any RCP's operating indicated DHR return temp. (DH2-TI-l and 2 on CC) will be used as the RCS temp.

6. Prior to plant cooldown verify that correct amount and concentration or boric acid is available for injection into the MU-RC system to provide required shutdown marign at cold conditions.

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1102-11

 -                                                                             Revision 21 09/06/79

7. When adding makeup water to MU-RC system insure that the water quality is within limits set forth in plant chemical manual.

8. During boration verify boron concentration every 30 PPM.

9. When rector power is less than 15% FP, do not request a printout of the following computer groups:

Gp.# Description 20 Worst Case Thermal Condition 31 Fluid Condition 38 Core Average Thermal Condition 39 Core Map Thermal Condition 40 All Thermal Output 54 Selected Assembly Thermal Condition

10. If any Safety Limit (defined in Technical Specification 2.1 and 2.2) is exceeded, the shift supervisor shall notify the Station / Unit Superintendent. The reactor shall be shut down. The licensee shall notify the Commis-sion, review the matter and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude reoccurrence.

Operation shall not be resumed until authorized by'the Commission.

11. If, during operation, the automatic safety system does not function as required, the Station / Unit / Unit Superintendent shall be notified. The shift supervisor shall take 6.0 1123 152

1102-11 Revision 21 09/06/79 appropriate action as outlined in the Tech Specs. Note that this appropriate action may include shutting down the reactor: Examples of " failure to function as required" are: (1) Setpoints exceeding limiting safety system settings (2) failure of protection system component in an untripped state.

12. When a Limiting Condition for Operation (defined in section 3 of'the Technical Specifications) is not met, the shif t supervisor shall notify the Station / Unit Superin-tendent. The reactor shall be shut down or remedial action taken g permitted byv,the Technical Specifications until the condition can be_ met. In tne event an LC0 is not met and the remedial action pennitted by the Tech.

Specs. does not correct the situation, the licensee shall notify the Commission, review the matter and record the results. of the review, including the cause of the condition a and the basis for corrective action taken to preclude reoccurrence. 11.3 Operating Procedure 11.3.1 Prerequisites for Cooldown (Indicate satisfactory completion of steps below by initiating next to each step and sign name at end of applicable section).

1. Reactor at 5% 4K/K subcritical boron concentration at 5320F with one reactor coolant pump running per loop and necessary safety rods withdrawn.

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1102-11 Revision 21 09/06/79

2. Degassing of reactor coolant system is complete in accordance with plar.t shutdown as per OP-1102-10. If additional degass is needed during cooldown refer to degas procedure OP-1102-12.

3. Heat dissipation using steam generators is in progress using turbine bypass valves.

4. Sufficient boric acid solution and reactor grade water available'.

to makeup for reactor coolant system during cooldown. Required final boron concentration determined as per OP-1103-4 and Figure 3. The combination of borated and demineralized water to effect makeup determined, also verify available boric acid solution is sufficient to maintain shutdown margin. NOTE: If the RCS is to be opened to R.B. atmosphere, i.e. safety valve removed, head off, etc., and containment integrity not maintained, it will be necessary to berate to refueling shutdown concentration.

5. Pressurizer level indicator / controller is in' auto, set to maintain pressurizer level at 220".

6 Let down flow from RCS is secured.

7. Emergency feed water ' pump auto-start-defeat switch in defeat.

8. OTSG level maintained between 97 and 99% on operate range level indication to keep main F.W. nozzles submerged, 11.3.2 Cooldown

_ 1. Lineup borated and demineralized water addition systems to make up to MU system during cooldown. Perform the following operations while cooling down. A. Add borated water as required to maintain MU tank normal le al. 8.0 i 1123 '54

1102-11 - Revision 21 09/06/79 B. When required boron addition is completed, add demineralized or borated RC bleed in batchts. If adding water of lesser boron concentration than that of reactor coolant system evaluate effects by monitoring source range instrumentation. NOTE: . Bo. ration and concentration makeup should be complete prior to placing DHR in operation.

1. Turn pressurizer heaters off.

2. Place the steam line rupture detection auto-defeat switch in defeat.

3. Place the following on computer trend recorders until cooldown is complete. Mark the recorders with date, time, and scale, and every scale change and time. When cooldown is complete remove chart paper date and time and attach to signed off procedure. During cooldown plot temperature / pressure in Figure 1 every 30 minutes. Mark time of point in curve every 2 hours.

Pt 512 Loop A Tcold Pt 515 Loop B Tcold Pt 505 RC pressure NOTE: If either RC-V2 and/or RC-V3 are closed, the valves shall be cycled every 100 0F during the cooldown until you have reached % 1400F. CAUTION: If cycled by use of their handwheel care shall be exercised such that you do not over torque the valve. CAUTION: Valve may have to be cycled more frequently to maintain proper pressure / temperature relationship. 9.0 o 1 1l -l c s-(,

e 1102-11 - Revision 21 09/06/79

4. Place turbine bypass valves in manual and adjust bypass valves and pressurizer spray valve to maintain cooldown rate and observe temp. and pres,ure linits of Figure 1.

NOTE: Maintain pressurizer level at 220" without exceeding the capacity of the makeup system. CAUTION: Maintain feedwater nozzles submerged throughout this procedure.

5. Start Aux, boilers in preparation for supplying gland sealing steam, if not already in operation.

6. At 1875 PSIG (RCS) stop cooldown and maintain steady RCS temp.

and pressure. When steady conditions are met insert safety rod groups that are still withdrawn and verify group 8 at i 27%. If refueling of reactor is to follow, fully insert rod group 8. NOTE: Inserting rod group 8 may add reactivity and a small increase in countrate may be observed.

7. Trip control rod drive breakers and depressurize to less than 1720 PSIG using spray valve.

8. At less than 1720 PSIG place all four reactor protective channels in shutdown bypass.

9. Reset RPS high flux trip point to 4.25% as per OP-1105-2, Appendix I.

10. Recock the group 1 safety rods (or all 4 groups) to full out position. Verify subcritical multiplication and plot 1/M vs.

Rod position during rod withdrawal to insure criticality is not attained on the safety group. Maintain 5% subcriticality. 10.0 11n' ir l \ u. J 3

. e 1102-11

Revision 21 09/06/79

11. At <l650 PSIG >l540 PSIG bypass high pressure injection.

12. Continue cooldown as defined in Fig. 1. Reset Pressure Level control setpoint to 100" (25%).

13. At 500 PSIG STM pressure open FW-V6 20 bypass running feed water pump and then secure feed water pump per OP-1106-3.

14 At <900 >540 PSIG (RCS) bypass low pressure injection.

15. At 700 PSIG (RCS) insure core flood valves CF VI A & 1B are shut and open and tag the power supplies to these values.

16. Place gland sealing stm on aux. steam as per 1106-10. OPEN AS-V17 to supply aux. stm. to aux. bldg.

17. At 150 PSIG STM pressure stop cond. booster pump per OP-1106-2.

18. At less than 500 PSIG (RCS) rack out reactor building spray pumps A & B to prevent unnecessary actuation. Close and tag BS-V17A, BS-V178, BS-V49A, and BS-V49B.

19. At 380 PSIG (RCS) line up reactor coolant pump seal leak off to Aux. Building drains per OP-1104-2.

NOTE: Switch to low range pressure indicatien at 450 psig to control pressure.

20. At 380 PSIG (RCS) insert safety rod groups which are withdrawn.

Insure A 1% ak/k shutdown margin by verifying RCS boron con-centration is greater than the concentration required for cold shutdown from Figure 3.

21. Open rod drive power supply bkrs. (Unit 10 & 11) and tag due to system depressurization.

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1102-11 - Revision 21 09/06/79 U

22. At 275 F verify RCS pressure is less than 425 psig and decreasing, then place NDTT auto /off control switch for tb electromatic relief valve RC-RV-2 in AUTO to actuate the 485 psig relief set point. Insure PRF-6-8 alarm is clear.

23. Shift to 1 R.C. pump in operation if not already done. This is accomplished by using OP 1103-6.

24. Place makeup control valve in manual and establish a 25 inch per hour increase in pressurizer level. Do not exceed 320 inches.

25. Insure that the BWST is not on recirc. using a Reactor Building Spray Pump, BS-P-1 A or B. With pressure controlled at 300-325 PSIG, place decay heat system in operation per OP 1104-4.

NOTE: Prior to starting Decay Heat Removal System, insure that Mechanical Draft Cooling Tower is in operation with a stable efficient temperature. After starting Decay Heat, monitor effluent temperature and AT closely. Insure that subsequent tower operation will not change aT at a rate greater than 2 F/hr. U

26. Maintain a one hour hold at 225 - 250 to compensate for step decrease experienced by the reactor vessei when DH system cooling is initiated.

27. During the one hour hold at 225 - 250 UF with both the decay heat system and RC pump running align the DHRS valves to change the pressurizer spray control from RC-V1 to the Quench spray valve RC-V4, per OP 1103-5.

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1102-11 . Revision 21 09/06/79

28. When satisfactory reactor coolant system pressure control can be maintained by RC-V4 only, shutdown the RCP per OP-1103-06 and line RCP seal leak off back to the make up tank.

29. Slowly open the auxiliary spray throttle valve DH-V64 to the pressurizer until a temperature increase is detected in the pressurizer surge line. Adjust the auxiliary spray throttle valve (in the close direction) until the temperature returns to its previous value. Depressurize the R.C. system to less than 125 PSIG as read on 0-500 PSIG R.C. low range indicator and allow pressurizer level increase to 320 inches.

NOTE: Do not exceed a cooldown rate of 1000 F in any one hour in the pressurizer. NOTE: This spray adjustment is to prevent pressurizer outsurge into the R.C. hot leg. The pressurizer surge temperature should be monitored closely throughout the continuation of cooldown. If the surge line temperature increases again, adjust the auxiliary spray throttle valve (in the close direction) until the temperature returns to its previous valve.

30. Close the turbine bypass valves.

31. After Decay Heat Removal System is in service, steam generator wet or dry layup may be initiated per OP-1106-16

32. Continue cooldown using DHR not to exceed 50 F in any one hour.

33. Secure RCP seal injection when below 190 F and 100 PSIG and secure make up system if plant shutdown is to be of a long duration or maintenance is to be performed.

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1102-11 Revision 21 09/06/79

34. Rack out the breakers for the makeup pumps to assure no inadvertant starts occur which could overpressurize the R.C.S.

0

35. At 140 F RC system temp., and 15 to 20 psig steam bubble in the pressurizer cooldown is considered complete. DHR system operation should be continued, however, to further reduce coolant temp. for personnel comfort and safety during refueling or maintenance, in accordance with OP-1103-11.

36. Secure all support systems when no longer required.

Performed By Date Signature Reviewed By SR0 or R0 License Dato Signature 14.0 1123 !60

HEAT-UP/C00LDOTI .

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ML19209B636: Difference between revisions

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ML19209B636: Difference between revisions

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