ML19209B625

Abnormal Procedure 1203-24,Revision 4, Steam Supply Sys Rupture Actuation on One Steam Generator.

ML19209B625
Person / Time
Site:	Three Mile Island
Issue date:	09/04/1979
From:	METROPOLITAN EDISON CO.
To:
References
1203-24, NUDOCS 7910100247
Download: ML19209B625 (8)

Text

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THREE MILE ISLAND NUCLEAR STATION UNIT #1 ABNORMAL PROCE:URE 1203-24 STEAM 3UPPLY SYSTEM RUPTURE ACTUATI:'i ON ONE STEAM GENERATOR Table of Effective Pages Paoe Date Rwision Pace Date Revision Pace Date Revision 1:

3.0 729 09/04/79 2 i 'UPORC CHA RMANE:

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-- 3 4.0 07/12/79 3 29.0 UN , 1 54.0 5.0 07/12/79 3 30.0 55.0 6.0 07/12/79 3 31.0 56.0 7.0 07/12/79 3 57.0 8.0 33.0 58 o 9.0 32.0 CONTROLLED COPY 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 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.C 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recomrne. pproval Unit 2 Staff Recommend proval Approval / I Date Approval / Date CognTzarit 0'ept. Head Cogniiant de6t. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recomm ds pproval h t.dt Date Ed/~ N / Date V- Chairman of PCRC Chairmah of P'O AC Unit 1 Superi tende t Ap oval Unit 2 Superinten ent A pr val 29 DAM?OJ Date $? Date ~

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1123 078. 8 B7ava5samT=uaa@KiGe@ tem 25:wi@g#Fs;MWuRym9ea42

. . :ifision 3 THREE MILE ISL ': 'iUCLEAR STATION UNIT =1 ASNORP. L ::0CEDURE 1203-24 STEAM SUPPLY SYSTE" RUPTURE ACTUATION ON ONE STE1" 3ENERATOR AZ2 . '. SYMPT 0MS

1. Rapid decrease of se::ndary steam pressure.

2. Electrical load re: :ing rapidly.

3. Decrease in pressuri:er level, R.C. Pressure, and cold leg temperature.

4. For a rupture insice :,e Reactor Building; Ir.:ication of increasing building : essure and temperature.

5. For a rupture outsi:2 :he Reactor Building; N:ise may be heard in Control Rc: or a report made from cersonnel outside the control ::om.

6. Decrease in main cc :enser hotwell level or ccr.densate storage tank level .

A2*.2 IMMEDIATE ACTION A. Automatic Action

1. When the Stea- Line Rupture (Feedwater Bl::k) System actuates (<60b;sig)ontheaffected07S3,the following valves auto close.

a) Startup Fei: water Control Valve FW-V-16A(B) .

b) Main Fee:wi:er Control Valve FW-V-17A(B).

c) Emergency Feedwater Valve EF-V-30A '3) .

d) Main Feedatter Block Valve FW- V- 5A '3 ) .

e) Startup Fee-dwater Block Valve PJ-V-92A(B).

03 DRM/[

1.0 1123 079

. , 1203-24 Revision 3 ,

07/12/79

2. Reactor Trips - Low pressure due to excessive initial cooldown.

3. Turbine Trip.

4. Pressurizer Hea ers on due to low RCS pressure.

5. Possible High Pressure Injection at 1500 psig in RCS and/or 4 psig Reactor Building Pressure.

6. Possible Reactor Building isolation at 4 psig in Building.

B.I Immediatt Manual Action For Steam Line Rupture on One OTSG.

NOTE: The parameters marked with an asterisk (*) will be reverified as the first step in followup action.

1. Manually trip the Reactor and perform the immediate manual actions in EP 1202-4 (Reactor Trip).

2. Determine which OTSG has the ruptured steam line.

The affected 0TSG should indicate lower steam pressure and lower water level (depending on magnitude of rupture).

• 3. Verify or establish Feedwater flow to unaffected 0TSG to maintain 30" on Startup Range.

• 4. Verify Bypass Valves (MS-V-3's) on unaffected OTSG are maintaining 1010 psig Header Pressure.

5. If the steam line Rupture Feedwater Block System actuated (<600 psig on the affected 0TSG) go to Hand on the ICS control stations for FW-V-16A(B), FW-V-17A(B), EF-V-30A(B), and close these valves on the 1123 080

. 3-24

. Revision 4 09/04/79 affected :T53. :nsure FW-V-5A(B) and FW-V-92A(B) are closed.

A24.3 FOLLONUP ACTION Objective:

The objective of this :"::sdure is to:

1. Trip the reactor 2n: :erform the immediate manual action to conserve RCS invs :ory.

2. Identify and isola:s r'a to the affected 0TSG(s) to limit RCS cooldown and/cr :srvent over pressurization of the Reactor Building.

3. Borate the RCS to assure it remains subcritical.

4 Stablize the plan: ' preparation for cooldown.

a. Reverifying - s :arameters marked with an asterisk in Immedia:e .5 ;al Action. Use redundant indication

, if available.

b. Verify ICS 5 a-":ns are in Automatic for the unaffected OTSG and tha: s plant stablizes at s 2155 psig s 545 F main:li-ing 1010 psig Header Pressure.

c. Commence plar.: ::o.idown on the unaffected 0TSG per OP 1102-11 (Fla : Cooldown),

d. If RB Isolation Occurred, reestablish RC pump motor and seal coolir.; when RB pressure goes below 3 psig.

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I.0 1123 081

& 0- 4

. Revision 3 STEAM 5'.07 I : I.N RUPTURE ACTUATI0tl C. 2 . ;_d GEt1ERATORS 32*.' SYMPTOMS

1. Rapid de reiss : :i:.'ndary steam pressure.

2. Electrica'. 1:i: 7:_:ing rapidly.

3. Decrease in : es ?. :er level, R.C. Pressure, and cold leg temoera:. e.

4. For a ruptars ' .3 :e the Reactor Building; Indication of increasir.; :_ ':f g pressure and temperature. (Possible high Raci:a:-f.' . 5 cels if a tube leak exists) .

5. For a ru?turs :_ :s the Reactor Building; floise may be heard ir. C: - : ::om or a report made from persor.nel outside the C: --:' :com.

6. Decrease ir. li- :.:ncenser hotwell level or condensate storage tar.k ' e , e-B2?.2 IMMEDIATE ACTION A. Automatic Acti:e

1. When the 5 ear ine Rupture Feedwater Block System actua es '<53' :sig) on both OTSGs, the following valves i. : : :se.

a) Sta r::.: rie: water Control Valves FW-V-16A/B.

b) Mai- Fee: vater Control Valves FW-V-17A/B.

c) E:e ;s c eedwater Valves EF-V-30A/B.

d) Mai- Fee .va:er Block Valves FW-V-5A/B.

e) S tt -::.: ree water Block Valves FW-V-92A/B.

P00R OlGINAL 4.0 m lic, 082 A

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, Revision 3 07/12/79

2. Reactor Trips - Low pressure due to excessive initial cooldown. l

3. Turbine Trip.

4. Pressurizer Heaters on due to low RCS pressure.

5. Possible High Pressure Injection at 1500 psig in

~

RCS and or 4 psig Reactor Building Pressure.

6. Possible Reactor Building isolation at 4 psig in Building.

B.II Immediate Manual Action For Steam Line Rupture on Both OTSG's NOTE: The parameters indicated with an asterisk (*)

will be reverified in the first step in the followup action.

1. Manually trip the Reactor and perform the immediate manual actions in EP 1202-4 (Reactor Trip).

2. Isolate Feedwater to both OTSG's. (The Steam Rupture Feedwater Block System will auto isolate the Feedwater System if OTSG Pressure decreases

<600spig.) Place the following ICS Control Stations in H nd and close FW-V-16A and B, FW-V-17A 7

and B and EF-V-30A and B.

3. Close MS-V-1A/8/C/D.

4. Chery Rx Building Pressure. If greater than 4 psig, assume rupture is inside Rx Buil 'ing and initiate full High Pressure Injection cooling, 5.0 1]u77 nnz

)os

. 1203-e.4 Pevision 3 .

0.7/12/79 CAUTION: Do not feed an OTSG rupture inside Rx Building to avoid over pressurizing the Reaction Building.

5. If Rx Building pressure is less than 4 psig (i.e.,

the rupture is outside the Rx Building) use an emergency feed pump to slowly feed one OTSG (preferably the OTSG with the higher pressure and level) and initiate RCS cooldown.

CAUTION: Before cooling RCS below 500 F, emergency borate to prevent Rx Restart accident.

CAUTION: If unable to initiate RCS cooling by feeding an OTSG within 10 minutes of Rupture System j actuation, initiate full High Pressure Injection Cooling.

B24.5 FOLLOWUP ACTION (BREAK AN BOTH STEAM GENERATORS)

~

Objective:

The objective is to:

1. Determine whether a good steam generator exists and reestablish feed to the good steam generator within 10

~

minutes or.

2. If the steam line break is outside containment reestablish emergency feed in a controlled manner to remove the decay heat within 10 minutes, or

3. Initiate full High Pressure Injection 'ooling thru the Electromatic Relief Valve, a) Reverify parameters in immediate Manual Action that are marked with an Esterisk (*). Use redundant indication whert available.

6.0 1123 084 .

Revision 3 07 b) If RCS cooling has oeen acheived using one/12/79 OTSG, emergency borate the RCS and continue cooldown per OP 1102-11 using emergency feed pumps as high pressure water source.

c) Attempt to locate and isolate steam line rupture by: Close MSV8A/B Close MSV2A/B NOTE: This will isolate steam to EF-P-1 assure motor driven pumps are on.

d) If either OTSG is dry, RCS cooldown rates must be monitored carefully so as not to exceed the maximum allowable OTSG shell to RCS temp differential of 100 F.

e) If full High Pressure Injection cooling was initiated monitor BWST level and shift suction to the Rx Building Sump at 3'. Do not throttle HPI cooling until heat removal by OTSG can be established or DH Removal can be placed in service. ,

t 7.0 1123 985. .. . -..-.

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