ML19209B595

Emergency Procedure 1202-5,Revision 7, Once-Through Steam Generator Tube Rupture.

ML19209B595
Person / Time
Site:	Three Mile Island
Issue date:	09/26/1979
From:	METROPOLITAN EDISON CO.
To:
References
1202-5, NUDOCS 7910100204
Download: ML19209B595 (7)

Text

5.h 1202-5 Revision 7 09/26/79

, THREE MILE ISLAND NUCLEAR STATION ~-

UtlIT #1 EMERGEliCY PROCEDURE 1202-5 OTSG TUBE RUPTURE 4 Table of Effective Pages

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Paae Date Revision Page Date Revision M Date Revision 1.0 07/12/79 6 26.0 '

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Approval // Date Approval /\/ Date Ccgnizant Dept. Head Cognizlnt D'eptlHes'd Unit 1 PORC ecommends Approval -

Unit 2 PORC Reco me pproval

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6A Date YMjf10 ' / Date I

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g Chairman of PORC Chairman'of PORD Unit 1 SuperintAdent Approval Unit 2 Superinten ent A pr i Date d / / ( Date i ~l Date STANDING PROCEDURE Supervisor of QC 7* '

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, 1202-5 Revision 6 07/12/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 EMERGENCY PROCEDURE #1202-5 OTSG TUBE RUPTURE 1.0 SYMPTOMS A. Initial loss of reactor coolant pressure and decrease in pressurizer level becoming stable after short period of time.

B. Make-up tank level decreasing C. RM-A5 off gas monitor alarm / alert / increased count rate.

O. Secondary sample analysis indicates activity in the secondary side.

2.0 IMMEDIATE ACTION A. Automatic Action

1. MU-V17 will open to compensate for reduced pressurizer l evel .

B. Manual Action

( An asterisk indicates a key parr. meter which requires reverification as a follow-up action.)

• l. Verify MU-V17 is maintaining pressurizer level at 220".

Close MU-V3 and start an additional make-up pump if ~

pressurizer level drops to 200".

• 2. Verify RMA-5 alarm / alert / increased count rate.

3. Notify Unit II Control Room to isolate auxiliary steam cross connect by closing AS-V23 (Unit 2) and AS-V-209 (Bypass).

4. If makeup tank level is decreasina at greater than 10 GPM (1 inch /3 minutes) and RMA-5 is in alarm, immediately begin reducing load at ,10%/ minute.

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5. Direct chemistry department to sample both OTSG's and analyze for radica .ivity (5, y, H, Na ', I-133, Cs-137) to determine which OTSG has the leak.

6. Using an RM-14, or equivalent instrument, take a gamma reading in each steam line outside the Reactor Building.

Attempt to take the readings on each steam line as close to the same relative position as possible.

7. Based on the readings taken in 5 and 6 above, attempt to determine which OTSG has the leak.

8. If makeup tank level 1 not decreasinc at greater than 10 GPM, calculate the RCS leak rate per Surveillence Procedure SP 1303-1.1. If the total primary to secondary leak rate through the tubes for both OTSG's exceeds 1 GPM go to COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of detection of 0TSG tube leak.

9. Isolate the atmospheric dump valves (MS-V4A,B) by closing MS-VISA & B to minimize any potential unmonitored radioactive gas release.

0AUTION: If condenser vacuum or circ water pumps are lost, it may be necessary to re-open MS-V15A/B and use MS-V4A/B for pressure control to avoid violation of pressure / temperature control limits.

10. Evaluate any radioactive releases from condenser vacuum pump vent, main steam safety valves, or other sources for 2.0 1122 551

i 1202-5 Revision 7 09/26/79 levels requiring Emergency Plan Monitoring AP 1004 and Notification Procedure AP 1044 C. Follow-up Action Objective:

This procedure is designed to achieve an expeditious cold shutdown condition while -inimizing the potential for radioactive releases through the main steam safety and relief valves, condenser vacuum pump vent, and turbine plant drains. Decay heat removal during this emergency is provided by the unaffected 0TSG (or least affected OTSG) until the Decay Heai. Removal System can be placed in operation at reduced pressure. The affected steam generator is isolated from service to minimize the potential for radioactive releases.

1. Reverify key parameters marked by an asterisk in the Immediate Manual Action section. Use alternate indications, if available, to confirm parameter values.

2. Verify that pressurizer heaters are energized as required to maintain RCS pressure at 2155 psig.

3. If reactor shutdown is required by the magnitude of tube  ;

leakage or radioactive release rate proceed as outlined below.

a. At 15% power place diamond in manual and fully insert the regulating groups 7,6, and 5 (this is to reduce likelihood of lifting secondary safety valves).

b. While reducing Rx Power to zero by inserting rod groups 7,6, and 5, go to manual on the turbine 3o 1122 352

1202-5 Revision 7 09/26/79 bynass valves and open the turbine bypass valves to take steam from the turbine and thereby reduce load,

c. Trip the turbine at 0 MW decreasing load. Place the turbine bypass back in automatic to maintain header pres:ure at 895 psig. Ensure makeup flow is adequate to maintain pressurizer level and to accomodate the RCS shrinkage due to the effects of leakage and cooldown.

d. Follow up on chemistry analysis requested in Step 5 of manual action. Verify that gamma analysis has been performed in accordance with Chemistry Procedure 1958 on samples taken from:

CE Steam Generator Inlet CE Secondary Side Steam Generator A CE Secondary Side Steam Generator B CE Pain Steam A CE Main Steam B NOTE: For a large rupture (greater than 50 gpm leakage) the leaking 0TSG level will hang up due to inleakage greater than steaming rate. For smaller leaks (Sodium-24) chemistry analysis will have to be used to determine which OTSG has the leak, t122 353 .

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e. Isolate the affected 0TSG by closing the following on the affected 0TSG when R.C.S. T c. is <545 F:

Main FW Reg. Valve FW-V17 A or R Main FW Block Valve FW-V5 A or B S.U. FW Reg. Valve FW-V16 A or B 5.U. FW Block Valve FW-V92 A or B Bypass FW Reg. Valve FW-V85 A or B Emerg FW Reg. Valve EF-V30 A or B Bypass Valves MS-V3 D/E/F or A/B/C Close main steam isolation valves MS-V1 A/B or MS-V1 C/D (assure the FW pump for the unaffected 0TSG is running, or run the FW pumps of' of auxiliary steam).

f. Take manual control of Main and Startup F.W. valves and adjust the uneffected 0TSG level as needed to u

obtain a Tave. of 532 F.

g. Adjust R.C.S. pressure setpoint to 1850 psig. Turn Pzr. Heater Banks 4 & 5 off.

NOTE: This will aid in lowering primary to sec-ondary leak rate.

h. Open the MU pump suction valve from the BWST MU-V14 A and B and isolate MU-V12 if required, due to low make-up tank level .

i. Begin a cooldown to cold shutdown as soon as possible in accordance with OP 1102-11 to minimize inleakage to the affected 0TSG.

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Terminate discharge from IWTS and IWFS until monitoring and controls are established. Open breakers for the following sump pumps to control discharge to the IWTS (IWFS):

Unit MCC Turbine Bldg. Sump Pumps SD-P5 10E 10 Turb.

SD-P2 A 1C IC Turb.

SD-P2 B lE ID Turb.

Powdex Sump Pumps SD-P1 A 4D 1A Turb.

SD-P1 B 4D 1B Turb.

k. Notify Health Physics to begin surveys of the Intermediate and Turbine Buildings to determine the need for cc,ntrolled areas. Initiate Emergency Plan if required, as a result of the surveys.

1. If OTSG tube leakage exceeded the limits of Tech Spec 3.1.6.3, an unscheduled inservice inspection of the affected OTSG must be conducted prior to startup pursuant to Tech Spec 4.19.3.c.l.

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