ML20205B127

Rev 2 to Emergency Operating Procedure EOP 35 E-3, Steam Generator Tube Rupture

ML20205B127
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	06/15/1988
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
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ML20204H467	List: A07413, Forwards Specific Emergency Operating Procedures for Use During Incident Response Ctr Activation ML20204H704 ML20204H734 ML20204H868 ML20204H928 ML20204H963 ML20204J027 ML20204J039 ML20204J092 ML20204J109 ML20204J115 ML20204J120 ML20204J128 ML20204J133 ML20204J139 ML20204J147 ML20204J497 ML20204J543 ML20204J565 ML20204J627 ML20204J633 ML20204J638 ML20204J642 ML20204J659 ML20204J669 ML20204J685 ML20204J707 ML20204J733 ML20204J739 ML20204J746 ML20204J767 ML20204J781 ML20204J786 ML20204J814 ML20204J824 ML20204J849 ML20204J853 ML20204J865 ML20204J878 ML20204J902 ML20204J914 ML20204J920 ML20204J939 ML20204J947 ML20204J954 ML20204J958 ML20204J965 ML20204J975 ML20204J982 ML20204J994 ... further results
References
EOP-35-E-3, NUDOCS 8810260189
Download: ML20205B127 (32)

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{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ STATION PROCEDURE COVER SHEET ( A. IDENTIFICATION \\v/ Number: E0P 35 E-3 Rev. 2

Title:

STEAM GENERATOR TUBE RUP1URE Prepared By: R.F. MARTIN / JOHN L. BUCKINGHAM B. REVIEW ! have reviewed the above procedure and have found it to be satisfactory. TITLE $!GNATURE DATE DEPARTMENT HEAD G [/ 99-- ~ e ~ j s C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED: Modifies intent of procedure and changes operation of systems as described in design documents. YES ( ) NO ( 7 (If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.) I ,I ENVIRONMENTAL REVIEW REQUIRED I 1 (Adverse environmental impact) YES ( ) NO (( D. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response. YES ( ) NO (( (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.) E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO(/ m PROCEDUREREQUIRES(PORd/SORCREVM F. (In addition to rev E items with a YES response t mustbedocumentedinthet>0Rk/50RCmeetingminutes.1 YES d NO ( ) %-./ G. PORC 50RC APPROVAL '50RC Meeting Number 3-? /- 2c 7 H. APPROVAL AND IMPLEMENTATION [ The attached procedure is hereby approved, and effective on the la

• be'ca:

l [ $ ~ D. *, ^ r r Station / Service / Unit Superintendent Effa;tive Data O SF301/9/s/SES/87-12/lof1 8910260189 801007 PDR ADOCK 050 Py3 P {

4 4 i j E0P 35 E-3 Page 1 Rev. 2 O STEAM GENERATOR TUBE RUPTURE l t l Page No. Eff. Rev. 1 - 29 2 l i ? l i I O l l I t !A r O

i l STEAM GENERATOR TUBE RUPTURE E0P 35 E-3 Page 2 Rev. 2 j 'l A. PL% POSE I i This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube l rupture. The operator should complete steps 1-21 in an expeditious manner to meet the 30 minute time requirement assumed in Chapter 15 of 1 the FSAR. B. ENTRY CONDITIONS This procedure was written for Modes 1, 2 and 3 assuming RHR System t not in service. Using this procedure when not in these modes requires a step by step evaluation te determine if the required action is still applicable to current plant conditions. 4 I 1. This procedure is entered from [ l-1 a. E0P 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 24 when i l l steamline radiation condenser air ejector radiation, or SG [ blowdown radiation is abnormal. i j b. E0P 35 E-0,* REACTOR TRIP OR SAFETY INJECTION, Step 30, t i E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 4, k EOP 35 E-2, FAULTED STEAM GENERATOR ISOLATION, Step 6, and EOP 35 FR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, i l Step 7, when secondary radiation is abnormal f l c. E0P 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 29 E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 3, i E0P 35 ES-1.2. POST-LOCA C00LD0kW AND DEPRESSURIZATION, j i Step 6, j E0P 35 ES-3.1, POST SGTR COOLDOWN USING BACKFILL, Step 4, E0P 35 ES-3.2, POST-SGTR C00LD0kW USING BLOVDOWN, Step 4, ) d E0P 35 ES-3.3, POST-SGTR C00LDOWN USING STEAM DUMP, Step 4, t E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00f r.D l RECOVERY DESIRED, Step 9, [ E0P 35 ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED { RECOVERY DESIRED, Step 4, and E0P 35 ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, i 1 Step 5. then a SG narrow range level increases in an l uncontrolled manner. d. E0P 35 ECA43.3, SGTR VITHOUT PRESSURIZER PRESSURE CONTROL, i Steps 2, 3, and 4, when pressurizer pressure control is [ restored. r E0P 35 E-1 series foldout page whenever any SG 1evel i e. increases in an uncontrolled manner or any SG has abnormal 4 radiation. s' I l J o.os4 ts. j i

ditMI UtNLRATOR [UbE RUPfURE E0P 35 E-3 Page 3 Rev. 2 n ('xJ STEP ACTIO4 EXPECTED RESPONSE RESPONSE NOT OSTAINED NOTE 1. Foldout page should be open 2. Personnel should be available for sampling during this procedure. 3. Seal injection flow should be maintained to all RCPs. 1 Check If RCPs Should Be Stopped a. ECCS Pumps - AT LEAST ONE 4. Go to Step 2 CHARGING PLMP OR SI PLHP RUNNING b. RCS pressure < 1435 psia b. Go to Step 2. (1700 psia FOR ADVERSE CONTAINMENT) c. STOP all RCPs O OP*W4-1 3 to

blLAM UthtRATOR IUSE RUPIURE E0P 35 E-3 Page 4 Rev. 2 \\v STEP ACTIONctXPECTED RESPONSE RESPONSE NOT OSTAINED 2 Identify Ruptured SG(s) Continue with Steps 5 through 12. WHEN ruptured SG(s) identified THEN do Steps 3 and 4. a. Unexpected increase in any SG narrow range level 01 b. High radiation from any SG sample 01 c. High radiation from any SG steamline

1) IF the radiation monitoring computer is NOT available.

THEN have an HP Technician manually ,c determine Main Steam (L Line Radiation - NORMAL. 01 d. High radiation from any SG blowdown line I J O C#%%81 3 64

7 SIEAM GENERAluR IUbE RUPllkE E0P 35 E-3 Page 5 Rev. 2 STEP ACTION EXPECTED RESPONSE RESPONSE NCT CETAINED CAUTION 1. If the turbine driven AFW pump is the only available source of feed flow, steam supply to the turbine-driven ATV pump must be maintained from at least one SG. 2. At least one SG must be maintained available for RCS cooldown. 3 Isolate Flow From Ruptured SG(s) a. Transfer the ruptured SG(s) atmospheric dump controller to MANUAL, adjust the setpoint to 1125 psig, and return the Controller to AUTO. O' b. Check ruptured SG(s) b. VMEN ruptured SG atmospheric dump - pressure < 1125 psig, CLOSED THEN verify SG atmospheric dump closed. IF NOT closed, THEN place atmospheric dump controller in manual ard close atmospheric dump. If atmospheric dump can M be closed, THEN CLOSE atmospheric dump isolation valve. If atmospheric dump isolation valve can NOT be closed THEN focally isolate atmospheric dump, c. CLOSE steam supply valves c. IF at least one MD AFV from ruptured SG(s) to pump running, THEN turbine-driven AFV pump locally isolate turbine-driven AFW pump d. Verify blowdown tsolation d. Manually close valvels) valve (s) from ruptured SG(s) - CLOSED G OFSNo9 3 44

blLNI bLnLKALUK ILbb N L F I L X2, LOF J3 E*J Fage D Rev. 2 ,n s t } \\v' RESPONSE NOT OBTAINED STEP ACTION. EXPECTED RESPONSE e. CLOSE ruptured SG(s) main e. Perform the following steam trip valves and bypass valves

1) CLOSE all remaining 30 main steamline isolation and bypass valves

2) CLOSE OR verify

. closed all valves in Table 1

3) Use intact SG(s) atmospheric dump for steam dump.

IJJ any ruptured SG can M be isolated from at least one intact SG, THEN go to E0P 35 ECA-3,1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCCOLED m RECOVERY DESIRED, \\ Step 1. f. CLOSE the main steam line drains upstream of the MSIVs. g. SG Blowdown Sampic Isolation valves - CLOSED O z _...

d1LA.'I GuitKAIOR IUbE RUFILKE EOP 35 E-3 Page 7 Rev. 2 3((j STEP ACTION EXPECTED RESPONSE RESPONSE NOT ORTAINED CAUTION If any ruptured fG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless needed f)r RCS cooldown. 4 Check Ruptured SG(-) Level a. Wide range level > 49%

a. Maintain feed flow to (34% on narrow range FOR ruptured SG until ADVERSE CONTAINMENT) at level > 49% (34% on nors.al operating narrow range FOR temperature of 560*F.

ADVERSE CONTAINMENT) If wide range NOT available, THEN maintain feed flow until narrdw range l level > 4% (34% FOR ADVERSE CONTAINMENT) Continue with Step 5. WHEN ruptured SG level i > 49% wide range (34% narrow range FOR ADVERSE CONTAINMENT), l THEN stop feed flow to ruptured SG(s). i i i L cPK48 5 344

blLN1 Vt.NLXALVX ILbt XLflLKL LOP 35 E-3 Fage 6 Rev. 2 O (v) STEP ACTION / EXPECTED RESPONSE RESPONSE NOT CSTAINED CAUTION If any PZR PORY opens because of high PZR pressure, Step Sa should be repeated after pressure decreases to less than the PORV setpoint. 5 Check PZR PORVs and Block Valves a. PORVs - CLOSED a. IF PZR pressure < 2350 psia, THEN manually CLOSE PORVs. IF any valve can NOT be closed THEN manually CLOSE its block valve. IF block valve can NOT be closed, THEN go to E0P 35 ECA-3.1, SGTR VITl! LOSS OF REACTOR () COOLANT - SUBC00 LED \\_, RECOVERY DESIRED, Step 1. b. Block Valves - AT LEAST b. OPEN one block valve ONE OPEN UNLESS it was closed to isolate an open PORV. 6 Check If SGs Are Not Faulted a. Check pressures in all a. Verit'y all faulted SGs SGs - NO SG PRESSURE isolated unless needed DECREASING IN AN for RCS cooldown UNCONTROLLED MANNER AJ No SG COMPLETELY

1) Steamlines DEPRESSURIZED

2) Feedlines IF NOT, THEN go to E0P 35 E-2. FAULTED STEAM GENERATOR ISOLATION, Step 1.

O] \\-- 3 s,.,...

5IEAM G' fE J.- NPIllRE EOP 35 E-3 Page 9 Rev. 2 m h ACTIOpttxPECTED RESPONSE RESPONSE NOT OBTAINED STEP CAUTION CST water source for AFV pumps will be necessary if DWST level decreases to < 80,000 gal. NOTE If the SG 1evels are out of the narrow range, the wide range SG level indication should be used to anticipate approach to the narrow range and also as an early aid in identifying previously undetected steam generator tube failures. 7 Check Intact SG Levels a. Narrow range level a. Maintain total feed > 4% (34% FOR ADVERSE flow > 525 spm until CONTAINMENT) narrow range level > 4% (34% FOR ADVERSE O CONTAINMENT) in at least one SG. b. Control feed flow to b. IF narrow range level in maintain narrow range level any intact SG continues between 4% (34% FOR ADVERSE to increase in an CONTAINMENT) and 50%. uncontrolled manner, TlfEN return to Step 1. CAUTION If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment. 8 RESET SI 9 RESET Containment Isolation Phase A And Phase B s h5.ta1 ) 44

.i I d4LNI OL?iLKA4UK 4Lbt XVriLKt E0P 35 E-3 Fage 10 Rev. 2 /m ( ) ) %,/ l STEP ACTION! EXPECTED RESPONSE RtlPONSE NOT OSTAINED 10 Instrument Air to Containment - Establish instrument air to l ESTABLISKED containment. 1) One instrument air compressor RlPNNING. 2) OPEN instrument air containment isolation

valves, 11 Verify All AC Busses -

a. Try to restore offsite ENERGIZED BY OFFSITE POWER powet b. IF necessary, T) FEN manually load the following equipment onto the ac emergency busses

1. Instrument air compressor

2. PZR heaters

3. Fuel building filter

[T system s_ /

4. Fuel pool cooling pump c.

Energize MCC 32-3T and verify it is supplying Inverter 6 I s h CM41 ) $4

i i STEAM GENERATOR TUBE RUPTURE E0P 35 E-3 Page 11 Rev. 2 [') l s/ s STEP ACTHMd.EXPE CTED RESPONSE RESPON$t NOT OBTAINED i CAUTION kCS pressure should be monitored. If RCS pressure decreases to < 300 paia (450 psia FOR ADVERSE CONTAINMENT), the RHR pumps must be manually res'.arted to supply water to the RCS. 12 Check If RHR Pumps should Be Stopped RCS pressure > 300 psia a. Go to Step 11 a. (450 psia FOR ADVERSE ^ CONTAINHENT). b. STOP RHR pumps and place in AUTO ( CAUTION Isolation of the ruptured SG(s) from the intact SG(s) to be used for RCS cooldown should be completed by closing the main steamline tsolation and bypass valves for the ruptured SG(s) or for the intact SG(s) before continuing to Step 13, unless a ruptured SG is needed for RCS coollown. 13 Check Ruptured SG(s) Pressure Go to E0P 35 ECA-3.1, SGTR 425 psig. WITil LOSS OF KEACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, Step 1. i O ,s.....

ditAM GENERATOR TUSE RUPTURE E0P 35 E-3 Page 12 Rev. 2 (~'T t_ / t STEP ACTIOP0 tIPECTED RESPONlt RE3PON8t NOT ORTAINED NOTE 1. Low steamline pressure J' should be blocked when PZR pressure decreases to < 2b'0 psia. 2. The low-Low TAVG interlock sh'uld be bypassed at 553*F to maintain steam dump operation 3. The RCP trip cirteria applies ONLY until an operator controlled RCS cooldown is i itiated in step 14 below. 14 Initiate RCS Coolv wn a. Determine required core exit temperature RUPTURED SG PRESSURE (PSIC) (ORE EXIT TFMPERATURT. (*F) NOR?tAL ADVERSE 4 ~~~ 1185 523 460 1085 512 467 985 499 452 885 488 452 785 474 436 685 458 418 585 4 '.0 397 513 425 377 1 a. Ownp steam to condenser b. Manually Uk locally dutp from intact SG(s) at steam at maximwn rate maxinium rate to atmosphere. IF intact SG(s) not avatlable. THEN use a faulted 3G OR go to E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUEC00 LED RECOVERY DESIRED, Step 1. c. Core exit TCs c. Return to Step 14b. c REQUIKED TEMPERArt'RE d. Stop PCS cooldown OU e

MLMI GENERAIOR ILbE RUFIL;KE ~ EOP 35 E-3 Page 13 Rev. 2 gy i ( ) l V STEP ACTION-EXPECTED RESPONSE RESPONSE NOT COTAINED l CAITTION RCS cooldown in Step 14 should be completed before continuing to Step )$. l l l l 15 Check Ruptured SG(s) Pressure - IF, pressure continues to l STABLE OR INCREASING decrease to wsthin 250 psi of I the intact SG(s) used for cooldown, THEN go to E0P 35 i l ECA-3.1, SGTR WITH LOSS OF LEACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1. 16 Check RCS Subcooling Based Go to E0P 35 ECA-3.1, SGTR On Core Exft TCs > 50*F WITH LOSS OF REACTOR CC.JLANT - l (110*F FOR ADVT.dSE SUBC00 LED REC 01'ERY DESIRED, CONTAINMENT) Step 1. l l 1 1 l

^ ~j, lt d A LN) OL.'ir KA A UM L U5L XUt'1UKL LVF jb b-j fage 14 Rev. 2 ~ . f 'y. G STEP j ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 17 Depressurize RCS To Minimize Break Flow And Refill PZR a., Normal PZR spray - A. Go to Step 18. OBSERVE AVAILABLE CAUTION PRIOR TO STEP 18. b. Spray PZR with maximum available spray UNTIL

1) RCS pressure < RUPTURED SG PRESSURE AND PZR level > 7% ( F% FOR ADVERSE CONTAINMENT)

M

2) PZR level > 73% (50%

FOR ADVERSE CONTAINMENT) E

3) RCS subcooling based on core exit TCs < 30'F (90'F FOR ADVERSE CONTAINMENT)

I c. Close spray valve (s)

1) Normal spray valve (s)

1) STOP RCP(s) supplying l

failed spray valve (s). l r

2) Auxiliary spray valve

2) Isolate auxiliary spray line.

d. Go to Step 20. OBSERVE CAUTION PRIOR TO STEP 20 t i I 1 i I } I i

STEAM GENERATOR TUBE RUPTURE E0P 35 E-3 Page 15 Rev. 2 i ) x_ - STEP ACTH3N/ EXPECTED RESPONSE RESPONSE NOT OBTAINED i CAUTION 1. The PRT may rupture if a PZR PORV is used to depres;urize the RCS. This may result in abnormal containment conditions. 2. Cycling of the PZR PORV should be minimized. NOTE The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PZR level. 18 Depressurize RCS Using PZR PORV to Minimize Break Flow And Refill PZR 3 f ') a. PZR PORV - AT LEAST ONE a. Establish auxiliary spray \\- AVAILABLE and return to Step 17b. IF auxiliary spray can NOT be established, TilEN go to E0P 35 ECA-3.3, SGTR WITIIOUT PRESSURIZER PRESSURE CONTROL, Step 1. 1 b. OPEN one PZR PORV UNTIL

1) RCS pressure < RUPTURED SG(s) PRESSURE MD PZR level > 7% (50% FOR ADVERSE CONTAINMENT)

QR

2) PZR level > 73% (50% FOR ADVERSE CONTAINMENT) 26

3) RCS sut oling based on core exit TCs < 30"F (90*F FOR ADVER'E CONTAINMENT) 7-s,

{ i 'N c. CLOSE PZR PORV c. CLOSE PORV block valve. C Pk41 1 3 84 t

f bitAll bhhERAION 1066 hUriUht EOF d5 E-3 Page 10 Rev. 2 ') 1 './ l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Check RCS Pressure - CLOSE PZR PORV block valves l INCREASING IF pressure continues to i decrease, THEN perform the following 1) Monitor for indication of leakage from PZR PORVs 2) Go to E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, STEP 1. t/ Ns-O PSCd.8 1 3 84

SIEAM GENERAIOR IUBE RUPIURE E0P 35 E-3 Page 17 'Rev. 2 -I} w/ STEP ACTION / EXPECTED RES.*0NSE RESFONSE NOT OBTAINED CAUTION Voiding in the upper head region should NOT preclude SI termination. SI KUST BE TERMINATED when termination criteria are satisfied to prevent overfilling of the ruptured SG(s) 20 Check If ECCS Flow Should Be Terminated a. RCS subcooling based a. 00 NOT STOP ECCS PUMPS. on core exit TCs GC TO E0P 35 ECA-3.1, > 30 F (90 F FOR SGTR WITH LOSS OF ADVERSE CONTAINMENT) REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, Step 1. b. Secondary heat sink b. 'Ij[ neither condition ^ satisfied, THEN DO NOT [)

1) Total feed flow to STOP ECCS PUMPS. Go to

\\m / SG(s) > 525 gpm E0P 35 ECA-3.1, SGTR AVAILABLE WITH LOSS OF REACTOR COOLANT - SUBC00 LED OR RECOVERY DESIRED, Step 1.

2) Narrow range level in at least one intact SG

> 4% (34% FOR ADVERSE CONT $INMENT) c. RCS pressure - STABLE OR c. DO NOT STOP ECCS PUMPS. INCREASING Go to E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, Step 1. d. PZR level > 7% (50% FOR d. DO NOT STOP ECCS PUMPS. l ADVERSE CONTAINMENT) Return to Step 13. l l O V l ChKAa 1 3 84

SitAM GENERATOR IUBE RUPTURE E0P 35 E-3 Page 18 Rev. 2 ) (' _/ STEP ACTICR4/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 STOP ECCS Pumps And Place In AUTO a. SI pumps b. All but one charging pump 22 Isolate Charging Pump Injection Flow Path a. IF two charging pump cold leg injection valves are i open, THEN CLOSE one valve. h. Establish 60 gpm normal charging path, c. CLOSE '.he Charging Pump miniflow isalations to the RWST (3CliS*MV8511 A/B). I d. CLOSE a Chatging Pump Cold / 'N Leg Injection valve. s 23 OPEN the Charging Pump Recirc Isolations 1 24 Control Charging Flow To Maintain PZ.< Level e n \\ \\._ / O P50^8 1 3 84

STEAM GENERATOR TUBE RUPIURE E0P 35 E-3 Page 19 Rev. 2 p O STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Verify ECCS Flow Not Required a. RCS subcooling based on a. Manually operate ECCS core exit TCs > 30'F pumps as necessary. Go (90'F FOR ADVERSE to E0P 35 ECA-3.1, SGTR CONTAINMENT) WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED, Step 1. b. PZR levdl > 7% (50% b. Manually operate ECCS FOR ADVERSE CONTAINMENT) pumps as necessary. IF level can NOT be maintained, THEN go to E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, Step 1. 26 Check IF Containment Spray should be stopped. a. Quench Spray pumps - a. Go to Step 27. RUNNING ( ) L/ b. Containment pressure b. Continue with Step 27. < 13 PSIA WHEN containment pressure < 13 PSIA, THEN do Steps 26c and d. c. RESET CDA signal. d. STOP containment spray pumps and place in AUTO.

1) STOP Quench Spray pumps.

2) STOP Containment Recire pumps.

3) CLOSE Chemical Addition Isolation valves.

27 Check VCT Makeup Control Adjust controls as necessary. System a. Makeup set for > RCS ) boron concentration b. Makeup set for automatic operation ( ~h LJ OPKA41 3 64

blLAM GENERATOR TUBE RUPTURE E0P 35 E-3 Page 20 Rev. 2 ( ) u.,. STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check If Letdown Can Be Established a. PZR level > 17% (50% FOR a. Continue with Step 29. ADVERSE CONTAINMENT) WHEN PZR level increases to > 17% (50% FOR ADVERSE CONTAINMENT), Tl!EN do Step 28b. b. Establish letdown b. Establish excess letdown in accordance with OP 3304A, CHARGING AND LETDOWN 29 Align Charging Pump Suction To VCT a. OPEN VCT to charging isolation valves b. CLOSE RWST to charging isolation valves (G i O) tV c5vu, s en

4 STEAM GENERATOR TUBE RUPTURE E0P 35 E-3 Page 21 Rev. 2 ( ) L/ STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINS 3 CAUTION RCS and ruptured SG(s) pressures must be maintained less than the ruptured atmospheric dump setpoint. 30 Control RCS Pressure And Flakeup Flow To flinimize RCS-To-Secondary Leakage a. Perform appropriate actica(s) from table RUPTURED SG(s) f NE L INCREASING DECREASING OFFSCALE PZR LEVEL I lilGH Increase RCS Increase RCS Increase RCS Makeup Flow t!akeup Flow ?!akeup Flow LESS TIL\\N 17% (50% AND AND (q') FOR ADVERSE CONTAIN?!ENT) Depressurize ?!aintaia RCS RCS Using And Ruptured Step 30b SG(s) Pressures Equal BETkIEN Depressurize Turn On flaintain RCS 17% (50% RCS Using PZR And Ruptured FOR ADVERSE Step 30b Ilea te rs SG(s) Pressures CONTAINMENT) Equal AND 50% BETVEEN Depressurire Turn On flaintain RCS 50% AND RCS Using PZR And Ruptured 73% (50% Step 30h ifcaters SG(s) Pressures FOR ADVERSC Ag Equal CONTAINt!ENT) Decrease RCS ffakeup Flow _ GREATER TilAN Decrease RCS Turn On flaintain RCS 73% (50% Makeup Flow PZR And Ruptured FOR ADVERSE llea te r s SG(s) Pressures CONTAINttENT ) Equa l b. Use normal PZR spray b. IF letdown is in service, per Step 30a TilEN use auxiliary spray. IF NOT, TilEN use one PZR (nv) PORV. OPKM 1 3 84

D A LAll OL.NLMA1VM IUbb MUr1LKt LOP 35 b-J Page 44 Rev. 2 '/ ) LJ STEP ACTH3N/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Check If Diesel Generators Should Be Stopped a. Verify ac emergency a. Try to restore offsite busses - ENERGIZED BY power to ac emergency 0FFSITE POWER busses. b. RESET any LOP, SIS, or CDA signal at MB2. c. Stop any unloaded diesel generator and place in standby d. RESET Station LOP at both Sequencer panels. e. RESET, then turn ON eac's Diesel Sequencer Au',omatic Tester toggle , witch. ('~'T f. CLOSE Feeder Breakers to 'x / Emergency Generator m Distribution Panels 3EGSwPNLIA at 32-1T-3H and 3EGS*PNLIB at 32-1U-3H l v cruu.i 34

SIEAM GENERATOR IUBE RUPIURE EOP 35 E-3 Page 23 Rev. 2 / 't N.) f RESPONSE NOT OBTAINED STEP ACTION / EXPECTED RESPONSE 32 Minimize Secondary System Contamination a. Verify steam isolated to MSRs b. Align auxiliary steam to auxiliary boiler supply per OP 3331A, AUXILIARY BOILER STEAM AND CONDENSATE c. Align gland seal steam to auxiliary steam supply per OP 3323D, TURBINE GLAND STEAM AND EXHAUST d. Isolate steam to turbine-driven feedwater pumps - VALVES 3TFM-V7 AND 3TFM-V8 CLOSED e. Isolate condensate recire to CST - VALVES 3CNS-V9 () AND 3CNS-V11 CLOSED \\m / f. Shutdown the condensate demir.eralizer mixed bed system per OP 3319C, CONDENSATE DEMINERALIZER MIXED BED SYSTEM. g. Sample Turbine Building and CPE sumps for radioactivity 33 Turn ON PZR liesters As Necessary To Saturate PZR Water At Ruptured SG(s) Pressure ____34 Check RCP Cooling - NORMAL a. RCP RPCCW System flow - a. Establish normal cooling FLOW EXISTS to RCPs per OP 3304A, CilARGING AND LETDOWN, OR OP 3330A, REACTOR PLANT COMPONENT COOLING WATER. b. RCP seal injection flow - b. Adjust as necessary using FLOW BETWEEN 8 - 13 gpm CllS-IICV-182 (V opycaa s ee

ditNI UthtKKlUM 'A ubb F.UP A UME LOF 3$ E-3 Fage 24 Rev. 2 / i L,/' STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Check If RCP Seal Return Flow Should Be Established a. RCS pressure > 115 psia a. Go to Step 36 b. OPEN seal leakoff header containment isolation valves - FLOW ESTABLISIIED c. Verify seal return flow from each RCP - PROPER FLOW EXISTS /'N., (V ) = N '\\'J L._ C P*A44 1 3 84

SIEAM GENERATOR TUBE RUPTURE E0P 35 E-3 Page 25 Rev. 2 ( ,l' STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If RCP seal cooling had previously been lost the affected RCP should not be started prior to status evaluation. NOTE RCPs should be run in order of priority (RCP 2, 1 THEN 3 or 4) to provide normal PZR spray. 36 Check RCP Status a. RCPs - AT LEAST ONE a. Try to start one RCP RUNNING

1) IF RVLMS head level OR plenum level < 100%

THEN raise PZR level 90% (90% FOR ADVERSE [s) CONTAINMENT),ND 3 \\~ / increase RCS subcooling based on core exit TCs 's 70*F (95'F FOR ADVERSE CONTAINMENT).

2) Establish conditions for tttrting an RCP per OP 3301D, REACTOR COOLANT PUMP OPERATION.

3) ST?RT one RCP.

IF an HCP can NOT be started, THEN refer to Table 2 to verify natural circulation. IF natural circulation NOT verified, THEN increase dumping

steam, b.

STOP all BUT one RCP O z _..

ditAtl bthtKAAUM IUbb MUFAUKL EUF 35 t-3 Fage Zb Rev. 2 ] v l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ____37 Check If Source Range Detectors Should Be Energized a. Check intermediate range a. Continue with Step 38. flux - < 10E-10 amps WHEN flux < 10E-10 amps, THEN do Steps 37b and c. b. Verify source range b. Manually energize detectors - ENERGIZED Post Accident Neutron

Monitors, c.

Transfer NR-45 recorder to source range scale 38 Shut Down Unnecessary Plant Equipment a. Align RPCCW for cooldown per OP 3330A, REACTOR PI. ANT COMPONENT COOLING WATER. ('~)/ b. Evaluate secondary plant (_, status and shut down equipment as appropriate. I 7" 's- / NPyta.1 3 04

STEAM GENERATOR TUBE RUPIURE E0P 35 E-3 Page 27 Rev. 2 l' \\ ) v STEP ACTIOP0' EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 Check status of steam generators a. Two steam generators a. With less than two intact intact sts ' generators, Consult with the Director of Station e Emergency Organization (DSE0) on advisability of isolating the ruptured steam generator (s) by closing the appropriate loop stop valves. b. No RCP's operating and b. IF operating RCP in plant verified in natural an intact steam generator circulation in accordance loop then go to 39.C. with Table 2. OR IF operating RCP in a ruptured steam generator 7-.s loop then go to Step 40. (v) c. Consult Director of Station Emergency Organization (DSEO) to close ruptured steam generator (s) loop isolation valves. rs ( ) v CIP*/V4 1 3 64

d a tNJ btM ~ ~ * ~~ '( t..g. s c -i 1 ~ I 1 L RFSPONSE F.!f 0STAl'/ED STEP AC,' # -{ , _40 Go Iw Cooldov .e. a. e UL 2t:., y1 i 0. b. Go to eor 3. 3.2, POST-SGTR C00Luchd 11 SING BL0k% WN, Step 1 O_R c. Go to E0P 35 ES-3.3, POST-SGTR C00LDok3 USING STEAM DUMP, Step 1 O__R. d. Ga to OP 0208, PLANT CJ0LD0kW -FINAL-om44.i t e.

l { ditAf uthEMAluK IUbE nUPAURE EOP 35 E-3 Page 29 Rev. 2 s ) t D. OPERATOR AIDS Table 1: SG Backup Isolation Valve Lineup. Table 2: Conditions for Natural Circulation Flow. i i 1 I i l s i O OPK44-2 3 44 I

I STEAM GENERATOR TUBE RUPTURE E0P 35 E 3 Page 1 of I Rev. 2 (~~b \\~-] j TABLE 1 SG BACKUP ISOLATION VALVE LINEUP VALVE FUNCTION 3 MSS-MSVI MAI4 STEAM STOP VALVE 3 MSS-MSV2 MAIN STEAM STOP VALVE 3 MSS-MSV? MAIN STEAM STOP VALVE 3 MSS-MSV4 MAIN STEAM STOP VALVE 3 MSS-MOV50A A REHEATER STEAM SUPPLY ISOLATION 3 MSS-MOV50B B REHEATER STEAM SUPPLY ISOLATION 3TME-MOV33 Gl.AND STEAM SUPPLY FROM MAIN STEAM 3 ASS-V971 MAIN STEAh! SUPPLY PCV INLET JASS-V969 MAIN STEAM SUPPLY PCV BYPASS JMSS-VI9 TURBINE BYPASS PV-47A ISOLATION 3 MSS-V21 TURBINE BYPASS PV-48A ISOLATION O' 3 MSS-V23 TURBINE BYPASS PV-49A ISOLATION 3 MSS-V25 TURB1NE BYPASS PV-47B ISOLATION 3 MSS-V27 TURBINE BYPASS PV-48B ISOLATION 3 MSS-V29 TURBINE BYPASS PV-49B ISOLATION 3 MSS-V31 TURBINE BYPASS PV-47C ISOLATION 3 MSS-V33 TURBINE BYPASS PV-48C ISOLATION 3 MSS-V35 TURBINE BYPASS PV-49C ISOLATION 3TFM-V7 SG FW PP IB MAIN STEAM INLET.tSOL 3fFM-V8 SG IV PP 1A MAIN STEAM INLET ISOL 3 MSS-V907 SG D SAMPLE ISOLATION 3 MSS-V908 SG D SAMPLE ISOLATION 3 MSS-V909 SG C SAMPLE ISOLATION 3 MSS-V910 SG C SAMPLE ISOLATION 3 MSS-V911 SG B SAMPLE ISOLATION 3 MSS-V912 SG B SAMPLE ISOLATION 3 MSS-V913 SG A SAMPLE ISOLATION 3 MSS-V914 SG A SAMPLE ISOLATION OP N 2 3 44

STEAM GENERATOR TUBE RUPTURE E0P 35 E-3 Page 1 of 1 Rev. 2 '~' w/ TABLE 2 The following conditions support or indicate natural circulation flow

1. RCS subcooling based on cose exit TCs > 30*F (90'F FOR ADVERSE CONTAINMENT)

2. SG pressures - STABLE OR DECREASING

3. RCS hot leg temperatures'- STABLE OR DECREASING

4. Core exit TCs - STABLE OR DECREASING

5. RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE

O OPKeel 3-84}}