ML19345E282

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Public Version of Revised Abnormal Operating Procedure AP/1/A/5500/06, Loss of Steam Generator Feedwater.
ML19345E282
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 12/03/1980
From:
DUKE POWER CO.
To:
Shared Package
ML19345E268 List:
References
AP-1-A-5500-06, AP-1-A-5500-6, NUDOCS 8012230548
Download: ML19345E282 (3)


Text

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?AGI 1 0F 3 DUKE PC'a*IK COMPANY McGUIRI NUC'IAR STA~!CN LOSS OF SM GINIRATOR ::.s*4A~IR 1.0 Svmcrces 1.1 Main Feedwa:e Pump 1A and 13 tripped (Firs: Out).

1.2 Decreasing S/G level and associated alarss.

1.3 S/G A, 3 C, D Flow Mismatch la C7 Flo Alert.

2.0 I:mnediate Action 2.1 Automatic 2.1.1 Possible Reactor ::1p-turbine nip.

2.1.2 If 2/4 lo-lo level alarms in 1/4 S/Gs or both C7 pumps =ip, CA pumps lA & 13 s. art and feed S/G's.

2.1.2 Of 2/4 lo-lo level in 2/4 S/Gs, O CA pump starts and f mods S/Gs.

2.1.4 Steam dumps arm and/or actuate, or SM PORVs actua:e.

2.2 Manual CAU'" ION Inaccurate Pressurizer and S/G level rand *,gs may occur during accident conditions involving break.s inside cour=d -c. (This is caused by depressuri-zation and/or reference leg heatup). Ref er to Mc-Guire Data 3cok Table 2.6 for conect conversions for actual level. Use backup instrumentation (i.e.:

CA Flow, SM ?:sssure, NC Pressure and 'Jide Range Th, Tc).

2.2.1 if Reactor Power is > 32, =mm!'y =1p .he reactor and proceed to AP/I/A/5500/07 (Rc.:rion. Etip).

2.2.2 If the :urbine fails :o trip wnen required, proceed to AP/0fA/5500/34 (Acticu Re:ulted fon. Ant 1~i'vd T1:.uitM Midad Sc,ta.m Everi) and perform amplicable steps concur ent w1:h subsequent steps in this procedure.

2.2.3 *f no reactor =1p is required, proceed to step 2.2.3.

2.2.4 Verify CA flow from a: least one =ain is being delivered .o :he S/G's via MC3 flow indicators. If not, manually operate pumps.

2.2.3 DO NOT regulate CA flow until level indicates in .he narrow range i

of >02.

2.2.6 Verify that heat is being removed from the reactor via .he S/Gs by noting the fcllowing:

l E012230$% .

I-- -

. e A?/1/A/5500/06 O ricz or 2 2.2.6.1 Au:oma:ic steam dump :o condense is concurring, if not occurring, place Steam Header Pressure Controller :o

"===1 and manually dump sesam or via S/G PORV's.

2.2.6.2 NC Tave is decreasing towards prograasned no-load

emperature (557*7) .

NOTE Atmospheric steam dump is blocked by a reactor trip.

Condenser dump by C-9 and/or P-12. If cooldown below 553*?

Tave is required the 3ypass Ints locks must be used.

. 2.2.7 Ensure all required automa:ic actions occur.

3.0 Subsecuent Actions 3.1 Insure all required immediate ac:1ons have occurred.

3.2 ? oceed :o EP/0/A/5000/05 (Nod.fiesttian of Umtaua./. Event.5) and perform applicable steps concurrent with subsequent steps in :his procedure.

3.3 If any pressuriser PORV's open on high pressurizer pressure, ensure re-seating at 2315 psig decreasing. If any pressurizar PORV doas not reseat, close its associated isolation valve.

3.4 Announce occurrence on plant paging system.

3.5 Reset CA modulating valves and TD CA Pump and control CA to all steam genera-tors to obtain and maintain no-load water level 25ll narrow ange.

3.6 Monitor CA Condensate Storage Tank Level and Upper Surge Tank Level. Verify CA Suction auto-swap to RN at 2.0 psig suction pressure.

3.7 Place Steam Dumps in " Pressure" mode and verify hair operation to remove decay hea:. If Steam Dumps are no: available, ensure opera: ion of S/G FORVs and/or Steamline Safsties :o remove decay hear.

i 3.3 If any S/G PORV does not reseat below 1065 psig, close its associated isolation valve.

3.9 If :he PCRV Isolation Valves cannot be closed or if any Sc==='dn= Safety fails open, proceed :o EP/7/A/5000/05 (Secondsty Line huu:ste).

3.10 If :he CA pumps are not available and if the hin Feedwa:er Pumps cannot be restarted and if the Hoewell and Condensats booster pumps are operating, depressurias: the S/Gs to 400 peig with :he Steam Dumps and/or S/G PCRVs and feed with the Hoewell and Condensate Soester Pumps.

3.11 Reduce NC pressure as necessar7 to maintain <1600 paid across the S/G :ubes.

3.12 In :he event sufficient feedwater cannot be made available, proceed :o AP/7/A/5500/05 (Inadcoun.tr. Care Cooling) for fur her ac: ions.

, . - , . _.., , ,_.. y--m_ _- , . , _ . _ , , . _ , _ _ _ ,, . .. , - . , , , , y~.. . , , . ,

e e AP/1/A/5500/06 PAGE 3 0F 3 3.13 Deter:nine cause for trip of C7 Pumps, C7 Isolation, valve nalfunction, acc. and take necessary corrective action.

3.11. Reset feedvater isolation if it has occurred.

3.15 Align feedvater flow to the upper feedvater no::les as follows:

S/G "A": Open 1CF-1263 (A S/G C7 to CA Nozzle Isci.)

Close IC7-35A3 (A S/G C7 Cont. Isol.)

S/G "3": Open 1C7-1073 (3 S/G C7 to CA Nozzle Isol.)

Close 1C7-30A3 (3 S/G C7 Cont. Isol.)

S/G "C": Open 1C7-12S3 (C S/G C7 to CA Nozzle Isol.)

Close 1C7-2SA3 (C S/G C7 Cont. Isol.)

S/G "D": Open 1C7-1293 (D S/G C7 to CA Nozzle Isol.)

Close 1C7-26A3 (S/G ID Feedvatar Cont. Isol.)

3.15.1 Close ICF-150 (Tempering Supply Shutoff) .

3.15.2 Open the following:

S/G "A" 1CF-134A (A S/G C7 Cont. Isol. Bypass)

S/G "3" 1C7-135A (3 S/G CT Cont. Isol. Bypass)

S/G "C" 1C7-136A (C S/G C7 Cont. Isol. Bypass)

S/G "D" 1C7-137A (D S/G CF Cont. Isol. Bypass) 3.16 Verify pressurizar level is restored to =25% and pressure at a value reached in Step 3.11.

3.17 Proceed to OP/1/A/6250/01 (Condensate and Feedveter System) for restart of Feedvater System.

.. .. . ..._ - . _ .. . _ . - _ _ . . . ~ . - . . ..... . - _ - ..---. . .- = . .... _ -. ~ . . . -.-.-

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.1 AP/1/A/5500/06 - LOSS OF STEAM GENERATOR FEEDWATER r NRC COMMENTS DUKE'S RESPONSE li Old Step New Step 1

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1.4 Deleted ,

1 i

j' 2.2.1, 2.2.2 2.2.1, 2.2.2 [

1 l Note after 2.2.5.2 Note after 2.2.5.2 4

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3.7 3.6 i x

l 3.10 3.9 i 3.14 3.12 i

1 3.17 3.19

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