ML19224B109
| ML19224B109 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/06/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2202-2.6, TM-0037, TM-37, NUDOCS 7906140058 | |
| Download: ML19224B109 (7) | |
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TMI DOCUMENTS DOCUMENT NO: [
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{ h 7f OF DOCUMENT PROVIDED BY COPY MADE ON ti METROPOLITAN EDISON COMPANY.
Wilda R. MullinEx, NRC 7906140058 49611 e
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THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROCECURE 2202-2.6 OTSG TUBE RUPTURE Table of Effective Pages Pace Date R evision Page Date Revision Page Date R evision 1.0 06/05/77 0
26.0 51.0 2.0 08/31/77 1
27.0 52.0 3.0 04/18/78 3
28.0 53.0 4.0 04/18/78 3
29.0 54.0 5.0
/06/78 4
30.0 55.0 6.0 04/18/78 3
31.0 56.0 7.0 3 2. '
57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 36.0 61.0 12.0 37.0 62.0 13.0 38.0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17-.0 42.0 67.0 43.0 68.0 18.0 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 Recommends Approval Unit 2 Staff Recommends Approval d'
Date
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Date Approval Approval Cc;nizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recommends Approval
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Date Chairman of PORC v'- Chairrnan of PORC I
a Unit 1 Superintendent Approval Unit 2 Superintendent Approval li Date (L> !&J:M Date /d 7
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Date Manager Generation Quality Assurance Approval 187 002,,
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2202-2.6
- n Revision 0
".f 06/05/77 THREE MILE ISLAND NUCLEAR STATION Apg z 3 1379 LLED COPY
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UNIT #2 EMERGENCY PROCEDURE 2202-2.6
[4AOTrn p ;.,' ' ' G J l Q O
OTSG TUBE RUPTURE
[1];
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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.
VA-R748 off gas monitor alarm.
D.
Secondary sample analysis indicates activity in the secundary side.
2.0 IMMEDIATE ACTION A.
Automatic Action 1.
MU-V17 will open to compensate for reduced pressurizer level.
I B.
Manual Action 1.
Verify MU-Vl7 is maintaining pressurizer level at 220".
Close MU-V376 and start an additional make-up pump if pressurizer level drops to 200".
2.
Verify VA-R748 alarm.
3.
Notify Unit I Control Room and isolate steam to Unit I by closing AS-V23.
4.
Direct c.9mistry department to sample both OTSG's and analyze for radicadivity s' y, H, I-133, Cs-137) to determine which OTSG has the leak.
5.
Using an RM-14, or equivali it instrument, take a gama 2
I 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.
187 003
=
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2202-2.C Revision 1 j
08/31/77 APR 2 3 1973 -
6.
Based on the readings taken in 4 above, attempt to determine which OTSG has the leak.
7.
If make-up-tank level is decreasing at greater than 10 GPM (1 inch /3 minutes) and VA-R748 is in clarm, immediately.
begin reducing load at 10%/ minute.
8.
CLOSE the affected 0TSG's atmospheric dump valve isolation valve (MS-Vl A or B) to eliminate the potential of leakage and an unwarranted release.
9.
If desired to aid in determining which OTSG is leaking, dump all MSR drains to the t.ondenser per 2106-3.1.
C.
Follow-Up Action 1.
If make-up-tank level is not decreasing at greater than 10 GPM, calculate the RCS leak rate per Surveillance Procedure 2301-3Dl.
If the identified leak rate exceeds 10 GPM or primary to secondary uTSG tube leakage exceeds 1 GP!1 or unidantified leakage exceeds 1 GPM proceed with Technical Specification 3.4.6.2 Action Statement.
2.
If make-up-tank level is decreasing at_ greater than 10 GPM and VA-R748 is in alarm 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 bypass valves and open the turbine bypass valves to take steam from the turbine and thereby reduce load.
2.0 187 004 a
1 2202-2.6 f
Revision 3 04/18/78 Apg 2 3 1971 CAUTION:
Do not increase OTSG Levels to 97-99% on the Operating
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Levels to avoid a possible R.C.S. Baron Dilution Accident during subsequent plant cooldown.
c.
Trip the turbine. Then place the turbine bypass valves back to automatic and verify the turbine bypass valves maintain header pressure at 895 psig.
d.
Follow up on chemistry analysis requested in Step 4 of manual action. Verify that gamma analysis has been performed in accordance with HP-1950 on samples taken from below listed points.
For a large rupture (greater than 50 gnm leakage) the leaking OTSG level will hang up.
For smaller leaks (Sodium-24) chemistry analysis will have to be used to determine which OTSG has the leak.
Steam Generator Inlet Steam Generator Inlet B Main Steam A Main Steam B Secondary Side Stm. Gen A Secondary Side Stm. Gen B e.
Isolate the effected 0TSG by closing the following on the ef fected OTSG when RCS Th is <545 F.
Main FW Reg. Valve FW-V30 A or B Main FW Block Out et Valv FW-V17 A or B l
S.U. FW Reg. Val ve FW-V25 A or B
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S.U. FW Block Inlet Valve FW-V26 A or B 187 005 3o
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e 2202-2.6 j)
Revision 3 A
04/18/78 / /
APR'2 3 13ifl.
S.U. FW Block Outlet Valve FW-Vl9 A or B Bypass FW S.V. Valve TW-V66 A or B Emerg. FW Reg. Valve EF-V11 A or B Emerg. FW Block Valve EF-V12 A or B Emerg. FW Reg. Valve Bypass EF-V33 A or B Emerg. FW Block Valve Bypass EF-V32 A or B Turbine Bypass Valves MS-V25 A or B MS-V26 A or B Turbine Bypass Block Valves MS-V23 A or B MS-V24 A or B Main Stm. Isolation Valves MS-V4 A or B MS-V7 A or B Stm. Gen. Reheat Stm.
MS-V15 A or B Isolation Valves i
Assure the FW pump for the unaffected 0TSG is running, or run the FW pumps off of Auxiliary steam.
CAUTION: The "A" FW Pump Turbine receives HP Steam from the "B" OTSG and the "B" FW Pump Turbine receives HP Stea.n from the "A" OTSG.
NOTE:
Monitor isolated steam generator pressure, and if it approaches 1050 psig (MS relief valve setpoint) re-establish a flowpath to the condenser via the turbine bypass valves.
f.
Take manual control of main and startup reg. valves
{
and adjust uneffected 0TSG 1evel as needed to obtain a Tave of 532 F.
4.0 87 ogg
h 2202-2.6 APR 2 3 UN Revision 4 10/06/78 g.
Place Pressurizer Pressure Controller in manual and adjust output to maintain RCS Pressure at 1850 psig.
Turn pressurizer heater banks 4 & 5 off.
NOTE:
This vill aid in lowering primary to sec.
leak rate.
h.
Open the MU pump suction valve from the BWST DH-V5 A anc'. B and isolate MU-V12 if required, due to low make-up-tank level.
i.
Begin a cooldown to cold shutdown as secn as possible in accordance with 2102-3.2 to minimize inleakage to the affected 0TSG.
j.
Open breakers for the following sump pumps to terminate any potential radioactive release:
Turbine Building Sump Pumps SD-P-1A Unit 3B MCC 2-31A SD-P-1B Unit 9C v"C 2-41A Control Building Area Sump Pumps SD-P-3A Unio 4B MCC 2-31C SD-P-3B Unit 5C MCC 2-41C k.
CLOSE the following valves:
SD-V48 Control Building area sump discharge to noi.-radioactive waste treatment bu.sding sump.
SD-V38 Turbine Building Sump discharge to non-i radioactive waste treatment building sump.
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WDL-Vil60 Secondary Chem. Lab drain to control and service building sump.
lQj gQy 5.0
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2202-2.6 Revision 3
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04/18/78 APR 2 3 m 1.
OPEN or insure OPEN the follcwing vahes:
WT-V123A(B)
Cond. Polisher reg. sump discharc;e to WDL misc.
CAUTION:
Insure spool piece is in place between WDL-V403(404) and WDL-V361.
WDL-V403(404)
Cond. Polisher reg. sump discharge to WDL Misc. spool piece isol.
WDL-V361 Con. polisher reg. sump discharge to WDL-F 8A/B.
SD-V29A Control Building area sump discharge to condensate polisher regeneration sump.
SD-V28A Turbine Building sump discharge to Cond.
polisher reg. sump.
WDL-Vll59 Secondary Chem Lab Drain to Cont. Drain Tanks.
m.
Insure WT-R3894 and 3895 are operating properly to direct radioactive wastes to the WDL Misc. System, n.
CLOSE BREAKERS OPENED IN STEP h.
Notify Health Physics to begin surveys of the Control o.
Building area and Trubine Building to determine the need for controlled areas.
Inititate Emergency Plan if required, as a result of the surveys.
i 6.0 187 008