ML20155H585

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Rev 5 Tp Procedure E.05, Excessive Heat Transfer
ML20155H585
Person / Time
Site: Rancho Seco, 05000000
Issue date: 10/26/1985
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20155H523 List:
References
RTR-NUREG-1195 E.05, E.5, NUDOCS 8605160292
Download: ML20155H585 (36)
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Text

{{#Wiki_filter:...- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. /Y Effective Date 10-26-85 Rev. 5 WP0004F l D-0063P E.05 EXCESSIVE HEAT TRANSFER Operator Action 1. Maintain Pressuri-1. Mainta'in pressurizer level above 100". zer level above 100" .1 Keep makeup to the minimum necessary. .2 1E pressurizer level is below 100" AND RCS pressure is decreasing THEN increase makeup as necessary. .1 Open HPI valve loop A 1 (SPV-23811). .2 Start HPI Pump P-238B (HPI Pump lined up to the BWST). i .3 Throttle loop A HPI injection valve SFV-23811 as necessary to control pressurizer level. .4 IE pressurizer level cannot be l maintained above 100" THEN ~ initiate Full HPI (Rule 1 and 2). k 2. IE it is apparent 2. IE it is apparent that one OTSG is that one OTSG is causing the overcooling. TREN go to causing the over-Step 21, otherwise continue. cooling, THEN go to Step 21 otherwise Indications continue. .1 Excessive MFW flow (H1RI) .2 Excessive AFW flow (H2PSA) .3 Higher level in one OTSG .4 Lower pressure in one OTSG (HIRI) ) i 8605160292 860306 PDR ADOCK 05000312 S PDR Rev. 5 E.05-1 k i I -, e m _. .J

II .l E.05 I EXCESSIVE HEAT TRANSFER 5+ 3. .4 Terminate steaming by verifying valves closed. Turbine B/P PSV-20563 PSV-20566 i PSV-20561 PSV-20564 F' ADV PV-20571A PV-20562A PV-20571B PV-205628 PV-20571C PV-20562C H2SFA and H2SFB Valve A OTSG B OTSG F AFW Bypass SFV-20577 SFV-20578 H2YS l Valve A OTSG B OTSG MS Aux FWP HV-20569 HV-20596 Main Sta to Reheaters MV-20598 HV-20597 Pegging Stm HV-32243 Main Sta to Aux Sta !!V-2056 5 HV-20560 i 4. 1E OTSG level and 4. LE OTSG 1evel and pressure have stabil-pressure have ized or are increasing, in BOTH OTSGs. stabilized or are (steam-leak / overfeed isolated) THEN go increasing, in to Step 14. Otherwise continue. BOTH OTSGs. (steam leak / overfeed Indications of level and pressure isolated) THEN go to Step 14. Other- .1 SPDS a wise continue. .2 HlRI g. .1 OTSG pressure e .2 OTSG level. Use S/U or wide range. l S. IF OTSG level and 5. IF OTSG 1evel and pressure are L pressure are decreasing in BOTH OTSGs, THEN go to decreasing in BOTH Step 24. Otherwise continue. OTSGs, THEN go to i Step 24. F Otherwise continue. I u i u Rev. 5 I E.05-3 l e I r r

E.05 sm,- EXCESSIVE HEAT TRANSFER OVERCOOLING IS OCCURRING FROM AN UNIDENTIFIED OTSG CAUTION i Shutting main steam to aux steam HV-20560 and HV-20565 causes

  • you to lose the air ejectors and sealing steam to the turbine.*

Condenser vacuum will decrease to 20" very quickly, causing g the TBV to fail shut. Therefore, close main steam to aux y steam HV-20560 and HV-20565 last and reopen first (as soon [ as possible).. L .......................re.......................................... t i 3. Isolate both OTSGs 3. Isolate both OTSGs.

L f

.1 Perform this Step (3.1) IE l OTSG level increases t 5 on the 5+ operating range, OTHERW CONTINUE WITH STEP 3.2 63 .1 Trip both MFW Pumps'. .I .2 Stop AFW Pump P-318. .3 Start / verify start of Motor Driven AFW Pump P-319. .4 Continue with Step 3.2. I 5+ .2 Terminate. flow to both OTSG's by + closing the following valves. H1RC or HISS Valve A OTSG B OTSG AFW Control FV-20527, FV-20528 l_HIRI m...._ Valve A OIgg B OTSG S/U FW Control FV-20575 FV-20576 MFW Control FV-20525 FV-20526 MFW Block FV-20529 FV-20530 N- - . ~ I 5+ .3 If feedwater flow continues, tr'ip appropriate feed pumps to 4 j + terminate flow. 3 I Rev. 5 I E.05-2 1 1 d ... ~ = -e, d

( ' q.', ~ E.05 EXCESSIVE HEAT TRANSFER 1 5+ 3. .4 Terminate steaming by verifying valves closed. Turbine B/P PSV-20563 PSV-20566 } PSV-20561 PSV-20564 ADV PV-20571A PV-20562A PV-205718 PV-20562B PV-20571C PV-20562C H2 SPA and H2SFB ~~ Valve A OTSG B OTSG AFW Bypass SFV-20577 SFV-20578 H2YS Valve A OTSG B OTSG MS Aux FWP HV-20569 HV-20596 Main Sta to Reheaters HV-20598 HV-20597 Pegging Sta HV-32243 Main Sta to Aux Stu HV-20565 HV-20560 4. 1E OTSG level and 4. 1E OTSG 1evel and pressure have stabil-pressure have ized or are increasing, in R2IK OTSGs, stabilized or are (steam leak / overfeed isolated) IHKE go increasing, in to Step 14. Otherwise continue. BOTH OTSGs. (steam leak / overfeed Indications of level and pressure isolated) THEN go to Step 14. Other- .1 SPDS ,j wise continue. q .2 HlRI } .1 OTSG pressure .2 OTSG level. Use S/U or wide range. S. IF OTSG level and 5. IF OTSG level and pressure are { pressure are decreasing in RgIK OTSGs, IHEN go to g decreasing in BOTH Step 24. Otherwise continue. g OTSGs, THEN go to 1 Step 24. Otherwise continue. 1 Rev. 5 E.05-3 4

p ~g I 4 E.05 EXCESSIVE HEAT TRANSFER 1 v i i PRESSURE AND LEVEL ARE STILL DECREASING ON ONE OTSG. 6. Complete isolating 6. Complete isolating the OTSG that has the OTSG that has the steam leak. j the steam leak. .1 The OTSG with decreasing level and/ or pressure has the st' sam leak. 2 .2 Verify closed the following' valve I on the LEAKING OTSG at Panel H1RI. Valve M B OTSG l MFW Block FV-20529 FV-20530 .3 Allow the steam leaking OTSG to boil dry. DO HOI go to Loss of g Heat Transfer. Section E.04. .......................v........................................... CAUTION Once the overcooling transient is terminated, decay heat will reheat the RCS. Since no mass was lost from the RCS, and additional mass was put in by the HPI System, an uncontrolled heatup could fill the pressurizer due to swelling of the system and cause as solid and/or ~- overpressure condition. YERI important to hold RCS temp constant, establish letdown to control pressurizer level. (l*F change in Tave = 5 inch chan .......................e.............ge in pressurizer level.) 7. Establish heat 7. Establish heat transfer to the OTSG transfer to the without the steam leak. OTSG without the j steam leak. .1 Establish MFN to only the good OTSG using Startup FW Control .1 Maintain pre-Valve FV-20575 (A OTSG) or o ] sent RCS temp. FV-20576 (B OTSG). (Rule 4) .1 IE OTSG level is < 8" on SU Range, use Aux FN only. j< I i l t 4 Rev. 5 s_. E.05-4 } ii l il- --. s-m

[E { .T E.05 1 ij EXCESSIVE HEAT TRANSFER I 1 4 7. .2 lE MFW is not available. THEN establish AFW to only the good OTSG (non-steam leaking). LE AFW control valves FV-20527 A OTSG, and FV-20528, B OTSG. were closed at HISS, the valve to be used, i needs to be placed in automatic at HISS to allow manual / auto control i at HlRC. .3 Adjust TBVs on OTSG without the I. steam leak to maintain RCS temp at its present value. .1 SPDS Post Trip Display OTSG Tsat Line (purple vertical j line) should be approximately t equal to Tc. ] .2 Tsat for OTSG pressure, at H1RI approximately equals wide range Tc at H1RI. i .3 IF TBVs fail to operate, use ADVs until TSVs are operable. 8. Control HPI as 8. Control HPI as necessary. (Rule 2) necessary. (Rule 2) .1 Avoid excessive subcooling margin. a .2 Energize pressurizer heaters to establish pressurizer saturate conditions when the low level interlock clears. (40") .3 When pressurizer saturate conditions are restored. maintain approximately 100 inches l { pressurizer level. .4 Reestablish letdown flow if p previously isolated. Rev. 5 j E.05-5 1

_... _. _ =... h Q

1 d

E.05 'I EXCESSIVE HEAT TRANSFER .l il

12. LE reactor vessel
12. 1E reactor vessel thermal shock limits thermal shock are exceeded (Rule 6). THEN perform limits are exceeded the following; otherwise continue.

(Rule 6), THEN perform the follow- .1 Stabilize temperature and pressure i ing; otherwise below the Interim Brittle Fracture continue. Curve (SPDS or Fig. 1) by depressurizing. i .1 Stabilize ( temperature and .2 Prevent any heatup or j pressure below pressurization. Maintain present l the Interim temp and pressure for at least 3 P Brittle Frac-hours. l 4 ture Curve (SPDS or Fig 1) .3 Contact Station Management. I by depressuri-l zing. .2 Prevent any i heatup or pres-surization. h Maintain present temp 1 and pressure for at least 3 hours. .3 Contact Station Management. i

13. Go to CP.102.
13. Go to CP.102.

I STATUS RCS is subcooled with pressure and temperature stable. Only I one OTSG is operable and steaming to the condenser or j atmosphere. i j l 4 I i f Rev. 5 E.OS-7 g I

k w a E.05 EXCESSIVE HEAT TRANSFER g i~ 9. IE RB temperature 9. IE RB temperature increases to 120*F QR increases to 120*F 75% humidity. IHEN start 4 RB gg 21% Emergency Coolers with NSCW and NSRN. humidity, THEN start 4 RB Energ-Indications ency Coolers. Temp TJR-07 at' Panel H2X Humidity TJR-06 at Panel H2X

10. IE there is a loss
10. IE there is a loss of subcooling of subcooling mar-margin, IHEN, go to Section E.03.

gin, IHEN, go to Otherwise continue. o Section E.03, Otherwise continue. Indications of Subcooling Margin .1 System pressure /inco're temperature above variable subcooling margin line on SPDS .2 Saturation Temperature for RCS pressure 50* or greater than l incores or Th .3 50* subcooling as read on subcooling margin monitors on c Panel H2SFA and H2SFB i s,

11. IP an OTSG tube
11. IF an OTSG tube rupture is indicated, rupture is indica-THEN go to SGTR Section E.06, Step 9.

ted, THEN go to Otherwise continua. SGTR Section E.06, Step 9. Otherwise Indications of SGTR continue. .1 Increased readings on air ejector off gas R-15004. .2 Increased readings on gland exhaust monitor R-15021. .3 At Panel H1DRNS (RM 11) .1 R-15047 M/S Line A 5 .2 R-15048 M/S Line B I-l l v h q" fU Rev. 5-i E.05-6 g

~~ _., _ ~ ~ l V 0 b E.05 l EXCESSIVE HEAT TRANSFER fj s-- i J OTSG PRESSURES AND LEVELS STABLIZED WITH BOTH OTSG ISOLATED. I p CAUTION I h Once the overcooling transient is terminated, decay heat will reheat the RCS. Since no mass was lost from the RCS, and additional mass was put in by the HPI System, an uncontrolled heatup could fill the pressurizer due to y swelling of the system and cause as solid and/or a ] overpressure condition. VERY important to hold RCS temp constant " establish letdown to control pressurizer level. 0 (1*F change in Tave = 5 inch change in pressurizer level.

  • ..............................................................).....

=

14. Establish heat
14. Establish heat transfer to both OTSGs.

transfer to both OTS G,s. .1 Establish MFW to both OTSGs using Startup FW Control Valves FV-20575 and FV-20576 on HlRI. (Rule 4) .1 1E OTSG level is < 8" on SU Range, use Aux FW only. .2 IE MFW is not availble. THEN establish AFW to both OTSGs. [ (Rule 4) IE AFW control valves FV-20527 A OTSG, and FV-20528 B OTSG, were closed at HISS, the valves need to be placed in automatic at HISS to allow manual / auto control at H1RC. b .1 Maintain pre- .3 Adjust TBV on each OTSG to maintain sent RCS temp-present RCS temperature. IE TBVs { erature. are not operable. THEN use ADVs until TBVs are operable, f .1 On SPDS Post Trip Display, j OTSG Tsat Line (purple i vertical line) should be approximately equal to Tc. } .2 Tsat for OTSG pressure, at l, H1RI, approximately equals 4 wide range Tc at HlRI. D b 5+ .4 If TBVs fail to operate, use ADVs d until TBVs are operable. F Rev. 5 E.05-8

_m._ 7 ~' b { f E.05 EXCESSIVE HEAT TRANSFER

15. Control HPI as
15. Control HPI as necessary.

(Rule 2) r necessary. (Rule 2) .1 Avoid excessive subcooling margin. .2 Energize pressurizer heaters to establish pressurizer saturate conditions when the low lever interlock clears. (40*) .3 When pressurizer saturate conditions are restored, maintain approximately 100 inches pressurizer level. .4 Reestablish letdown flow if previously isolated. l .......................~........................................... CAUTION Once the overcooling transient is terminated, decay heat will reheat the RCS. Since no mass was lost from the RCS, l and additional mass was put in'by'the HPI System, an uncontrolled heatup could fill the pressuriter due to l swelling of the system and cause as solid and/or overpressure condition. VERY important to hold RCS temp constant, establish letdown to control pressurizer level. / I (l*F change in Tave = 5 inch change in pressurizer level.) NOTE I Condenser vacuum if lost would disable TBVs and MFPs. In the l OTSG isolation steps HV-20597 and HV-20598 main steam to aux ) steam were shut which'would cause a loss of turbine seal steam, air ejectors, and condenser vacuum. i

16. IP there is a loss 3 R.,

F there is a loss of subcooling margin l of subcooling mar- ) HEN go to Section E.03, otherwise ontinue. i gin THEN go to i Section E.03, ~ otherwise continue. Indications of Loss of Subcooling Rev. 5 E.05-9 l g l

. ~.. _ _ - - - - - - - - - - l E.05 EXCESSIVE HEAT TRANSFER 1 I i

18. IE A OTSG tube rup-
18. IE a'OTSG tube rupture is indicated, I

ture is indicated, THEN go to SGTR Section E.06 Step 9. THEN go to SGTR Otherwise continue. Section E.06, Step l 9. Otherwise Indications of SGTR continue. .1 Increased readings on air ejector off gas R-15004. j l .2 Increased readings on gland i exhaust monitor R-15021. .3 At Panel H1DRMS (RM-11) .1 R-15047 M/S Line A .2 R-15048 M/S Line B

19. IP reactor vessel
19. IF reactor vessel thermal shock limits thermal shock are exceeded (Rule 6), THEN perform

) limits are exceeded the following; otherwise continue. 1 (Rule 6). THEN perform the follow- .1 Stabilize temperature and pressure ing; otherwise below the Interim Brittle Fracture continue. Curve (SPDS or Fig. 1) by depressurizing. .1 Stabilize temperature and .2 Prevent any heatup or pressure below pressurization. Maintain present the Interim temp and pressure for at least 3 i Brittle Frac-

hours, ture Curve s

(SPDS or Fig 1) .3 Contact Station Management. by depressuri-

zing, f

.2 Prevent any heatup or pres-surization. Maintain i present temp i and pressure y for at least i 3 hours, .3 Contact Station } Management. L 1 Rev. 5 4 E.05-11 i i \\

j I 'i E.05 s _, EXCESSIVE HEAT TRANSFER s c 16. .1 System pressure /incore temperature above variable subcooling margin line on SPDS e .2 Saturation Temperature for RCS 4 pressure 50* or greater than j incores or Th .3 50* subcooling as read on subcooling margin monitors on i. Panel H2SFA and H2SFB

17. Start QHE RCP per
17. Start QEK RCP per loop.

loop. .1 A loop pump .1 Start A loop pump RCP-210B first first and let and let RC system overcome initial g RC system pressure transient. overcome initial pressure transient. .2 Start B loop .2 Start B Loop Pump RCP-210D (par. ,~~ ~ Pump RCP-210D. spray). RC Pump start interlocks. .1 <30% Reactor power .2 RCP motor oil lift > 1750 psig .3 RCP motor upper bearing oil level i 2 inches .4 RCP motor lower bearing oil ~ level i 2 inches .5 Seal injection flow > 3 gpa .6 RCP CCW flow > 307 gym .7 To start fourth RCP Tc > 500*F .8 Motor 86 Lockout (Motor Protection Relay) Normal.- Green Light Din Abnormal - Green Light Bright 1 .1 I.; 1 i Rev. 5 E.05-10 1 m - ,3._. . _ _ ~ - _, -.v ~-- M

E.05 A EXCESSIVE HEAT TRANSFER 1 a.

20. Maintain stable RCS 20. Maintain stable RCS temperature and temperature and pressure.

Notify Station Management. pressure. Notify Go to OP B.4. Station Management. Go to OP B.4. STATUS An overcooling has occurred due to either excessive FN or a e steam -leak. If there are other abnormal symptoms, treat them j per the applicable section of this procedure. If there are no j abnormal' symptoms, this procedure is complete. I \\ l n .g i i L I 1 t, i l i l I Rev. 5 E.05-12 F w C8'IP *- FM'MP ^ '*f , T M+* 6 *M N .r--- ,v 4ema- -. - -...-u. A N

...m_..___m____. .__..m... 1 ') I' E.05 EXCESSIVE HEAT TRANSFER f -l OVERCOOLING IS OCCURRING FROM ONE APPARENT OTSG l l'

21. Isolate the over-
21. Isolate the overcooling OTSG.

E cooling OTSG. .1 Perform this step (21.1) ONLY IF OTSG level increases to 95% on the ~ 5+ operat'ing range. OTHERWISE CONTINUE WITH 21.2. g f? L .1 Trip both MFW Pumps. .2 Stop AFW Pump P-318. .3 Start / verify start of Motor Driven AFW Pump P-319. Verify L AFW flow on Panel H2PS. .4 Continue with Step 21.2. v ~ 5+ .2 Terminate flow to both OTSG's by closing the following valves. H1RC or HISS Valve A OTSG B OTSG AFW Control FV-20527 FV-20528 H1RI Valve A OTSG B OTSG L S/U FW Control FV-20575 FV-20576 MFW Control FV-20525 FV-20526 MFW Block FV-20529 FV-20530 l-5+ .3 If feedwater flow continues, trip l appropriate feed pumps to terminate flow. .4 Terminate steaming by verifying valves closed. Turbine B/P PSV-20563 PSV-20566 PSV-20561 PSV-20564 ADV PV-20571A PV-20562A f PV-20571B PV-20562B l PV-20571C PV-20562C 4 H2SFA and H2SFB Valve A OTSG B OTSG AFW Eypass SPV-20577 SPV-20578 l I-Rev. 5 E.05-13 i t

. - - - -. ~, - - - - - - - - - = - l l E.05 [ EXCESSIVE HEAT TRANSFER BOTH OTSGs ARE ISOLATED BUT LEVELS AND/OR PRESSURES ARE STILL DECREASING.

24. Initiate HPI
24. Initiate HPI cooling (Rule 1).

cooling. .1 Manually initiate SFAS channels lA and IB ONLY at HlRC. .1 Immediately take manual control and open RCP Seal Return Isolation Valves SFV-24004 and SFV-24013 at H2SFA and H2SFB. .2 Open HV-21505, EMOV Block Valve (HIRC). j' .3 Run one RCP as long as subcooling margin is maintained.

25. IF Rx vessel PTS
25. IF Rx vessel PTS limits are exceeded limits are exceeded THEN DO NOT allow RCS pressure to THEN DO NOT allow increase.

Maintain thermal shock RCS pressure to region on Figure 1. increase. Maintain thermal shock .1 >100*F/hr cooldown rate below 500*F region on Figure 1. .2 HPI flow with RCPs off below 500*F

26. Ensure isolation
26. Ensure isolation of MFW to both OTSGs.

I of MFW to both OTSGs. .1 Verify closed the following valves: l A OTSG B OTSG MFW Block Valve FV-20529 FV-20530 MFW Control Valve FV-20525 FV-20526 l MFW S/U Valve FV-20575 FV-20576 I i Rev. 5 E.05-15 i e l

E.05 EXCESSIVE HEAT TRANSFER m 21. .4 H2YS Valve A OTSG B OTSG MS Aux FWP HV-20569 HV-20596 Main Sta to Reheaters HV-20598 HV-20597 Pegging Sta HV-32243 l Main Sta to Aux Stu HV-20565 HV-20560

22. IE pre'ssure and
22. IE pressure and level have' stabilized level have stabili-or is increasing on the overcooling zed or is OTSG (steam leak / overfeed isolated),

increasing on the THEN go to Step 14. Otherwise overcooling OTSG. continue. (steam leak / Indications of Level and Pressure overfeed isolated). .1 SPDS IHER go to Step 14. Otherwise .2 HlRI continue. .1 OTSG pressure [ .2 OTSG 1evel use S/U or wide range. l

23. Go to Step 6.
23. Go to Step 6.

\\_/ ) 1 i I I Rev. 5 E.05-14 1 4 1 .. _ _ _ = t

i 1 i

l E.05 0

EXCESSIVE HEAT TRANSFER li i

27. Jft EB pressure,
27. R RB pressure, temperature, or temperature, or humidity is increasing. THEN go to humidity is Step 38.

increasing, THEN <j go to Step 38. .1 RB pressure on H2X. .2 RB temperature on TJR-07 at Panel H2X. 4 .3 RB humidity read on TJR-06 at } Panel H2X. j l N I 1 i A J f a t l 9 Rev. S j E.05-16 i m ~*e~ ~~-+==w:-=__..en_,,g_=_.

y i 1 1 E.05 1 EXCESSIVE HEAT TRANSFER ] BOTH OTSGs HAVE STEAM LINE BREAKS OUTSIDE THE RB.

28. Start and run one
28. Start and run one RCP in each loop as long as minimum subcooling margin is RCP in each loop j

{ as long as minimum maintained. subcooling margin is maintained. .1 Indications .1 System pressure /incore temperature above variable subcooling margin line on SPDS. .2 Saturation temperature for RCS pressure 50* or greater than incore or Th* .3 50' subcooling as read on the Subcooling Margin Monitors on Panel H2SFA and H2SFB.

29. Establish heat
29. Establish heat transfer to BOTH OTSGs.

i transfer to BOTH OTSGs. .1 Start AFW Pump 319 and AFW Pump 318 on electric drive from Panel HISS. .2 Trickle feed both OTSGs using AFW 1:. control valves FV-20527 for A OTSG and FV-20528 for B OTSG at Panel HlRC.

30. Secure HPI
30. Secure HPI cooling.

cooling. I

31. Commence RCS cool-
31. Commence RCS cooldown (AFW flow

-j down (AFW flow determines cooldown rate). j determines cool- ? down rate). .1 AFW flow to the OTSG will control the cooldown rate of the RCS. j l .2 Monitor AFW flow to each OTSG at Panel H2PS. .3 Monitor RCS Te at: .1 SPDS .2 HlRI .4 DO NOT exceed 100*F/hr cooldown rate. Rev. 5 ti E.05-17 A i e-

4 y u E.05 D EXCESSIVE HEAT TRANSFER

32. IE tube to shell
32. 1E tube to shell AT approaches 150*F AT approaches on either OTSG. THEN slow the cooldown ll 150*F on either as necessary to prevent exceeding the OTSG, IHgg slow 150*F ar limit.

the cooldown as necessary to .1 Tube to shell AT computer Point prevent exceeding A OTSG - G-613 the 150*F AT B OTSG G-614 limit. ~ NOTE Ensure adequate source of feedwater. l

33. IE pressure and
33. 1E pressure and level can be restored level can be to both OTSGs, IHER go back to Step 14, restored to both otherwise continue.

4{ OTSGs, THEN go !} back to Step 14, .1 Conditions Otherwise continue. .1 Pressure in OTSG can be controlled at about saturation pressure for the cold leg temperature. .2 Appropriate OTSG level. Rule 4 34 1E pressure and

34. IE pressure and level can be restored t

level can be to ONLY ONE OTSG, IHgg go back to restored to ONLY Step 6 otherwise continue. ONE OTSG, M go back to Step 6 .1 Conditions otherwise continue. .1 Pressure in OTSG can be controlled at about saturation pressure for the cold leg temperature, d, .2 Appropriate OTSG level. M (Rule 4) ( 35 1E a OTSG tube

35. lE a OTSG tube rupture is indicated, rupture is indi-IHER go to Step 52, otherwise cated IHgg go to continue.

!( Step 52, otherwise continue. Indications .1 Steam Line Monitors R-15047 and R-15048. +4 ~- Rev. 5 E.05-18 j I [ 1, __ _p-__ ~ ~

r E.05 EXCESSIVE HEAT TRANSFER BOTH OTSGs HAVE STEAM LINE BREAKS OUTSIDE THE RB. 't

28. Start and run one
28. Start and run one RCP in each loop as l}

RCP in each loop long as minimum subcooling margin is i j as long as minimum maintained. ' i subcooling margin ' l is maintained. .1 Indications .1 System pressure /incore ) temperature above variable subcooling margin line on SPDS. .2 Saturation temperature for RCS pressure 50* or greater than incore or T - h .3 SO' subcooling as read on the Subcooling Margin Monitors on Panel H2SFA and H2SFB.

29. Establish heat
29. Establish heat transfer to BOTH OTSGs.

i transfer to BOTH OTSGs. .1 Start AFW Pump 319 and AFW Pump 318 on electric drive from Panel MISS. .2 Trickle feed both OTSGs using AFW control valves FV-20527 for A OTSG and FV-20528 for B OTSG at Panel H1RC.

30. Secure HPI
30. Secure HPI cooling.

cooling.

31. Commence RCS cool-
31. Commence RCS cooldown (AFW flow down (AFW flow determines cooldown rate),

determines cool-down rate). .1 AFW flow to the OTSG will control the cooldown rate of the RCS. .2 Monitor AFW flow to each OTSG at i Panel H2PS. .3 Monitor RCS Tc'at: .1 SPDS .2 HlRI .4 DO NOT exceed 100*F/hr cooldown l rate. i Rev. 5 E.05-17 j 4 1 1 y =....

c' E.05 EXCESSIVE HEAT TRANSFER 35. .2 Radiation readings for steam lines displayed on SPDS alpha-numeric and on H1DRMS (RM-11). .3 Gland Steam Radiation Monitor, b R-15021 .4 Air Ejector off gas. R-15004

36. IP a small break
36. IP a small break LOCA has also LOCA has also occurred, THEN go to CP.103 Step 11.

l occurred. THEN go Otherwise continue. to CP.103 Step 11. Otherwise continue. Indications .1 Increase RB sump level. .2 RB Radiation alarms. l

37. Go to OP B.4,
37. Go to OP B.4 Section 5.0.

Section 5.0. ) l STATUS i The RCS is being cooled by trickle feeding BOTH OTSGs with [ AFW. BOTH OTSGs have steam line breaks outside of the RC. i 'i b b 9 Rev. 5 E.05-19 i

e E.05 EXCESSIVE HEAT TRANSFER s- ..s' AT LEAST ONE AND POSSIBLY BOTH OTSGs HAVE STEAM LINE BREAKS IN THE RB. ~ i

38. 1E it is determined 38. IE it is determitted that at least one that at least one steam line break has occurred outside

-]j ~ steam line break the RB, IHEN secure from HPI coolin. has occurred out-if initiated and go to Step 41, side the RB, THEN otherwise continue. secure from HPI ] coolin'g -if initiated and go to Step 41, otherwise continue.

39. Verify HPI
39. Verify HPI cooling (Rule 1).

cooling. 3 .1 Manually initiate SFAS channels 1A i and 1B ONLY at HlRC. .1 Immediately take manual control and open RCP Seal Return Isolation Valves SFV-24004 and SFV-24013 at H2SFA and H2SFB. .2 Open HV-21505 EMOV Block Valve (H1RC). .3 Run one RCP as long as subcooling margin is maintained.

40. Go to CP.104.
40. Go to CP.104.

1 i't STATUS The RCS is being cooled by HPI cooling. At least one and possibly both OTSGs have steam line breaks in the RB and neither OTSG can be fed unless it is later determined that one j OTSG has a steam line break outside the RB. l l t = .i j Rev. 5 '~ ^ E.05-20

E.05 EXCESSIVE HEAT TRANSFER y ONE OTSG HAS A STEAM LINE BREAK OUTSIDE THE RB AND THE OTHER OTSG HAS A STEAM LINE BREAK INSIDE THE RB.

41. Immediately start 41.'

Immediately start 4 RB Emergency 4 RB Emergency Coolers.with NSCW and NSRW flow. U Coolers with NSCW and NSRW flow. .1 Start 4 Emergency Coolers on H2SFA and H2SFB. .2 Start NSRW and NSCW Pumps on H2SFA and H2SFB.

42. Start and run one
42. Start and run one RCP in each loop as RCP in each loop long as.a minimum subcooling margin is as long as a maintained.

minimum subcooling o margin is .1 Indications maintained. .1 System pressure /incore temperature are above variable subcooling margin line on SPDS. .2 Saturation temperature for RCS Pressure 50' on greater than incore or T ' h .3 50* subcooling as read on the subcooling margin monitor on ~' Panel H2SFA and H2SFB. N-43.' Establish heat

43. Establish heat transfer to only the transfer to only OTSG with the steam line breakeoutside the OTSG with the of the RB.

~ steam line break outside of the RB. .1 Start AFW Pump 319 and AFW Pump -l 318 on electric drive from Panel HISS. ~ .2 Trickle feed the OTSG with the steam line break outside the RB using AFW Control Valve FV-20527 for A OTSG and FV-20528 for B OTSG at Panel HlRC.

44. Secure HPI
44. Secure HPI cooling.

cooling. l 1 1 Rev. 5. E.05-21 i

i 1 E.05 EXCESSIVE HEAT TRANSFER l

45. If. there is a loss
45. If,there is a loss of subcooling of subcooling mar-margin, IHgg, go to Section E.03.

gin, IHgg go to Otherwise continue. Section E.03, j l otherwise continue. Indications of Subcooling Margin .1 System pressure /incore temperature above variable subcooling margin line on SPDS .2 Saturation. Temperature for RCS b pressure 50' or greater than l incores or Th i .3 50* subcooling as read on subcooling margin monitors on i Panel H2SFA and H2SFB

46. 1E tube to shell
46. IE tube to shell AT approaches 150*F AT approaches on either OTSG, IHEN slow the cooldown 150*F on either as necessary to prevent exceeding the OTSG, IHgg slow 150*F AT limit.

the cooldown as i necessary to .1 Tube to shell AT computer point: s_, prevent exceeding A OTSG - G-613 I the 150*F AT B OTSG - G-614 limit. l t HOIE Ensure adequate source of feedwater.

47. IE pressure and
47. IE pressure and level can be restored i

i level can be to both OTSGs, IHEE go back to Step 14 restored to both otherwise continue. OTSGs, IHEE go back to Step 14, .1 Conditions otherwise continue. .1 Pressure in OTSG can be l controlled at about saturation pressure for the cold ~1eg temperature. t .2 Appropriate OTSG 1evel. Rule 4 t l l Rev. 5 E.05-22 in

n.,__....__. t E.05 EXCESSIVE HEAT TRANSFER ONE OTSG HAS A STEAM LINE BREAK OUTSIDE THE RB AND THE OTHER OTSG HAS A STEAM LINE BREAK INSIDE THE RB. i i

41. Immediately start
41. Immediately start 4 RB Emergency 4 RB Emergency Coolers with NSCW and NSRW flow.

Coolers with NSCW and NSRW flow. .1 Start 4 Emergency Coolers on H2SFA and H2SFB. g i .2 Start NSRW and NSCW Pumps on H2SFA and H2SFB. ,P

42. Start and run one
42. Start and run one RCP in each loop as f

RCP in each loop long as a minimum subcooling margin is as long as a maintained. L minimum subcooling [ margin is .1 Indications y maintained. .1 System pressure /incore temperature are above variable subcooling margin line on SPDS. l- .2 Saturation temperature for RCS pressure 50* on greater than incore or T. 3 .3 50* subcooling as read on the subcooling margin monitor on Panel H2SFA and H2SFB.

43. Establish heat
43. Establish heat transfer to only the transfer to only OTSG with the steam line break outside the OTSG with the of the RB.

steam line break outside of the RB. .1 Start AFW Pump 319 and AFW Pump 318 on electric drive from Panel HISS. .2 Trickle feed the OTSG with the steam line break outside the RB using AFW Control Valve FV-20527 for A OTSG and FV-20528 for B OTSG at Panel HlRC. 1 i

44. Secure HPI
44. Secure HPI cooling.

i l cooling. ff 1

l Rev. 5 E.05-21 L

l {

2 I a E.05 ) EXCESSIVE HEAT TRANSPER l t

48. 1F pressure and
48. IP pressure and level can be restored level can be to ONLY ONE OTSG, THEN go back to restored to ONLY Step 6 otherwise continue.

ONE OTSG, THEN go back to Step 6 .1 Conditions otherwise continue. .1 Pressure in OTSG can be [ controlled at about saturation s pressure for the cold leg l temperature. } .2 Appropriate OTSG level. g (Rule 4) l

49. IP a OTSG tube
49. IP a OTSG tube rupture is indicated, y

rupture is indi-THEN go to Step 52, otherwise 1 cated. THEN go to continue. 3 Step 52, otherwise continue. Indications j .1 Steam Line Monitors R-15047 and i R-15048. 1 .2 Radiation readings for steam lines i displayed on SPDS alpha-numeric i and on H1DRMS (RM-11). .3 Gland Steam Radiation Monitor. R-15021 .4 Air Ejector off gas. R-15004

50. IP a small break
50. IP a small break LOCA has also

~ j LOCA has also occurred, THEN go to CP.103 Step 11. i occurred. THEN go Otherwise continue. to CP.103 Step 11. Otherwise continue. Indications ] .1 Increase RB sump level. .2 RB Radiation alarms. l

51. Go to CP.102.
51. Go to CP.102.

~ s STATUS The RCS is being cooled by trickle feeding one OTSG which has a steam break outside the RB. The other OTSG has a steam line break inside the RB and cannot be fed. Rev. 5 3 E.05-23 ij ,_,+-.__m, ~'

Y ~ E.05 EXCESSIVE HEAT TRANSFER E \\s, l A DOUBLE STEAM LINE BREAK HAS OCCURRED CONCURRENT WITH A SGTR. 1 NOTE Method of RCS Cooling is determined by the section of the l procedure that directed you here. 4

52. Turn off all par
52. Turn off all par heaters.

6 heaters. T

53. Confirm high radi-
53. Confirm high radiation readings and ation readings and verify the tube ruptured OTSG.

verify the tube q ruptured OTSG. .1 Have Rad-Chen sample steam lines. .2 Use frisker on cold lab cation columns. j

54. lE RCPs are
54. lE RCPs are running. IHEM use normal running, IHEE use pzt spray (PV-21509 or HV-21520) to normal pzr spr'ay reduce RCS pressure during cooldown.

(PV-21509 or HV-215020) to reduct 1 RCS pressure during s-cooldown. NOTE DQ HQI use auxiliary spray if the AT between the spray water (T-003) and the przr (T-009) exceeds 410*F. J

55. lE RCPs are not
55. LE RCPs are not running. IHgg manually j

running, IEEE align auxiliary par spray from HPI by ] manually align closing HV-23801 (H2SFB) and opening auxiliary pzt HV-23802 (H2SFB). Auxiliary spray can spray from HPI be controlled with SFV-23810 (H2SFB). 1 O r f

a l-E.05-24 Rev. 5 ll

[1L.----

1 p 0 E.05 EXCESSIVE HEAT TRANSFER i

56. Begin cooldown
56. Begin cooldown and depressurization, and depressuriza-Keep subcooling' margin between the tion.

Keep sub-variable subcooling margin line and cooling margin the VSM-30 line on the SPDS QR between the vari-between 50-80*F able subcooling to minimize primary to secondary margin line and

leakage, y

the VSM-30 line on 1 the SPDS gg .1 lE normal or auxiliary par spray 5 ? between 50-80*F to is not available, Iggg use par minimize primary vents HV-21515 and HV-21517 to secondary (H2PSA). Open the EMOV Block leakage. Valve HV-21505 (HIRC) and the EMOV PSV-21511 (HIRC) to reduce pressure further if required. y

57. Cooldown at the
57. Cooldown at the maximum attainable maximum attainable cooldown rate by varying AFW flow.

pg rate by varying NOf exceed 100*/hr. AFW flow, pq EgI exceed 100*/hr.

58. Block SFAS auto-
58. Block SFAS auto-initiation of channels initiation of
  1. 1 and #2 before reaching 1600 psig IE channels #1 and #2 full HPI.is not required.

gq HQI wait before reaching for 1600 psig to continued with this 1600 psig IE full procedure. HPI is not required. QO NOT wait for 1600 psig to continued with this procedure.

59. lE tube to shell
59. IE tube to shell AT approaches AT approaches 150*F, IHgg reduce the cooldown rate.

); 150*F, THEN reduce j the cooldown rate. .1 Indications: .1 ' G-613 (A OTSG) or G-614 (B OTSG .2 AT = Sum of OTSG Shell T/Cs - T-Number of T/Cs ~ OTSG A T/Cs OTSG B'T/Cs T-051 T-052 T-053 T-054 i T-055 T-056 T-057 T-058 T-059 T-060 .2 Reduce the AFW feed rate. Rev. 5 t E.05-25 ri L e_ w -- - 3 f, ,.___.,,m-

s..... I[ E.05 EXCESSIVE HEAT TRANSFER \\s- . i j

60. IE core cooling is
60. IE core cooling is by forced by forced circula-circulation, THEN go to B.4 Section tion, IHEM go to 5.0 to continue plant cooldown.

B.4 Section 5.0 to continue plant cooldown.

61. IE core cooling is
61. IE core cooling is by natural g

by natural circula-circulation. THEE go to B.4 Section y) ation IEEE gd to 6.0 to continue plant cooldown. B.4 Section 6.0 to J continue plant cooldown. NOTE The primary to secondary leak will continue until the RCS is drained below location of the leak. ( STATUS The RCS is subcooled and the pressurizer is controlling RCS pressure. A double steam line break has occurred concurrent with a SGTR. The RCS is being cooled'by trickle feeding one I or both OTSGs. i .i w -1 Rev. 5 .I '~ E.05-26 .l am e e4.**= m m% d,M g %.s..-...._ 41aeum h ome +-m - __ _. %gg -ey g m ms k g

y ? b r L FIEIRE 1 REACTut Com. ANT SYSTEM INTERIM FRACTtRE LIMIT ND FGtCED FLOW AND THERMAL SHOCK OPERATING REGION o ~ g:. 4+ 3200 q j g IEE: Maintaining the reactor b .. coolant subcooled takes 3M ~ l l precedence over the Interie NO FORCED FLOW lE 8rittle Fracture Curve OPERATING 8AND j(8&W74-1122501page6) W/HPI 2M '! INTERIM stkTTLE FRACTI* 2600 E C1RVE BREAK POINT 5-YARIA8lf : SU8C00 LED INTERIM BRITTLE lETENERATtmE PRE 55tRE FRACTURE CURVE m 4-MARG " i 2400 i[ 3 l: 303 250 z lE 500 1500 w 2200 _= = j 2000 RESTRICTED REGION r. (. 1800 i T. 5. CURVE 3.1.2-2 NOT LIMIT g gg )M -[ S >= M 5 1200 -- OPERATING REGION f g i ~ ~ ~~ INCGtE TC 5 TO MONITIIt'. -SATURATION { CURVE PREFEUtED At.TUtNATE ! j 800 - 1)T9254 79256 - 2)T9258 T9260 T9263 T9252 =_-- 3 )T9272 u 600 - i4 J 79266 T !5) T9286 T9270 - _J RESTRICTED REGION 5 400 - EEEEgggNNg,ggg Eggg EEEEEEEM ). _ - ~ .200 - - - _ - - - ~ .l ()* 0 EiiiiiiiEiiiiiiiiiEEiilliEliliiiiiiiiiim

== ~ O 100 200 3b 400 5bo 6bo 70( j !!El!CATED RC TENERATURE

  • F

] Rev. 5 E.05-27 's I r. - _. - - - - - ~ ~ - - - - - + - - -

~ i i i E.05 i EXCESSIVE HEAT TRANSFER

56. Begin cooldown
56. Begin cooldown and depressurization.

and depressuriza-Keep subcooling margin between the tion. Keep sub-variable subcooling margin line and cooling margin the VSM-30 line on the SPDS OR between the vari-between 50-80*F able subcooling to minimize primary to secondary a margin line, and leakage. the VSM-30 line on c the SPDS OR .1 IF normal or auxiliary pzr spray between 50-80*F to is not available. THEN use pzr [ minimize primary vents HV-21515 and HV-21517 i to secondary (H2PSA). Open the EMOV Block leakage. Valve HV-21505 (H1RC) and the EMOV { PSV-21511 (H1RC) to reduce pressure further if required. t

57. Cooldown at the
57. Cooldown at the maximum attainable maximum attainable cooldown rate by varying AFW flow.

DO l rate by varying NOT exceed 100*/hr. l AFW flow. DO NOT exceed 100*/hr. ~

58. Block SFAS auto-
58. Block SPAS auto-initiation of channels initiation of
  1. 1 and #2 before reaching 1600 psig [F channels #1 and #2 full HPI is not required.

DO NOT wait before reaching for 1600 psig to continued with this-1600 psig IF full procedure. HPI is not required. DO NOT wait for 1600 psig to continued with this procedure. i

59. IF tube to shell
59. IF tube to shell AT approaches a

AT approaches 150*F, THEN reduce the cooldown rate. 150*F, THEN reduce the cooldown rate. .1 Indications: .1 G-613 (A OTSG) or G-614 (B OTSG .2 AT = Sum of OTSG Shell T/Cs - T' Number of T/Cs q OTSG h T/Cs OTSG B T/Cs r T-051 T-052 T-053 T-054 T-055 T-056 T-057 T-058 T-059 T-060 .2 Reduce the AFW feed rate. f Rev. 5 E.05-25 e o ~ t

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-. ~ ~ ~. - ~.. _. _ 4,. L FIGURE 3 P i HIGH PRESSURE INJECTION FLOW i < 84P.,- 1 VS. REACTOR COOLANT SYSTEM PRESSURE i 1000 ____a .__..r-j .._......__._._4_.._ c .. =. _ = _._ 0; g JU ..g__. .w x-__._ _ - __.._ - n;;.-.;. :;. :,, _-- ._-. y 3.-... ~.. ,,y. __+_...u.=.n:-----.=:=== -1___ 800 - ..\\ .C.. __... -,----_._,'N..__.-t-*-

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_= =. _ n. FIGURE 2 CORE EXIT THERMOCOUPLE TEMPERATURE FOR INADEQUATE CORE CCOLING 3000 2800 -.i. 2600 I I at:ic* 2 i { 9'n'ru io' j se.e s.. l 2200 and fuel ;in REGION 3 damage possible._ j Gas sea *ratloa j Tclad <u.::*r. and fuel,l8 2000 ,,,, ii,,iy, l Tclad <l800'F. 4 n 1000 _J L t s ]

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  • f

[ REGION 4 ~ ~ 1200 Significant gas 9eneration and clad, d e.. .ie. j 1000

== .n Glow I

Subcooled f

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