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Operating Procedure 1102-10,Revision 16, Plant Shutdown.
	ML19209B639
Person / Time
Site:	Three Mile Island
Issue date:	08/15/1979
From:	; METROPOLITAN EDISON CO.
To:	;
References
	1102-10, NUDOCS 7910100263
	Download: ML19209B639 (15)
	v • d • e

' evis on le f ,, 08/15/79 THREE MILE ISLAND NUCLEAR STATION 'O RC C A' R V' A N UNIT #1 OPERATING PROCEDURE 1102-10 UN'F 1 PLANT SHUTDOWN Table of Effective Pages CONTROLLED COPY Revision Pace Date Revision Pace Date Revision Paae Date 1.0 26.0 51.0 11/22/76 9 52.0 2.0 04/04/74 1 27.0 3.0 08/15/79 16 28.0 53.0 4.0 08/15/79 16 29.0 54.0 5.0 08/15/79 16 30.0 55.0 6.0 08/15/79 16 31.0 56.0 7.0 08/15/79 16 32.0 57.0 8.0 08/15/79 16 33.0 58.0 9.0 08/15/79 16 34.0 69.0 10.0 08/15/79 16 35.0 60.0 11.0 08/15/79 16 36.0 61.0 12.0 08/15/79 16 37.0 62.0 .

13.0 08/15/79 16 38.0 63.0 14.0 08/15/79 16 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 18.0 43.0 68.0 19.0 44.0 69.0 20.0 , 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recom er' s Approval Unit 2 Staff Recommends pproval

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" Date Approval Date Approval ,,

Coghizant' Dept. Head Cogniza'nt DepI. H'ead Unit 1 oORC Recommends Approval Unit 2 PORC Recomm d Approval J A V!fW Date Yl ' #

99 / \ Date Chairmanbf PORC 1/Chairrnan of PORC Unit 1 Superi tendent Approval Unit 2 Superintendent A pr val

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DateT/ir/77 ,1\J , Date STANDING PROCEDURE /\. Date Supervisor of QC 79101 00 b 'U ll o/"165 _,

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"e '- Revision 9 NOV 2 21976 THREE MILE ISLAND NUCLEAR STATION UNIT #1 OPERATING PROCEDURE 1102-10 PLANT SHUTDOWN TO HOT SHUTDOWN ,

Table of Contents

10.1 REFERENCES

10.2 LIMITS AND PRECAUTIONS 10.2.1 Equipment 10.2.2 Administrative 10.3 OPERATING PROCEDURE 10.3.1 Prerequisites 10.3.2 Procedure 1.0 11 0 '66

1102-10

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4/4/74 l'

Revision 1

10.1 REFERENCES

10.1.1 Reactivity Balance Calculation OP 1103-15 10.1.2 Makeup & Purification Syste= OP 1104-2 10.1.3 Integrated Control Syste: OP 1105-4 10.1.4 Turbine / Generator OP 1106-1 10.1.5 Feedvater OP 1106-3 10.1.6 Plant Limits and Precautions OP 1101-1 10.1.7 Hydrogen Addition & Degassification OP 1102-12 10.1.8 Pressurizer Operation OP 1103-5 10.1.9 Reactor Coolant Pump Operation OP 1103-6 10.1.10 Plant Cooldown OP 1102-11 10.2 LEfITS ANI ?RECAUTIONS 10.2.1 Equipment 10.2.1.1 Maintain gland sealing after turbine is taken off line.

10.2.1.2 Maintain pressurizer level within the li=its of Figure 1.

10.2.1.3 When turbine load is less than 65 MWE (15% reactor power) verify that t he turbine bypass valves operate to maintain header pressure setpoint.

10.2.2 Adninistrative 10.2.2.1 During bora : ion verify boron concentration every estimated 30 ppm.

10.2.2.2 Maintain cakeup tank level above the low level alarm.

10.2.2.3 Cooldown rate to 525 F shall be no greater than 140 F/hr.

10.2.2.4 Cooldown of the R.C. System without degassing may result in excess hydrogen and airborne radioactivi y vhan reactor vessel head is renoved.

P00R ORIGIEL -v llL0 .,7

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Revision 15 08/15/79 10.2.2.5 When reactor power is less than 155 FP, do not request a printout of the following computer groups:

Gp.# Descriptien 20 Worst Case Thermal Condition 31 Fluid Condition 38 Core Average Thermal Condi "on 39 Core Map Thermal Condition 40 All Thermal Output 54 Selected. Assembly Thermal Condition 10.2.2.6 If any Safety Limit (defined in Technical Specification 2.1 and 2.2) is exceeded, the shit t supervisor shall notify the Station / Unit Superintendent. The reactor shall be shut down.

The licensee shall notify the Commission, review the matter and record the results of the review, including the cause of 4

the condition and the basis for corrective action taken to preclude reoccurrence. Operation shall not be resumed until autho:ized by the Commission.

10.2.2.7 If, during operation, the automatic safety system does not function as required, the Station / Unit Superintendent shall be notified. The shif t supervisor shall take 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 a protection system component in an untripped state.

3.0 1123 '68

Revision 16 08/15/79 10.2.2.8 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 Superintendent. The reactor shall be shut down g remedial action taken g permitted by the Technical Specifications until the condicion can g met.

In the event an LCO is not met and the remedial action permitted 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 and the basis for corrective action taken to preclude reoccurrence.

10.3 OPERATING PROCEDURE NOTE: If plant shutdown is occurring before the refueling shutdown date, follow the plant shutdown procedure which follows.

If plant shutdown is in preparation for the refueling outage, begin boration of the RCS immediately upon start of power reduction. DO NOT flood feedwater nozzles UNTIL the RCS boron concentration is greater

'than the cold shutdown value from Figure 2. Continue borating toward refueling baron concentration.

Regard all other sections of shutdown procedure which follows.

10.3.1 Prerequisites NOTE: Indicate satisfactory completion of prerequisites by initialing each step and sign name at end of applicable section.

4.0 1123 '.69

,evision 16

. - 08/15/79 10.3.1.1 Reactor Operating at Power 10.3.1.2 If shutdown is preparatory to cooldown, degassification should be in progress as per OP 1102-12 and shouid be completed before reactor power is decreased below 15 percent. OP 1102-12 also includes degassification if forced to shutdown.

Degassing may be delayed until the cooldown is started (if modifications to the pressurizer gas space sample system are not completed) to eliminate uncontrolled gas releases. If cooldown is preparatory to opening the Reactor Coolant System for maintenance, degassification should be continued until the hydrogen concentration is reduced to less than 5 cc/kg or as low as practicable.

10.3.1.3 Verify that the required Reactor Coolant System boron concen-tration has been determined to maintain the reactor at 5% ak/k subcritical at 532 0F, 4

NOTE: Boron concentration depends on length of time at hot shutdown in regard to xenon buildup or whether cooldown is intended.

If the RCS is to be opened to R.B. atmosphere, i.e.,

safety valve removed, head off, etc., and containment integrity not maintaired, it will be necessary to borate to refueling shutdown concentration.

10.3.1.4 If stay at hot shutdown is expected to be less than the time to reach the equilibrium xenon which existed at the time of shutdown (see figure 3), calculate boron concentration require-ment to meet 5% ak/k subcriticality limit taking credit for the negative reactivity for 100% FP equilibrium xenon worth.

5.0 1123 '.70

. . . . - ~...=-n..

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Revision 16 08/15/79 10.3.1.5 If stay at hot shutdown is expected to approach or be greater than the time to reach the equilibrium xenon which existed at the time of shutdown (.see figure 3), commence boration to achieve the boron concentration specified for 5% ak/k subcriti-U cality at 532 F.

NOTE: In case of a stuck Rod or cooldown is certain, Borate immediately to 70UF,1% ak/k shutdown concentration as shown on Figure 2.

10.3.1.6 Verify that makeup water at the required boron concentration is lined up to be added to the makeup tank when required as per OP 1103-4.

Performed By Date Signature Reviewed By

, SR0 or R0 License Date Signa ture 6.0 112: !71

.. . Revision 16 08/15/79 10.3.2 Procedure NOTE: Indicate satisfactory completion of below steps by initialing each step and sign name at end of applicable section.

10.3.2.1 Log the following in the Centrol Room Operator's Log Book:

a) Date and Time b) Reactivity Balance from the computer (Operators Group 22) c)' Rod Position d) Baron Cor. centration e) Reactor Coolant Average Temperature f) Effective Full Power Days (EF,PD)~

~

10.3.2.2 Reduce reactor power using " unit master" to approximately 40%.

10.3.2.3 At approximately~ 80% reactor power, secure moisture separator drain pumps in accordance with OP 1106-12.

10.3.2.4 At approximately 305 MWE (40% reactor power):

a) Reduce the number of operating Main Feedwater Pumps to one (1) as per OP 1106-3.

b) Reduce the number of operating heater drain pumps to one (1).

10.3.2.4.1 Secure one (1) booster pump and one (1) condensate pump at approximately 25% Reactor Power.

10.3.2.5 Continue reducing ULD to 15% reactor power.

a) Open turbine drains as per OP 1106-14.

NOTE: When either OTSG goes on low level limit, place SG Load Ratio ATc H/A station to hand as per OP 1105-4 7.0 1123 '.72

- - Revision 16 08/15/79 b) Place the Loose Parts Monitor Neutron Noise and Loose Parts low alarm switches in DEFEAT per 1105-14.

10.3.2.6 At approximately 15% power, notify Chemistry Department to place OTSG sample lines (CE-8 and 9) in service, obtain samples and maintain flow during shutdown.

10.3.2.7 P1 ace the turbine EHC control to manual, verify that ICS trips to " track" if not already in track and then reduce generator load from the EHC controller to minimum load specified in OP 1106-1. Verify that the turbine bypass valves operate to maintain the turbine header pressure between 895 and 885 psig.

10.3.2.8 If shutdown is preparatory to cooldown reduce the number of operating reactor coolant pumps to one per loop as per

, OP 1103-6.

10.3.2.9 Shut the letdown isolation valve MU-V3.

10.3.2.10 Add water to the makeup tank to maintain MU tank level in normal operating range as per OP 1104-2.

NOTE: Boric acid concentration of makeup water was previously determined based on shutdown /cooldown condition intended.

10.3.2.11 With both steam generators at low level limit, place the "SG/ Reactor Demand Hand / Auto Station in Hand and reduce SG/ reactor demand to zero as per OP 1105-4.

10.3.2.12 Place Reactor Demand station in Hand. Decrease reactor power to 10 percent and hold at that level while performing the following:

8.o llE '73

Revision 16 08/15/79

a. Take the main generator off line and trip turbine as specified in OP 1106-1. When TMI #1 Generator is tripped (GB102 and GBil2 opened), open GB105 and GBil5 on order of the Lebanon Dispatcher unless the unit is to be resynchronized within one (1) hour.

b) Fill the pressurizer water level to 320 inches.

NOTE: Monitor turbine header pressure and turbine bypass valve demand to insure that the bypass valves open to maintain turbine header pressure setpoint.

NOTE: Increase in pressurizer level is necessary to insure makeup capability is not exceeded during following step.

CAUTION: Power reduction to 5% must not exceed a cooldown

, rate of 140 F/hr.

NOTE: Do not allow pressurizer level to drop below 220 inches.

10.3.2.13 At 5 percent reactor power place the Diamond Rod Control Station to manual and gradually reduce reactor power to 10-8 amp on the intermediate range instrumentation.

NOTE: While decreasing reactor power from 5 percent to 10-8 amp (a) maintain cooldown limitations of 140 F/hr. (b) if shutdown is to hot shutdown only, place the pressurizer level controller to manual and reduce the pressurizer level to 100 inches, maintaining limits shown in Figure 1.

(c) if preparatory to cooldown maintain pressurizer 9.0 1123 174

08/15/79 level controller in auto and maintain level at 22C inches.

10.3.2.14 When the reactor is. stable at 10-8 amps with zero startup rate, record critical data: boron ppm, RCS temperature, rod position, and time /date.

10.3.2.15 Insert regulating groups 7, 6 & 5 and leave group 8 at previous operating position.

10.3.2.16 If not already done, change to one R.C.P. operating in each loop. Insure that the reactor is 5% Ak/k subcritical, borate if necessary (Safety rod groups 2, 3 and 4 can be inserted if necessary).

. _ _ . . _ . . _ _ . 10.3.2.37.- Raise OTSG level to 97-99"an-the.-operating range. ---

NOTE: Open the bypass line'(FWV 85 A & B) around the feedwater control valves fully open, and control OTSG level by opening the Turbine Bypass Valves

, as necessary to lower level (see Figure #4).

10.3.2.18 With the Reactor Coolant' Average Temperature between 532 U

and 525 F, the Safety Rod Group 1 (2, 3 and 4 can also be withdrawn), and the reactor greater than 5% ak/k subcritical (as per Figure 2 boron cencentration) the plant is in hot shutdown condition. If cooldown is intended, utilize OP 1102 Plant Cooldown.

Performed By Date Signature Reviewed by SR0 or R0 License Date Signature 10.0 1123 !75

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