ML20245K883

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Simulator Certification Submittal,Vol 4: 'Performance Test Rept.'
ML20245K883
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/29/1989
From: John Parillo
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20245K850 List:
References
NUDOCS 8907050291
Download: ML20245K883 (373)


Text

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_ _ _ _ _ . _ _ _ _ _ . _ _ . - - - - - - - - - , - - - - - - _ _ - - - . - - - _ - - - - - - --- m--'

O VOLUME 4 i

MILLSTONE UNIT 2 SIMULATOR PERFORMANCE TEST REPORT

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isR7288848s8886 P PDC

MILLSTONE UNIT 2 SIMULATOR MALFUNCTION CAUSES AND EFFECTS Approved:

ssisfant pervisor, Operator Training Date: .]~5-/.9P3 O

MALFUNCTION LIST MALF NO. RSCCW O CC01 RSCCW PUMP TRIP A. P-11A S. P-118 C. P-110 CCO2 RBCCW HEADER RUPTURE VARIABLE: 100% EtUALS 2,968 GPM LEAK RATE AT 120 P5ID A. LOCATED AT P-11 A DISCHARGE (DOWNSTREAM OF CHECK VALVE)

8. LOCATED AT P-11B DISCHARGE (DOWNSTREAM OF CHECK VALVE)

C. LOCATED AT P-11C DISCHARGE (DONNSTREAM OF CHECK VALVE)

SCO3 RBCCW SURGE TANK MAKEUP VALVE FAILURE VARIABLE: 100% EtVAL5 VALVE FULLY OPEN CC64 RfCCW HEAT EXCHANGER TUSE LEAK ,

VARIABLE: 100% E8UAL5 100 GPM LEAKAGE AT 100 Pf!D l A. HX-18A I

s. NX-188 l C. KX-18C CC05 RBCCW TEMPERATURE CONTROL FAILURE VARIABLE: 100% E90ALK 194 DEG r A. T!C-6308 (HX A)
5. TIC-6397 (KX B)

C. TIC-6306 (KX C)

CC66 LOSS OF RBCCW TO R0P l VARIABLE: 100% CSUALS TOTAL FLOM BLOCKAGE A. RCP-A C. RCP-C i S. RCP-8 D. RCP-D CCS? LOSS OF RSCCW 70 CEA COOLERS O- VARIABLE A. HX-34A 100% EGUAL5 TOTAL FLOW BLOCKAGE C. HX-340 i

S. HX-345 '

CCet LOSS OF RBCCW TO CONTAINMENT AIR RECIRCULATION COOLER I VARIABLE: 100% CSUALS TOTAL FLOW BLOCKAGE l A. HX-354 C. HX-350 l S. KX-358 D. HX-350 1 CC89 L055 0F RSCCW TO LETDOWN HEAT EXCHANGER VARI ABLE: 100X EtVAL5 VALVE FULLY 5 HUT CC10 RBCCW LEAK IH5!DE CONTA!NMENT VARI ABLE: 100X EGUAL5 156 GPM AT 120 PSID A CEDM COOLER A B CCDM COOLER B C: CEDM COOLER C Rev: 0 Date: 3/1/39 Pare: 1 of 29

MALTUkCTION 1.!$T MALF NO. HVAC CONTAINMENT _,

CNet CONTAINHCNT AIR RCCIRCULA1.ICN FAN TRIP s A. F-14A C. F-14C B. F-148 D. F-140 Rev: 0 Date: 3/1/89 Page: 2 of 29

MALFUNCTION LIYT MALF O

l NO. CORE CRet FUCL CLAD FAILURE VARIASLE: 190X EtVALS 2X SAS GAP ACTIVITY CRert INCORE NI FA! LURE VARIASLE: 100X E4UAL51160 MV OUTPUT 5!GNAL CR4211 (Alt RH1) CR0231 (97 RHi) CRS251 (C6 RH1) CR9271 (C16 RHI)

CRe212 (Alt RH2) CR9232 (97 RM2) CR9252 (C6 RH2) CRS272 (C16 RH2) l CR9213 (A10 AH3) CR9233 (87 RH3) CR0253 (C6 RH3) CR0273 (C16 RH3) 1 CR0219 (Alt RH4) PRS 234 (B7 RH4) CRS254 (C6 RH4) CR8274 (C16 RH4)

CRe221 (85 RH1) cn9241 (515 RH1) CRS261 (C13 RH1) CR9281 (Cit RH1)

CR0222 (85 RH2) CR9242 (315 RH2) CRS261 (C13 RH2) CR0282 (Cit RH2)

CR4223 (85 RH3) CR0243 (815 RH3) CRS263 (C13 RH3) CR9283 (Cit RH3) ,

CRG229 (05 RH4) CR0244 (B15 RH4) CR9269 (C13 RH4) CR0204 (C18 RH4) l 1

CRetti (03 RH1) CRetill (D7 RH1) ORett31 (Ett RHt) ORet151 (F11 RH1)

CR0291 (03 RH2) ORettit (D7 RH2) Catst33 (Ett RMS) ORet152 (Fil RH2)

C:t0293 (03 RH3) CRet113 (07 RH3) CRS2133 (Ett RH3) 0R02153 (Fit RH3)

CR9219 (03 RH4) CR02119 (07 RH9) CR02139 (Ett RM9) ORet189 (F11 RH9 3 CR02191 (D5 RH1) OR0titt (011 RN1) ORet191 (F3 RM13 GRet181 (F19 RH1)

SRS2182 (D5 RH2) ORetitt (011 RMS) CRetitt (F3 RMS) ORet162 (Fit RMS)  !

QR02183 (D5 RH3) ORetit3 (011 RN3) CRet193 (F3 RM3) 0R01183 (F19 RM3)

CR92194 (05 RH4) CRet129 (011 RM9) ORet199 (F3 RH9) OR01169 (Fit RM9)

CR92171 (G9 RH1) ORet198 (J7 RH1) CRettil (L9 RH1) ORett31 (LIS RHt)

CRe2172 (GS RH2) ORet192 (J7 RMS) ORettit (L9 RMS3 ORett39 (LIG RMS3 CR82173 (09 RH3) Catt193 (J7 RM3) ORett13 (L9 RM3) ORett33 (L16 RN3)

CR02174 (G9 RH4) CRett19 (L9 RM93 0R02t39 (L16 RM9)

QRONM (G18 RMS) ORet199 (J7 RN9)

CR421s2 (Git RH2) CRet201 (J16 RH1) CRettti (L6 RMS) 0R02991 ORett99 (LIG RM1)

(LIS RMS)

O CR02183 (Git RH3) ORettet (J16 RMS) CRettti (L6 RNS) 0R02193 (Lit RM3)

CRG2104 (Git RH4) ORet209 CRett03 (J1G RH3) CRettt3 (J16 RM9) ORetit9 (L6 (L6 RMS)

RM9) ORett99 (LAS RH4)

CR92251 (Nit RH1) OR0tt71 (M17 RH1) CR02291 (R$ RM11 0R09311 (Sit RMS)

CRG2252 (N11 RMS) 0R02271 (M17 RHS) ORett92 (R$ RMS) ORet312 (Sit RMS)

CR02253 (N1i RH3) CRet173 (N17 RH3) CRet293 (R6 RM3) 0R01313 (Sit RH3)

CR02254 (M11 RH4) CRet279 (N17 RH4) CRett99 (R6 RH4) OR02319 (Sit RH4)

CR02261 (NIS RN1) 0Rettet (R9 RH1) CRet301 (S3 RM13 ORet311 (Ste RH1)

CRettet (Mit RMS3 CRettet (R4 RH2) CRet301 (S3 RMS3 0R01391 (Ste RMt)

CRet263 (N15 RH3) CRett03 (R4 RN3) ORS 2303 (S3 RH3) ORet393 (Ste RH3)

CRet144 (N15 RH4) ORet209 (R9 RH4) CRet309 (S3 RH9) OR01329 (Ste RH9)

CR02331 (T2 RH1) CR02351 (T16 RH1) CRG2371 (Vil RMS 3 CR82332 (T2 RH2) CR92352 (T16 RH2) CRS2372 (V15 RM2)

CRS2333 (T2 RH3) CR92353 (T16 RH3) CRG2373 (V15 RM3)

CRS2334 (T2 RH4) CR02354 (T16 RH4) CR42374 (Vil RN4)

CRS2341 (T9 RH1) CRS2361 (Vit RH1) CRS2381 (Vil RMS )

CRG2342 (T9 RM2) CR02362 (V11 RH2) CR42382 (Vil RM23 l

CRS2343 (79 RH3) CR92363 (V11 RH3) CR02383 (Vit RM3)

CR42344 (T9 RH4) CRS2364 (Vit RH4) CR42384 (Vit RN4 )

CR02391 (W4 RN1) CRet411 (W16 RH1) CR02431 (X11 RM13 CR92392 (N4 RH2) CRS2412 (W16 RH2) CR42432 (X11 RMS3 CRS2393 (N4 RH3) CR62413 (W16 RH3) CRG2433 (X11 RM3)

CR02394 (W4 RH4) CR02414 (W16 RH4) CR42434 (X11 RH9)

CRS2491 (NG RH1) CR92421 (X7 RH1) CR92441 (X19 RMS )

9RS2402 (W6 RH2) CR02422 (X7 RH2) CRt2442 (X19 RMS)

CN02403 (W6 RH3) CR02423 (X7 RH3) CR02443 (X19 RM3)

CRS2404 (N6 RH4) CR02424 (X7 RH4) CR42444 (X19 RH4)

CR02451 (Y14 RM1)

CRe2452 (Y14 RH2)

O CR02453 (Y14 kH3)

CRe2454 (Y14 RH4) Rev:

Date:

0 3/1/89 Page: 3 of 29

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MALFUNCTION LIST MALr NO. CCRC CR03 INCCRE THERNCCCUPLC FA!LURF VARIA0LE: 100X ESUALS 2500 DEG F OUTPUT CR031 (A19) CR0319 (05) CR0319 (JS7) CR0320 (R04)

CR032 (805) CR0311 (07) 040320 (J16) CR0329 (R06)

CR033 (007) CR0312 (D11) CR9321 (Lt4) CR0330 (503)

CR034 (015) CR0313 (E20) CR0322 (L96) CR03'41 (511)

CR035 (C06) CR0314 (r03) CR0323 (L16) CR0332 (520)

CR036 (C13) CR0315 (F11) CR0324 (L10) CR0333 (Tet)

CR037 (C16) CR0316 (F19) CR0225 (Nit) CR0334 (Tet)

QR030 (Cit) CR0317 (G09) CR0326 (N15) CR0335 (T16)

CR439 (D3) CR0310 (GIS) CR0327 (N17) CR0336 (v11)

CR0337 (vis)

CR0330 (vit)

CR0339 (N64)

CR0340 (N06)

CR0341 (N16)

CR0342 (X87)

CR0343 (X11)

CR0344 (X19)

CR0345 (Y14)

O Rev: 0 Date: 3/1/89 Page: 4 of 29

MALFUNCTION LIST

-, j MALF NO. CNENICAL AND VOLUME CONTROL l O

1 CV91 LETOONN LINC RUPTURE IN5IDE OF THE CONTAINMENT (UNISOLATABLE)

VARIA0LE: 190X E4UALS 299 GPM LEAK RATE AT 2250 PSID CVet LETDONN LINE RUPTURE IN THE AUXILI ARY BUILDING ,

VARIABLE: 190X ESUAL5 209 GPM LEAK RA'i'E AT 2250 PSID i i

CV63 LETDONN NEAT EXCHANGER TUSE RUPTURE VARIABLE: 100X E00AL5100 GPM LEAK RATE AT 250 PS!O CV94 CHARGING TRIP A. P-104 C. P-100

8. P-100 CW45 LETDONN TEMPERATURE TRAN5MITTER (TE-223) FAILURE VARIABLE: 190X EtVALS MAX. INSTURMENT RANGE (299 DES F)

CV96 LETDOWN PRE 55dRE TRANSMITTER FAILURE (PT-201)

VARIABLE: 190X E00AL5 MAX. INSTRUMENT RANGE (669 PSIG)

CV97 VCT LEVEL TRAN5MITTER FAILURE VARIABLE: 199X EtUALS MAX. INSTRUMENT RANGC (199X)

A. LT-226 S.LC-227 CV98 VCT MAKEUP CONTROL FAILURE (STUCK IN MANUAL)

CV99 O!LUTION ACCIDENT VARIABLE: 100X ESUALS 50 GPM LEAK RATE N!TH PMM AVAILABLE CV10 INADVERTENT 90 RAT!0N ACCIDENT (10 GPM NITH DA PUMP RUNNING)

LETOONN BACK PRES $URE CONTROL FAILURE O CV11 VARIABLE: 100X EtVAL5 DIVERGENT O5CILLATION IN PRE 55URE CONTROL VCT LEAKAGE CV12 VARIABLE: 100X E00AL5 199 GPM LEAK RATE AT 20 PSIO CV13 CHARGING LINE LEAK IN5IDE CONTAINMENT VARIABLE: 190X EtUALS $90 GPM LEAK RATE AT 2250 P510 CVig CHARGING LINE LEAK IN AUXILI ARY BUILO!NG VARIABLE: 100X CtVALS 100 GPM LEAK RATE AT 2258 P5!O OVL5 VCT REJECT FAILURE (2-CH-500 FAILS TO VCT) l CV16 RN5T TO CNARGING PUMP SUCTION LEAKAGE ,

VARIABLE: 100X EtVALS 50 GPM MITH NORMAL OPERATING DIFFERENTI AL PRES 5URE tV17 80RIC ACIO PUMP FAILURE A. P-194 B. B-198 DV10 LETDONN LINE RUPTURE IN5IDE THE CONTAINMENT VARIABLE: 100X EtVALS 200 GPM LEAK RATE AT 2250 P510

$Vit DIU.' TION SATCN CONTROL FAILURE OV20 CNaRGING LINE LEAK IN5!DE THE CONTAINMENT VARIABLE: 196X E90AL5 100 GPM AT 2250 P5ID CV21 CHARGING LINE LEAK BEFORE 2-CH-429 IN AUXLIARY DUILDING VARIABLE: 100X EtVALS 100 GPM AT 2259 P5ID O Rev: 0 Date: 0/1/89 Page: 5 of 29

MALFUNCTION LIST l

MALF NO. CIRCULATING MATER .

CW81 CW PUNP TRIP A. P-6A C. P-SC B. P-48 D. P-6D ,

1 CH02 TRAVELING SCREEN FOULING VARIABLE: 100% EtUAL5 NAX. DP OF 58 INCHES W.C.

A. SCREEN A S. SCREEN 8 C. SCREEN C 0. SCREEN D l CW93 SCREEN WASH PUMP AUTO START FAILURE A. P-8A S. P-88 ,

1 l

CW84 MAIN CONDEN5ER TUBE RUPTURE (MINOR)  ;

VARIABLE: 100X EeUAL5 1 GPM LEAK RATE WITH NORMAL VACUUM A. MS-A S. WS-S C. W8-C D. WS-D CW85

  • LOS5 OF WATERS 0X PRIMING QHf6 MAIN CONDEN5ER TUSE SHEET FOULING VARIABLE: 100% EtUALS 50X FLON REDUCTION A. CONDENSER A C. CONDEN5ER C B. CONDEN5ER S D. CONDEN5ER D l CW87 CW PUMP FAILURE TO START l A. P-44 C. P-60 B. P-48 D. P-6D l CWet MAIN CONDEN5ER Tutt RUPTURE (MAJOR)

O VARIABLE:

A. WB-A 199X EGUAL5 200 GPM LEAK RATE NITH NORMAL VACUUM IN CONDENSER AND THE WATERBOX FILLED S. WS-S 0. WS-C D. MS-D l

  • MALFUNCTION NOT CEP.TIFIED 1

1 Rev: 0 Date: 3/1/89 O- Page: C of 29

MALFUNCTION LIST j O MALT NO.

ELECTRICAL DISTRIBU210N EDet LC55 0F M55T EDSt LOSS OF RSST E083 LOSS OF 395KV LINES

4. 319 LIME C.383 LINE i B.371 LIME D.348 LINE I EDS9 LOSS OF 6. 9KV SUS A. 25A
8. 255 ED85 LO55 0F 9.16KV SUS A. 244 B. 2MB C. 240 D. 24D E. 24E F. 2%F l gggs LoS5 Or steV sus A. 224 B. 228 C. 12C D. 22D E. 22E F. 22F EDt? L055 0F MCC A. MCC22-1 A 1.MCC22-3C 5.MCC22-2A J.MCC22-1De C.MCC22-3A K.MCC22-1DS
0. M CC22-18 L.MCC22-29 E.MCC22-28 M.MCC22-1E F. MCC22-1CA N.HCC22-2E G.MCC22-100 0.MCC22-1F l H.MCC22-2C P.MCC22-2F O Rev:

L Cato: 2/1/89 Page: 7 of 29

MALFUNCTION LIST HALF Wo. ....._...... .......... ......................... ......

ELECTRICAL O!STRISUTION EDG8 FAILURE Or 6.9KV BUS AUTO BUS TRANSTER A. 25A E. 258 5969 LC55 0F 120 VAC INSTRUNENT SUS A. IAC-1

8. IAC-2 EDie LO5s or its VDC BUS A. Sus tota
s. BUS 2018 CD11 INVERTER / REGULATED AC FAILURE TO VITAL AC SUSES C, INV-3 TO V!AC-3 E. INV-5 TO VI AC-1 A. INV-1 TO U!AC-1 F. !NV-6 TO VI AC-2
8. INV-2 TO VIAC-2 D. INV-4 TO VIAC-4 ED13 LO55 or VITAL DC D!5TR180T!0N PANEL A. 201A-1U C. 2018-1V
s. 201A-2V D. 2018-2V ED19 LOSS Or ANNUNCIATOR POWER SUPPLY ON MAIN CONTROL 80AR05  ;

I EDis LOSS or 125 VDC SUS 2010 E015 LOS5 of VITAL INSTRUMENT AC PANEL A. VIAC-1 C. V!AC-3 B. VIAC-2 D. VIAC-4 E017 FAILURE Or 4.16KV BUS AUTO BUS TRAN5FER 1 A. 240 B. 240 Edit LOS5 Or 4.16KV TO EMERGENCY BUS 240 AND 240 1

)

O Rev: 0 Date: 3/1/89 Page: 8 of 09

O l

l MALFUNCTION LIST MALF N0. ELECTRICAL GENERATION i EG81 MAIN GENERATOR TRIP EGG 2 MAIN GENERATOR AUTC VOLTAGE REGULATOR FAILURE TO MANUAL EG83

  • MAIN GENERATOR MANUAL VOLTAGE REGULATOR SETPOINT ERROR  !

VARIABLE: 100%

  • P6AXIMUM MANUAL VOLTAGE REGULATOR OUTPUT-E606
  • MAIN GENERATOR FIELD FLASH FAILURE EG07 MAIN GENERATOR AUTO VOLTAGE REGULATOR OSCILLATION 100X s +/-1999 VOLY OSCILLATION AT 19 VOLTS /5EC ]

EG90 DIESEL GENERATOR CUTPUT BREAKER FAILURE A. 15G-12U-2

8. 15G-13U-2 )

I EGet DIESEL GENERATOR BREAKER AUTO CLO5URE FAILURE O A. 15G-12U-2

8. 15G-13U-2

)

i EGit L!ESCL GSENERATOR AUTOMATIC VOLTAGE REGULATOR FAILURE VARIBLE: 199X * +/-100 VOLT 05CILLATION AT 1 VOLT /5E0 A. 0/G 12U (USE ONLY NNEN 0/0 ON LINE)

8. 0/G 13U (U$C ONLY NNEN D/G ON LINE)

EGli DIESEL GENERATOR AUTO START FAILURE A. D/G 12U S. 0/G 13U EG12 DIESEL GEN LOAO 000tTROL FAILURE 100Z s +/-1 NZ OSCILLATION IN 1 SECONDS i A. O/G 12U i S. O/G 13U

  • !!ALFUNCTION NOT CEPTIFIED Rev: C Date: 3/1/89 Page: 9 of 29

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) MALFUNCTION LIST ENGINCLRED 5AFETY M..ALF

___ . M_9., .........................._______. ___ ... ...... ___............

1 E591 AUTO AUX FEED INITI ATION FAILURE A-5YS A B-5YS B E541 SPURICUS ESAS SIGNAL CH A-1 5!

S-2 51 Eff) ESP 5!GNAL FAILURE TO ACTUATE A-(AM-563)

B-(AM-515)

C-(AM-5233 0-(AM-602)

E-(AM-664) ,

r-(AM-615) '

G-(AM-619)

ESD9 E5 ACT CABINETS LO55 CT PWR A-sf/5ENSOR A i

s-85/SEN50R S I C-5EH50R C l o-5EN50R D CSD6 D/G SEtVENCER 81 FAILURE AT AA-2 SEC AB-8 SEC AC-19 SEC

() AD-20 SEC D/G SEGUENCER 82 FAILURE AT BA-2 SEC es-s SEC BC-19 SEC 50-20 SEC Rev: 0 Date: 3/1/89 Page: 10 of 29 O

O MALFUNCTION LIST MALF NO. FEEDWATER FWei LOSS OF CONDEKSER VACUUM VARIABLE: letX s VACUUM DECREASES TO TURSINE TRIP SETPO!NT WITHIN 5 MINUTES FH91 CONDEN5ER NOTMELL LEVEL CONTROL TRAN5MITTER FAILURE VARIABLE: iteX s MAX. RANGE OF INSTRUMENT FWG3 CONDENSATE PUNP TRIP A-P2A 8-P2B C-P2C FH94 CONDENSATE MIN. FLOW RECIRC. VLV FA! LURE <

VARIABLE: 199Z s FULL DPEN FWG5 CONDENSATE DEN!N N!GN DELTA P VARIABLE: 199X a 198 PSID INCREASE AGOVE NORMAL FULL FLON i DELTA P l FW86 FEE 0 WATER PUMP TRIP ,

I A-P1A B-P!S FW97 l LP NEATER1.

VARiA.LE: 55 VA.LV.E.

BYPA.x s PL.EAKAGE..

.5 PS!

(;;)

FHet NP NEATER SYP&55 VALVE LEAKAGE j VARIABLE: 188X s 1tte GPN 8 1000 PSI i FWet FECO REG. VALUE FAILURE VARIABLE: 100% s FULL OPEN A-FW514 ,

B-FM518 FWie FEE 0 RCG. VALUE OSCILLATION VARIABLE: ) 54X CAUSE5 O!VERGENT OSCILLATION A-rN514 s-rN518 FW11 FEED PUMP MIN. FLOW RECIRC. VALVE FAILURE VARIABLE: Seex = rULL OPEN A-rN354 8.EN35.s l

Rev: 0 Date: 3/1/09 O Page: 11 of 29 b-_-_-_--_-_--------

MALFUNCTION LIfJ MALF No. FEEDWATER O -------

FW12

---~~-----------------------------------~~------~~~~----~~

CONDN5 ATE SURGE TANK LEVEL CONTROL FAILURE VARIABLE: 100% a MAX. INDICATOR LEVEL FW13 HEATER ORAIN PUMP TRIP A-P3A B-P3B FW19 HEATER ORAIN TANK HIGH LEVEL CONTROL FAILURE VARIABLE: 100X s MAX. RANGE TWip FM HEATER HIGH LEVEL DUMP FAILURE VARIABLE: 19tX a FULL OPEN AA/AB-6A/B HEATER CA/CB-4A/S HEATER CA/EB-1A/S HEATER BA/ts-5A/S HEATER DA/DS-2A/B HEATER FW16 FW HEATER HORMAL LEVEL CONTROL VALVE FAILURE I VARIABLE: 199X s FULL OPEN AA/AB-64/5 CA/CS-4A/S EA/ES-1A/S BA/88-5A/S DA/DB-2A/S FMit LPFW HEATER TUDE RUPTURE VARIABLE: 190X s 159X OF HEATER ObMP CAPAt!LITY AA-46A BA-854 CA-84A DA-034 EA-82A AB-366 es-s5: es-s*s os-s3s Es-sss FN2e AUX. FEEDWATER PUNP TRIP A-P9A 3-P98 C-P4 FW21 AUX. FEEDWATER P!PE BREAK VARIABLE: 198X s teet GPM S 1998 PSI

\ A-AFW HDR 1 1

B-AFW HOR 2 FW22 CONDENSATE STORAGE TANK LEAK VARIABLE: SteX a 25000 GPM FW23 LO55 0F AIR TO FEED PUMP AIR NOTOR A-P1A B-P18 l FW25 FM LINE DREAK INSIDE CONTAINMENT VARIABLE: 199X 1 X 10(7) L8M/NR S 1998 PSI A-HDR A B-HDR R FW26 AUX. FEED PUMP O!5CHG VALVE CLOSED A-P9A B-PSB C-P4 I

rW27 rw LINC BREAK IN TB VARIAeLE: 1eeX a 6 X te(s) LeM/HR S 1999 PSI A-HDR B-HDR TH79 HEATER ORAIN TANK NORMAL LEVEL CONTROL VALTE FAILURE VARIABLE: 100X s FULL OPEN FW29 HPFW MEATER Tutt RUPTURE VARIABLE: 199X a 156X OF IMO!VIDUAL HEATER DUMP CAPA81LITY A=81A O '-

Rev: 0 Date: 3/1/89 Pa:e: 1; of 29

1 l

I MALFUNCTION LIST NALF NO. INSTRUNENT AIR l

IAtt INSTRUNENT AIR NEADER RUPTURE i VARIABLE: 100% a 1500 SCFN LEAM 8 100 P5! i l

IA02 AIR COMPRESSOR TRIP l A=F2 0-F3C B-F3A C-F3B IA03 LOSS OF INSTRUMENT AIR IN CONTAINMENT VARIABLE: 100X s 300 SCFM LEAM $ 100 P51 IAS4 LOSS OF INSTRUMENT AIR TO FEED REGULATING VALVES A-2-FM-51A B-2-FW-515 IAtf INST AIR NEADER RUPTURE IN TURBINE SU!LO!NG VARIABLE: 198X s 309 ScrN AT 100 PSI O

l Pev: 0 O Date:

Page:

3/1/89 13 of 29

MALFUNCTION Lis?

$__(.U_0. pp{f,(({p},,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, , ,, ,,,,,,,,,,,,,,,,

M501 MAIN STEAM HEADER RUPTURE IN CONTAINMENT VARIABLE: 100X s 19 X 10(6) LBM/NR 8 1800 P5IG A. MAIN STEAM HEADER 81

8. MAIN STEAM HEADER 82 M592 MAIN STEAM HEADER RUPTURE OUTSIDE THE CTMT BEFORE THE M51V VARIABLE: 100X s 19 X 18(6) LBM/HR S 1948 P!SG A. MAIN STEAM HEADER 81 l B. MAIN STEAM HEADER 82 l M583 MAIN STEAM HEADER RUPTURE DONNSTREAM OF MSIV'S VARIABLE: 100X s 1 X tet?) LBM/MR AT 1999 PSID MJf4 MSR SECOND STAGE PRE 550RE CONTROL VALVE FAILURE A-2-MS-79A B-2-M5-799 M505 M5R STEAM SUPPLY ISOLATION VALVES FAIL OPEN A-2-MS-2A B-2-MS-25 M596 MSIV SPURICUS CLO5URE A. 2-MS-64A s B. 2-MS-648 l M587 MAIN STEAM LINE SAFETY VALVE FAILURE I VARIABLE: 100X s 795,000 LBM/HR AT 1999 P51  !

A. 2-MS-247 l B. 2-MS-239 l M500 GLAND SEAL REGULATOR FAILURE VARIABLE: 100X s 20 P5IG SETPOINT M511 EXTRACTION STEAM MOTOR OPERATED ISCLATION VALVE INADVERTENTLY $ NUTS A-2-ES-775 (44) D-2-ES-77C (35) G-2-ES-800 (1A)

B-2-E5-77A (48) E-2-E5-77F (2A) H-2-E5-92 (13)

C-2-ES-770 (34) F-2-ES-77E (2B)

M512 STEAM LEAK INTO CONTAINMENT VARIABLE: 100X s 5 X 18(4) LBM/NR AT 1998 PSID Rev: 0 O Date:

Page:

3/1/89 14 of 29

O MALFUNCTION LIST MALF N0. MAIN STEAM l

Ni1} M0!5TURE SEPARATOR DRAIN TANK NORMAL LEVEL CONTROL FAILURE VARIABLE: 100% s 100% OPEN A-MSRDT 1A C-P5R1DT 1A E-M5R2DT 14 5-MSROT 1B D-K5R1DT 1B F-MSR2DT 18 N5tu M0ISTURE SEPARATOR SECOND STAGE TUBE RUPTURE VARIABLE: 100% s 1 X 10(6) LBM/NR S 600 Pi!D A-MSR 1A B-MSR 18 1

M515 M0ISTURE SEPARATOR FIRST STAGE TUBE RUPTURE VARIABLE: 100% a 500,000 LBM/HR AT 258 P5ID  !

A-MSR 1A 3-MSR 13 M516 MOISTURE SEPARATOR ORAIN TANK HIGN LEVEL CONTROL VALVE FAILURE VARIABLE: 160% s 100X OPEN A-MSRDT 1A 8-MSRDT 18 C-MSR1DT 1A D-MSR1DT is E-MSR2DT 1A F-MSR2DT 18 MALFUNCTION LIST MALF NO, PLANT PROCESS COMPUTER ................

PC61 LOSS OF PLANT COMPUTER O Rev: 0 Date: 3/1/89 Pane: 15 of 29

l O

MALFUNCTION LIST l MALF No. REACTOR COOLANT RCet RCS CRUD BURST VARIABLE:

100% a MAX. MC RELEASE RELATIVE TO Mar. LETDOWN ~ ~ ~ ~ '

RADI ATION MONITOR INDICATION '

R002 RCS NOT LEO BREAM VA..!ABLE: 100% a 180,088 LBM/5EC 8 2250 PSIA A-LOOP 1 B-LOOP 2 RC03 RCK COLD LES BREAN VARIABLE: 100% s 100,969 LBM/5EC 9 2250 PSIG 4-LOOP 1A C-LOOP 2A B-LOOP IB D-LOOP 28 R005 REACTOR NEAD VENT LEAK VARIABLE: 100% = 299 GPM S 2258 PSIA 2005 PRE 550R12ER SAFETY VALVE FAILURE VARIABLE: 100% a FULL OPEN  :

A-RC-200  !

B-RC-201 RCS6 PRE 55URIZER PORY FAILURE O VARIABLE: 100% a FULL OPEN A-RC-402 B-RC-404 RCS7 RCP LOWER MECHANICAL SEAL FAILURE VARIABLE: 100% a NO PRES 5URE OROP ACROSS SEAL A-RCP A C-RCP O B-RCP B D-RCP D RCOS RCP MIDDLE MECNANICAL SEAL FAILURE VARIABLE: 100% s NO PRESSURE DROP ACROS5 SEAL A-RCP A C-ROP C B-ACP S D-ROP D RC99 RCP UPPER MECHANICAL SEAL FAILURE VARIABLES 100% a NO PRESSURE DROP ACROSS SEAL A-RCP A C-RCP O B-RCP S D-RCP D O Rev: 0 Date: 3/1/89 Page: 16 of 29

1 O

MALFUNCTION LIST MALF M0. REACTOR CCOLANT RC10 RCP VAPCR SEAL FAILURE VARIABLE: 100% s NC PRE 55UE OROP ACROSS SEAL A-RCP A C-RCP O B-RCP 5 D-ACP O RC11 RCP LOCKED ROTOR A-RCP A C-RCP C B-RCP S D-RCP O Rpl1 RCP 0!L LEAK VARIABLE: 100% = 189 GPM LEAK A-RCP A C-RCP C S-RCP B D-RCP O RC13 RCP SHAFT BREAK A-RCP A C-RCP C B-RCP B D-RCP D RC14 RCP SPEE0 SEN51HG CIRCUIT FAILURE O A-RCP A B-RCP 3 C-RCP O D-RCP D RC15 RCP SEAL PRES 5URE OSCILLATION VARIABLE: 130% a +/- 383 PSI ON LONER SEAL A-RCP A C-RCP C S-ACP S D-ACP O

  • t/T MAKE-UP VALVE FAILURE RQ$6 AC17
  • t/T HIGH PRESSURE VARIABLE 0-180% s 9-100 P51 SETP0 INT RC18
  • t/T RUPTURE DISC TAILURE Rost
  • LOSS Or e/T LEVEL VARIABLE 100% a 50 GPM 9 9 P5IA IN TANK RC20 RCP THERMAL DARRIER TUBE RUPTURE VARIABLE 100% a 58 GPM S HCRMAL DP N!TNIN NX (2100 P510)

A-RCP A C-RCP C t-RCP B D-RCP O

  • MALFUNCTION NOT CERTIFIED O Rev: 0 Date: 3/1/C9 Page: 17 of 29 j

MALFUNCTION LTST O NALF NO. CRD ASSENSLY RDet DROPPED CCA

$1-CEA 81(R67) te-CEA 828(RG2) 39-CEA 839tRG7) 55-CEA 355(RG4) i 02-CEA 82(RG5) 21-CEA 821(RG2) 90-CCA 948(RG7) 56-CEA 856(RG4) 03-CEA 83(RGE) 22-CEA 822(RG2) 91-CEA 841(RG7) 57-CEA 857(RG4) 44-CEA 84(RGE) 13-CEA 823(RG2) 91-CEA 842(SDA) 58-CEA 858(RG3) 05-CEA 85(RG5) 14-CEA 024(RG2) 93-CEA 843(5D4) 59-CEA 859(RG7) 66-CEA 36(508) 25-CEA 825(RG2) 44-CEA 844(504) 60-CEA 868(RG3) 07-CEA 87(508) 26-CEA 326(RG1) 95-CEA G45(SDA) 61-CEA 861(RG3) 08-CEA 88(5D8) t?-CEA 827(RG1) 46-CEA SMEtSDA) 62-CEA 362(RG7) 49-CEA 89(508) 28-CEA 828(RG1) 97-CEA 947(504) 63-CEA 363(RG3) 14-13 P1 N/A 29-CEA 929(RG1) 98-CEA 344(504) 64-CEA 864(RG3) 14-CEA 814(RG6) 34-CEA 838(RG1) 99-CEA 848(504) 65-CEA 865(RG7) 15-CEA 815(RG6) 31-CEA 331(RG1) 50-CEA 858(RG9) 66-CEA 866(RG3) 16-CEA 816(RG6) 32-CEA 832(RGL) 51-CEA 851(RG4) 67-CEA 867(RG3) 17-CEA 817tRG6) 33-CEA 833(RG1) 52-CEA 352(RG9 ) 68-CEA 868(RG7) 18-CEA 310(RG2) 34-37 P2 N/A 53-CEA 853(RG9) 69-CEA 869(RG3) 19-CEA 819(RG2) 38-CEA 838(RG7) 54-CEA 854(RS9)

RDet STUCK CEA SEE MALF RD01 FOR GENERIC CONPONENTS ,

RD03 CEA PARTIAL DROP VARIASLE: 188X a its STEP DROP DONN (MAX) (61 TOTAL)

SEE NALF RDet FOR GENERIC COMPONENTS R0eg rJECTED CEA 01-CEA 381(RG7) 62-CCA 86t(RG7) 41-CEA 841(RG7) 65-CEA 865(RG7)

RODS CCA SCSUENCE FAILURE O VAR!ASLE: 108% = 19 SEC DELAY SETNCEN DENAND SIGNALS SEE MALF RDG1 F0 GENERIC COMPONENTS RBDS IN-NOLD-0UT SN! TON FAILURE RD97

  • CEA POSIT!DN INDICATION FAILURE (REED SN)

VARIABLE: 188% a 188 STEP LAG IN INDICATION FROM ACTUAL CCA P051730N (61 TOTAL)

RDet CCA PULSE COUNTER FAILURE VARIASLE: 188X a it STEP LAG IN PUL5E COMPUTATION (DONE ONLY IN tex INCRENENTS) l SEE MALF RD81 FOR GENERIC CONPONENTS Rpg) SRCKEN CNTROL ELEMENT ASSEMSLY SEE NALF RD81 FOR GENERIC COMPONENTS RDie CONTINU0US SANK INSERTION A-5DA C-RG1 E-RG3 0-RGE 1-RG7 B-508 D-RG2 F-RG4 N-RG6 RD11 COUTINUCUS BANK WITNDRANAL A-504 C-RG1 E-RG3 0-RGE I-RG7 8-5D8 D-RG2 F-RG4 N-RG6 PM)11 CMI FAILURE

  • MALFUNCTION NOT CERTIFIED Rev: 0 Date: 3/1/89 Page: 18 of 29

i

-. l

)

MALFUNCTION LIST NALF N0. SNUTDONN COOLING l

RNG1 LPSI PUMP TRIP  !

ArP42A B-P428 l RN#2 LOS$ OF LP5! PUMP SUCTION  ;

A-P42A B-P428 l RH9) SNUTDONN COOLING FLON CONTROL FAILURE VARIABLE: 190X s DIPLAYED FLON 1900 GPM EREATER THAN ACTUAL i FLON RN94 LPS! PUNP SEAL FA! LURE VARIABLE: 199X s te GPN AT 30 P5tG A-P424 B-P928 RN95 5/D COOLING HEAT EXCNANGER TUDE RUPTURE VARIAeLE: 194X a 100 GPM S 160 P510 A-500 HX A 3-500 HX 3 )

RN66 CONTAINMENT SPRAY PUMP TRIP A-P43 A B-P93 8

) RH97 LPSI FLON CONTROL VALVE FAILURE A-2-51-615 C-2-51-535 s-2-51-525 0-2-51-645 Rev: 0 Date: 3/1/89 0 Page: 19 of 29

1

,1 i

MALFUNCTION L15T l MALF NO. RADIATICH MONITORING ........

RN81 ARCA RADIATION NONITORING FAILURE VARIA8LCt 180X s FULL SCALC DCFLCCTION A RIT-7898 CTNT SER50HAL ACC55 K RIT-8241 CTMT HIGH RANGC ,

8 RIT-7891 SERVICE PLATFORM L RIT-8142 SPCNT FUCL POOL NN l C h!T-7892 ORUMMING ARCA M RIT-8156 SPCNT FUCL POOL NC l D RIT-7894 5AFCGUARD ARCA N RIT-8157 SPCNT FUCL POOL SC C RIT-7895 5AMPL SINN 0 RIT-9799A CONTROL ROOM VCHT F R27-7896 14' 6' ARCA P RIT-97998 CONTROL ROOM VENT G RIT-7497 -45' 6* ARCA 8 RIT-4299A 81 MAIN STCAM LINC H RIT-7499 CONTROL ROCM R RIT-42998 81 MAIN STM ATM DUMP 1 R17-8139 SPCNT FUCL POOL SM S RIT-4299C #2 MAIN STEN 1 LINE J RIT-8248 CTMT HIGH RANGC ,

RM97 AIR 40RNC PROCC55 RADI ATION MON 1 TOR FAILURE i VARIA8LCt 189X = FULL SCALE DCFLCCTION '

A RIT-5899 STCAN JCT AIR CJECTOR J RIT-82628 CTMT GA5COUS 8 RIT-8811 CONTROL ROOM VENT K RIT-8424A RAD ARCA VENT PARTCT C RIT-81234 CTMT PARTICULATE L RIT-84398 RAD ARCA VENT GA5COUS O RIT-81238 CTMT GASCOUS M RIT-8997 CHARGING PUNP 4 OCGA5 C RIT-8132A UNIT 2 STK PARTICULT N RIT-8998 VCT-5AMPLC ROOM F RIT-81328 UN37 2 STK GASC005 0 RIT-8999 SFP PUMP S NX G RIT-8145A FUCL HDLING PARTIC P RIT-9895 MASTC GA5 015 CHARGE N RIT-81958 FUCL NOLING GASC005 4 RIT-Silt UNIT 2 STM NIGN RANGC

! RIT-8267A CTMT PARTICULATE l

1

() RM83 L18UID PROCC55 RA01 ATION FAILURC VARIABLC 188X a FULL SCALE DEFLCCTION A-RIT-282 FAILCD FUCL GR055 C RIT-9899 CLEAN MASTC DISCNARGE 8-RIT-282A FAILCD FUCL LINCAR F RIT-9116 ACR NASTC C15 CHARGE C-RIT-M262 5/G SLORDORN G RIT-9327 CONOCNSATC REC 0VCRY 0-RIT-6838 R8CCM J

, RMSW TANK RUPTURE OF T-19A VARIA8LCt 188X s 16,888 CURICS O Rev: 0 Date: 3/1/09 Page: 20 of 29

() Makr NO. REACTOR PROTECTION MALFUNCTION LIST RPet RPS NOI5Y TEMPERATURE IMPUT VARIABLE: 199X s +/- 25 DEG F OSCILLATION A-TC-112HA I-TE-122HA l

l B-TE-112H3 J-TE-122MB C-TE-112HC K-TC-122HC 0-TE-112ND L-TE-122HD E-TE-112CA M-TE-122CA F-TC-112CB N-TC-122C8 G-TE-112CC 0-TC-122CC H-TE-112CD P-TE-122CD RPS2 SPURIOUS REACTOR TRIP (MCMENTARY AT MANUAL PUSH 5UTTONS)

RPG4 MANUAL REACTOR TRIP FAILURE A-MANUAL TRIP in C-MANUAL TRIP 3A 3-MANUAL TRIP 24 0-MANUAL TRIP 4A RP85 RP5 MATRIX P0HER SUPPLY FAILURE A-P5 5 E-P5 9 I-P5 13 3-P5 4 F-P5 19 J-P5 14 <

C-P5 7 G-P5 11 N-P5 15  !

D-P5 8 H-P5 12 L-P5 16 RP85 TM/LP CALCULATOR FA! LURE VARIABLE 0-194X a 15De TO 2500 PSIA A-CHAN A C-CHAN C B-CHAN 8 D-CHAN D

{

RP47 LPC CALCULATOR FAILURE VARIABLE 199X a 20X PONER DONN SH!rT ON OPERATING CURVE A-CHAN A C-CHAN C B-CHAN S D-CHAN O RPSS DELTA T PONER CALCULATOR FAILURE VARIABLE: 100% a 125X OF DELTA ? POWER RANGE A-CHAN A C-CHAN 0 B-CHAN S D-CHAN D Rev: 0 O Date:

Page:

3/1/89 21 of 29

O MALFUNCTION LIST MALF NO. REACTOR PROTECTION ............

RPfp RCS FLO TRAN5MITTER FAILURE VARIABLE: 0-100% = -8 TO 69 P5ID A-PDT-111A E-PDT-121A B-PDT-litt F-POT-121B C-POT-111C G-PDT-1210 0-PDT-111D H-PDT-121D RPie P2R PRESSURE TRANSMITTER FAILURE VARIABLE: 0-196X z 1500-2500 PSI A A-PT 192A C-PT-192C 8-PT 1928 D-PT-1920 RP11 RCS 5AFETY CHANNEL HOT LEG TEMPERATURE TRAN5MITTER FAILURE VARIABLES 9-100% a $15 TO 665 DEG F A-TE-112HA C-TE-122HA B-TE-112HB F-TE-122H3 0-tea 112HC 5-TE-122HC D-TE-112HD H-TE-122HO I

RP12 RC5 5AFETY CHANNEL COLO LEG TEMPERATURE TRAN5 HITTER FAILURE VARIABLE: e-166Z = 465 TO 615 DEG F A-TE-112C4 E-TE-122CA B-TE-112CB F-TE-122CD O C-TE-112CC D-TE-18200 E-TE-122CC H-TE-12200 RP13 5/G LEVEL TRANSMITTER FAILURE (SAFETY CHANNEL)

VARIABLE: 199X a MAXIMUN OUTPUT A-LT 1113A E-LT 11234 3-LT 1113B F-LT 11238 C-LT 1113C E-LT 1123C D-LT 18130 H-LT 11230 RPl4 5/6 PRE 55UC TRANSMITTER FAILURE VARIABLE: 100% s lett PSIA A-PT 1913 A E-PT 1923 A B-PT 1913 8 F-PT 1923 8 C-PT 1913 C E-PT 1923 C D-PT 1913 0 N-PT 1923 0 l

l i

I I Rev: 0 l Date: 3/1/89  !

O Page: 22 of 29 l

_ _ _ _ __o

i O

MALFUNCTION LIST NALF NO. REACTOR PROTECTION RP15' N!DE RANGE CHANNEL FA! LURE VARIABLE: 0-100X a 10(-8) - 150% i A-CH A C-CH C B-CH B D-CH D ,

RP16 WIDE RANGE CHANNELN0!5Y VARIABLE: 0-198X s 9-1960 COUNTS AB0VE BACNGROUND i l

A-GM A G-GM G t-CH 8 D-CH D l

,RP12 NIDE RANGE HIGH VOLTAGE FAILS A-CH A C-CH C B-CH 3 0-CH D RP19 POWER RANGE CHANNEL FAILURE VARIBLE: 0-100% a 0-200X INDICATION A-LR A C-LR C B-LR 5 D-LR D sRP19 POWER RANGE LOWER DETECTOR FAILURE VARIABLE: 0-100% n 0-199X INDICATION A-LRL A C-LRL C 8-LRL B D-LRL D RP29 POWCR RANGE UPPER DETECTOR FA! LURE VARIABLE: 0-199% z 9 190X INDICATION A-LRU A C-LRU C B-LRU 5 D-LRU D RP21. POWER RANGE CHANNEL NOI5Y VARIABLE: teeX s +/- SX ( tex OF TOTAL BAND WIDTH) 4.ew a e.ew e -

8-CN 8 D-CH D SP22 POWER TRIP TEST INTERLOCK FAILURE A-LR A C-LR C .

B-LR S D-LR D .

RP23' POWER RANGE RANDON No!5E VARIABLE: 196X s 2 MINUTC DELAY SETHEEN 10X SP!KE -

A-LR CH A C-LR CH C B-LR CH B D-LR CH D ,

~'

RP19 C0NTAINMENT PRES 5URE TRANSMITTER FA! LURE (SAFETY CHANNEL)

VARIABLE: 186X a 60 PSIG A-PT-8113 C-PT-811F5 8-PT-8114 D-PT-81156 RP25 INADVERTENT REACTOR TRIP CIRCUIT BREAMER OPENING A-TCB-1 E-TCS-E B-TCB-2 F-TCB-6 C-TCB-3 6-TCB-7 D-TCS-4 H-TCS-8 O Rev: 0 Date: 3/1/89 Page: 23 of 29

n O MALFUNCTION LIST NALF NO. ..... .....

,,.._,... REACTOR CONTROL....................................

RX81 PZR SPRAY VALVE FAILURE VARIA9LC 100% a FULL OPEN A-RC-198E B-RC-199F RXG2 L0ff 0F PZR HEATERS VARIABLE: 190X s NININUM 1ZERO) OUTPUT A-PROP GRP 1 D-5/U GRP 1 R-PRCP GRP 2 E-S/U GRP 3 C-B/U GRP 1 F-8/U GRP 9 RXt3 PZR PRESSURE CONTROL FAILURE VARIABLE: e.1 sex s 1588 TO 1589 PSI A A-PT 100 X B-PT 100 Y RXt4 PIR LEVEL CONTROL FAILURE VARIABLE: 0-169Z s 6-198X INDICATCO LEVEL A-LT tit X 8-LT 119 Y RX95 TURBINE FIRST STAGE PRESS TRAN5 FAILURE VARIABLE: 0-194X s 8-750 F516 (

4-PT 4298  :

8-PT 4300 I RK96 TAVG PROGRAN CALCULATOR e-teex FAILURE

= 515-s15 pCG r i VARIAstti A-RP5 81 p-RPS 92 RXt7 RCS CONT 40L CHANNEL HOT LEG TEMPERATURE TRAN5NITTER FAILUl VARIABLE: 0-199X s 0 - 1999 OEG F i

(

A-TE 111 X B-TC 111 X l

RX8s RC5 CONTROL CHANNEL COLD LEG TEMPERATURE TRAN5NITTER FAILU VAR!AtLE: 4 10ex a e - 1646 OCG r A-TE 111 Y C-1E 121 Y 8-TC 115 D-1E 125 Rev: 0 Date: 3/1/39 Os Page: 2? of 29 b____ -

i i

i MALFUNCTION L!$T ,

l MALF NO. REACTOR CONTROL l

RXS9 RC5 LOW RANGE PRES 5URE TRAN5MITTER FA! LURE VARIABLE: 0-198Z s 9-1699 P5IA A-PT 103 5-PT 103-1 l

RX10 5/G FEED FLOW TRAN5MITTER FAILURE i VARIABLE: 0-160Z s 0-5.3E6 LSM/NR A-rf 5258A #1 5/G MAIN C-rf 5259A $2 5/6 MAIN 3-rf 52685 81 5/G ALT D-rT-52698 82 5/G ALT RX11 MAIN STEAM FLOW TRAN5MITTER FAILURE l VARIABLE: 0-190% s 0-6.3 E6 LBM/NR A-rf 92934 81 5/G MAIN C-rf 424t A $2 5/G MAIN I 8-FT 92939 81 5/G ALT D-FT 42918 82 5/G ALT l 5/G LEVEL TRAN5MITTER FAILURE (RX CONTROL CHANNEL)

RX12 i VARIABLE: 0-100Z s 0-194Z INDICATE 0 LEVEL A-LT 5271 81 5/G MAIN C-LT 5273 82 5/G MAIN 3-LT 5272 81 $/G ALT D-LT 5274 82 5/G ALT RX13 ATM05PHERIC DUMP VALVE FAILURE VARIABLE: 194X s VALVE FULL OPEN ($$5,999 LSM/NR)  :

i A. 2-MS-19

s. 2-MS-1,4A ee l

RX14 MAIN STEAM DUMP VALVE FAILURE VARIABLE: 100Z s VALVE FULLT OPEN A. 2-MS-249 C. 2-MS-247 B. 2-MS-294 D. 2-M5-296 RX15 MAIN STEAM LINE PRES 5URE TRANMITTER FA! LURE l

VARIABLE: 198Z s MAX. TRAN5MITTER RANGC

A. PT-4215 (6-1000 PSIA)
3. PT-9216 (See-teet PSIA)

O Rev:

Date:

0 3/1/09 Page: 25 of 29

MALTUNCTICN LIST I

MALF NO. STEAM GENERATOR 5001 STEAM GENERATOR TURE LEAK ($ MALL) k -

VAP!ABLE: 100% s is GPM AT $250 PSIC A. 5/G 1 S. 5/6 2 5G02 STEAM GENERATOR TUDE RUPTURE VARIABLE 100Z s 3000 GPM T 1250 PSIO A. 5/6 1 B. 5/6 2 NALF NO. SarETY INJECTION 5191 serETY INJECTION LOOP CNECK VALVE LEAKAGE VARIABLE: 100Z s it GPM S 2000 PSID i A-51 LOOP 1 A (2-52-217 ) C=51 LOOP 2A (2-51-237) l g-ft LOOP is (2-51-227) 0-51 LOOP 2s (2-51-297)

Exos 517 LEVEL LON VARIABLE 100X s it GPM S 200 PS!D A-51 TANK 1 C-51 TANK 3 i B-51 TANK 2 0-51 TANK 4 l

$183 51T LON PRES $URE VARIABLE: 100X z 29 PSI A DROP / MINUTE FROM TANK NDP A-51 TANK 1 C-51 TANK 3 5-51 TANK 2 0-5! TANK 4 5394 NPSI PUMP TRIP A-P41A B-P41B C-P910 5187 NPSI FLON CONTROL VALVE FAILURE (FAIL TO OPEN)

A-2-51-616 C-2-53-626 E-2-51-636 6-2-51-646 R-2-51-617 D-2-SI-627 F-2-51-637 H-2-St-697 5112 5t TANK CNECK VALVE LEAKAGE VARIABLE: 100X s at GPM e 2068 P5ID A-51 TANK 1 (2-51-215) C-51 TANK 3 (2-51-235)

B-51 TANK 2 (2-51-225) 0-51 TANK 4 (2-51-295)

Rev: 0 Date: 3/1/39 Page: E6 of 29

O MALFUNCTION L15T MALF N0. SERV!CE WATER . . . . . . . . . . . . . . . . . . _  :..............

SWet SERVICE WATER PUMP TRIP A. P-5A B. P-58 C. P-5C SW92 SW SIDE OF TBCCW HEAT EXCHANGER FOULING VARIABLE: 100X s TOTAL FLOW SLOCKAGE WITH APPROPRIATE LOSS OF MEAT TRANSFER A. NX-17A B. NX-178 C. HX-170 SW83 SW SIDE OF RBCCW HEAT EXCHANGER FOULING VARIABLE: 100X s TOTAL TLOW BLOCKAGE MTH APPROPRIATE LOSS OF HEAT TRANSFER A. H-18A 5. HX-itS 0. XH-100 (Hg4 DIESEL GENERATOR HEAT EXCHANGER / STRAINER FOULING VARIABLE: 188X s TOTAL FLOW BLOCKAGE WITH APPROPRIATE ,

L055 0F HEAT TRANSFER l A. 0/G 12U NX 3. D/G 13U HX UN!50LTABLE SERVICE WATER NEADER RUPTURE IN TURBINE BUILDING l SW45 VARIABLE: SSSX a 5,000 GPM LEAK RATE AT 54 PSIO O A. LOC JUST UP5TREAM 2-5W-3.28 ON A MOR

3. LOC JUST UP5TREAM 2-5W-3.2A ON 8 NDR SW96 ISOLTABLE SERVICE WATER HEADER RUPTURE IN TURBINE BUILDING 100X s 5,990 GPM LEAK RATE AT 50 P5!O l VARIABLE: '

A. LOCATED JUST DOWNSTREAM 2-5W-3.23 ON *A*

HEADER

'8' NEADER

3. LOCATED JUST 00MNSTREAM 2-5W-3.2A ON SW97 5ERVICE WATER TBCCM TEMPERATURE CONTROL VALVE FAILURE VARIABLE: 198X s VALVE FULLY OPEN A. 2-5W-88A B. 2-5H-885 C. 2-5N-640

)

5H98 SERVICE HATER RSCCW TEMPERATURE CONTROL VALVE FAILURE l VARIABLE: 19tX s VALVE FULLY OPEN A. 2-5W-8.14 8. 2-5W-8.18 C. 2-5W-8.10 '

D. 2-5W-247 E. 2-5W-246 F. 2-5W-245 )

KW99 REDUCED SERVICE WATCR PUMP CAPABILITY i VARIABLE: 198X s TOTAL FLOW SLOCKAGE

& P-5A B.P-E8__ C. P -50 . __ l l

Rev: 0 Date: 3/1/39 Page: 27 of 29

() MALF NO. TURBINE CONTROL TC91 TUR[tNE TRIP TCS2 TURBINE THROTTLE PRES 5URE LIMITER FAILUME VARIABLE: 0-196X s 0-1999 PSIG TGly LOAD $NED VARIABLE: 0-199% a FULL LOAD - NO LOAD TC85 TURBINE STOP VALVE FAILURE VARIABLE: 100% s FULL OPEN A-M5V 1 C-M5V 3 8-M5V 2 D-M5V 4 TCSE TURBINE CONTROL VALVE FAILURE VARIABLE: 100% s FULL OPEN A-CV 1 C-CV 3 8-CV 2 0-CV 4 TC07 FIRST STAGE PRES 5URE FEEDBACK FAILURE VARIABLE: 100% s 1999 PSIG TCSS ENC HYDRAULIC FLUID PUMP FAILURE A-P81A s-Pass O

MALFUNCTION [IST MALF No. TURBINE BUILD CLOSED COOLING WATER TPet TBCCM TRIP A. P-7A C. P-7C

8. P-78 TPf2 TBCCW HX TEMPERATURE CONTROL FAILURE VARIABLE: 100% a 184 DEG F SETPOINT A. NX-17A C. HX-170 B. HX-178 Tf83 TDCCW LEAK VARIABLE: 100% a 1,066 GPM LEAK RATE AT 80 PSID TPA4 L055 0F STATOR COOLING VARIABLE: 100% a COMPLETE LOSS OF STATOR L!tUID COOLING FLOW O Rev: 0 Date: 3/1/89 Page: '3 of 29

MALFUNCTION LIST NALP N0. TURBINE

(/ ..._... ... .. - .....-. ....... _ ................... .......... _

7U91 LOS5 OF LUBE O!L TO TURBINE BEARING VARIABLE: B-199X

  • AMOUNT OF FLON REDUCTION A-BEARING 1 T-SEARING 6 B-BEARING 2 6-BEARING 7 C-BEARING 3 M-BEARING 8 D-BEARING 4 I-BEARING 9 E-DEARING 5 J-BEARING 10 YUSS TURBINE SCARING NIGN V!BRATION VARIABLE: 1987. s it NIL INCREA5E ABOVE BASELINE V!BRATION LEVELS A-NP C-LP 2 E-EECITER B-LP 1 D-GENERATOR 7003 SNAFT Dt!VEN LUBE O!L PUNP REDUCED CAPACITY VARIABLE: 1997. s NO DIFFERENTI AL DEVELOPED BY PUNP TUG 4 FA! LURE OF TURBINE LUBE O!L PUMP 5 A-N5P B-EB0P C-TG0P TUSE TURBINE BEARING L!rf PUNP AUTO START FAILURE A-LP-A 0-LP-D B-LP-B E-LP-C C-LP-C T-LP-r O

MALFUNCTION L!st NA(T NO. NASTE DISPOSAL ND01 CONTAINMENT SUNP DISCHARGE FA! LURE (5 NUT!

A. 2-5 5 F-1 F. ,1 B. 2-55P-15. 2 NDB2 CONTAINMENT SUNP O!$ CHARGE FAILURE (OPEN)

A. 2-55P-15.1 B. 2-55P-15. 2 l

O P.ev : 0 Date: 3/1/89 Page: 29 of 29

[ MALFUNCTION CAUSE AND EFFECTS i

I Plant: MP2 Malfunction #: CC01A - Pila CC01B - P11B CC01C - P11C Malfunction

Title:

RBCCW Pump Trip.

Malfunction Type: Generic.

Malfunction Cause: Low Suction Pressure Switch Failure.

Plant Status Normal full power operation.

Malfunction Effects:

Malf A - RBCCW pump PllA discharge pressure flow and current indications will decrease to minimum. Pila stator and bearing temperatures _as indicated on the plant process computer will decrease. RBCCW flow will be lost to.the following components:

Spent Puel Pool HX A CNTMT Air Recirc Units A and C

-O RV Support Coolers CEDM Air Coolers shutdown Cooling HX A Waste Gas Compressors Primary Drain Tank and Quench Tank Cooler LPSI Pump A Seal Cooler HPSI Pumps A and B Seal Coolers CNTMT Spray Pump A Seal Cooler ESF Room A Air Cooling Coils j BA Evaporator Coolers j RCP A and C Thermal Barrier and Lube oil Coolers i j

Temperatures within associated systems which have lost .

I cooling flow will begin to increase. RBCCW header "A" flow ')

indication will' decrease to minimum. RBCCW pump B may be aligned and then started to supply header "A" to restore the lost flow. The pump handswitch amber indicating light will illuminate. Subsequent auto or manual closing attempts will not allow the pump breaker to remain shut. Tech Specs maybe impacted, unless flow can be restored to the RBCCW header. ]

The following alarms will actuate as their setpoints are l reached:  ?

l 3

Rev: 0 1/31/89' l Date:

1

l RBCCW Pumps. Misaligned RBCCW Hdr Press Lo RCP Cooling Water Low Flow CEDM Cooler Low Flow RBCCW Quench Tank and'PDT HX Flow Low -

I Control board indications are:

RBCCW Pump Amps Decrease ,

RBCCW Pump. Status Lights RBCCW Header "A" Pressure and Flow Decrease CAR RBCCW Flow Decrease Malf B - This malfunction will be similar to Malf A.except PilB will be the affected component.

Malf C - This malfunction will be similar to Malf A except'PilC will' be the affected component.

If a pump-supplying the "B" header alone is failed the- 9 following components will loose RBCCW flow:

Spent Fuel Pool HX B Containment Air Recire Units B and D RV Support Coolers Shutdown Cooling HX B-

-h t

U Blowdown Quench Tank Cooler Degasifier Vent Condenser and Eff Cooler

-)

Letdown HX LPSI Pump B Seal Cooler HPSI Pump C Seal Cooler CNTMT Spray Pump B Seal Cooler ESF Room B Air Cooling Coils RCP B and D Thermal Barrier:and Lube Oil Coolers Malfunction removal will restore the selected failed pump suction pressure switch to normal.

Reference:

26022, 28122 SH. 11, 32015 SH. A, 1, 2, 3, 40, 49, 32043.

SH. 1, 37006, SH. 2, 3, 4 and 5

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Rev: 0 Date: 1/31/89 i

' MALFUNCTION CAUSE AND' EFFECTS 'l

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Plant: MP2, Malfunction 4: CCO2A - P11A .;

CCO2B - P11B  !

.CCO2C - P11C ]

i d

Malfunction

Title:

RBCCW Header Rupture. Located at-Pila (B,C) j downstream of pumps discharge check valve. 1 Malfunction Type: Generic / Variable 100%' equals.2,000.gpm leak' rate at 120 psid.

Malfunction Cause: Piping weld failure.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will result in a loss of mass from RBCCW header "A".to the RBCCW pump and HX room.. RBCCW surge-O tank indicated levels will deccease allowing-automatic-makeup to refill the tank at low-severities. As the leak rate exceeds the makeup ability surge tank level will. ]

continually drop allowing-the header associated with'the i

leak to be identified due to the surge tank weir. As'the surge tank level decreases the RBCCW pump discharge pressure will~ decrease and running current increase.' When the NPSH requirements are below that.necessary to operate the pump it will begin to cavitate as indicated be oscillating pump current, pressure and flow indications.

Components cooled by RBCCW header "A"'will begin increasing in temperature. The RBCCW pump will tripfon' low suction pressure after a time delay if it' remains low.

RBCCW Tech Specs will be impacted, when there is no' flow.

The following alarms will annunciate if their setpoints are reached:

RBCCW RM Sump Level Hi RBCCW Surge Tank Auto Makeup.

RBCCW Surge Tank' Level Hi/Lo RBCCW Hdr A Press Lo RCP Cooling Water Low Flow CEDM Cooler Low Flow RBCCW Quench Tank and PDT.HX Flow Lo l Rev: 0 l Date: 1/31/89' I i

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l k Control Board Indications are:.

RBCCW Surge Tank Levels Decrease RBCCW Header Pressures and Flows Decrease  !

RBCCW Pump Current Increases CAR RBCCW Flow Decreases l

  • li The leak may be isolated by shutting the RBCCW pump i discharge and the RBCCW pump suction valves. RBCCW pump B i may then be aligned and started on the A header to restore  ;

its flow.  ;

1 Malf B - This malfunction will be similar to Malf A with the 1 rupture being located at P11B discharge.

Malf C - This malfunction will be similar to Malf A with the rupture being located at PllC discharge and "B" being the  :

affected header. l Malfunction removal will restore the selected rupture point to normal to stop the RBCCW leakage. I REFERENCb3: 26022, 26021, 26024, 32015 SH. 1, 2, 3, 7, 48, 37006 i SH. 2, 3, 4 and 5.

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!O Rev: 0 Date: 1/31/89

____________________________a

4 MALFUNCTION CAUSE AND EFFECTS U(~g Plant: MP2 Malfunction #: CC03 i

Malfunction

Title:

RBCCW Surge Tank Makeup Valve Failure. ]

Malfunction Type: Variable 100% equals valve fully open.  !

Malfunction cause: Valve mechanical failure.

Plant Status: Normal full poner. W 1

Malfunction' Effects:

This malfunction will position and maintain'the RBCCW surge tank valve at the selected severity. If failed shut the valve will not open at its automatic makeup setpoint (approx l 6 inches above tank weir). Operation of the valves assoc- 1 lated handswitch on CO6 will have no effect on valve operation. valve status will be displayed on CO6.

Failure of the valve in an open position at low severity leak rates or no leakage at all will result in the surge

/~' tank overflowing to the floor drain. The second PMW pump

()N will start if in standby.

The following alarms will annunciate if their setpoints are reached:

RBCCW Surge Tk Auto Makeup RBCCW Surge Tk' Level Hi/Lo  ;

1 Control Board Indications are:

RBCCW Makeup Valve Position Indication RBCCW Surge Tank Level

References:

26022, 26024, 32015 SH 7, 48, 32006 SH'4.

( Rev: 0 Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CC04A'- Hx 18A CC04B - Hx 18B CC04C - Hx 18C Malfunction

Title:

RBCCW Heat Exchanger Tube Leak.

Malfunction Type: Generic / Variable 100% equals 100 gpm leakage at 100 psid. i Malfunction cause: Tube failure.

Plant Status: Normal full power. l

'1 Malfunction Effects: 1 Malf A - This malfunction will result in leakage from RBCCW Hx A to.  ;

the service water system. RBCCW surge tank level will decrease initially at the severity rate until automatic makeup to the tank starts. At this time the leak rate (at full severity) should be exceeded by the makeup ability. If the tank makeup valve is open for greater than three minutes an associated makeup alarm will annunciate..

} I The leak may be isolated by removing the "A" heat exchanger from service. This will require having the "A" header supplied by a different RBCCW pump'than P11A as its suction i valves must be shut along with the heat exchanger outlet valves and pump discharge header crossconnect, j The following alarms will actuate as.their setpoints are exceeded:

RBCCW Surge Tank Auto Makeup Control board indications are:

RBCCW Surge Tank Levels Decrease Malf B - The effects of this malfunction will be similar to Malf A with'the tube leak being located in RBCCW Hx B.

Malf C - The effects of this-malfunction will be similar to Malf A with the tube leak being located in RBCCW Hx C.

Rev: 0 Date: 1/31/89

- _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - - - _ . _ . _ _ _ _ __)

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l O' Malfunction removal will return the selected failed heat exchanger to normal by stopping the tube leak.

]

Reference:

26022, 26008 SH. 1, 32015 SH. 7, 48,~37006 SH. 4 i

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Rev: 0 1 Date: 1/31/89

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( MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CC05A - TIC 6308 (Hx A)

CC05B - TIC 6307 (Hx B)

CC05C - TIC 6306 (Hx C)

Malfunction

Title:

RBCCW Temperature Control Failure.

Malfunction Type: Generic / Variable 100% equals 100*F.

Malfunction Cause: Heat exchanger outlet TT fails at a fixed setpoint.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - At low severities of this malfunction the service water outlet temperature control valve on RBCCW Hx "A" will close in an attempt.to maintain the desired RBCCW temperature.

This desired temperature will be set as a remote function in lieu of an individual locally controlled TIC. This will i

cause the outlet temperature of RBCCW Hx "A" to increase leading to an overall increase in supply water temperatures on RBCCW header "A". If the increase in temperature is significant the RBCCW surge tank level will increase.

With the malfunction set at higher severities above the temperature controlling setpoint the service water outlet temperature control valve will open. This will cause the outlet temperature of RBCCW Hx "A" to decrease leading to an overall decrease in supply water temperatures.on RBCCW header "A". If the decrease in temperature is.significant the RBCCW surge tank level will decrease to reflect it.

The following alarms will actuate as their setpoints are exceeded:

RBCCW Hx Temp Hi control board indications are:

RBCCW Heat Exchanger Outlet Temperature Increases The operator may limit the effects of this malfunction by placing an operable RBCCW heat exchanger in service.

Rev: 0 l

Date: 1/31/89 1

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0

% Malf B - The effects of this malfunction will be similar to Malf A with the temperature control of Hx B being the'affected component.

Malf C - The effects of this malfunction will be similar to Malf A with the temperature control of Hx C being the affected component.

Malfunction removal will restore the selected failed j tempt:rature transmitter on the RBCCW heat exchanger. )

Reference:

26022, 26008 SH. 1, 2, 32015 SH. 48, 37006 SH. 4 1

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Rev: 0 Date: 1/31/89

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'-(//} MALFUNCTION CAUSE AND EFFECTS i

Plant: MP2 Malfunction #: CC06A - RCP-A CC06B - RCP-B i CC06C - RCP-C l CC06D - RCP-D )

{

i 1

Malfunction

Title:

Loss of RBCCW to RCP.

Malfunction Type:. Generic / Variable 100%. equals total flow blockage.

Malfunction cause: Blockage at individual supply line isolation valve.

Plant Status: Normal full power. f l

l Malfunction Effects:

g Malf A - RCP RBCCW cooling water flow will decrease as the malfunction severity level is increased. RBCCW header "A" flow will decrease by the amount of that which drops to the RCP. RCP RBCCW. outlet temperature will increase. RCP )

pump motor, bearing and seal associated temperatures will  ;

increase pump seal flow and pressure will reflect the j

increase in seal temperature. When any pump bearing i temperature exceeds 350*F its bearing will begin to seize leading to a higher motor load. The pump will eventually trip on an overcurrent device. Pump oil reservoir' levels will increase due to the higher oil temperatures. A l manual or automatic pump trip will-eventually occur at high malfunction severities. The reactor / turbine will be tripped manually or automatically'if the RCP is lost.

The following alates will actuate.as their setpoints are i exceeded: ,

i RCP Clg Water Temp Hi

.RCP Clg Water Flow Lo RCP Bleedoff Temp Hi i RCP Lower Seal Temp Hi '

RCP Oil Clr in Temp Hi RCP Oil Clr Out Temp Hi RCP Upper Guide Temp Hi RCP Lower Guide Temp Hi  ;

Rev: 0 Date: 1/31/89

i 1

0

-(l) RCP Upper Thrust Temp Hi RCP Lower Thrust Temp Hi 'l RCP Lwr Brg Oil Temp Hi RCP RBCCW Outlet Temperature Increase '

RCP Pump Bearing Temperatures Increase RCP Pump Bleedoff Temperatures Increase i RCPfPump Current Indication Increases i Malf B - The effects of this malfunction will be similar to that of l malfunction Malf A with RCP B being the.affected  !

component, j Malf C - The effects of this malfunction will be similar to that of malfunction Malf A with RCP C being the affected component. j; Malf D - The effects of this malfunction will be similar to that of malfunction Malf A with RCP D being the affected component.

M41fsnction removal will restore the blocked RBCCW supply line on the selected failed reactor coolant pump.

1

REFERENCES:

26022 SH. 1, 2, 26032, 32007 SH. 39, 37006 SH. 2. l (1) l 1

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Rev: 0 Date: 1/31/89 l

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MALFUNCTION CAUSE AND EFFECTS j

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%J 1 1

Plant: MP2 Malfunction #: CC07A - Hx 34A- j CC07B - Hx 34B j CC07C - Hx 34C j 1

I Malfunction

Title:

Loss of RBCCW to CEA coolers.

Malfunction Type: Generic / Variable 100% equals total flow blockage.

Malfunction cause: Blockage at individual supply line isolation valve.

Plant Status: Normal full power.

1 l

Malfunction Effects:

l Malf A - CEA air cooler "A" RBCCW flow will decrease as the malfunction severity level is increased. RBCCW header A i flow will decrease by the amount of that which drops to the i air cooler. CEDM fan 13A discharge temperatures as  !

monitored by a computer point will increase. Reactor cavity ,

- area temperatures will begin to increase.

f(_)% The following alarms will actuate as their setpoints are exceeded:

CEDM Cooler Low Flow Control board indications are:

RBCCW Header Flow Decreases CEDM Cooler Fan discharge Temp Increases Reactor Cavity Temperatures Increasing Malf B - The effects of this malfunction will be similar to that of Malf A with CEDM cooler "B" being the affected component.

Malf C - The effects of this malfunction will be similar to that of Malf A with CEDM cooler "C" being the affected component.

Malfunction removal will restore the blocked RBCCW supply line on the selected failed CEDM cooler to normal.

Reference:

26022, 26028 SH. 1, 32031 SH. 1, 37006 SH. 3 Rev: 0 Date: 1/31/89 i

i 1

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/'] MALFUNCTION CAUSE AND EFFECTS l

%./

Plant: MP2 Malfunct' ion #: CC08A - Hx 35A I CC08B - Hx 35B  !

CC08C --Hx 35C i CC08D - Hx 35D Malfunction

Title:

Loss of RBCCW to Containment Air Recirculation Cooler.  ;

Malfunction Type: Generic / Variable 100% equals total flow ,

blockage. I Malfunction cause: Blockage of individual supply line upstream of isolation valve.

Plant Status: Normal full power.

i Malfunction Effects:

. Malf A - RBCCW flow to containment air recirculation cooler "A" will decrease as the malfunction severity level is increased. CAR fan "A" discharge temperature will increase leading to an overall reduction in the heat removability of the containment air recirculation and cooling system. Containment air temperature will increase at a rate to reflect the amount of cooling which was lost.

Containment humidity levels will also increase slightly and then stabilize along with temperature at higher values. ECCS Tech Specs may be affected.

The following alarm will actuate as its setpoint is exceeded:

Containment Air Temp (computer only)

Control board indications are:

Containment Air Temperature Increasing on TI-8096 at Col and Computer

, Containment Humidity Levels Increase l

The consequences of this malfunction may be limited by running additional CAR units and/or increasing RBCCW flow to operable CAR cooling heat exchangers.

Rev: 0 Date: 1/31/89

Malf B - The effects of this malfunction will be similar to that of Malf A with CAR cooler "B" being the affected component.

Malf C - The effects of this malfunction will be similar to that of l Malf A with CAR cooler "C" being the affected. component. I Malf D - The effects of this malfunction will be similar to that of ,

Malf A with CAR cooler "D" being the affected component.

Malfunction removal will restore the blocked RBCCW supply line on the selected failed CAR cooling unit to normal.

REFERENCES:

26022, 26028 SH. 1.

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( /N U Rev: 0 Date: 1/31/89

("] MALFUNCTION CAUSE AND EFFECTS

%..) 1 Plant: MP2 Malfunction #: CC09 I

Malfunction

Title:

Loss of RBCCW to Letdown Heat Exchanger.

Malfunction Type: Variable 100% equals valve fully shut.

Malfunction Cause: LD TCV (2-CH-223) positioner failure.  !

l I

Plant Status: Normal full power.

1 1

Malfunction Effects:

This malfunction will override the ability of the letdown ]

temperature controller to automatically position the letdown heat l exchanger RBCCW outlet temperature control valve. Its position will i be solely dependent on malfunction severity. At high severities, ,

l when the valve's actual position is shut further than that desired by its temperature control, RBCCW flow will be reduced through the I)\

\- letdown heat exchanger. RBCCW header "B" flow will decrease, RBCCW l pressure will increase and RBCCW heat load will decrease to reflect  !

the lower LDHX RBCCW flow. CVCS letdown temperature will increase l leading to higher VCT temperatures, bypassing of purification ion exchangers and isolation of CVCS process monitoring instrumentation ,

if their temperature setpoints are exceeded. If pressure existing l within the letdown side of the heat exchanger, flashing will occur.

This will be seen as pressure and flow oscillations on the letdown I line.

If malfunction severity levels cause a greater than necessary RBCCW flow , letdown temperature will decrease. This will cause higher RBCCW header flow and lower header pressure. ]

l The following alarms will actuate as their setpoints are exceeded:

Letdown Hx Outlet Temp Hi VCT Temp Hi Boron / Rad Monitor Flow Lo control board indications are:

Letdown Temperature Isolation RBCCW Header Flow Indication VCT Temperature Indication I Rev: 0 Date: 1/31/89

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O. ' Malfunction removal will restore the l_etdown temperature. control

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valve positioner to' normal allowingLthe associated temperature controller to position the valve.

REFERENCES:

26022, 26017, 37006 SH. 2.

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Rev: 0 Date: 1/31/89

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/~h MALFUNCTION CAUSE AND EFFECTS NA Plant: MP2 Malfunction #: CC10A - Hx 34A l CC10B - Hx 34B CC10C - Hx 34C Malfunction

Title:

RBCCW leak at inlet to CEA coolers.-

i N

Malfunction Type: Generic /Veriable 100% equals 150 GPM leak.

Malfunction Cause: Leak at inlet to CEDM cooler, j Plant Status: Normal full power.

Malfunction Effects:

Malf A - CEA air cooler "A" RBCCW flow will decrease as the j malfunction severity level is increased. CEDM fan 13A discharge temperatures as monitored by a computer point {

will increase. Reactor cavity area temperatures will

() begin to increase. Ctmt sump level will increase. ]

The following alarms will actuate as their setpoints are exceeded:

CEDM Cooler Low Flow Ctat Sump Alarm control board indications are:

RBCCW Surge Tank Decreases CEDM Cooler Fan Discharge Temp Increases Ctmt Sump Level Increases Malf B -

The effects of this malfunction will be similar to that of Malf A with CEDM cooler "B" being the affected component.

Malf C -

The effects of this malfunction will be similar to that of Malf A with CEDM cooler "C" being the affected component. l 1

Malfunction removal will restore the leaking RBCCW supply line on the selected failed CEDM cooler to normal. Cooler outlet temperature will return to normal.

REFERENCES:

26022, 26028 SH. 1, 32031 SH. 1, 37006 SH. 3.

Rev: 0 Date: 3/1/89

_ _ _ _ _ _ - - . - - 1

l r~s MALFUNCTION CAUSE AND EFFECTS N-  ;

Plant: MP2 Malfunction #: CH01A - F14A CH01B - F14B i CH01C - F14C CH01D - F14D ;

Malfunction

Title:

Containment Air Recirculation Fan Trip l

Malfunction-Type: Generic, Non-variable Malfunction cause: Thermal overload contact (49) failure Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in a trip.of the selected CAR fan motor. An annunciator will alarm indicating the fan has tripped. The f an wil' be prevented from starting, either manually or on a SIAS sequencer start signal. If the affected CAR fan was; being used for containment cooling, the loss of the' fan will reduce the heat removal ability of the associated containment air cooler.  ;

This will result in gradually increasing containment temperatures and humidity levels.

Operator action in response to this malfunction should be to start additional cooling unit fans or increasing their associated cooling water flow.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

CTM Air Recirc Fan A (B,C,D) Trip Due to the loss of CAR fan, the Tech. Spec. for number of operable CAR cooling units will be impacted.

Removal of malfunction will restore the selected failed fan thermal overload contact to normal allowing the fan to be started.

References:

26028, 28128, 32022 Rev: 0 l ' k'O 1

J Date: 1/31/89 I

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MAL? UNCTION CAUSE AND EFFECTS' l

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[A J j Plant: MP2 Malfunction #: CR01 Malfunction

Title:

Fue'. Clad Failure. ,

Malfunction Type: Variable. 100% equals 2% Gas Gap Activity, i

1 Malfunction cause: Clacding Failure, i Plant EL&tus: Normal fill powe r.

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Malfunction Effects: ~ l This malfunction results in the release of fuel gap activity into I the RCS resulting in a homogeneous mixture throughout the RCS. The j letdown failed fuel monitor RM-202 and RM-202A will be the. major ,

indicator of this malfur etion.  !

J The failed fuel monitor will' spike upwards and then decrease-to some H higher steady state valte then before the malfunction.

)

Area rad monitors in the vicinity of-letdown' and CVCS will increase. I Major radiation monitort affected are as follows:

RM-7894 Engineering Safeguards Area Rad Monitor.

RM-7895 Primary Sample Sink Area Rad Monitor

! RM-7896 14'6" Aux Bldg Rad Monitor RM-7897 -45' Aux Bltg Rad Monitor Radiation area levels within and outside the containment will l increase as noted on the following monitors:

I RM-7890 Ctmt Per Acc ess Area Rad Monitor RM-7891 Ctmt Refuel Machine Area Rad Monitor l RM-8240 Ctmt 14'6" Iast Area Rad Monitor RM-8241 Ctmt 14'6" Fest Area Rad Monitor At 100% severity, the fcllowing 5 Radiation Monitors are expected to. j be in alarm RIT 7891, 7f95 & 7896, RM 202 &'202A.  !

I Rev: 0 Date: 3/1/89 s !____ ____-___ _ _ - _ -

The increase in RCS activity will result in high activity levels

' transmitted to associated' systems wherever RCS leakage"is involved.

RCS Tech Specs may be impacted,-depending on RCS sample results.

The simulator must be re-initialized to recover from this malfunction.

REFERENCES:

FSAR and Reference Plant' Data Book, Event #39.

I O Date:

Rev: 0 3/1/89

MALFUNCTION CAUSE AND EFFECTS l

Plant: MP2 Malfunction #: CR02 1

Malfunction

Title:

Incore NI Failure.

~

Malfunction Type: Generic / Variable, 100% = 1100 millivolts. CR02  !

(1-1 thru 45-4; 180 Total). f i

Malfunction Cause: Cable Fault.  ;

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Plant Status: Power operation. j l

l Malfunction Effects:

1 L

Malf 1 This malfunction-fails the incore self powered rhodium- 3' detector located in assembly A10. Its output to computer point R391 will remain at'its fixed malfunction  ;

l severity setpoint (0-1100 MV) while the actual power level in the detector area may be changing. The l

,A . uncorrected detector signal will' alarm on the PPC if j the severity produces > 600 MV signal. The PPC ]

calculates a corrected detector signal CVR391 based on 1 the R391 incore detector value affected by this l malfunction. If the corrected detector. signal CVR.391 ]

exceeds its alarm limit, a separate Plant Process-  !

Computer (PPC)' alarm is' produced. -These corrected signal incore detector alarms are covered by Tech Specs, l

Note: If an uncorrected detector signal of > 600 MV is detected, corresponding corrected' detector signal alarms are inhibited as unreasonable, s

. Depending on the severity used, incore tilt and radial I peaking factors may be affected and the "F *-T'" -( '

Annunciator (C-04 DB-ll) and PPC alarms CVfRT and CVINTILT may actuate.

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Malf 1-2 Effects similar to malfunction 1-1 except the remaining through detectors located in A10, B5, B7, B15, C6, C17 . . .

45-4 etc. will be individually affected.

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1 Rev: 0 i Date: 3/1/89-

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1 Malfunction removal will restore the selected failed incore self powered rhodium detector output to normal. .l 1

REFERENCES:

PPC Specifications SP-211A, Incore Rhodium. Monitoring, PPC Analog Input List.  ;

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MALFUNCTION CAUSE AND EFFECTS

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i Plant: MP2' Malfunction #: CR031.(2-45) j Malfunction

Title:

Incore' Thermocouple Failure.  !

l Malfunction Type: Generic / Variable. 100% equals 2500*F Output. .

i Malfunction Cause: Cable Failure. l Plant Status: Normal full. power.

i Malfunction Effects: i Malf 1 - This malfunction fails the Incore Thermocouple detector located in assembly A10. Its. output to the ICC System j will remain at its fixed malfunction severity setpoint ,

(0-2500 F) while the actual. temperature may change. Tech  !

s Specs may be impacted.

70 F is the lowest severity that should be used (2.8%).

since these thermocouple have a reference junction in the computer room. Failure below 70 F is unlikely.

The following alarms may be received depending.on whether a Fac I or Fac II thermocouple:

Facility 1 Saturation Trouble (< 40 F subcooling)

Facility 2 Saturation Trouble Facility 1 Core Exit Temp Hi (> 625*F CET)

Facility 2 Core Exit Temp Hi Malf 2 - Effects similar to Malf 1 except detectors in other 45 - assemblies will be affected.

Malfunction removal will rostore the output to normal.

REFERENCES:

FSAR, Analog Input List, System Description.

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Rev: 0 Date: 3/1/89

l r- MALFUNCTION CAUSE AND EFFECTS k j i

Plant: MP2 Malfunction #: Cv01 1

Malfunction

Title:

Unisolable' letdown line rupture inside CTMT between the RCS and 2-CH-515.

Malfunction Type: Variable, 0-100%, 100% equals 200 gpm at 2250 psid.

I Malfunction Cause: Rupture of the letdown line upstream of 2-CH-515.

Plant Status: Normal full power operation.

J Malfunction Effects: This malfunction results in a partial failure of the letdown line inside containment. The leak is unisolable, located 3 betwee,n the letdown tap from the RCS and the first isolation valve, )

(2-CH-515). i 1

At 100% severity, the leak causes a sharp reduction in letdown flow to less than 20 gpm. This decrease is due to both the decrease in ,

letdown line pressure and the letdown flow control valve throttling O closed in response to the pzr level decrease.

Pzr level will decrease rapidly causing the first, then second backup charging pumps to start. At maximum charging and minimum letdown, pzr level will continue to decrease approximately 1% per minute. VCT level will decrease approximately 3% per minute. The PPC program for RCS leak rate will indicate RCS leakage approaching 200 gpm as data is accumulated. Securing charging and letdown will accelerate pzr level decrease to approximately 3% per minute.

Due to the large imbalance between charging and letdown flowrates across the regenerative heat exchanger, both temperatures will rapidly drop to be slightly above VCT temperature, Pzr pressure will decrease slowly to 2200 psia. The backup heaters will energize, raising pressure slowly to 2225 where they deenergize.

Allowed to continue without operator action, pzr pressure will cycle between 2200 and 2225 psia until pzr level decreases to 20% and all heaters deenergize.

Containment conditions slowly change to indicate a small RCS leak.

CTMT normal sump level, CTMT temperatures, dewpoint, narrow range pressure, CTMT particulate and gaseous radmonitors all increase to indicate a release of high energy fluid, with activity,-inside CTMT.

l Rev: 0 v Date: 3/1/89 l

l L-___--________-_____-_________________-_______-______ . _ _ . _ .s

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() The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

I J

" Letdown Flow Lo" "Pzr Pressure Selected Channel Deviation Hi/Lo" l "Pzr Ch 'X' Level Hi/Lo" "Pzr Ch 'Y' Level Hi/Lo" Due to the leak being unisolable, Tech. Specs. will require an orderly shutdown for unidentified leakage exceeding limits and AOP 2568 requires a manual reactor trip for ECS leakage exceeding the capability of CVCS to maintain pzr level. RCS cooldown and 1

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depressurization will be required to minimize the leakage.

Removal of CV01 will stop the leakage and pzr level and pressure control systems will respond to restore normal pzr level and pressure.

Introduction of CV01 at lesser severities will cause similar effects of proportionally smaller magnitudes with the following exceptions.

- Pzr level will be maintained with two backup charging pumps, one  :

backup. charging-pump, or letd'un flow decrease as severity is l i

decreased.

l

- Pzr prestare will be maintained by the proportional heaters at low .

severities. I

REFERENCES:

P&ID 26017, CEN 128 Case E2.

() Rev:

Date:

0 3/1/89 l

MALFUNCTION CAUSE AND EFFECTS l

Plant: MP2 Malfunction #: CV02

)

Malfunction

Title:

Isolable letdown line rupture in the Aux Bldg between 2-CH-089 and the letdown flow control valves.

1 Malfunction Type: Variable, 0-100%,.100% equals 200 gpm at 2250 psid. l 4

Malfunction cause: Rupture of the letdown line downstream of 2-CH-089. j I

Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in a partial failure of the letdown line in the Aux Bldg. The leak is 1 olable, located between valve 2-CH-089 and the letdown flow control valves.

At 100% severity, the leak causes a sharp reduction in letdown flow to less than 20 gpm. This decrease is due to both the decrease in g letdown line pressure and the letdown flow control valve throttling ,

, closed in response to the pzr level decrease.

Pzr level will decrease rapidly causing the first, then second backup charging pumps to start. At maximum charging and minimum letdown, pzr level will continue to dicrease approximately 1% per minute. VCT level will decrease approximately 3% per minute. The PPC program for RCS leak rate will indicate RCS leakage approaching 200 gpm as data is accumulated. Securing charging and letdown will terminate the leak and pzr level will stop decreasing with the exception of RCP.bleedoff (4 gpm).

Due to the large imbalance between charging and letdown flow rates l across the regenerative heat exchanger, (in favor of letdown), both temperatures will rise rapidly then undergo two step decreases as the .

backup charging pumps start. Final temperatures will stabilize higher j than pre-leak values. 1 Pzr pressure will decrease slowly to 2200 psia. The backup heaters j '

will energize, raising pressure slowly to 2225 psia where they deenergize. Allowed to continue without operator action, pzr pressure will cycle between 2200 and 2225 psia until pzr level decreases to 20%

and all heaters deenergize.

l l; Rev: 0

' Date: 3/1/89

. _ _ _ - _ _ _ - - _ i

fg Leakage occurring in the West -5 piping penetration room will fell Q through the floor grates to the "A" safeguards room. The Aux. Bldg.

ventilation will reflect increasing airborne activity levels on the

" Charging Pps/Degasifier Area" exhaust radmonitor. The Unit 2 stack gaseous and particulate monitors will increase as the airborne activity is transported, via main exhaust, up the Unit 2 stack.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

" Letdown Flow Lo" "Pzr Pressure Selected Channel Deviation Hi/Lo" "Pzr Ch 'X' Level Hi/Lo" "Pzr Ch 'Y' Level Hi/Lo"

" Process Mon. Rad Hi-Hi/ Fail" Due to the leak being isolable and accessible, Tech. Spec. leakage i limits will not be exceeded, (after isolation), and repairs may be

! attempted. The leak may be specified as " body to bonnet on the in

service letdown flow control valve". This specific location allows isolation of the leak by closing the inlet and outlet FCV isolations, l (simulated by removal of CV02). Shifting to the alternate letdown FCV would allow restoration of normal charging and letdown. If the leak is specified as non-repairable, an orderly shutdown will be required.

i operator action to secure letdown using 2-CH-515, 516, or 089 will stop the leak.

Removal of CV02 will stop the leakage and pzr level and pressure control systems will respond to restore normal pzr level and pressure.

Introduction of CV02 at lesser severities will cause similar effects of proportionally smaller magnitudes with the following exceptions:

Pzr level will be maintained with two backup charging pumps, one backup charging pump, or letdown flow decrease as severity is decreased.

Pzr pressure will be maintained by the proportional heaters at low-severities.

REFERENCES:

P&ID 26017 and 26028, CEN 128 Case E2. j O Rev:

Date:

0 3/1/89

'l 1

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CV03 i

l l

Malfunction

Title:

Letdown Heat Exchanger Tube Rupture.

1 Malfunction Type: Variable. 100% equals 100 gpn leak rate at 250 psid.

1 Malfunction Cause: Tube f ailu~r e .

I 1

Plant Status: Normal full power.

1 l

Malfunction Effects:

This malfunction will result in leakage to the.RECCW system of reactor coolant from the letdown heat exchanger. As the leak rate is increased, the letdown pressure will decrease causing the letdown pressure control valve to throttle down to maintain its controlled setpoint pressure. The tube leakage will also cause pressurizer level O to decrease, thus causing the letdown flow control valve to throttle down. The actual leak rate will be dependent on the position of the letdown flow control valve and the pressure maintained within the i Letdown Heat Exchanger.

]

VCT level will decrease at a rate equal to the actual system outleakage until makeup to the VCT is started.

The leakage into the RBCCW system will result in the RBCCW surge tank )

level increasing. Process radiation levels as monitored by RIT-6038 j will increase to reflect the increase in activity caused by the tube leak. Activity levels within the RBCCW system will be dependent on RCS activity levels as they pass to the CVCS. Tech specs will not be ,

impacted. 1 The following alarms will actuate when their setpoints are exceeded:

VCT Level Lo Letdown Flow Lo  ;

Letdown Press Hi/Lo RBCCW Surge Tk Level.Hi/Lo Process Monitor Hi Rad / Fail. j O Rev:

Date:

0 1/31/89 i j

._--_-___O

() Control board indications are:

Decreasing VCT Level Decreasing Letdown Press and Flow Increased Charging Flow Increasing RBCCW Surge Tank Level Increasing RBCCW System Rad Levels.

The leak into the RBCCW system may be stopped by securing letdown flow from the RCS. If RBCCW system pressure exceeds the pressure maintained within the CVCS side of the LDHX, mass will be lost from the RBCCW system. If the letdown pressure control valve is opened at this time, the RBCCW will leak, through the letdown line into the VCT.

Malfunction removal will restere the integrity of the letdown heat exchanger.

REFERENCES:

26017, 26022, 32031 SH. 21, 37006 SH. 2, 4, 28500 SH.

195, 196 O

l <

Rev: 0 l Date: 1/31/89

.fg MALFUNCTION CAUSE AND EFFECTS N_A i

Plant: MP2- Malfunction #: Cv04A P18A l l

CV04B P18B CV04C P18C l

1 Malfunction

Title:

Charging Pump Trip.

Malfunction Type: Generic /Non-Variable.

I Malfunction cause: Thermal overload Contact (49) Failure.

J Plant Status: Normal full power.  !

Malfunction Effects:

Charging pump A will trip and'its handswitch will indicate that its  ;

motor contactor is open. This will result in a momentary total loss  !

of charging flow when only one pump is initially operating. Due to  ;

(

g, the loss of charging _ flow to the letdown regenerative heat exchanger, its letdown outlet temperature will increase. If the outlet temperature rises above 470 degrees F, automatic letdown isolation will occur. The increase in letdown temperature will add to the heat load on the letdown heat exchanger. The letdown temperature control valve will attempt to maintain the controlled outlet temperature on the letdown heat exchanger. If its outlet temperature cannot be maintained below 145 deg F the ion exchanger bypass valve 2CH-520 will open and the boronmeter/ rad mon isol valve 2CH-521 will shut.

Tech Specs will be impacted if less than two charging pumps are operable.

Pressurizer level will decrease causing the letdown flow control valve to throttle down to a minimum flow ~29 gpm (if letdown had not already isolated). When indicated level falls below 2.5% of its programmed setpoint, the first backup charging pump will start to restore charging flow and pressurizer level.

The following alarms will actuate as their setpoints are exceeded:

Charging Flow Lo Letdown Regen Hx Outlet Temp Hi Letdown Hx Outlet Temp Hi Boron / Rad Monitor Flow Lo. 1

Rev
0 Date: 1/31/89

1

)

Control board indications are:

Charging Flow Decreases 1

The pump will not operate if a manual or automatic start attempt is  !

made. l 1

Malf B - Effects similar to Malf A with charging pump B being the affected component.  ;

Malf C - Effects similar to Malf A.with charging pump C being the l' affected component.

Malfunction removal will restore the selected failed charging pump overload contact to normal, allowing it to be started.

REFERENCES:

26017, 32009 SH. 26, 27, 33, 34, 40, 41, 42, 43, 37006 SH. 2, 28500 SH. 220, 222, 223, 224 4 i

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() Rev:

Date:

0 1/31/89

l 7 MALFUNCTION CAUSE AND EFFECTS k.' -

l l Plant: MP2 Malfunction #: CV05 Malfunction

Title:

Letdown Temperature Transmitter (TE-223) Failure.

(

Malfunction Type: Variable. 100% equals maximum instrument range (200 F).

Malfunction cause: Transmitter failure.

1 Plant Status: Normal full power.  !

Malfunction Effects:

1 This malfunction will fail the indicated and controlled temperature.as  !

sensed.by the outlet of the letdown heat exchanger and displayed on j the letdown temperature controller. The indicated value will fail to j the severity. level as selected. If the value selected is above the l

/'_ normal temperature control setpoint (120 degrees F) the RBCCW TCV j

\ (2-CH-223) will throttle to fully open position in an attempt to reduce the indicated temperature. This will result in the actual j{

1etdown temperature, as displayed by TI-224 to decrease, leading to i lower volume control tank temperatures. ]

i selected severity levels below the controlled setpoint will cause the letdown TCv to throttle shut leading to higher letdown heat exchanger outlet and volume control tank temperatures. If outlet temperature should exceed 145 degrees F, the ion exchanger will be bypassed and the boron / rad monitor flow will be isolated automatically.

Manual control of the letdown TCV will not be affected and may be used to restore the letdown temperature to normal.

The following alarms will actuate when their setpoints are exceeded:

Letdown Hx Outlet Temp Hi VCT Temp Hi Boron / Rad Monitor Flow Lo.

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()- Rev:

Date:

0 1/31/89 l l

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j Control board indications are:

Increasing / Decreasing LDHX Outlet Temp Increasing / Decreasing VCT Temp.

Malfunction removal will restore the letdown-temperature transmitter .;

(TE-223) operation to normal.

REFERENCES:

26017, 26022, 28500 SH. 222 )

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I O- Rev:

Date:

0 1/31/89

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l MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CV06 i

Malfunction

Title:

- Letdown Pressure Transmitter Failure-(PT201).

Malfunction Type: Variable. 100% equals maximum range (600 psig).

Malfunction Cause: Transmitter Failure

.)

Plant Status: Normal full power.

Malfunction Effects:

Letdown pressure indication will fail to the value selected by malfunction severity. If the value selected is greater than the setpoint value, the letdown pressure control valve will open in an attempt to reduce the indicated pressure. This will cause a decrease in actual letdown pressure. Letdown flow will initially increase slightly due to reduced back pressure. It will then be reduced as the  ;

(~

s letdown flow control valves throttle down to restore pressurizer l level. j If severity levels below the setpoint pressure are selected, the letdown pressure control valve will shut in an attempt to raise the letdown pressure. This will result in actual letdown pressure increasing. If the pressure exceeds the LDHX relief valve 2CH-345 i setpoint, it will lift and relieve to maintain letdown pressure. The f

letdown flow control valve will open slightly, due to the increased i back pressure and loss of letdown flow to maintain pressurizer level.  :

VCT level will decrease at the relief valve leak rate as letdown flow through the letdown pressure control valves will be stopped.

The following alarms will actuate when their setpoints are exceeded:

Letdown Press Hi/Lo Letdown Flow Lo.

j l

l Rev: 0.

Date: 1/31/89

-i

Control board indications'are:

Letdown Pressure Letdown Flow.

Manual control of the letdown pressure controller will allow manual positioning of the associated valve. This may be used to limit the consequences of this malfunction. i Malfunction removal will restore PT-201 functions to normal.

REFERENCES:

26017, 26020, 28500 SH. 195 O

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i 0

O Date:

Rev:

1/31/89 l 1

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MALFUNCTION.CAUSE AND EFFECTS Plant: MP2 Malfunction #: CV07A LT 226 CV07B LC 227-I Malfunction

Title:

VCT Level Transmitter Fail.

I Malfunction Type: Generic / Variable. 100% equals maximum transmitter j range. j Malfunction Cause: Transmitter Failure. ]

j Plant Status: Normal full power.

Malfunction Effects:

1 Malf A - This malfunction will fail the transmitted level as ]

displayed by LI-226 and associated controlled devices. The

,s indicated level will fail at the selected severity. If a ,

level of greater than 72% is selected, automatic makeup to l (N} the VCT will not initiate and a VCT high level alarm would  !

never actuate if actual VCT exceeded 90%. If automatic  !

makeup was in progress and a level less than 86% was selected, automatic makeup would not stop. The VCT low level alarm function will also be affected by this . j malfunction. Shifting of letdown to waste or charging pumps l suction to the RWST on their associated VCT level setpoints ]

(88% and 5% respectively) will'not be affected by this i malfunction).

The following alarms will actuate when their setpoints are exceeded: .

VCT Level Hi VCT Level Lo.

Control board indications include:

VCT Level Ind (LI-226) l Rev: 0 Date: 1/31/89

__-___-_ a

Malf B - This malfunction will affect the control functions of~

LC-227. -Depending on the severity selected, the following functions as controlled by VCT level may or may not occur.

If a severity of greater than 5% is selected and actual VCT level falls below this value, the charging pump suction will not automatically shift to the RWST. If the charging pump suction pressure decreases to 10 psia, the pumps will trip.

If a level below 88% is selected,. letdown will not automatically divert to the radwaste system. The volume control tank low-low level alarm will also be affected by this malfunction. VCT automatic makeup control and low level alarm will not be affected by this malfunction.

Malfunction removal will restore the selected failed VCT level transmitter to normal.

REFERENCES:

26017, 28500 SH. 227, 226.

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l

[

Rev: 0 Date: 1/31/89

~l

.l1 i

g- MALFUNCTION CAUSE AND EFFECTS

.V i

Plant: MP2 Malfunction #: CV08 Malfunction

Title:

VCT Makeup Control Failure. ,

l Malfunction Type: Generic /Non-Variable. j Malfunction cause: Makeup mode selector. switch mechanical failure, apparently stuck in its manual position. .;

l Plant Status: Normal full power. ,

1 Malfunction Effects:

With this malfunction inserted in the manual position, operator control of the associated components will be the only means.of supplying makeup water to the volume control. tank.. If VCT makeup, other than any manual operation is in progress,-it will stop as if.it J

<~s were secured when the manual makeup mode were selected. Operation of 1

( the makeup mode selector from its manual position will produce no ,

direct observable effects due to switch operation.

I Malfunction removal will restore the makeup mode selector switch )

operation to normal. i

REFERENCES:

26017, 32009 SH. C, 4, 5, 21, 22, 23 l

I I

s i

i Rev: 0

\ Date: 1/31/89 i

MALFUNCTION CAUSE AND EFFECTS (v~]

Plant: MP2 Malfunction #: Cv09 Malfunction

Title:

Dilution Accident.

Malfunction Type: Variable. 100% equals 50 gpm leak rate with PMW available.

Malfunction Cause: Inadvertent opening of 2-CH-180, PMW supply to charging pump suction.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will result in leakage from the primary makeup water system directly to the suction of the charging pumps. The leakage into the system will be dependent on the charging flow rate. The

('N. makeup requirements of the VCT will decrease as the severity level is increased. The amount of primary makeup water flow will be displayed and totalized at C04F flow indicators. When the VCT level rises above 88%, its diversion valve will open to restore level to 85%.

The reactor coolant system boron concentration level will decrease as j primary makeup water enters the system. This will result in reactor 9 power increasing, possibly leading to a high power trip if the l condition is allowed to continue. j Control board indications are:

PMW Flow Increases Reactor Power Increases Boron Concentration Decreases.

The consequences of this malfunction may be limited by control rod insertion, addition of boric acid, stopping charging flow, or securing both PMW pumps.

Malfunction removal will stop the PMW source of leakage through 2CH-180.

REFERENCES:

26017, 28500 SH. 207

> Rev: 0

\ Date: 1/31/89

1 l

{ MALFUNCTION CAUSE AND EFFECTS l j

Plant: MP2 Malfunction #: CV10 Malfunction

Title:

Inadvertent Boration Accident.

i Malfunction Type: Generic l

l Malfunction Cause: Boric acid pumps fail.to stop simultaneously with j a 10 gpm leakage through 2-CH-514 (BA pump J emergency supply to Chg pump suction). i

)

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will result in leakage of boric acid from Boric Acid Storage Tanks directly to the suction of the charging pumps. When a boric acid pump is started from its handswitch, it cannot be stopped. j.

/,_) This, coupled with the leakage through 2-CH-514, will result in boric j

(_/ acid flow to the charging pumps suction. If an additional BA pump is J run, the flow rate would be larger. This will result in reduced I makeup requirements to the volume control tank and continued loss of mass from the associated boric acid storage tank. -1 l .

j The reactor coolant system boron concentration will increase as boric I acid enters the system. This will result in reactor power decreasing. )

Control board indications are:-

, i i

Boric Acid Pump running Boron Concentration Increases Reactor Power Decreases.

The boric acid pump cannot be stopped with its associated handswitch l once it is started. The consequences of this malfunction may be l limited by the addition of primary makeup water to the RCS.

Malfunction removal will stop the leakage through 2-CH-514 and allow the boric acid pumps to be stopped.  !

REFERENCES:

25017, 32009 SH. 4.

p) t Rev:

Date:

0 1/31/89

1 l

l MALFUNCTION CAUSE'AND EFFECTS Plant: MP2 Malfunction #: CV11 l

Malfunction

Title:

Letdown Back Pressure Control Failure.

Malfunction Type: Variable. 100% equals divergent oscillation in ]

pressure control.

Malfunction cause: Valve controller gain problem.

Plant Status: Normal full power.

Malfunction Effects:

I This malfunction will result in unstable letdown pressure control when PIC-201 is in its automatic mode. .The controller integral gain setting will be the affected component which will affect the letdown pressure valves' response to maintain the setpoint pressure. .As the

('] severity level is increased, the response time of the control valve

(_ / will decrease. At low severities, (less than 50%), oscillations in letdown pressure control will be seen but will not be divergent. I Larger severities will lead to divergent oscillations. It will be necessary to initiate a disturbance in letdown pressure control to start an oscillation.

As letdown pressure rises it will be limited by the letdown heat l exchanger inlet relief valve 2-CH-345. Flashing of the water in the  ;

letdown line will be seen as pressure and flow oscillations if. letdown pressure drops below that of saturation for the existing temperature. ]

Manual operation of the LD pressure controller may be used to restore LD pressure to normal.

The following alarm will actuate if its setpoint is exceeded:

Letdown Press Hi/Lo.

Control board indications are:

Letdown Pressure Letdown Flow.

Malfunction removal will restore letdown pressure control to normal.

()

REFERENCES:

26017, 28500 SH. 195.

Rev: 0 Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS

)

Plant: MP2 Malfunction #: CV12 l

Malfunction

Title:

VCT Leakage.

Malfunction Type: Variable. 100% equals 100 gpm leakrate at 20 psid.

Malfunction Cause: Unisolatable weld leak at bottom of the VCT.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction results in the leakage of mass from the volume control tank into the VCT room. The liquid mass will be drained to the aerated liquid waste tank. The airborne activities will rise as indicated on RIT-8998 (VCT,. sample room, LRR tank area), RIT-8999 (SFP pump and Hx area), and RIT-8132A/B stack gab exhaust monitors.

7s

\ volume control tank level will decrease, requiring makeup to maintain its level. If the level is allowed to drop below 5%, the charging pump suction will automatically shift to the refueling water storage tank.

The following alarms will actuate if their setpoints are exceeded:

Process Mon Rad Hi Hi/ Fail [RM 8998, 8999, 8132A, 8132B)

Process Mon Rad Hi VCT Low Level Alarm control board indications are:

Volume Control Tank Level Decreases Radwaste system ventilation radiation levels increase as detected by RM-8998, 8999 and 8132A/B.

Malfunction removal will restore the integrity of the volume control tank.

REFERENCES:

26017, 26028, 26029, 26021, 26024, 28018, 37006 SH. 4.

(

Rev: 0 Date: 1/31/89 1

- . _ . _ _ . . _ . _ _ . _ _ _ __._____._____m_____M

MALFUNCTION ~CAUSE AND EFFECTS

. g[~'\

Plant: MP2 . Malfunction #: CVl3 Malfunction

Title:

Charging Line Leak Inside Containment.

Malfunction Type: Variable. 100% equals 100 gpm leak rate at 2250 psid.

Malfunction Cause: Pipe rupture on Loop 2A charging line between 2-CH-432 and 2-CH-518.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction results in the leakage of reactor coolant into the containment environment. As the severity level is increased, and  !

depending upon the number of running charging pumps, the effective Oj charging flow into the RCS-will decrease. Pressurizer level will )

decrease with the level control system responding to restore it by '

starting additional charging pumps and shutting the letdown flow control valve. When the leak rate exceeds the CVCS makeup ability, i pressurizer level will continuously drop, possibly requiring a manual i reactor trip. The increased charging flow will result in a decreasing ]j VCT level requiring additional makeup to maintain it. Pressurizer pressure will decrease along with its level causing its control system to respond by energizing additional heaters in order to maintain it.

Tech Specs may be effected by this malfunction due to an inoperable charging flowpath.

The containment humidity, temperature, and pressure will increase to reflect the RCS leakage. Radiation levels, as depicted by containment atmospheric gaseous, particulate and area monitors, will increase in '

reflection to the CVCS activity levels. The containment sump level will increase to reflect the leakage accumulated. 3 The following alarms will actuate if their setpoints are exceeded: i VCT Level Low Pressurizer CH X/Y Press Hi/Lo l Pressurizer CH X/Y Level Hi/Lo Containment Air Particulate Rad Hi Containment Air Gaseous Rad Hi

(~T Containment Norm Sump Level Hi/Lo.

Rev: 0 IQ Date: 1/31/89 l

'l Control board indications are:

l Decreasing VCT Level Decreasing Pressurizer Pressure and Level i Increasing Temperature, Pressure, Humidity and Radiation Levels within the containment l Increasing Containment Sump Level. 4 The consequences of this malfunction may be limited by isolating the loop 2A charging line and shutting 2-CH-518.

Malfunction removal will restore the integrity of loop 2A charging line to normal.

REFERENCES:

26017, 26024, 26028, 28500 SH. 69, 37006 SH. 1, . 2 .

()

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() Date:

Rev: 0 1/31/89 l

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MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CV14 Malfunction

Title:

Charging Line Leak in Auxiliary Building.

Malfunction Type: Variable. 100% equals 100 gpm leak rate at 2250 psid.

Malfunction cause: Piping failure on charging line between 2-CH-429 and containment penetration.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will result in leakage from the charging'line into the west piping penetration room of the_ auxiliary building. As the f s severity 1-vel is increased, effective charging flow into-the RCS'will decrease. rhe number of running charging pumps will also affect the

(- ) leakage from the RCS. The pressurizer level will decrease with its level control system responding to restore it by starting additional charging pumps and shutting the letdown flow control valve. When the leak rate exceeds the CVCS makeup ability, pressurizer level will continuously drop. A manual reactor trip may be performed if leakage is in excess of makeup. VCT level will decrease at a rate to reflect the running of additional charging pumps and the reduction in letdown flow. Additional makeup will be required to maintain the VCT level.

Pressurizer pressure will decrease along with its level, causing its control system to respond in an attempt to maintain it at its controlled setpoint. Tech Specs maybe impacted.

Leakage from the charging line will enter the west piping penetration room. The leakage will result in airborne activity levels increasing on the charging pump and degasifier area an6 Unit 2 stack gas process monitors. Liquid mass from the leak will be collected by the aerated waste system.

The following alarms will actuate when their setpoints are exceeded:

VCT Level Lo Process Mon Rad Hi Hi/ Fail.

Rev: 0 Date: 1/31/89

1 Control board indications are:

Decreasing VCT Level Increased Charging Flow Decreased Letdown Flow l Increased Auxiliary Building ventilation Radiation, Malfunction removal will restore the integrity of the charging line.

REFERENCES:

26017, 26021, 26024, 26028, 26029, 37006 SH. 2, 4, 28018.

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nevt 0 j Date: 1/31/89 i I

MALFUNCTION CAUSE AND EFFECTS f]

NJ l

Plant: MP2 Malfunction #: CV15 Malfunction

Title:

VCT Reject Failure.

Malfunction Type: Generic, Non-Variable.

Malfunction cause: 2-CH-500 fails in VCT position.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will fail the letdown to Radwaste System diversion' valve, (2-CH-500), in its divert to volume control tank-position. If volume control tank level exceeds 88%, as sensed by LC-227, automatic diversion of letdown flow will not shift to the radwaste system.

Operation of 2-CH-500 assoc- lated handswitch (HS2500) will not allow O positioni progress,ngitofwill 2-CH-500.

stop.

If automatic diversion to RWS is in If letdown is allowed to continue filling the VCT, its pressure will also increase leading.to relief valve.2-CH-ll5 actuation.

The following alarms will actuate when their setpoints are exceeded:

VCT Level Hi ,

VCT Press Hi/Lo. l 1

control board indications are:

Increasing VCT Level Increasing VCT Pressure.

Malfunction removal will restore 2-CH-500 operation to normal. j

REFERENCES:

26017, 26020, 28500 SH. 227, 37009 SH. 28, OP 2304A.

1 1

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, Rev: 0 Date: 1/31/89 i

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l g-- MALFUNCTION CAUSE AND EFFECTS 3

Plant: MP2 Malfunction #: cvl6-Malfunction

Title:

RWST to Charging Pump Suction Valve Leakage.

4 Malfunction Type: Variable. 100% equals 50 gpm with normal operating j DP.

.I Malfunction Cause: . Leakage Past12-CH-192. ')

Plant Status: Normal full power. 4 Malfunction Effects:

This malfunction will provide a source of borated water to the charging pump suction'line. In order for the leakage to exist, i 2-CH-504 must be open and the head supplied by the RWST to the charging pump suction must be greater thanfthat supplied by the. volume-control tank. Supplying makeup water and/or boric acid through

(~)'T

( 2-CH-196 will also affect the consequences of this malfunction. The actual valve position of 2-CH-192 or control of its operator will not 3 be affected by this malfunction. H The boric acid concentration of the RWST leaking to the charging pump suction will cause CVCS and RCS boron concentration to increase. This will cause negative reactivity to be inserted, causing reactor power to decrease.

The leakage will also cause an increase in the effective letdown flow rate which will result in VCT level rising.

The leakage will stop if.2-CH-504 is shut.

Ma). function removal will stop the leakage through 2-CH-192.

REFERENCES:

26017. l l

i I

l f Rev: 0

\- Date: 1/31/89 )

I

__=____-_________ __ _ _ .i

[) MALFUNCTION CAUSE AND EFFECTS s-Plant: MP2 Malfunction #: CV i ?.". P19A CV17B P19B Malfunction

Title:

Boric Acid Pump Failure.

Malfunction Type: Generic.

Malfunction cause: Broken Coupling.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will prevent boric acid pump A from developing any pump discharge pressure if an automatic or manual start attempt is made or is in progress. Its gg associated pump discharg: pressure indication will decrease

(_j to minimum, along with the-flow developed. Contractor.

status indication on CO2 will not be affected._ Reactivity control Tech specs may be impacted.

If a blended makeup is in progress, boration of the associated system will stop and only PMW will be passed to that system.

Malf B - The effects of this malfunction will~be similar to Malf A with boric acid pump B being the affected component.

Malfunction removal will restore operability of the selected failed boric acid pump.

REFERENCES:

26017, 28500 SH. 208, 32009 SH. 4.

A

'\j Rev: 0 Date: 1/31/89

i MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CVl8 Malfunction

Title:

Isolable letdown line rupture inside CTMT between q the RHX and 2-CH-516.

i Malfunction Type: Variable, 0-100%, 100% equals 200 gpm.at 2250 psid.  ;

Malfunction Cause: Rupture of the letdown line between 2-CH-516 and the RHX.

Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in'a partial failure of the letdown line inside containment. The leak is' isolable, located between isolation valve 2-CH-516 and the regenerative heat exchanger.  ;

i At 100% severity, the leak causes'a sharp reduction in letdown; flow to  ;

less than 20 gpm. This decrease is.due to both the decrease'in 1

(~T letdown line pressure and the letdown flow control valve throttling i

\ms/ closed in response to the pzr level decrease.

Pzr level will decrease rapidly causing the first, then second backup charging pumps to start. At maximum charging and minimum letdown, pzr level will continue to decrease approximately 1% per minute. VCT level will decrease approximately 3% per minute. The PPC program for RCS leak rate will indicate RCS leakage approaching 200 gpm as data.is accumulated. Securing charging and isolating letdown by closing either 2-CH-515 or 516 will stop the leakage and pzr' level will stop decreasing with the exception of RCP bleed off (4 gpm).

Due to the large imbalance between charging-and letdown flowrates across the regenerative heat exchanger, both temperatures will rapidly drop to be slightly above VCT temperature.

Pzr pressure will decrease slowly to 2200 psia. The backup heaters will energize, raising pressure slowly to 2225 psia where.they deenergize. Allowed to continue without operation action, pzr pressure will cycle between 2200 and 2225 psia until pzr level decreases to 20% and all heaters deenergize.

O Rev:

Date:

0 3/1/89

1 l

\s containment conditions slowly change to indicate a small RCS leak.

CTMT normal sump level, CTMT temperatures, dewpoint, narrow range pressure, CTMT particulate and gaseous radmonitors all increase to indicate a release of high energy fluid, with activity, inside CTMT.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

" Letdown Flow Lo" "Pzr Pressure Selected Channel Deviation Hi/Lo" "Pzr Ch 'X' Level Hi/Lo" "Pzr Ch 'Y' Level Hi/Lo" Due to the leak being. isolable, Tech. Spec. . leakage limits will not be exceeded, (after isolation), however, the leak is inaccessible at )

power and an orderly shutdown will be required.

~

{

operator action to secure letdown by shutting 2-CH-515 or 516 will stop the leak.

I Removal of CV18 will stop the leakage and pzr level and pressure  !

control systems will respond to restore normal pzr level and pressure.

Introduction of Cvl8 at lesser severities will cause similar effects of proportionally smaller magnitudes with the following exceptions:

Pzr level will be maintained with two backup charging. pumps, one O' -

backup charging pump, or letdown flow decrease as severity is decreased.

1 Pzr pressure will be maintained by the proportional heaters at low I severities.

REFERENCES:

P&ID 26017, CEN 128 Case E2.

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MALFUNCTION CAUSE AND ErrECTS

]

Plant: MP2 Malfunction #: CVl9 l

Malfunction

Title:

Dilution Batch Counter.

Malfunction Type: Generic /Non-Variable.

i Malfunction Cause: Batch Counter contact Failure.

I Plant Status: Normal full power.

'I Malfunction Effects.

This malfunction will cause 2-CH-210X (primary makeup flow control valve) to remain open when its associated controller is in automatic, PMW batch switch has counted down to zero, and the " dilute" mode of l CVCS makeup is selected. " Auto", " man", and " borate" makeup mode controls will be unaffected and will allow 2-CH-210X to operate

. properly. 2-CH-210X will also operate properly if its associated flow controller is placed in manual. Dilution of the system being filled will continue if a makeup operation was in progress. W The following alarm will actuate when its setpoint is. exceeded:

PRI Makeup Flow Hi/Lo.

Control board indications are:

PMW Flow Indication on FRC-210X PMW Flow Indication on FOI-210X.

Malfunction removal will restore the PMW batch' counter operation to normal.

REFERENCES:

26017, 28500 SH. 207A, B, C, 32009 SH. A, C, 21, 22.

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() Rev:

Date:

0 1/31/89 ,

i

l MALFUNCTION CAUSE AND EFFECTS

{}

Plant: MP2 Malfunction #: Cv20 Malfunction

Title:

Charging Line Leak Inside containment.

Malfunction Type: Variable. 100% equals 100 gpm leak rate at'2250 psid.

Malfunction Cause: Pipe rupture on Loop 1A charging line upstream of .

e-CH-519.

Plant Status: Normal full power.

Malfunction Effects:  !

This malfunction results in the leakage of reactor coolant into the I containment environment. As the severity level is increased the effective charging flow.into the RCS will decrease. Leakage also

\ affected by # of running charging pumps. Pressurizer level will (ls- decrease with the level control system responding to restore it by the starting of additional charging pumps and shutting of'the letdown flow control valve. When the leak rate exceeds the CVCS makeup ability, i pressurizer level will continuously drop. If leakage exceeds makeup j capability a manual reactor trip may be directed. The increased i charging flow will result in a decreasing VCT level requiring .

additional makeup to maintain it. Pressurizer pressure will decrease  !

along with its level, causing its control syster to respond by l energizing additional heaters to maintain it.

The containment humidity, temperature, and pressure will increase to reflect the RCS leakage. Radiation levels as depicted by containment atmospheric gaseous, particulate and area monitors will increase in i relation to the CVCS activity levels. The containment sump level will  !

increase to reflect the leakage accumulated. Tech Specs will be j impacted.

The following alarms will actuate if their setpoints are exceeded: l VCT Level Low l Pressurizer CH X/Y Press Hi/Lo Pressurizer CH X/Y Level Hi/Lo  !

i Containment Air Particulate Rad Hi Containment Air Gaseous Rad Hi Containment Norm Sump Level Hi/Lo.

r i Rev: 0 Date: 1/31/89 .

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

i

/^ -

control board indications are:

Decreasing VCT Level Decreasing Pressurizer Pressure and Level  ;

Increasing Temperature, Pressure, Humidity, and Radiation Levels within the containment  !

Increasing C6ntainment Sump Level. j r

Isolation of loop 1A charging line will not stop the leakage if the charging flow is maintained through the regenerative heat exchanger.

The charging header isolation valve 2-CH-429 may be shut, (stopping the leak), and charging directed to the HPSI header to maintain the l pressurizer level. )

Malfunction removal will restore the integrity of loop 1A charging 1 line.

REFERENCES:

26017, 26024, 26028, 28500 SH. 69, 37006 SH. 1, 2. i

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MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CV21 Malfunction

Title:

Charging Line Leak Upstream of 2-CH-429.

Malfunction Type: Variable. 100% equals 100 gpm leak rate at 2250 psid.

Malfunction Cause: Pipe rupture upstream of 2-CH-429.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will result in leakage from the charging line of reactor coolant into the west piping penetration room of the auxiliary l

building. As the severity level is increased effecting charging flow into the RCS will decrease. Leakage also dependent on # cf ritnning i charging pumps. The pressurizer level will decrease with its level control system responding to restore it by starting of additional charging pumps and shutting of the letdown flow control valve. When the leak rate exceeds the CVCS makeup ability pressurizer. level will continuously drop. If leakage exceeds makeup capability, a manual reactor trip maybe directed. VCT level will decrease at a rate to reflect the running of additional charging pumps and the reduction in letdewn flow. Additional makeup will be required to maintain the VCT level. Pressurizer pressure will decrease along with its level causing its control system to respond in an attempt to maintain it at its controlled setpoint. Tech Specs will be impacted.

Leakage from the charging line will enter the west piping penetration room. The leakage will result in airborne activity levels increasing on the charging pump and degasifier area and Unit 2 stack gas process monitors. Liquid mass from the leak will be collected by the aerated waste system.

The following alarms will actuate when their setpoints are exceeded:

VCT Level Lo i Process Mon Rad Hi/Hi Fail l

Rev: 0 Date: 1/31/89

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\ Control board indications are:

l Decreasing VCT Level.

Increasing Charging Flow 3' Decreased Letdown Flow Increased Auxiliary Building Ventilation Radiation Leakage can be stopped by securing all running charging pumps and j closing VCT outlet valve 2-CH-501.  ;

1 Malfunction removal will restore the integrity of the charging  !

line. j

REFERENCES:

26017, 26081, 26024, 26028,'26029, 37006 SH. 2 ,- 3 , 28018.

1

() Rev:

Date:

0 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CWOlA - P6A CWO1B - P6B CWOlC - P6C CWOlD - P6D Malfunction

Title:

Cire Water Pump Trip Malfunction Type: Generic Malfunction cause: 51X Relay Failure Plant Status: Normal Full Power Malfunction Effects:

Malf A - Circulating water pump A will trip and circulating water flow through condenser waterbox A will stop.

Current and discharge pressure indication for the pump 9 will decrease. The effects on condenser vacuum will be dependent on turbine load and circulation water inlet tempera:ure. If vacuum decreases the generator output will also decrease. A turbine / reactor trip will occur if condenser vacuum drops below 22.5" hg. The plant trip may be averted by load reduction or circulating water flow re-establishment through its crossconnect.

If circulating water inlet temperature is low enough the unit output may not be affected by the loss of a pump. Tech specs will not be affected.

The following alarm will actuate:

Cire ' rater pump A overload / trip.

The amber light on CW pump A handswitch will be illuminated when the handswitch is in its normal after close position. The pump will not be able to be restarted.

Malf B - Effects similar to Malf A except CW pump B is the major affected component.

Malf C - Effects similar to Malf A except CW pump C is the major affected component.

Rev: 0 h Date: 1/31/89 I

4

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l Malf D - Effects similar to Mal'f A except'CW pump D is the major.

affected' component.

Malfunction removal will restore the selected failed CW pump over current relay to normal.

REFERENCES:

26008, 32013 SH. 1, 2, 3, 4 1

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,_ MALFUNCTION CAUSE AND EFFECTS b

Plant: MP2 Malfunction #: CWO2A - Screen A CWO2B - Screen B CWO2C - Screen C CWO2D- Screen D Malfunction

Title:

Traveling Screen Fouling l

Malfunction Type: Variable / Generic, 100% equals max DP of 50 inches water.

Malfunction Cause: Trash Buildup.

Plant Status: Normal Full Power Malfunction Effects:

Malf A - Screen A traveling screen differential level will increase. When the level reaches 6" the screen wash gg pump selected for auto operation will start and all s j screens will shift to slow speed. When the level reaches 9" the standby screen wash pump will start and all screens shift to fast speed. If the level i increases to 30" cire pump A will trip resulting in a j loss of flow to the A condenser waterbox. The differential level developed across the screen will be dependent cn1 circulating pump flow rates.

The following alarms may actuate:

Traveling Screen DP Hi Cire Water Pump A Overload Trip.

Malf B through D -

Similar to Malf A with screens B, C, and D being individually affected.

Malfunction removal will permit the selected failed l screen differential level to be restored to normal as a function of the operability of the screen wash system.

REFERENCES:

26008, 32013 SH. 1, 8, 12

./~N Rev: 0

(_) Date: 1/31/89

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MALFUNCTION CAUSE AND EFFECTS l Plant: MP2 Malfunction #: CWO3A - P8A  !

CWO3B - P8B j

Malfunction

Title:

Screen Wash Pump Auto Start Failure.  ;

i Malfunction Type: Generic Malfunction Cause: Auto Start Failure on High DP.

Plant Status: Normal Full Power Malfunction Effects:

Malf A - This malfunction will prohibit automatic starting of  ;

screen wash pump "A" on high screen differential level )

(DL). It will affect its auto and standby modes as i selected through the use of remote functions. Screen differential level will increase at approximately'1"/10 minutes with normal flow through the screen. At t 6" r3 differential level the screen wash pump (s) selected to

(_,) auto would normally start to reduce the scrrien DP.

Failure of the "A" pump if selected to auto will allow the D.L. to increase. At'approximately 9" D.L. the standby pump should start. Failure of this. pump will allow continued trash buildup on the screens. Circ water pumps will trip when its respective screen reaches a 30" D.L.

The following alarms may actuate:

Traveling Screen DP Hi Circ Water Pump A Overload Trip.

Malf B - Effects similar to Malf A except screen wash pump "B" is the major affected component.

Malfunction removal will allow automatic startup of the selected failed screen wash pump.

REFERENCES:

26008, 32013 SH. 8, 9 h

L/

Rev:

Date:

0 1/31/89 1

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MALFUNCTION CAUSE AND EFFECTS Plant: MP2- Malfunction #: CWO4A - WB-A CWO4B - WB-B CWO4C - WB-C CWO4D - WB-D Malfunction

Title:

Main Condenser' Tube Leak (Minor)

Malfunction Type: Generic / Variable, 100% equals 1 gpm leak at normal vacuum in condenser and the waterbox is full of water. )

Malfunction cause: Tube leak.

Plant Status: Normal Full Power Malfunction Effects:

Malf A - This malfunction will cause leakage from the circulating water system into condenser A.

Conductivity levels, as displayed by CR-5448, on condenser "A" hotwell will increase. Condenser "C" O . conductivity level will also increase on a delayed basis due to mixing within the hotwell. Hotwell level makeup requirements will be reduced due to the addition of mass from the circulating water system.  !

1 The following alarms may actuate:

A Hotwell Cond Hi.

Malf B - Effects similar to Malf A except the "B" condenser is the major affected component.  ;

i Malf C - Effects similar to Malf A except the "C" condenser is j the major affected component.

i Malf D - Effects similar to Malf A except the "D" condenser is the major affected component.  ;

Malfunction removal will stop the tube leak on the i

selected failed condenser.

i

REFERENCES:

26008, 26005, 26025 i

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,Q Rev: 0  ;

(,) Date: 1/31/89 i

-~ MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: CWO6A - Condenser A CWO6B - Condenser B CWO6C - Condenser C CWO6D'- Condenser D Malfunction

Title:

Main Condenser Tube Sheet Fouling.

Malfunction Type: Generic / Variable, 100% equals 50% blockage ~of-flow.

Malfunction cause: Trash Buildup.

Plant Status: Normal Full Power Malfunction Effects:

Malf A - This malfunction will reduce the effective circulating water flow through main condenser A. Circulating pump running current will increase as will the condenser C outlet temperature. Due to the reduction in condenser heat transfer ability, the condenser vacuum will decrease. This effect will also'be dependent on circulating water inlet temperature and the turbine load. The plant electrical load will decrease if the condenser vacuum decreases. A turbine / reactor trip will occur if vacuum decreases to :22.5" HG.

The following alarms may actuate:

Hi Condenser Delta T Hi Condenser Disch T.

Malf B - Effects similar to Malf A except condenser B is the major affected component.

Malf C - Effects similar to Malf A except condenser C is the major affected component.

l

/ Rev: 0 Date: 1/31/89

Malf D - Effects similar'to Malf A except condenser D is the major affected component.

Malfunction removal will restore the condenser tube sheet to normal.

REFERENCES :- 26008.

O Rev: 0 Date:- 1/31/89

MALFUNCTION CAUSE'AND EFFECTS Plant: MP2 Malfunction #: CWO7A - P6A C407B - P6B.

CWO7C - P6C CWO7D - P6D Malfunction

Title:

Circ Water Pump Failure to Start.

Malfunction Type: Generic Malfunction Cause: Pump Discharge valve Contact Failure. ,

Plant Status: Normal Full Power l

Malfunction Effects:

Malf A - This malfunction will prevent starting of circulating water pump "A" due to a failed opea contact (33/A HV-6538) in its breaker closing circuit. Pump

~

discharge valve position indication and operation will operate normally. If this malfunction is inserted-((_h

/ while the pump is running the pump will be. tripped off without any trip annunciators. }

Malf B - Effects similar to Malf A except CW pump "B" is the j major affected component. l l

Malf C - Effects similar to Malf A except CW pump "C" is the J major affected component.

Malf D - Effects similar to Malf A except CW pump "D" is the major affected component. I 1

Malfunction removal will permit normal operation of'the selected failed circulating water pump discharge ,

contact. j 1

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REFERENCES:

32013 SH. 1, 12 I

)

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' ) Rev: 0

'-' Date: 1/31/89 l

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MALFUNCTION CAUSE AND EFFECTS _.

Plant: MP2 Malfunction #: CWO8A - WB-A CWO8B - WB-B CWO8C - WB-C CWO8D - WB-D Malfunction

Title:

Main Condenser Tube Rupture (Major).

Malfunction Type: Generic / Variable, 100% equals 200 gpm leak rate with normal vacuum in condenser and the water box filled.

Malfunction Cause: Tube Rupture.

Plant Status: Normal Full Power Malfunction Effects:

Malf A - This malfunction will cause leakage from the circulating water system into condenser A.

Conductivity levels as displayed by CR-5448 on f.

r condenser "A" hotwell will increase. Condenser B, C,

( and D conductivity levels will also increase on a delayed basis due to mixing within the hotwell.

Hotwell level makeup requirements will be reduced with the overflow being pumped back to the condensate surge tank.

The following alcrr'.2 may actuate:

A Kotr911 Cond Hi High Effluent conductivity.

Malf B - Effects similar to Malf A except the leakage is into condenser B.

Malf C - Effects similar to Malf A except the leakage is into condenser C.

O)

(_ Rev:

Date:

0 1/31/89

i Malf D'- Effects similar to Malf A except.the leakage is into condenser D.

Malfunction removal will stop the-tube leakage on the selected failed condenser.

REFERENCES:

26008, 26005, 26025 ,

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O Rev: 0

-Date: 1/31/89

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( MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: ED01 Malfunction

Title:

Loss.of NSST j 1

l Malfunction Type: Generic l ,

1 Malfunction cause: Faulty Differential Relay (87T) ]

Plant Status: Normal Full Power Malfunction Effects:

This malfunction will f.nitiate a NSST channel I lockout. It will l cause a turbine generator and reactor trip. The 6.9KV_ feeder breakers to bus 25A and 25B from the NSST will be tripped open.

The 4.16KV feeder breakers to bus 24A and 24B will be tripped open and locked out. Fast transfer of 6.9KV and 4.16KV power to j

/~ buses 25A, 25B, 24C, and 24D from the RSST will occur. The j

(>] generator field breaker will be tripped and locked out. Lockouts will be resetable through use of remote function after malfunction removal.

Main generator output and normal station service transformer _ load "

indications will decrease to zero. The reserve station service transformer load will increase to reflect the inplant load.

l The following alarms will actuate:

1 NSST Lockout Channel I NSST Undervoltage  !

6.9KV Bus 25A NSS Supply Bkr Trip 6.9KV Bus 25B NSS Supply BKR Trip i Reactor / Gen Prot Turbine Trip )

Generator Pri Pilot Wire Monitor Loss 1

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Control board indications that change are:

NSS7 'foltage (6.9KV, 4KV)

NSST Watts (6.9KV, 4KV)'

NSST Amps (6.9KV, 4KV)

RSST Voltage (6.9KV, 4KV)

RSST Watts (6.9KV, 4KV)

RSST Amps (6.9KV, 4KV)l Malfunction removal'will permit resetting of generator protective lockout relays. (86T)

REFERENCE:

30041 SH. 3, 4, 30042 SH. 1, 30043 SH. 1, 32001 SH. 3, 32005 SH. 17, 22, 23, 32006 SH. 4A, 8 O

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Date:

0 1/31/89-

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MALFUNCTION CAUSE AND EFFECTS

(

i Plant: MP2 Malfunction #: ED02 Malfunction

Title:

Loss of RSST Malfunction Type: Generic

)

Malfunction cause: Differential Relay Failure (87T). ]

Plant Status: Hot Standby Malfunction Effects:

This malfunction will cause a channel I reserve station service transformer lockout. The lockout will cause RSST-audio-tone frequency-shift primary and secondary transfer trips to be developed. The 6.9 KV RSST feeder breakers to buses 25A and 25B J (22S2-25A-2 and 22S2-25B-2) will be tripped open and locked out j on transformer undervoltage. 4.16 KV main feeder breaker i i

( (22S3-2-2 to buses 24C and 24D will be tripped open and locked out. The RSST 345 KV motor operated disconnect (15G-22S1-4) will be. automatically opened.and locked out after the RSST feeder breakers are open.

The 6.9 KV buses 25A and 25B, along with the.ir respective loads, will be deenergized.

I The resultant undervoltage on bus 24C and bus 24D will trip their supply breakers (22S3-24C-2 and 22S3-24D-2). Load shed signals will trip nonessential loads and buses (24C to 24A, 24D to 248,.

24E to 24F tie breakers and 24C and 24D main feeder breakers i trip).

The diesel generators will start and their output breakers will shut to reenergize buses 24C, 24D, and 480V loads that were not deenergized on load shed. The load sequencer will then restart essential equipment through ESAS modules. Electrical Tech Specs maybe impacted.

The following alarms will actuate:

RSST Lockout Channel I RSST Primary Audio Tone TT Trip Oper RSST Backup Audio Tone TT Trip Oper Rev: 0 f~/)

N- Date: 1/31/89 t

RSST Undervoltage RSST Trouble 6.9 KV Bus 25A/25B RSS Supply Bkr Trip

-4KV Bus 24G to Bus 24C/D Bkr Trip 4KV Bus 24C from Bus 24G Bkr Trip i 4KV Bus 24D from Bus 24G Bkr Trip 1 4KV Bus C/A Tie Bkr Trip 4KV Bus C/B Tie Bkr Trip ESAS UV (1A-1D, 2A-2D) Trip (24C-240) )

Diesel Gen'(120,-13U) Auto Start .j Malfunction removal will permit resetting of RSST: lockout #

trip device as an observed and used PCM remote function.

1

REFERENCES:

30041 SH. 5, 32005 SH. 30, 31, 32, 33, 32001 SH. 12 ~, t 32002 SH. 11, 12, 13, 14, 21, 22, 32005 SH. 23, )

30044 SH. 4, 10,.16, 17, 30001. l I

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MALFUNCTION CAUSE AND EFFECTS

{

Malfunction (: ED03A 310 Line ,

Plant: MP2 ED03B 371~Line ED03C 383 Line ED03D 348 Line Malfunction

Title:

Loss of 345 KV Lines Malfunction Type: Generic Malfunction cause: Individual Line Fault Plant Status: Normal Full Power Malfunction Effects:

Malf A - Insertion of this malfunction will result in the immediate opening of 345KV breakers 15G-7T-2 and 15G-8T-2 and the loss of the 310 transmission line.

O Deenergization of a single line will have no other visible effects of the operation of the main generator.

Malf B - Effects similar to Malf A except that 345KV breakers 15G-4T-2 and 15G-5T-2 will open resulting in the loss of the 371 line.

Malf C -

Effects similar to Malf A except that 345KV. breakers 15G-1T-2 and 15G-2T-2 will open resulting in the loss ,

of the 383 line and Unit 1 reserve station service transformer 15G-21S (alternate supply to 4.16KV Bus l

24E). J Malf D - Effects similar to Malf A except that 345KV breakers 15G-14T-2 and 15G-15T-2 will open resulting in the loss of the 348 line.

4 Loss of all four transmissionThe lines willloss large result of in a l total loss of offsite power.  ;

electrical load on the main generator will Thisresult in will l the backup of heat in the primary system.  :

result in an increase in primary system temperatures  !

and pressures with a likely trip on high RCS pressure.

Generator coastdown will initiate to maintain power to -

the reactor coolant pumps. The 4.16KV buses will be momentarily deenergized until power is restored by the f-s diesel generators.

I Rev: 0 Date: 1/31/89 l

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j Malfunction removal will allow reclosure of breakers on O- the selected failed line'through the use of a remote function common.to all breakers except.15G-8T-2 and -l t

15G-9T-2. Electrical Tech specs may be impacted.

REFERENCES:

Convex OI #6913 and #6401, Reference Plant Data Book, Event #19.

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Rev: 0 Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS

' Plant: MP2 Malfunction #: ED04A. 25A Bus ED04B 25B Bus Malfunction

Title:

Loss of'6.9KV Bus Malfunction Type: Generic Malfunction Cause: Switchgear Ground Fault Causing an Overcurrent Trip Plant Status: Normal Full Power Malfunction Effects: ,

Malf A - The Bus overcurrent will result'in' tripping main feeder breaker 252-25A-2 from the NSST and locking out.the:

main feeder breaker 22S2-25A-2 from the'RSST. Bus voltage' indication will decrease to minimum. NSST wattage and current indication will decrease to reflect O the deenergization and loss of loads,on. bus 25A.

The following major. loads will loose power:

Reactor-Coolant Pump P40A Reactor Coolant Pump P40C Condensate Pump P2A Condensate Pump P2B The following alarm will actuate:

6.9KV Bus 25A NSS Supply Bkr Trip.

Reenergization of'6.9KV bus 25A will not be permitted

'through either of its NSST or RSST supply breakers due to lockouts.

Malfunction removal will reset the breakers overcurrent device. ' Breaker closure willEbe permitted after its lockout is reset through breaker control switch-operation.

Malfunction insertion with a RSST supply breaker shut will cause similar results, Rev: 0 f-sg. Date: 1/31/89

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Malf B -- Effects similar to Malf A 6.9KV bus 25B being the.

( affected component. Major: loads supplied from bus 25B are:

Reactor Coolant Pump P40B Reactor Coolant Pump P40D Condensate Pump'P2C.

Reference:

30041 SH. 1.through.7, 30003, 32001 SH. 11through'4, Reference Plant Data Book,' Event #35.

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- MALFUNCTION CAUSE AND EFFECTS V

Plant: MP2 Malfunction-#: ED05A- 24A Bus ED05B 24B Bus ED05C 24C Bus ED05D 24D Bus ED05E 24E Bus  !

ED05F 24F Bus Malfunction

Title:

Loss of 4.16KV Bus I Malfunction Type: Generic 1 Malfunction Cause: Switchgear Ground Fault Causing an Overcurrent Trip Plant Status: Normal Full Power Malfunction Effects:  ;

I

) Malf A - This malfunction will result'in an overcurrent trip of 4160V main feeder breaker 253-24A-2. The resulting lockout of this breaker will also trip and lockout tie i breaker 24C-lT-2. Bus 24A and its associated loads will be deenergized. Bus 24C will be deenergized, loads shed and then reenergized by diesel 12U. Loads will be picked up through load sequencer operation on j bus 24C. Fast transfer of 24C power from the RSST source will be blocked when a plant trip occurs. i Electrical Dist. Tech Specs may be impacted.

Bus 24A voltage indication will decrease to minimum.

Current and voltage indication will decrease to reflect the load lost on the NSST.  ;

The following major loads will lose power:

! Heater Drains Pump A l Main Circ Pump A Main Circ Pump C 480V Transformer to Bus 22A (Bus 22A lost) 480V Transformer to Bus 22C (Bus 22C lost)

Bus Tie to 4160V Bus 24C.

, Rev: 0

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The following alarms will actuate:

I 4KV Bus 24A NSS Supply Bkr Trip i 4KV Bus 24C/A Tie Bkr Trip l 480V Load Center 22A/B/C/D Bus volts Lo. l Reenergization of 4160V bus 24A will not be-permitted through either NSST supply or 24C tie breaker due to i

. lockouts.

Malfunction removal will reset'the breakers overcurrent device. Breakers which were tripped or had an associated lockout activated may be shut after their lockouts are reset through breaker control' switch operation.

Malf B - Effects similar to Malfunction A with 4160V bus 24B  ;

being the major component affected. Major loads supplied from bus 24B are:

Heater Drains Pump B I Main Circ Pump B I Main Circ Pump-D j 480 Volt Transformer 228 (Bus 22B lost) j 480 Volt Transformer 22D (Bus 22D lost) )

-Bus Tie to 4160V Bus 24D.

Electrical Dist. Tech Specs may be impacted.

Malf C - Bus 24C overcurrent will cause bus tie breaker 24C-1T-2 to trip, thus'deenergizing bus 24C. Lockouts will be imposed on breakers 2S3-24A-2, diesel 120 will start <

and its output breaker will.make a close attempt after load shed of the bus is completed. Its output breaker will then trip, causing the diesel engine to also shutdown. Electrical Tech Specs will be impacted due to the loss of the vital bus. .

1 l

The following alarms will be received:

4KV Bus 24C/A Tie Bkr Trip ,

i Diesel Gen 12U Auto Start Diesel Gen 12U Bkr Trip.

If this malfunction is inserted while bus 24C is being supplied by the RSST breaker 22S3-24C-2 will be tripped and locked out causing the loss of loads on bus 24C and 24A. Major loads supplied from bus 24C are.  ;

I Service Water Pump A AFW Pump A RBCCW Pump A O Rev:

Date:

0 1/31/89 1

I i

o f

( HPSI' Pump A LPSI Pump A Containment Spray Pump A Bus Tie to 4160V Bus 24A.

Bus Tie to 4160V Bus 24E 480 Volt Transformer 22E.

Malf D - Effects similar to malfunction C with 4160V bus 24D .

being the major component affected. Major loads )

supplied from bus 24D are:  !

Service Water Pump C AFW Pump B RBCCW Pump C HPSI Pump C .

LPSI Pump B j Containment Spray Pump B  ;

Bus Tie to 4160V Bus 24E (normally open) {

I Bus Tie to 4160V Bus 24B 480 Volt Transformer 22F. j Electrical Dist. Tech Specs will be impacted due to the loss of a vital bus.

1 Malf E - Bus 24E overcurrent will cause tie breaker 24C-2T-2 to trip and lockout. RSST 15G-21S supply through breaker f'/

s_

s 21S3-24E-2 will also be locked out. Major loads which will be lost when 24E is deenergized are:

1 Service Water Pump B RBCCW Pump B l HPSI Pump B.  !

Tech specs may be impacted, depending on whether any of these 3 pumps are being taken credit for operability.

Malf F - Bus 24F overcurrent will trip and lockout feeder breaker 21S3-2-2. Bus 24F will be reenergized upon malfunction removal.

REFERENCES:

30004, 30005, 30006, 30043 SH. 1-6, 30044 SH. 1-20, 32002 SH. 1-23.

l I

t i Rev: 0' Date: 1/31/89 i

MALFUNCTION CAUSE AND EFFECTS r3

't/

Plant: MP2 Malfunction #: ED06A 22A Bus ED06B 22B Bus ED06C 22C Bus ED06D 22D Bus ED06E 22E Bus ED06F 22F Bus Malfunction

Title:

Loss of 480KV Bus Malfunction Type: Generic Malfunction Cause: Switchgear Ground Fault Causing an Overcurrent Trip.

Plant Status: Normal Full Power Malfunction Effects:

/~ Malf A - 480V supply breaker 24Al-lx3-2 will trip open. Voltage

(,]/ and current indications for bus 22A will decrease to zero. 4160V bus 24A load will decrease to reflect the loss of 480V transformer 22A.

The following alarms will actuate:

480V Load Center Bus 22A Supply Bkr Trip 480V Load Center 22A/B/C/D Bus Volts Lo.

Power will be lost to the following major loads:

Turbine building battery charger DC4 TBCCW Pump A Pressurizer Backup Heater Group #1 MCC22-1A McC22-2A MCC22-3A.

The affected plant backup systems will respond appropriately with components actuating as necessary.

A closure attempt of 22A normal or tie feeder breaker will result in their immediate tripping open.

Malfunction removal will allow restoration power to bus 22A and associated loads.

7s

( ) Rev:

Date:

0 1/31/89

Malf B - Effects similar to Malfunction A except 480V bus 22B is the affected component. Major loads lost are.: q Main Transformer Cooling Equip Supply #2 TBCCW Pump B Pressurizer Heater Backup Group #2 Station Air Compressor F2 Condensate Polishing MCC 1A1 MCC22-1B MCC22-2B. j Malf C - Effects similar to Malfunction A except 480V bus 22C is the affected component. Major loads lost are:

Pressurizer Heater Backup Group #3 Main Transformer Cooling Equip Supply #1 MCC22-lCA  ;

MCC22-lCB McC22-2C MCC22-2C MCC22-3C '

IAC-C  ;

Malf D - Effects similar to Malfunction A except 480V 22D is the l affected component. Major loads lost are:

TBCCW Pump C

\~ Pressurizer Heater Backup Group #4 Condensate Polishing MCClB1 MCC22-lDa McC22-lDB l McC22-2D. j Malf E - Effects similar to Malfunction A except 480V bus 22E is ,

J the affected component. Tech specs will be impacted.

Major loads lost are:

Pressurizer Heater Prop GRP P-1 MAG-Jack M-G Set No. 1 Battery Charger DCl CAR Unit F14A CAR Unit F14C Battery Charger DC3 Hydrogen Recombiner H29A MCC22-lE MCC22-2E Malf F - Effects similar to Malfunction A except 480V bus 22F is the affected component. Tech Specs will be impacted.

Major loads lost are:

() Rev:

Date:

0 1/31/89 4


____________s

Pressurizer Heater Prop GRP P-2 Mag-Jack M-G Set No. 2 Battery Charger DC2 CAR Unit F148 CAR-Unit'F14D.

. Hydrogen Recombiner H29B McC22-1F MCC22-2F.

REFERENCES:

30007, 300008 O

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1 Rev: 0 .

Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction 4: ED07 A. MCC22-1A E. MCC22-2B I. McC22-3C M. McC22-1E B. MCC22-2A F. McC22-lCA J. MCC22-lDA N. MCC22-2E C. McC22-3A G. MCC22-lCB K. MCC22-lDB O. MCC22-1F D. McC22-1B H. MCC22-2C L. MCC22-2D P. MCC22-2f Malfunction

Title:

Loss of MCC Malfunction Type: Genetic Malfunction Cause: Faulty overcurrent device on the individual supply to the MCC.

Plant Status: Normal Full Power Malfunction Effects:

Malf A - The tripping of McC22-1A supply breaker will result in deenergization of the MCC and all of its associated loads.

The affected systems will respond appropriately for the loss of these components with any backup components responding according to their individual logic.

The following alarm will actuate:

480V MCC Feeder 22-1A/2A/3A Bkr Trip.

Malf B through Malf P - Effects respond simi.'arly to Malf A with major MCC's affected as listed above. Tech specs will be impacted for Malfunction M, N, O and P, since these are vital MCC's.

Malfunction removal will restore power to the selected failed MCC.

REf2dENCES: OP 2388, 30008.

() Rev:

Date:

0 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: ED08A 25A Bus ED08B 25B Bus Malfunction

Title:

Failure of 6.9KV Bus Auto Transfer.

1 Malfunction Type: Generic I Malfunction Cause: Failure of associated bus fast transfer interlocl contact. i Plant Status: Plant Trip from Full Power  ;

Malfunction Effects:

Malf A - This malfunction will prevent closing of contact 83xl/15G-225 in the closing scheme of the RSST supply breaker to bus 25A (22S2-25A-2). When the NSST supply breaker to bus 25A (2S2-25A-2) opens, the RSST supply

(~'}

\_- breaker to that bus will not automatically close, which will result in the deenergization of the bus and associated equipment. .

6.9KV bus 25A may be reenergized by manual operation of its RSS? aupply breaker (22S2-25A-2).

Malf B - Effects similar to Malf A with bus 25B and its associated RSST supply breaker (22S2-25B-2) being the affected components.

Malfunction removal will restore the selected failed bus fast transfer interlock contact to normal.

References:

32001 SH. 1, 2

( Rev: 0 Date: 1/31/89

l 1

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)

MALFUNCTION CAUSE AND EFFECTS i

Plant: MP2 Malfunction #: ED09A IAC-1 ED09B IAC-2 i

i Malfunction

Title:

Loss of 120 VAC Instrument Bus  !

I l

Malfunction Type: Generic '

Malfunction Cause: Faulty supply breaker at the Instrument. Supply Panel.

Plant Status: Normal Full Power Malfunction Effects:

1 Malf A - The opening of the supply breaker to 120V regulated AC ]

instrument panel IAC-1 will result in loss of power to 1 its associated loads. The affected plant. systems.will .

(" respond appropriately for the loss of the various  ;

components and any backup components will respond according to their individual control logic.

The following alarms will actuate:

120 VAC Reg Inst Pnl IAC-1 Trouble 120 VAC Reg Inst Pnl IAC-1 on Alt Supply Malf B - Effects similar to Malf A except 120V regulated AC instrument panel IAC-2 is the major affected component.

Malfunction removal will restore power to the selected failed regulated AC instrument panel from its emergency source. A remote function is available to shift the instrument AC supply to its normal source.

References:

OP 2345A, 30022, 30024, OP 2388

() Rev:

Date:

0 1/31/89

i MALFUNCTION CAUSE AND EFFECTS .

i I

Plant: MP2 Malfunction #: ED10A Bus 201A ED10B Bus 201B I

Malfunction

Title:

Loss of  ?"V DC Bus j

Malfunction Type: Generic ].

I Malfunction Cause: Bus short circuit Plant Status: Normal Full Power i

Malfunction Effects:

i Malf A - 125 VDC bus 201A supply breaker will trip open thus q deenergizing the bus causing its amperage indication to i decrease to zero. Subsequent closure attempts of

, associated bus supply breakers will not allow reener-

, gization of the bus. The following major loads will be  !

lost:

125 VDC Vital Inst PNL 201A-1V 125 VDC Vital Inst PNL 201A-2V 125 VDC Dist PNL 201A-1 125 VDC Dist PNL 201A-2 Inverter 2-INV-1 Inverter 2-INV-3 The affected systems will respond appropriately for the loss of power supplied by these components. Backup components will respond according to their individual control logic. Electrical tech specs will be impacted, since these are vital buses.

Malf B - Effects similar to Malf A except 125 VDC bus 201B is the major affected component. The following major loads will be lost:

125 VDC Vital Inst PNL 201B-1V 125 VDC Vital Inst PNL 201B-2V 125 VDC Dist PNL 201B-1 125 VDC Dist PNL 201B-2 Inverter 2-INV-2 Inverter 2-INV-4.

I

-( Rev:

Date:

0 1/31/89

Malfunction removal will allow restoration of power to the selected failed bus through the use of remote functions on bus supply breakers.

References:

30024, 30022, OP 2388 O

Rev: 0 Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #:

EDllA INV-1 to VIAC-1 ED11B INV-2 to VIAC-2 EDllC INV-3 to VIAC EDllD' INV-4 to VIAC-4 EDilE INV-5 to VIAC-1 EDilF INV-6 to VIAC-2 Malfunction

Title:

Inverter / regulated AC failure to vital AC buses.

Malfunction Type: Generic Malfunction cause: Loss of inverter / regulated 120 VAC power supply.

Plant Status: Normal Full Power Malfunction Effects: ,

Malf A - This malfunction will cause a loss of the AC output from inverter 2-INV-1. Inverter amperage-indication will decrease to zero. 120 VAC vital. instrument panel VIAC-1 power source will be shifted to'its emergency supply via its associated static switch operation. The shift will not interrupt power to associated. loads on  !

VIAC-1. Electrical Tech-specs may be impacted.

The following alarms will be received:

Inverter INV-1 Trouble VIAC-1 on Emergency Supply.

Malf B - Effects similar to Malf A except 2-INV-2 is the major affected component.

Malf C - Effects similar to Malf A except 2-INV-3 is the major affected component.

Malf D - Effects similar to Malf A except 2-INV-4 is the major affected component.

/' Rev: 0 I

Date: 1/31/89

) Malfunction removal will restore the selected failed inverter AC output. Restoration of the vital instrument AC power to its normal source through static switch operation will-be accomplished by individual remote function operation.

Malf E - This malfunction will cause a loss of the AC output from Inverter 2-INV-5 and will cause the loss of VIAC-1 if it is on the emergency supply. If INV-5 is not supplying the VIAC-1, alarms only will be received.

Malf F - Effects simulate to MALF E except 2-INV-6 is the affect component and VIAC-2 may be deenergized if 2-INV-6 was supplying VIAC-2.

REFERENCES:

30024, 32031, 37006, OP 2388 O

() Rev:

Date:

0 1/31/89

[

['}

\_e-MALFUNCTION CAUSE AND EFFECTS l

Plant: MP2 Malfunction #:

ED13A 201A-1V l ED13B 201A-2V ED13C 201B-1V ED13D 201B-2V Malfunction

Title:

Loss of Vital DC Distribution Panel.

I Malfunction Type: Generic d

Malfunction Cause: Faulty Supply Breaker Plant Status: Normal Full Power Malfunction Effects:

Malf A - This malfunction will cause deenergization of 125 VDC

[~'

s vital instrument panel 201A-1V and its associated loads. Bus 201A current indication will decrease to reflect the loss of the panel. Electrical tech specs ,

will be impacted, since these are vital buses.

The following alarms will actuate: 1 125 VDC VI Inst PNL 201A-1V/2V Trouble.

i The affected plant systems will respond. appropriately for the loss of associated power supply and any backup components will respond according to their. individual control logic.  ;

Malf B - Effects similar to Malf A except panel 201A-2V is the major affected component.

Malf C - Effects similar to Malf A except panel 201B-lV and bus 201B are the major affected components.

Malf D - Effects similar to Malf A except panel 201B-2V and bus 201B are the major affected components.

( Rev:

Date:

0 1/31/89

i i

Malfunction removal will reshut the faulty supply breaker to the selected failed vital DC instrument 3 panel. J 1

1 i

References:

30022, 30024, 32031 SH. 4, OP 2388 1

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' Rev: 0 Date: 1/31/89

k MALFUNCTION CAUSE AND EFFECTS O i Plant: MP2 Malfunction #: ED14 j Malfunction

Title:

Loss of_ Annunciator Power Supply on Main-Control Boards q l

Malfunction Tyge: ' Generic Malfunction cause: Faulty Supply Breakers Plant Status: Normal Full Power Malfunction Effects:

Total loss of power to the annunciator system panel RC22 will prohibit operation of.any window annunciator or sound generating device within the system. Crywolf functions will continue to display at the PCM but will have no visual or audible affect of the control boards. Tech specs will be impacted.

}

Malfunction removal will restore the annunciator power supply.

Reference:

OP 2387A

-)

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1 Rev: 0 i

\ Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS

'\ s Plant: MP2 Malfunction #: ED15 Malfunction

Title:

Loss of 125 VDC Bus 201D Malfunction Type: Generic Malfunction cause: Short Circuit on Bus Trips Feeder Breaker Plant Status: Normal Full Power Malfunction Effects:

The short circuit will result in tripping the bus feeder breaker causing the 125 VDC turbine battery bus and associated loads to deenergize. The turbine battery and associated-charger 201D (DC4) will remain connected to its bus. Bus 201D and battery charger-amperage will decrease to minimum.

() The following major : ads will lose power:

Main Turbine EBOP SGFP Turbine EOP P60A SGFP Turbine EOP P60B Inverter 2-INV-5 Inverter 2-INV-6 125 VDC Dist PNL 201D-1.

The affected systems will respond appropriately for the loss of these components with any backup components responding according to their individual control logic.

The following alarms will actuate:

Inverter INV-5 Trouble Inverter INV-6 Trouble.

Malfunction removal will reclose the open supply breaker to restore power to bus 201D.

Reference:

30022 SH. 9, 30023, 32031 SH. 2 f} Rev: 0 As Date: 1/31/89

I l i

l MALFUNCTION CAUSE AND EFFECTS

's / I Plant: MP2 Malfunction #: ED16A VIAC-1 (VA-10) )

ED16B VIAC-2 (VA-20) 1 ED16C VIAC-3 (VA-30) j ED16D VIAC-4 (VA-40) )

Malfunction

Title:

Loss of Vital Instrument AC Panel Malfunction Type: Generic Malfunction Cause: Static Switch Failure-Plant Status: Normal Full Power Malfunction Effects: I Malf A - This malfunction will cause the static switch (VS1) feeding 120 VAC vital instrument panel #1 to fail so q

,f-s' that neither the normal or the emergency power supply ,

j is passed. VIAC-1 and all of its associated loads will 1

f

\~-) be deenergized. Amperage indication on INV-1, 125 VDC bus 201A and battery charger 201A will decrease.

Affected plant systems will respond appropriately for l the loss of the various components with any backup j componen's actuating according to their individual i control logic. Electrical tech specs will be impacted, since this is a vital bus.

Malf B - Effects similar to Malf A except VIAC-2, INV-2 and bus i 201B sre the major affected components. ,

1 Malf C - Effects similar to Malf A except VIAC-3, INV-3 and bus 201A are the major affected components.

Malf D - Effects similar to Malf A except VIAC-4, INV-4 and bus 201B are the major affected components.

Malfunction removal will restore the selected failed static switch operation to normal.

References:

30022 SH. 14, 15, 16, 17, 30024, OP 2388, Reference ~

Plant Data Book, Event #46.

p

(_,) Rev: 0 Date: 1/31/89

/"' MALFUNCTION CAUSE AND EFFECTS k

l Plant: MP2 Malfunction #: ED17A 24C Bus I ED17B 24D Bus Malfunction

Title:

Failure of 4.16KV Bus Auto Transfer Malfunction Type: Generic Malfunction cause: Failure of associated bus fast transfer interlock contact.

l Plant Status: Plant Trip from Full Power i

Malfunction Effects:

Malf A - This malfunction will prevent closing of contact  ;

83X1/15G-225 in the breaker closing scheme of the RSST l supply breaker to bus 24C (22S3-24C-2). When the NSST 1 supply breaker to bus 24A (2S3-24A-2) opens during fast O transfer, the RSST supply breaker to bus 24C will remain open. This will result in.the deenergization of buses 24A and 24C. Bus 24C will shed loads and will be reenergized by diesel generator 12U. Loads will be sequenced back on bus 24C. Bus 24A will remain deenergized due to tripping open.of tie breaker 24C-lT-2. Electrical tech specs will-be impacted.

Malf B - Effects similar to Malf A except 4.16KV bus 24D and its associated RSST supply breaker (22S3-240-2) and loss of bus 24B are the major affected components.

Malfunction removal will restore the selected failed bus fast transfer interlock contact to normal.

References:

32002 SH. 1, 2 l

(

' Rev: 0 Date: 1/31/89 f

f

MALFUNCTION CAUSE AND EFFECTS.

Plant: MP2 Malfunction #: ED18 Malfunction

Title:

Loss of 4.16KV to Emergency Bus 24C'and 24D Malfunction Type: Generic Malfunction-Cause: Inadvertent opening of 2253-2-2 (A702) due to Faulty Tripping Mechanism.

Plant Status: Hot Standby Operation Malfunction Effects:

This malfunction will result in tripping of the 4.16KV bus 24G feeder breaker to buses 24C and 24D. Main feeder breakers 22S3-24C-2 and 22S3-24D-2 will be tripped open on an associated breaker interlock with 22S3-2-2.

The resultant undervoltage on bus 24C and bus 24D will cause load shed signals to be developed which will trip nonessential loads and buses.

The diesel generators will start and their output breakers will shut to reenergize buses 24C, 24D and 480V loads that were not ,

tripped off during load shed. The load sequencer will then "

restart essential equipment through ESAS modules.

Breaker 2253-2-2 will not be able'to be reclosed if a closure attempt is made and the malfunction is still inserted.

Electrical tech specs will be impacted, since-these are vital buses.

The following alarms will actuate: l 4KV Bus 24G to Bus 24C/D Bkr Trip 4KV Bus C/A Tie Bkr Trip 4KV Bus D/B Tie Bkr Trip  ;

ESAS UV (1A-lD, 2A-2D) Trip (24C-24D)

Diesel Gen (12U, 13U) Auto Start Diesel Gen (120, 13U) Ready to Load Sequencer (1,2) Operating Rev: 0 Date: 1/31/89

4 i

i i

Malfunction removal will permit closure of the tripped supply breaker 2253-2-2 thus allowing power _to be restored from the RSST.

.to the emergency 4KV buses.-

Reference:

32002 SH. 21 ~, 1, 2 l

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Rev: 0 Date: 1/31/89 ,

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MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: EG01 Malfunction

Title:

Main Generator Trip Malfunction Type: Generic Malfunction Cause: Faulty Main Generator Differential Relay (87G)

Plant Status: Normal Full Power Malfunction Effects:

Malfunction insertion will cause the main gener'ator to trip resulting in opening of the generator output breakers (15G-8T-2 and 15G-9T-2), generator field breaker and exciter field breaker.

The main turbine will' trip causing a reactor trip on loss of load protection. Exciter and main generator electrical status indication will decrease to minimum values.

[ Auto bus transfer to the reserve station service supply will

= occur on 6.9 KV and 4.16 KV buses (25A, 25B, 24A, 248, 24C and 24D).

The atmospheric and steam dump valves will open to reduce and control RCS average temperatures. Pressurizer level and pressure-will be restored by their respective control systems after initially decreasing. The feedwater regulating bypass valves will ramp open to their 75% open position to allow feeding the Steam Generators at or greater than the steam flow rate.

The following alarms will actuate:

Turbine generator lockout trip channel I/II Reactor / Gen prot turbine trip Exciter field breaker trip Generator field breaker trip Generator backup audio tone TT operation 6.9 KV bus 25A, 25B NSS supply bkr trip 4 KV bus 24A, 24B NSS supply bkr trip.

"~% Rev: 0 Date: 1/31/89 ,

L___-__________--_______________________________________ .

(N Control board indications are:

N_/l Generator / turbine trip Reactor trip Station service loads shift to RSST.

Malfunction removal restore the faulty generator differential relay to normal.

Reference:

32005 SH. 19A, 20A, 21, 23, 24, 27, 28, 31, 32006 SH.4A, 8, 37006 SH. 4,5, Reference Plant Data Book, Event #25 and #34

?

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/m Rev: 0 Date: 1/31/89

('s-}

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: EG02 Malfunction

Title:

Main Generator Auto Voltage Regulator Failure to Manual.

Malfunction Type:' Generic Malfunction Cause: Automatic changeover to manual due to cont.act (60AX) failure.

Plant Status: Normal Full Power Malfunction Effects:

Insertion of this malfunction will.cause automatic shifting of.

the main generator voltage. regulator to manual control. If the transfer null meter was balanced prior to the shift, there will be no transient effect on the generated voltage output. If not

/~T properly balanced, the generator voltage and reactive amp load (m,/ will be affected. If the manual regulator is set above the auto regulator, a less lagging or higher leading power factor will be observed. If the manual regulator is set below the auto regulator a less leading or higher lagging power factor will be observed.

The following alarms will actuate:

Exciter auto trip to manual.

Control board indications are:

Exciter mode status ,

Generator voltage and current.

Malfunction removal will allow transfer to the automatic voltage regulation mode.

Reference:

32005, OP. 2324A

/ Rev: 0

' \ Date: 1/31/89

1 i

1 1

4 l'~

i MALFUNCTION CAUSE AND EFFECTS 1

i Plant: MP2 Malfunction #: EG07 Malfunction

Title:

Main Generator Auto Voltage Regulator Oscillation.

Malfunction type: Variable 100% = +/- 1000 volt Oscillation at 10 volts /sec.

1 Malfunction Cause: Drifting Reference Voltage in' Auto. Regulator caused by feedback controls varying /failing.

Plant Status: Normal Full Power {

l Malfunction Effects:

( Malfunction insertion will cause the generator terminal voltage l

%- to oscillate at the selected severity. Reactive load on the main generator will vary proportionally with the output voltage.

]

Generator field current and voltage will vary.

The AC voltage regulator will automatically shift to the DC manual regulator if the maximum excitation limit is exceeded for 5 seconds. When the regulator shifts to manual, the oscillation will stop.

The following alarms will actuate when their setpoints are-exceeded:

i Maximum excitation limit Exciter auto trip to manual.

Control board indications are:

Generator field voltage and current j Generator reactive load indication.

1 i

L Malfunction removal will restore the AC automatic regulator control to normal.  ;

I

~

Rev: 0

- Date: 1/31/89 j l

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1 Actual generator' terminal'and 345 KV. system, voltage'should not change when the generator.is tied ~to the grid during the malfunction.

Referen'ce 32005 SH.-12, 13,'14' l

O J l

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Rev: 0 1/31/89 O Date:

rx MALFUNCTION CAUSE AND EFFECTS

! )

,1 Plant: MP2 Malfunction #: EG08A 15G-12U-2

-~

EG08B 15G-13U-2 Malfunction

Title:

Diesel Generator Output Breaker Failure Malfunction Type: Generic Malfunction cause: Mechanical failure prohibits auto and manual clasure.

Plant Status: Diesel Generator Operations.  !

I Malfunction Effects:

Ma'.f A - This malfunc ..n will prevent closure of the diesel generator supply breaker to bus 24C. If the breaker is shut prior to malfunction insertion, it will not trip open due to malfunction insertion. Breaker trip pro-tective features will function to operate the breaker

/~}

(_,/ properly. With the breaker open, subsequent breaker ,

closure attempts, either automatic or manual, will not l close the breaker. The breaker control switch amber indicating light will be energized when its positioned to NAC. Tech specs will be impacted.

Malf B - Effects similar to Malf A with 15G-13U-2 r.nd bus 24D being the affected components.

Malfunction removal will permit auto or manual closure of the selected failed diesel generator output breaker.

Re f e rence : 32041 SH. 1 l

l f/,I Rev: 0

\- Date: 1/31/69

i l

j) MALFUNCTION CAUSE AND EFFECTS-kJ 1 4

P3 ant: MP2 Malfunction #: EG09A 15G-120-2 )

EG09B 15G-130-2 Malfunction

Title:

Diesel Generator Breaker Auto Closure Failure Malfunction Type: . Generic Malfunction cause: Load shed contact in breaker closing circuit j Ilils open.  !

l Plant' Status: Diesel Generator Operation (LNP)

Malfunction Effects:

1 Malf A - This malfunction will prevent automatic' closure of diesel generator output breaker 15G-120-2 to bus 24C.

Manual breaker closure will be permitted. During loss of normal power conditions, the diesel will come up to ,

' speed and voltage but its associated breaker will not~

(~. l

\ close. Tech specs will be impacted. l l

The following alarms will actuate:

l Diesel Gen 120 ready to load.

Control board indications are:

Diesel Gen frequency Diesel Gen voltage.

Mclf B - Effects similar to Malf A with Diesel Generator output ,

breaker 15G-13U-2 being the affected component.

Malfunction removal will permit automatic closure of the selected failed diesel generator output breaker.

.R__E f e r e n c e : 32041 SH. 2 i

l

() Rev:

Date:

0 1/31/89

/~T MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: -EG10A- D/G 12U EG10B D/G 130 Malfunction

Title:

Diesel Generator Automatic Voltage. Regulator Failure Malfunction Type: Generic Malfunction Cause: Drifting reference voltage in auto regulator.

Plant Status: Diesel Generator Operations. This malfunction only valid after D/G is synchronized and closed in on the bus.

Malfunction Effects:

Note: This malfunction should be inserted only after.the D/G' has been synchronized and closed in on the bus.

Malf A - Malfunction insertion with diesel generator 120 running

-[~

s- )' after synchronization, will cause the diesel generator reactive load to oscillate. The bus voltage will be dependent on its station service transformer supply voltage. The oscillation will vary'around the setting of the automatic voltage regulator output only. Manual control will not be affected and may be.used to limit the effects of this malfunction.

Malf B - Effects similar to Malf A with diesel generator'13U automatic voltage regulator being the affected component.

Malfunction removal will permit normal automatic

. voltage regulation on the selected failed diesel generator.

Reference:

32041 SH. 11 O Rev:

Date:

0 1/31/89

.J MALFUNCTION CAUSE ltND EFFECTS

'( )

Plant: MP2 Malfunction #: EGilA D/G 12U 'I l

EG11B D/G 13U

\

Malfunction

Title:

Diesel Generator Auto Start Failure Malfunction Type: Generic Malfunction Cause: Shorted LNP contact in engine control circuit.

Plant Status: Diesel Generator Operations (LNP),

Malfunction Effects:

1 Malf A - This malfunction will prohibit automatic starting of diesel generator 12U from a loss of power initiated i signal. Manual starting of the engine from control room panel CO8 will not be inhibited. Output voltage f and frequency will'not be developed until it is: .

1 manually started. Diesel generator SIAS or. auto-start

( alarms will not actuate as they are low speed I dependent. Tech specs will be impacted.

Malf B - Effects similar to Malf A with diesel generator 130 l being the affected component. i Malfunction removal will permit automatic start signals to the selected failed diesel engine.

Reference:

32041 SH. A, 3, 4, 11, 14 l l

1 i

( .Rev: 0 Date: 1/31/89

i a

MALFUNCTION CAUSE AND EFFECTS

[

1

'I Plant: MP2 Malfunction #: EG12A D/G 12U EG12B D/G 130 Malfunction

Title:

Diesel Generator Load Control Failure Malfunction Type: Generic / Variable 100% - +/- 1 Hertz oscillation in 10 seconds.

Malfunction cause: Amphenal connector failure.

I, Plant Status: Diesel Generator Operations. ]

Malfunction Effects: .j 1

Malf A - This malfunction will cause.an oscillation in diesel 1 generator speed control around its governor setpoint. l It will occur whether operating in synchronous or. i synchronous modes. With the diesel running i ]s  ;

unparalleled, its frequency will vary at the severity rate. Synchronizing attempts will be more difficult at high severities as synch-check circuit logic must,be .{

met to achieve breaker closure. If successful parallel lj operation is achieved, the' diesel may trip on reverse power if a low electrical load is maintained. Parallel 1 operation will result in true power load variances.

Tech Specs may be impacted.

Malf B - Effects similar to Malf A with D/G 13U speed being the j affected component.  !

Malfunction removal will restore the selected failed diesel generator load control to normal.

Reference:

32041 SH. 9 j i

-[v ) Rev: 0 i

Date: 1/31/89

-)

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: ES01A P9A ES01B P9B k

1 Malfunction

Title:

Auto Aux Feed Initiation System Failure.

Malfunction Type: Generic Malfunction Cause: Timer Mechanical Failure (62Z1/62Z2) )

Plant Status: As required to create S/G low level auto start of Aux Feed System.

Malfunction Effects:

Malf A - This malfunction will prevent the automatic' starting of I auxiliary feed pump A. Manual starting from C21 and CoS l will not be inhibited. If the #1 steam generator level cannot be maintained above 12% an auto initiation signal {

t will be generated but the action of the 3 min 25 see timer -

~ associated with the startup of P-9A will kne blocked. Tech  ;

specs will be impacted. j Malf B - Effects similar to Malf A except that the automatic starting i of auxiliary feed pump B will be blocked. j i

The following alarm (s) will be received: ,

Auto start AFW "A" ,

Auto start AFW "B".

Malfunction removal will allow proper timer operation.

Note: Insertion of both malfunctions simultaneously will cause  ;

failure of both pumps to start and both valves to open. 1

REFERENCES:

32012 SH. 44, 45, 46, 11, 12, 28500 SH. 370-373 i

i l

() Rev:

Date:

0 1/31/89

f-MALFUNCTION CAUSE AND EFFECTS

(  ;

Plant: MP2 Malfunction #: ESO2A Channel 1 SI  ;

E502B Channel 2 SI  !

Malfunction

Title:

Spurious Engineered Safety Feature Signals, i

Malfunction Type: Generic Malfunction Cause: Inadvertent Manual Pushbutton Operation.

Plant Status: Normal full power.

Malfunction Effects: j

, Malf A - Insertion of this malfunction will initiate a channel one. f safety injection actuation. Actuation modules #514 through 525 (SIAS), #502 through 507 (CIAS), and 508 (EBFAS) will H trip to cause related equipment to actuate. The channel actuation may be reset without removing the malfunction.

() The following major effects will be observed:

- Safety injection pumps that start will not inject flow as long as the reactor coolant system pressure is above the pump's shutoff head

- Concentrated boric acid is lined up and pumped into the RCS by the charging pumps

- CVCS letdown flow is stopped The injection of boric acid into the RCS will cause reactor power and average RCS temperatures to decrease. This will cause secondary. steam-pressure to decrease resulting in the dropping of generated output.

The cooldown of the RCS will cause primary system pressure and pressurizer level to drop. A reactor trip on TM/LP protection will most likely occur first on this event.

Malf B - Effects similar to Malf A except that channel 2 SI and its associated components will be actuated. Associated modules are #614-625, 602-607 and 608.

Rev: O LO. Date: 1/31/89 i

i l

1

[~') Malfunction removal will have no' visible effect on  !

U performance of the simulator as the faulty signal will only appear momentarily.  ;

REFERENCES:

28150, OP-2*84, 39047 l

j i

i i

i i

1 1

O Rev: 0 O* Date: 1/31/89

fs 6s.LTUNCTION'CAUSE AND EFFECTS Plant: MP2 Malfunction #: ES03A.- AM503 ES03B - AM515 ES03C - AM523-E503D - AM602-ES03E - AM604 ES03F - AM615 ES03G - AM619 Malfunction

Title:

-ESF Signal Failure to Actuate.

Malfunction Type: Generic Malfunction Cause: Electronic' gate failure in associated module l- prevents actuation of system components.

Plant Status: Normal full power.

Malfunction Effects:

( ) Malf A - This malfunction will prevent actuation of the components activated by actuation module #503. The module will appear to work properly if.it is triggered either. manually or automatically. The modules associated alarm functions will also work properly. The auto test inserter will respond to reflect the fault. Components normally actuated by this-module-are steam gen #1 blowdown valve 2-MS-220A and sample line valve 2-MS-191A.- Tech. specs will be impacted. Refer to OP 2384 (ESAS) for equipment affected.

Malf B - Effects similar to Malf A except that AM-515 will be the major affected component.

Malf C - Effects similar to Malf A except that AM-523 will be the major affected component.

Malf D - Effects similar to Malf A except that AM-602 uill be the major affected component.

Malf E - Effects similar to Malf A except that AM-604 will be the major affected component.

Rev: 0 f

1/31/89

\ Date:

I-Malf F - -Effects similar to Malf A except that AM-615 will be'the major affected component.

Malf G - Effects similarIto Malf A=except that AM-619 will be the major affected. component.

REFERENCES:

28150 SH 1-4, OP 2384.

l l

l l

l' LO 1

l l

l l-i, l

l l

Rev: 0 Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS ,

i Plant: MP2 Malfunction #: ESO4A Sensor Channel A and Actuation Cabinet #5 ESO4B Channel B and )

. Actuation Cabinet #6 l ESO4C Channel C ESO4D Channel D Malfunction

Title:

ESAS Actuation / Sensor Cabinet Loss of Power.

Malfunction Type: Generic Malfunction Cause: Faulty AC Supply Breaker.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - Insertion of this malfunction will cause the loss of 120 VAC

/' to ESAS sensor cabinet A and actuation cabinet number'5

( (channel 1). All metered indication'on sensor cabinet A will decrease to zero. All lights will'be extinguished and

{

logical functions of handswitches and pushbuttons on the failed panels will be inoperable. The actuation modules will not go into a trip condition or cause any related ESF equipment to actuate from channel one. Tech specs will be impacted.

1 Actuation modules on cabinet 6 will go into a 1/3 logic j state except for purge valves (AM-601) which will be tripped '

on a 1/4 signal.

The following alarms will be received: ,

RWST Ch A Level Lo Lo PZR Press Lo Lo A  ;

CTM Press Hi A CTM Press Hi Hi A STM Gen Press Lo Lo A Channel "A" CTMT Air Particulate Rad Hi AEAS Ch A SFP Area Rad Hi CTM Rad Actuation Sig Ch 2 Trip ESAS Auto Testing System Failure ESAS UV 1A Trip Bus 24C ESAS.UV 2A Trip Bus 24D.

Rev: 0 Date: 1/31/89

) -Malfunction A. removal will restore power fully to'the sensor cabinet. Restoration of power.to the' actuation cabinet will not reenergize its 24 VDC supply as' indicated by fuse: lights being out. All of the actuation cabinet' functions will'be inoperable until the remote function to replace fuses is utilized. Total restoration of power will'noticause any actuation modules to trip.

-Malf B - Effects similar to Malf A except that sensor cabinet B-and actuation cabinet 6 will be the major affected components.

Malf C - Effects similar to Malf A except that only. sensor cabinet C will lose power.

Malf D - Effects similar to Malf A except that only sensor cabinet D.

-will-lose power.

REFERENCES:

28150, 39047, OP-2384.

]

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i I

i i

Rev: 0 N

Date: 1/31/89 1________ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ __

_ _ _ __ _ j

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: ES06AA:- 2 see ES06AB - 8 sec ES06AC - 14 see ES06AD - 20 see ES06BA -- 2 sec .

ES06BB - 8 sec

  • ES06BC - 14.sec I ES06BD - 20 sec .j 1

Malfunction.

Title:

D/G Sequencer Failure.-

Malfunction Type: Generic Malfunction Cause: Timer Failure at selected increment.

4 Plant Status: LNP as required for D/G operation.

l Malfunction Effects:

7

~

l Malf AA - With the sequencer not in operation the insertion.of this malfunction will cause the actuation cabinet 5 sequence one light to extinguish. When the sequencer starts, equipment which should start on the seg 1 signal will not start.

This malfunction will not inhibit operation of other com-ponents which are operated by seq 2, 3, or 4. Tech specs  ;

will be impacted. Refer to OP 2384 (ESAS) for effected l l equipment.  !

l Malf AB through AD -

Effects similar to Malf AA except that the diesel generator H7A sequencer times listed above as generic components may be individually affected.

l Malf BA through BD -

Effects similar to Malf AA except that the sequencer times for diesel generator H7B on actuation cabinet 6 will be individually affected.

i, Rev: 0 Date: 1/31/89 1

-- --------------_-----_,___m.____.__

i~

Malfunction Removal will restore the operation of the faulty timer to normal. If the timer had initiated its associated equipment will start.

l

REFERENCES:

28150, 39047, OP-2384 O

,V l

i I

l 1

l l

l l

6 Rev: 0 Date: 1/31/89 1

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: FWOI

~

Malfunction

Title:

Loss of Condense: Vacuum.

Malfunction Type: Variable, 100% = vacuum decrease to Turbine Trip Setpoint in 5 minutes.

Malfunction cause: Air In-Leakage (undefined location)

Plant Status: Normal full power operation.

Malfunction Effects:

This malfunction will result in the loss of condenser vacuum and plant efficiency. At low severities the effects may be minimized by load reduction and the use of additional air removal equipment. The decreasing vacuum will cause reduced efficiency of the main turbine e temperatures.resulting in a decreased electrical output and higher condensate If the condenser vacuum falls below 22.5" hg, a turbine trip will occur. If vacuum falls below 15" hg the turbine bypass valve operation will be inhibited. Turbine coastdown time will be decreased by degraded vacuum. If vacuum drops below 10" hg the SGFP turbines will trip.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Condenser Vacuum Lo Condenser Vacuum Lo Lo Trip Condenser Steam Dump Bypass Lo Vacuum Inhibit Malfunction removal will stop the vacuum leak. Recovery of vacuum will be dependent on the air removal capability.

REFERENCES:

26012 i

I O Rev:

Date:

0 1/31/89 1

4 j

/' MALFUNCTION CAUSE AND EFFECTS i

i Plant: MP2 Malfunction #: FWO2 l

Malfunction

Title:

Condenser Hotwell Level Control Transmitter (LC 5143) Failure.

Malfunction Type: Variable, 100% = Maximum range of Instrument.

Malfunction cause LC 5143 Fails at Selected Severity Level.

Plant Statu,s Normal full power operation.

Malfunction Effects:

This malfunction will fail the hotwell reject level control valve controller. Failing the controller below its normal setpoint will result in the opening of 2-CN-219 and the lowering of hotwell level.

The surge tank to hotwell level control valve will then open to maintain a lower hotwell level.

If a level control setpoint is selected which is higher than normal l LCV-5143 will remain shut. Any transient which causes hotwell level I to increase, (condenser tube leaks) will end up with level being l maintained high. )

i control board indications are as follows: 1 I

Condenser Hotwell Level  :

Demin D/P Increase The reject valve closure on low SG feed pump suction will not be  !

affected by this malfunction. l!

The following alarms, key to event diagnosis, will occur as their {

setpoints are exceeded:  !

Condenser Level Lo Condenser Level Hi  !

Removal of malfunction will restore LC-5143 operation to normal.

t

REFERENCES:

26005

[\ '"#

Rev: 0 Date: 1/31/89 .j l

l I

y l;

f-' MALFUNCTION CAUSE AND EFFECTS

\,.))

Plant: MP2 Malfunction #: FWO3A - P2A 1 FWO3B - P2B {

FWO3C - P2C ,

i 1

Malfunction

Title:

Condensate Pump Trip.

l Malfunction Type: Generic /Non-Variable.

1 l

Malfunction Cause: Low Hotwell Level. switch actuation. J Plant Status: Normal full power operation. j Malfunction Effects:

This malfunction results in contact closure and seal-in trip of 1 condensate pump A, (B, C). The tripped pump will not be able to be ]

restarted. Condensate header pressure will decrease resulting in

(~3 the standby pump starting at 400 psig. If sufficient condensate

-V flow and pressure cannot be maintained, the feedwater' pumps will be tripped on low suction pressure.

The following alarms, key to event diagnosis, will occur as their setpoints are exceededi ,

1 Condensate Pump Dis Press Lo SGFP A/B Suction Flow Lo SGFP A/B Suction Press Lo Malfunction removal will restore the selected failed hotwell level contact to normal. The trip seal-in feature may then be reset with '

the appropriate pump handswitch.

REFERENCES:

32012 SH. 14, 26005 i

l I

Rev: 0

' Date: 1/31/89 i

' .l

.I I

1

]

l gs MALFUNCTION CAUSE AND EFFECTS j 1

?

Plant: MP2 Malfunction #: FWO4 Malfunction

Title:

Condensate Minimum Flow Recirculation Valve )

Failure.

Malfunction Typg: ' variable. 100% = valve-Full open.

I 1

Malfunction cause: Mechanical Failure of 2-CN-218. I Plant Status: Normal. full power operation.

Malfunction Effects:

This malfunction results in failure-of the condensate pump recirc ]

valve in an open position while at power causing an increase in  !

condensate header flow and reduced header pressure. Pump current will increase with the increase in flow.

() Failure of the valve to open when minimum flow is required will result in the pump overheating. The pump motor current will l

increase to trip its circuit breaker as the pump seizes. Pump seizure will occur in approximately 10 minutes. 1 The following alarms, key to event' diagnosis, will occur as their setpoints are exceeded:

)

1 SGFP A/B Suction Press Lo I Condensate Demin System Trouble Removal of malfunction will restore the' condensate minimum flow recirc valve operation to normal.

REFERENCES:

26005, 28500 SH. 566 l

O Rev: 0 Date:. 1/31/89 3

l 1

l p MALFUNCTION CAUSE AND EFFECTS

(

Plant: MP2 Malfunction #: FWO5 .

1 Malfunction

Title:

Condensate Demineralized High Differential Pressure.

1 l

Malfunction Type: Variable: 100% - 100 psid increase above normal. {

Malfunction Cause: Suspended solid buildup in derineralizers. l Plant Status: Normal full power operation.

Malfunction Effects:

As the severity level of the malfunction is increased the differential pressure across the condensate demineralized system i will increase. Feed pump suction pressure will decrease leading to lower feedwater header pressures. The feedwater regulating valves i

/" will open to maintain steam generator levels. If feed pump suction  ;

(_ pressure falls below 245 psig for greater than 5 seconds the feed  !

pumps will be automatically tripped. The demineralized bypass valve may be used to reduce the developed differential pressure.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Condensate Demin System Trouble SGFP A/B Suction Press Low S/G Level Setpoint Deviation High/ Low Removal of malfunction will restore the demin D/P to normal.

I I

REFERENCES:

26005, 26801 SH. 1 C Rev: 0

\- J Date: 1/31/89

__j

"s . MALFUNCTION ~CAUSE AND EFFECTS

(_J.

Plant: MP2 Malfunction #: FWO6A - A SGFP FWO6B'- B SGFP Malfunction

Title:

SG Feedwater Pump Trip.

Malfunction Type: Generic, Non-Variable.

Malfunction Cause: Faulty Low Vacuum Trip Switch.

Plant Ststus: Normal full power operation.

Malfunction Effects:

This malfunction results in the immediate trip of the selected steam generator feed pump. The feed pump's turbine low pressure stop valve will close and the pump speed will reduce to zero RPM. SGFP discharge pressure will decrease to its suction pressure value.

(_ The remaining feed pump will try to assume the required flow. At power levels greater than 65% one feedwater pump will'not be able to provide the required flow. As the flow decreases so will the D/P across the FRV's and the level inventory in the' steam generators.

A reactor trip on low S/G water level will occur at approximately 36% with subsequent AFW auto initiation if either S/G level falls below 12% for greater than'205 seconds.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

SGFP A Turbine Trip SGFP A Suction Flow Lo Steam Gen 1/2 Level Hi/Lo SG Lo Level Trip Ch A/B/C/D S/G Level Setpoint Deviation High-Low Removal of malfunction will restore the selected failed SGFP vacuum trip switch to normal allowing for restart of the affected SGFP.

REFERENCES:

26002, 26005, 32012 SH. 7, 9.

l) Rev: 0

\s /

Date: 1/31/89

i I

.i i

MALFUNCTION CAUSE AND EFFECTS O .

i Plant:- MP2 Malfunction #: FWO7 l Malfunction

Title:

Low Pressure Heater Bypass Valve Leakage.

Malfunction Type: Variable, 100% = 1000 gpm 0 500 psi.

.i Malfunction Cause: Seat Leakage Past 2-CN-15.  ;

1 Plant Status: Normal full power operation.

Malfunction Effects:

1 This malfunction results in less heat added to the feedwater as it  :

flows to the drains coolers through the number 2 heaters. Heater ]

outlet temperatures as monitored by computer points will increase.  :

The temperature of the feedwater entering the steam generators will  ;

decrease which will cause an increase in reactor power. Plant  !

efficiency will decrease. I O The following alarms, key to event diagnosis, will occur as their <

i setpoints are exceeded:

None expected.

Removal of malfunction will stop the leakage through 2-CN-15.

REFERENCES:

26005.

i Rev: 0 l

N. Date: 1/31/89 l' _ _ _ _ - _ _ _ _ _ _ _ ~

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: FWO8 High Pressure Heater Bypass Valve Leakage.

~

Malfunction

Title:

Malfunction Type: Variable, 100% = 1000 gpm 0 1000 psi.

Malfunction cause: Seat leakage past 2-FW-6.

"I Plant Status: Normal full power operation.

Malfunction Effects:

I This malfunction.results in less heat added to the feedwater as it ')

flows through the high pressure feedwater heaters. Heater outlet temperatures as monitored by computer points will increase. 'The temperature of the feedwater entering the steam generators will i decrease. This will cause an increase in reactor power. Plant efficiency will decrease.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

None expected ,

I 1

Removal of malfunction will stop the leakage through 2-FW-6. j

REFERENCES:

26005 i

['T Rev: 0

\~/ Date: 1/31/89 l

l I

MALFUNCTION CAUSE AND EFFECTS I l Plant: MP2 Malfunction #: FWO9A. 2-FW-51A FWO9B 2-FW-51B  ;

i l

Malfunction

Title:

Teed Regulating Valve Failure. I

-l l

Malfunction Type: Generic / Variable. 100% = Full Open. j i

Malfunction cause: Mechanical Binding at selected position. j Plant Status: Normal fu]1 power operation.

4 4

Malfunction Effects:

This malfunction results in removal of all automatic and manual I modes of control.on selected feed regulating valve. Malfunction  ;

insertion at a severity level of valve position greater than that

- necessary to maintain S/G level will cause an increase in water (s-), level. If steam' generator level. exceeds 90% FRV closure will not occur due to its inoperability. The turbine will-trip on high water level if its associated trip is not bypassed.  !

1 At severity levels which position the FRV in a less open than j desired position, steam generator levels will decrease.- If a j reactor / turbine trip occurs an excessive cooldown will occur as  ;

rampdown of the affected FRV will not take place.  ;

1 The following alarms, key to event diagnosis, will occur.as their l setpoints are exceeded:

Steam Generator 1/2 Level Hi/Lo Steam Generator 1/2 Level Hi/Hi SG Lo Level Trip Ch A/B/C/D S/G Level Setpoint Deviation High/ Low Removal of malfunction will restore operability of the selected  ;

failed feed regulating valve to normal.

REFERENCES:

26005.

bg,/ Rev: 0 Date: 1/31/89 i

5 b_____________________________._____ __ j

u a

. MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: FW10A 2-FW-51A FW10B 2-FW-51B i

Malfunction

Title:

Feed Regulating Valve Oscillation. , i Malfunction Type: Generic, Varit.ble.

Malfunction Cause: Feedback Positioner Failure.

Plant Status: Normal full power operation. l l

i Malfunction Effects:

This malfunction results in Feed Regulating valve.1 or 2'(if selected) to respond erratically to automatic demand. signals. A transient will have to be initiated by the operator to observe the malfunction <:ffects. At less than: 50% severity the invoked

()

/s transient will be handled by the level control system as observed by l the convergent oscillation. At high severities,-(> 50%), divergent oscillations will occur which could lead to a high or low level turbine / reactor trip. Manual control of the FRV may be used to control the transients and will not be affected by the malfunction.-

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Steam Generator 1/2 Level Hi/Lo Steam Generator 1/2 Level Hi/Hi SG Lo Level Trip Ch. A/B/C/D Steam Generator Level Deviation High/ Low Malfunction removal will restore proper operability to the selected failed feed regulating valve.

REFERENCES:

26006.

l O

Rev: 0

\> Date: 1/31/89 l

]

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/ MALFUNCTION CAUGE AND EFFECTS Plant: MP2 Malfunction #: FWilA- 2-FW-36A FWilB 2-FW-36B Malfunction

Title:

SGFP Minimum Flow Recirc. Valve Failure. 1 Malfunction Type: Generic, Variable. I Malfunction Cause: Mechanical' Failure.  ;

Plant Status: Normal full power operation. .

l Malfunction Effects:

This malfunction will fail the minimum flow control valve associated  !'

with the A (B) main feed pump. Failing this valve open while at power cause a decrease in feed pump discharge pressure. Condensate

_ header flow will increase resulting in a decrease in condensate header pressure. Feedwater flow to the steam generators will decrease while the FRV's open in an attempt to maintain steam generator water level. ~If the feed pump capacity-can exceed the bypass flow rate, a low level trip may be averted.

If the minimum flow valve is left shut at levels which require pump minimum flow, pump heatup will occur. ,

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Condensate Demin Sys. Trouble Steam Generator 1/2 Level Hi/Lo SG Lo Level Trip Ch. A/B/C/D Removal of malfunction will restore the selected failed minimum flow recirculation valve operability to normal. ,

REFERENCES:

26006.

l Rev: 0 Date: '/31/89

r ,

l l

-- E MALFUNCTION CAUSE AND EFFECTS-

'N J l

Plant:: MP2 Malfunction #: 'FW12 LIC-5417 j

l

-l Malfunction

Title:

. Condensate Surge' Tank LeveliControl Failure.

l Malfunction Type: Variable, 100% = Maximum Level. l

-1 Malfunction cause: Mechanical Failure. 1 Plant Status: Normal full power operation.

1 Malfunction Effects:

Malfunction insertion at low severities will prevent makeup water from the condensate storage tank from entering th: hotwell makeup-

]

line. This may result in lossoof hotwell makeup if condensate . level j drops below its low tank level interlock-with makeup valve 2-CN-241. 1 High level' severities will cause higher levels to be-maintained in- ]

g the surge tank with makeup being/ supplied by the condensate storage ~

tank. The surge tank may overflow with the leakage being lost. /

~

The following alarms, key to event diagnosis, will occur as their q setpoints are exceeded: q l

Condensate Surge Tank Level Hi/Lo Condensate Storage Tank Level Lo/Lo Lo j

Due to the reduced CST level, Tech. Specs. will' require verifying CST inventory greater than 150,000 gallons.

Removal of malfunction will restore condensate surge tank level control to normal.

REFERENCES:

26005.

i H l

l i

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/~h -

Rev: 0 Date: 1/31/89 l

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MALFUNCTION CAUSE AND EFFECTS I

Plant: MP2 Malfunction #: FW13A_- A Htr Drn Pump FW13B - B Htr Drn Pump Malfunction

Title:

Heater Drains Pump Trip.

Malfunction Type: Generic, Non-Variable.

Malfunction Cause: Faulty Low Level Trip Switch.

i Plant Status: Normal full power-operation.

Malfunction Effects:

This malfunction results in the selected heater drain pump trip and not be able to restart. The heater drains tank level will increase and control on its high level dump at approximately 62 to 72%. The heater drains tank normal level control valve 2-HD-109 will open I fully while pump B runs at full capacity. Feed pump' suction and

.(,) ('s condensate header pressure will decrease.

l I

Loss of-heater drains flow will result in a loss of-plant efficiency. If sufficient flow cannot be maintained to the steam generators, their levels will drop to cause a turbine / reactor trip.

The effects of this malfunction may be reduced if-turbine load is reduced.

The following alarms, key to event diagnosis, will occur as their j setpoints are exceeded:

Condensate Demin System Trouble SGFP A/B Suction Flow Low Steam Generator Level Hi/Lo S/G Level Lo Trip Ch. A/B/C/D Malfunction removal will restore the selected failed heater drain pump low level trip switch to normal, allowing pump restart.

REFERENCES:

26004, OP 2320.

'~')

k/

Rev: 0 Date: 1/31/89

i r- MALFUNCTION CAUSE AND EFFECTS j f

)

Plant: MP2 Malfunction #: FW14 - LC5061 <

l Malfunction

Title:

Heater Drain Tank High Level Control-Failure.

Malfunction Type: Generic, Variable.

i Malfunction cause: Controller Failuce. R Plant Status:~ Normal full power operation.

Malfunction Effects:

This malfunction results in the hrater drains tank high level dump-controller to attempt to control level at the severity selected. If the control level selected is leder than the normal level control valve setpoint, heater drains will be dumped to the condenser and less into the feedwater header. Heater drain tank level will  ;

(~T decrease. Feed pump suction pressure will decrease leading to lower )

(_) feedwater flows and condensate header pressures. If heater drains tank level drops to 12% the heater drains pumps will be automatically tripped on low level.  !

Higher than normal (62-72%) levels may be achieved when tank level is being maintained on the high level dump and also if the incoming )

flow exceeds the pumping capability. j The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Condensate Demin System Trouble SGFP Suction Flow Low Htr Drain Tank Level Hi/Lo Heater Drain Pump Trouble Removal of malfunction will restore the heater drains tank high level dump controller to its normal setpoint.

REFERENCES:

26004, OP 2320.  !

l Rev: 0 O(./ Date: 1/31/89 I

J

I i

MALFUNCTION CAUSE AND EFFECTS l

Plant: MP2 Malfunction 1#: FW 15-AA/AB - 6A/B Heater BA/BB - '5A/B Heater  :!

CA/CB - 4A/B Heater -f DA/DB - 2A/B Heater EA/EB - 1A/B Heater J

Malfunction

Title:

Fw Heater High Level Dump valve Failure.  !

Malfunction Type: Generic, Variable,_100% = valve full open.

Malfunction Cause: High Level Dump. Control Valve Failure.

Plant Status: Normal full power operation.

Malfunction Effects:

/~N Malf AA - This malfunction will fail open th'e high level dump valve i from heater 6A to the condenser, 2-HD-ll28. With this 1 '

valve failed open the normal level' valve will shut down thus stopping drains flow through~the drains cooler 7A.~

i The level in heater 6A will decrease resulting in a loss- l of its efficiency.

Malf AB - Effects similar to Malf AA except heater 6B'high' level i dump valve is the major affected component along with B H i

train components.

Malf BA - Failure of heater SA'high level' dump valve open will l result in its level decreasing and its normal level j control valve shutting to stop drains flow to heater 6A.  !

This will result in a loss of efficiency from heaters 5A, 6A and 7A. 1 Malf BB - Effects similar to Malf BA except heater-58 high~ level dump is the major affected component along with a B train components.

Failure of heater 4A high level dump valve open will i I Malf CA -

result is less flow to heaters SA, 6A and 7A with subsequent loss of their efficiency. ,

Rev: 0

[~

' \- Date: 1/31/89

---___j

Malf CB - Effects similar to Malf CA except heater 4B high level

'l dump and B train components will be affected.

Malf DA - Failure of heater 2A high level dump valve open will~

result in' less flow to the heater drains tank, and loss of heater 2A efficiency.

Malf DB - Effects similar to Malf DA except heater 2:B high level dump and B train components will be affected.

Malf EA - Failure of heater lA high. level dump valve open will.

result in less flow to heater 2A-and more flow to the heater drains tank.

Malf EB - Effects similar to Malf EA except heater 1B high level dump and B train components will be affected.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

FW Htr lA (B) Low Level Alarm Fw Htr 2A (B) Low Level Alarm Fw Htr 3A (B) Low Level Alarm Fw Htr 4A (B) . Low Level Alarm Fw Htr 5A (B) Low Level Alarm Fw Htr 6A (B) Low Level Alarm Removal of malfunction will restore high level dump valve operation to normal.

REFERENCES:

26004, OP-2320.

l l

) Rev:

Date:

0 1/31/89 l

L______________________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _

fg MALFUNCTION CAUSE AND EFFECTS

\~-)

Plant: MP2 Malfunction #: FW16 AA/AB - 6A/B-BA/EB - SA/B CA/CB - 4A/B DA/DE --2A/B EA/EE - 1A/B Malfunction

Title:

FW Heater Normal Level' Control Valve Failure.

Malfunction Type: Generic,. Variable, 100% severity - valve wide open.

Malfunction Cause: Mechanical Failure at desired valve position.

Plant Status: Normal full power operation.

Malfunction Effects:

AA - Failure of heater 6A normal. level control valve open will result in its heater level decreasing, a loss of its O efficiency and eventually loss of drains flow to drains cooler 7A. If the valve is failed shut heater 6A level'will be maintained by operation of its high level dump valve.

AB - Effects similar to Malf AA except heater 6B normal. level dump and B train components will be affected.

BA - Failure of heater SA normal level control valve open will result in its level decreasing, loss.of its efficiency and.

eventual loss of flow to downstream heaters. If the valve is failed shut heater level will be. maintained by operation of its high level dump.

BB - Effects similar to Malf BA except heater 5B normal level dump and B train components will be affected.

CA - Failure of heater 4A normal level control valve open will result in its level decreasing, loss of efficiency.and eventual loss of drains flow to downstream heaters. If the valve is failed shut its heater level will be maintained by operation cf its high level dump.

CB - Effects similar to Malf CA except heater 4B normal level control valve and B train components will be affected.

O Rev:

Date:

0 1/31/89

7 l

i DA - Failure of heater 2A normal level control valve open will ,

result in a~ loss of its level and eventual flow to the heater i drains tank. Its efficiency will also decrease. If the valve  !

is failed shut its heater level will be maintained by l operation of its high level dump.

i DB - Effects similar to Malf DA except heater 2B normal'1evel l control valve and B train components will be affected. a EA -' Effects similar to Malf DA except Heater 1A is effected.

Normal level control flow drains to heater 2A and high level dumps to the heater drain tank.

EB - Effects similar to.Malf DA except Heater 1B is effected. ,

Normal level control flow drains to heater 2B and high level {

dumps to the heater drain tank. 1 Malfunction. removal will restore the selected failed normal level dump valve operation to normal. ]

The following alarms, key to event diagnosis, will occur as j their setpoints are exceeded: ]

i Fw Htr lA (B) Hi (Low) Level Fw Htr 2A (B) Hi (Low) Level  ;

Fw Htr 3A (B) Hi (Low) Level  !

Fw Htr 4A (B) Hi (Low) Level O Fw Htr SA (B} Hi (Low) Level Fw Htr 6A (B) Hi (Low) Level I 1

Removal of malfunction will' restore normal level control valve I operation.to normal.

REFERENCES:

26004' OP-2320.

l

() Rev:

Date:

0 1/31/89

(*]- MALFUNCTION CAUSE AND. EFFECTS N/

Plant: MP2 Malfunction #: FW18-AA-#6A BA-#5A CA-#4A AB-#6B' BB-#5B CB-#4B DA-#3A EA-#2A DB-#3B EB-#2B-Malfunction

Title:

Low pressure FW heater tube rupture.

Malfunction Type: Generic, Variable. Variable: 100% = 150% of individual heater dump capability.

Malfunction Cause: Tube Failure.

Plant Status: Normal full power operation.

Malfunction Effects:

AA - This malfunction results in a reduction in condensate flow

\ due to leakage into the "shell" side of heater 6A.

Condensate header flow will increase and its pressure.will l decrease. As the severity level is-increased the heaters f normal and high level dump control valves will open. j Heater drains flow from the upstream heater will be shut 4 off on a high level. Plant efficiency will: decrease due to )

the inoperable heater.

AB - Effects similar to Malf AA except heater 6B is the major affected component.

BA-BB - Effects similar to Malf AA except #5 heaters are affected.

CA-CB - Effects similar to Malf AA except that high level in #4 heaters will trip closed the associated extraction steam supply MOV and associated bleeder; trip valve. The ,

associated heater will fill until solid and its relief l valve will actuate. Plant efficiency will decrease due to -I the inoperable heater.  :

i DA-DB - Effects similar to Malf CA except heater #3A/B are the affected components. [ Note that 3A/3B Heaters have no normal or High Level Dump talves)

EA-EB - Effects ~similar to Malf CA axcept heater #2A/B are the affected components. j

(',_, -

~

Rev: 0 Date: 1/31/89 i

___n___ _ _ _ _-

J

ll l

1 The following alarms, key to event diagnosis,:will occur as their setpoints are exceeded:

Fw Htr 1A (B) Hi Lvl FW Mtr 4A (B) Hi Lvl 1 Fw Htr 2A'(B) Hi.Lvl.. Tw Htr'5A (B) Hi Lvl Fw Htr 3A-(B) Hi Lvl Tw Htr.6A'(B) Hi Lvl '

Malfunction' removal will,stop the tube leak in the selected .

failed feedwater heater. )

i 1

REFERENCES:

26004,'OP'2320. ]

l l

l l

1 i

O l

!. j i

j l

1 l

1 i

i i

Rev: 0 l Date: 1/31/89 j i

I i

1

1 f- MALFUNCTION CAUSE AND EFFECTS

(~) .

I i

Plant: MP2 Malfunction #: FW20A P9A FW20B P9B  ;

FW20C P4 I i

Malfunction

Title:

Aux. feedwater pump trip.

Malfunction Type: Generic /Non-variable.

,I Malfunction Cause: Breaker mech. failure (FW20A/B) and faulty 'j overspeed trip (FW20C) device. l 1

i Plant Status _: Normal full power operation, i Malfunction Effects:

Malf A - This malfunction will trip AFW pump 9A if running and prevent it from being automatically or manually started.

O. If running its current will decrease to,zero and its discharge pressure will decrease to the pumps suction value. AFW flow will stop if the failed pump was the only ,

running pump. Steam generator levels will decrease at  ;

their steaming rate. Amber pump handswitch' lights will )

illuminate as a function of handswitch and breaker  !

position.  !

Malf B - Effects similar to Malf A except AFW pump 9B is the major affected component.

Malf C - This malfunction will trip AFW pump P4 (Terry Turbine) if running, prevent it from being reset using remote  !

function, or come up to speed on its governor when steam is admitted to it. Remaining effects similar to Malf A.

The overspeed trip alarm at C05 (C15) will be received when the malfunctions activated.

The following alarms, key to event diagnosis, will occur  !

as their setpoints are exceeded:

Aux Feed Pp Mtr A Trip / Trouble.

Aux Feed Pp Mtr B Trip' Trouble.

Aux Turbine Driven reed te O ci :eed Trip i

[ Rev: 0 i

\~ Date: 1/31/89  :

j Due to the-loss of one or more aux feed' pumps. Tech.

) Specs.-should be referred to for appropriate LCO action j statement requirements. J, Malfunction removal on the selected failed. pump will allow 1 proper breaker operation or the ability to reset the turbine overspeed trip mechanism. <

REFERENCES:

26002, 26005, 30005,.32012 SH. 11, 32020 SH. 7, 8,J42, 44. {

l 1

I

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i l

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() Rev:

Date:

0 1/31/89 i

1 J_______________ _

1

't i

1 i

(~T MALFUNCTION CAUSE AND EFFECTS

\-)- ]

1

)

-~ Plant: MP2 Malfunction #: FW21 A-AFW HDR 1 FW21 B-AFW HDR 2 d j

l Malfunction

Title:

Aux. Feedwater Pipe Break.

l Malfunction Type: Generic / Variable. Variable: 100% = 1000 gpm 0 'l 1000 psi.

Malfunction Cause: Pipe rupture downstream of aux fw flow element j prior to check valve.

Plant Status: Normal full power operation.

')

Malfunction Effects:

Malf A - This malfunction will result in leakage of auxiliary feedwater into the east piping penetration room and collected in aerated waste drain tank. With AFW being

(]/

s. supplied at a fixed rate to steam generator number 1 the AFW flow indication will increase and the supply pressure I will decrease as severity level is' increase. Effective f i

flow to the steam generator will also decrease. Shutting j of the AFW discharge header isolation valve on #1 header I will permit use of the Aux Feed Pumps un #2 header to SG

  1. 2.

1 Malf B - Effects similar to Malf A except ATW header #2'is the ]

major affected component, i The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Aerated Waste Panel Trouble S/G Level 1/2 High/ Low Due to the aux feedheader break, Tech. Specs. will be referred to to determine appropriate TSAS requirements. i Malfunction removal will restore the selected failed AFW i header to normal.  :

gg

REFERENCES:

26005, 28015.

() Rev:

Date:

0 1/31/89 l

(' MALFUNCTION CAUSE AND EFFECTS

(

Plant: MP2 ' Malfunction #: FW22 Malfunction

Title:

Condensate Storage Tank Leak.

Malfunction Type: Variable. Variable: 100% = 25000 gpm.

Malfunction Cause: Weld Leak at bottom of Tank.

Plant Status: Normal full power operation.

Malfunction Effects:

This malfunction results in leakage from the condensate storage tank-to the storm drains. As the' storage tank level decreases makeup to the condensate surge tank and hotwell will be lost due to'the storage tank low level interlock. Further loss of level will cause the loss'of the normal supply.to the AFW pumps and condensate transfer pump supply to the condensate surge tank and-hotwell.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Condensate Storage Tank Level Hi/Lo Condensate Storage Tank at Minimum Level i Condensate Storage Tank Level Lo Lo 1 Due to the loss of CST inventory, Tech. Specs. will require i referencing for applicable TSAS.

Malfunction removal will stop the condensate storage tank. leakage.

REFERENCES:

25005, 32012 SH. 30.

l

() Rev:

Date:

0 1/31/89

1 l

i l MALFUNCTION CAUSE AND EFFECTS l

Plant: MP2 Malfunction #: FW23 A-P1A FW23 B-PlB i

Malfunction

Title:

Loss of Air to Feed Pump Air Motor.

l Malfunction Type: Generic. l l

l Malfunction cause: Crack in Air Supply Line causes Loss of Air. 1

-l Plant Status: Normal full power operation.

I Malfunction Effects:  ;

i Malf A - Loss of air to the air motor on main feedwater pump A will cause the pump speed to decrease slowly to approximately J 3000 rpm. Control of pump speed with the individual pump controller will be inhibited. The hydraulic jack may be i used to control pump speed along with the MSC from 3,000

(/

(_ to 5,150 rpm. As the failed pumps speed decreases feed header pressure and flows will decrease. The feed regulating valves will open fully in an attempt to maintain steam generator level. If steam generator level is not maintained above 36% a reactor / turbine trip will occur.

l Malf B - Effects similar to Malf A except the air motor on main 1 feedwater pump B will be the major affected component. 1 The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

S/G Level Deviation High/ Low SGFP A (B) Suction Flow Low j Malfunction removal will restore air for the proper operation of the selected failed feed pump air motor.

REFERENCES:

26002, Sys Desc, OP-2321. j

(

-( Rev: 0 Date: 1/31/89 j s

I

I MALFUNCTION CAUSE AND EFFECTS

.O  !

i Plant: MP2 Malfunction #: FW25A(B)

Malfunction

Title:

Main feed line break inside CTMT.

FW25A #1 SG Teed Header  !

FW25B #2 SG Feed Header l

Malfunction Type: Variable,.0-100%, 100% equals 1 x 10' lbm/hr. at '

1000 psig.

I Plant Status: Normal full' power operation. ]

i Malfunction Effects: This malfunction results in an unisolable feed line break, inside CTMT, on the feed header to'the affected SG. )

At 100% severity, feed flow to the affected SG spikes upward.

Post-trip, indicated feed flow ramps downward in response to I throttling by the FRV controller, then goes to zero when MSIS j actuates.

Level in the affected SG swells pre-trip then rapidly drops off-scale low post-trip. Level in the intact SG drops to ~ 10% post-trip and remains due to no feed, (.MEIS), until AFW is actuated.

Pressure in both SG's spike.to ~950 psia on the trip. The affected SG pressure ramps down to < 50 psia in ~3 minutes. . MSIS is' actuated'as its setpoint is exceeded. Pressure in the intact SG bottoms out ~860 psia over the same period.

Tc from the affected SG initially rises due to lack of " cold" feed than ramps down post-trip to bottom out ~490 F when the SG boils dry

~3 minutes later.

Post trip, both Th's and the intact Tc follow the affected~Tc down to bottom out slightly higher, ~500 F. All RCS temperatures will slowly ramp up after the affected SG boils dry.

SIAS is actuated on CTMT pressure ~15 seconds after the break occurs, i then peaks ~18 psig in ~3 cinutes, then slowly decreases. CTMT' temperature rises to >200*F in ~1 1/2 minutes then. slowly increases to l ~215 F.

Pzr level and pressure both decrease post-trip. Pzr pressure bottoms

~1200 psia when the affected SG boils dry then slowly recovers. Pzr level bottoms ~0% in ~3 minutes, then rapidly increases due to RCS heatup after the affected SG has emptied.

Rev: 0 rO Date: 3/1/89

The emergency CTMT sump shows a slow small increase as the escaped steam is condensed.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

"Pzr Press. Lo-Lo A(B,C,D)" j "Stm Gen. Press. Lo-Lo A(B,C,D)" .1 "SIAS Actuation Sig. CH 1 (2) Trip" "MSI Actuation Sig. CH 1 (2) Trip" "Pzr CH X (Y) Level Lo-Lo" )

" Steam Generator 1 Level Hi/Lo" q

" Steam Generator 2 Level Hi/Lo" J l

Operator action required to mitigate the accident includes securing 2 )

RCP's at 1600 psia pzr pressure, preventing auto aux feed addition to  !

the affected SG and securing the remaining 2 RCP's if SCM decreases below 30"F. Operator action will be required to prevent PTS, including the following: ,

- Prevent RCS reheat by opening the ADV on the intact SG.

- Securing or throttling HPSI as conditions permit.

Restoring letdown.

- Reestablishing pzr pressure control.

Removal of the malfunction stops leakage from the affected feed header  !

which stops the RCS cooldown and/or allows restoration of normal feed to the affected SG.

Introduction of FW25A(B, ht lesser severities will cause similar effects with the following exceptions: )

- SG blowdown will take longer, RCS temperatures and pzr level and pressure will bottom out at lower values. CTMT temperature and i pressure will rise more slowly, but peak at higher values.

- At low severities, RCS temperatures and pressures are only slightly affected. A plant trip is generated by low SG level.

REFERENCES:

P&ID 26005, CEN 128 Case B5A O Date:

Rev: 0 3/1/89

, ]

)

I i

1 i

("] MALFUNCTION CAUSE AND EFFECTS l

\_/ {

.l Plant: MP2- Malfunction #: FW26 A-P9A B-P9s l

C-P4 l

Malfunction

Title:

Aux. Feed Pump Dischg valve closed.

Malfunction Type: Generic.

1 Malfunction Cause: AFW pump manual discharge valve inadvertently closed. j

-j Plant Status: Normal full power operation.

Malfunction Effects:

Malf A - Malfunction insertion will result in the immediate closure of 2-FW-9A on AFW pump 9A. The pumps discharge pressure will increase to its shutoff head value. Pump motor l current indication will decrease. The pump will not be

[ able to be used as a source of AFW to either steam ]i generator.

Malf B - Effects similar to Malf'A except that AFW pump 9B is the major affected component.

Malf C - Effects similar to Malf A except that AFW pump 4 is the i major affected component.

i The following alarms, key to event diagnosis, will occur as their setpoints are exceeded: 1 None Due to the inability to feed via affected AFW pump, Tech.

Specs. will require referencing applicable LCo's. -l Malfunction removal will reopen the selected failed AFW' pump discharge valve.

REFERENCES:

26005, i

() Rev:

Date:

0 1/31/89

i l

)

i

~

MALFUNCTION CAUSE AND: EFFECTS i

Plant: MP2 Malfunction #: FW27 A - HDR A i FW27 B - HDR B l

)

Malfunction

Title:

FW line break in Turbine Building. l Malfunction Type: Generic / Variable. Variable: 100% - 6 x 10(6).  ;

lbm/hr 0 1000 psi.-

]

Malfunction Cause: Leak' located just downstream of main feed flow  !

element.  !

l l

Plant Status: Normal full power operation. j l

Malfunction Effects: l Malf A - This malfunction will cause a.feedwater line leak from header A into the turbine building. .The subcooled liquid

(} will be collected in the condenser pit.

Indicated feed flow to the No. 1 steam generator will increase but the actual-feed flow to the affected  ;

generator will decrease. Feed header pressure will I 4

decrease thus affecting the flow into steam generator No.

2. Steam generator levels will decrease to cause a reactor trip if feed flow cannot be maintained.

reedwater mass loss through the ruptured line will ,

continue as long as the header is pressurized. j i

9 Auxiliary feedwater may be used to recover level in the steam generators, if a reactor trip occurs.

Malf B - Effects similar to Malf A except feedwater header A within j the turbine building is the major affected component.

i The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Cond Pit Sump A (B) Lvl Hi RC Loop 1 Cold Leg Temp Hi ,

RC Loop 2 Cold Leg Temp Hi l SG Lvl Deviation Hi Le (h Rev:

Date:

0 1/31/89 j i

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ . . _ _J

j i

j

! Malfunction removal will stop the leak on the selected failed feedwater header.

REFERENCES:

26005. l J

j l

I 1

l l

I O-Rev:

Date:

0 1/31/89 I

L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i

/s MALFUNCTION CAUSE AND EFFECTS N.,] ,

1 I Plant: MP2 Malfunction #: FW28 ,

1 Malfunction

Title:

Heater Drain Tank Normal Level Control Valve Failure.

Malfunction Type: Variable. Variable: 100% = full open.  ;

Malfunction cause: Discharge control valve (LC5063) fails at selected position.

Plant Status: Normal full power operation.

Malfunction Effects:

This malfunction results in failure of the heater drains tank normal level control valve. Failure of the valve at a position greater than normally maintained will result in opening of its normal level control valve to lower heater drain tank level. Heater drain pump

(~')

(_/ flow will initially increase. If level drops below 12% the heater drains pumps will be automatically tripped off.

If the selected position to be maintained is less than normal, the normal level control valve will close to raise level. Heater drain pump flow will initially drop. Higher levels may be maintained by modulation of the high level dump valve. Total loss of heater drains flow to the feedwater header at full power will result in inadequate feed pump suction flow.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Htr Drain Tk Level Hi/Lo Heater Drain Pump Trouble Malfunction removal will restore normal heater drain tank level control to normal.

REFERENCES:

26004/OP-2320.

[~')

(> Rev: 0 Date: 1/31/89

I ') - MALFUNCTION CAUSE AND EFFECTS

\~/ ,

Plant: MP2 Malfunction #: FW29 A - #1A Heater i FW29 B - #1B Heater j l

Malfunction

Title:

High Pressure Feedwater Heater Tube Rupture.

1 Malfunction Type: Generic, Variable. Variable. 100% = 150% of l individual heater dump capability.

t.cifunction Cause: Tube Failure.

Plant Status: Normal full power operation. i

,l l

Malfunction Effects:

Malf A - This malfunction results in a reduction of feedwater flow due to leakage into the "chell" side of high pressure feedwater heater lA. Condensate header flow will increase iO' while its pressure decreases. As the severity level is increased the heaters normal level and high level dump will open.

If the total mass entering the heater exceeds the capacity of the dump valves the heater level will continue to rise.

Hi level in the heater will shut its associated motor operated extraction steam isolation and check valves. At i this time the heater will fill until solid and its relief i valve will actuate. Plant efficiency will decrease due to ]

the inoperable heater. l Malf B - Effects similar to Malf A except HPFW heater #1B is the major affected component.

The following alarms, key to event diagnosis, will occur ,

as their setpoints are exceeded: l FW Htr lA/lB Lvl Hi Malfunction removal will stop the tube leak on the ,

selected failed high pressure feedwater heater. -'

('

REFERENCES:

26004, 26005

(_]/ Rev: 0 Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant:- MP2 Malfunction #: IA01-Malfunction Tit _le: Instrument Air Header Rupture.

Malfunction Type: Variable 100% - 1500 scfm at 100 psi.

Malfunction cause: Unisolable Air Leak Downstream of IA Filter L216.

Plant Status: Normal full power.

Malfunction Effects: Note: This malfunction should only be.used with the "C" IAC not available'in order to have nystem pressure decrease significantly.

Malfunction insertion will cause an unisolatable instrument air leak. Instrument air header pressure will decrease at a rate

/* proportional to the difference between the

' severity' level and the available system capacity. The standby instrument air compressor.will start in an-attempt to restore system pressure. As pressure continues to drop station air will automatically crossconnect with instrument air and,its header will be isolated and slowly bleed.down.

The' severity level at its maximum value will-exceed the plant compressor capability.

As iret. air pressure continues to decrease, plant air operated valves not fit with individual accumulators will move to their failed positions. The plant systems will accurately respond to these valve failures.

Plant will trip on low S/G levels due to SGF Pp flows _ decreasing by SGP Pp speed de-creasing,'HD system flow decreasing, and SGF Pp suction pressure decreasing.

A crossconnect air supply remote function from' Unit 1 station air may be used to mitigate the effects of this malfunction.

0-O Rev:

Date: 1/31/89

( :-}

'O.

()

~

Malfunction removal,will stop the source of leakage thus allowing..the system to be.

repressurized.

The following alarms.will be received:

Low Instrument Air. Pressure Low Turbine Bldg. Air Pressure l

' Low Ctmt Instrument Air Pressure )

'2 The following major components will be.

effected by loss of. Instrument Air:

1. Containment ~ Bldg: see IA03-l 2. Aux Bldg'-, Charging / Letdown /Make-up.

Atmospheric Dump Valves, RBCCW FCV's l

j

3. Turbine Bldg - Main Feed. Reg Valves, Feed' Reg Bypass. Valve,'SGF Pp speed controls,  ;

turbine bypass / Steam Dump Valves. ]

1

REFERENCES:

26009, 32017, AOP.2563.

O .

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Rev: 0 j

l Date: 1/31/89  :

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j 1

g- MALFUNCTION CAUSE AND EFFECTS f

~

%/

l Plant: MP2 Malfunction #: IA02A F2 (Station Air l Compressor)

IA02B F3A ("A" Inst Air Compressor)

IA02C F3B ("B" Inst Air Compressor)

IA02D F3C ("C" Inst Air Compressor)

Malfunction

Title:

Air Compressor Trip. l Malfunction Type: Generic..

Malfunction Cause: ' Loss of Compressor Cooling. (IA02A,B,C) Motor' ]

Overload (IA02D). l 1

Plant Status: Normal full power. i

,/ Malfunction Effects: i Malf A - This malfunction will cause a loss of TBCCW cooling to the station air compressor. The compressor will continue to run until it is shutdown on high discharge temperature (approx 2 minutes). If the compressor is started ~with this malfunction already inserted it will run for approximately 2 minutes before shutting down. The compressor will not be able to be restarted until the compressor has cooled off.

The station air header pressure will decrease resulting in a loss of air to the intake air eductor and backup air supply to containment instrument air. .

Unit 1 station air (remote function) may be used as a backup source.  !

The following alarms may be received:  !

SAC Aft Clr Temp Hi Station Air Hdr Press Lo Malf B - Effects si,milar to Malf A except instrument air' compressor F3A is the major affected component. IAC F3C or IAC F3B will restore instrument header pressure if started as will the station air compressor if the system is crossconnected.

[~\ $ Rev: 0

(/ Date: 1/Sl/89 l

1 l

Malf C - Effects similar to Malf B.

Malfunction removal will restore proper cooling ability to i the selected failed a.'r compressor. J Malf D - This malfunction will cause "C" Instrument Air compressor motor overloads to open resulting in motor trip. The compressor will not restart with malfunction inserted. IAC F3A.and/or F3B will restore instrument air header pressure  ;

if started. F3C compressor will not restart until reset l with remote function after the malfunction has been removed. j i

The following alarms may be received:

i Inst Air Comp C & Dryer Trouble

Reference:

26007, 26008, 32017 i

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() Rev:

Date:

0 1/31/89

t' MALFUNCTION CAUSE AND EFFECTS k

Plant: MP2 Malfunction #: IA03 l

l Malfunction

Title:

Loss of Instrument Air in Containment Malfunction Type: Variable 100% - 300 SCFM leak @ 100 psi Malfunction cause: Unisolable air leak on Containment Instrument Air I Receiver j 1

Plant Status: Normal full power.

Malfunction Effects: )

This malfunction will cause an instrument air leak into the containment. The standby IAC may start and station air will automatically crossconnect in an attempt to maintain instrument air header pressure. Isolation of the containment instrument air supply lines will allow the instrument air header to maintain pressure.

('A Containment air operated valves will move to their failed position as the containment air header pressure decreases.

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The following alarms may be received:

Instr Air Hdr Press Lo Station Air Hdr Press Lo Ctm Air Receiver Press Lo The following major components in Ctmt will be affected by loss of air.

1. 2-EB-88 and 2-EB Ctmt Radmonitor Isolation Valves close
2. 2-CH-506 RCP Seal Bleed Off Isolation Close
3. 2-CH-507 RCP Seal Bleed Off Relief Valves Open
4. Both Pzr Spray Valves Close
5. 2-CH-515 and 2-CH-516 Letdown Isolation valve Close
6. Approx 7 cycles of air in the accumulators for aux spray and both charging header loop stop valves.

Malfunction removal will stop the air leak on the containment air receiver.

REFERENCES:

26009, 32017 Rev: 0 I\') Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: 3A04A 2-FW-51A 2A04B- 2-FW-51B Malfunction

Title:

Loss of Instrument Air to Feed Regulating Valves.

Malfunction Type: Generic.

Malfunction Cause: IA pressure sensor' switch. failure causing lock-up of FRV's by de-energizing air isolation solenoids.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will hold feed regulating valve'at its-position regardless of the feedwater control demand signal.

The valve will shut if a main steam isolation signal or high-level downcomer level signal is developed.

The following alarm will be received:-

Feedwater Regulating Valve 1 Locked Malf B - Effects similar to Malf A except FRV 2 is-the major affected component.

Malfunction removal will restore the faulty instrument air pressure sensor switch on the selected failed feed regulating valve.

Reference:

26005, 32012 SH. 31

-( ) Rev:

Date:

0 1/31/89

1

T MALFUNCTION CAUSE AND EFFECTS NY Plant: MP2 Malfunction #: IA05 Malfunction

Title:

Instrument Air Header Rupture in Turbine Building.

Malfunction Type: Variable. 100% = 300 SCFM at 100 psi.

I Malfunction Cause: Header leak downstream of 2-IA-25.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will cause an instrument air leak into the turbine building. The standby instrument air compressor may start and l' station air will not automatically crossconnect due to a flow limiting orifice. The rate of leakage will be within the capacity

. of the plants air supply capability providing that sufficient air compressors are operable.

(s)

If instrument header pressure cannot be maintained due to inoperable air compressors the containment instrument air header may be kept ,

pressurized by crossconnecting it with station air through  !

2-SA-23.1.

With instrument air isolated or depressurized in the turbine building associated valves in the turbine building will shift to their fail position as a function of their air supply pressure.

The major effect will be the loss of MSR drains to the Heater Drains Tank and the loss of flow to the SGFP suctions due to this decrease in heater drains flow. The HDTK level control valves has back up air so they will not be effected by closing 2-IA-25. Plant could trip if there is no operator actions to restore SGFP flow and D/P.

Alarms received:

Low Turbine Bldg Air Pressure.

Malfunction removal will stop the turbine building instrument air header leakage thus allowing the system to repressurize.

REFERENCES:

26009 m

Rev: 0

('~') Date: 1/31/89

a l.

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: MS01A(B) 1 Malfunction

Title:

Unisoleble main steam line rupture on the affected steam generator inside CTMT.

MS01A. SG.#1 MS01B SG #2 Malfunction Type: Variable, 0-100%, 100% equals 1.9 x 10' lbm/hr-at- l l

1000 psia. )

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l Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in a rupture.inside-CTMT on the steam header from the affected SG. l At 100% severity, level in the affected SG spikes upward due to' swell then rapidly drops to offscale low in approximately one. minute. ;A reactor trip'is generated on SG level. Level in the intact.SG drops l

() rapidly post-trip to <20%.

Pressure in the affected SG drops to <100 psia in approximately 2 j

minutes then slowly ramps toward CTMT pressure. An MSIS is generated.

as the pressure decreases below 500 psia.

Pressure in the intact SG drops rapidly until MSI occurs then decreases steadily to approximately 500 psia.. g All RCS Th and Tc temperatures rapidly decrease to approximately'460*F with Tc from the affected SG-leading and spiking lower.than Tc from the intact SG. If RCP's are secured, a large delta T will develop with Tc from the affected SG being significantly lower than all'other RCS temperatures.  ;

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RCS shrinkage drops pzr level to 0% indicated in approximately one 1 minute and will remain offscale for approximately 2 minutes, then rapidly increases.

Pzr pressure drops rapidly.during the SG blowdown phase.(approximately 1 1/2 minutes) to bottom out approximately 600 psia then slowly r'3 Cove r s .

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Date:

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Containment conditions rapidly increase to indicate a large high CTMT pressure energy fluid leak with no indications of activity.

increases to >25 psig over several minutes. CSAS initiates spray, however maximum CTMT pressure is only slightly above the setpoint and CSAS may be avoided due to prompt operator action. CTMT temperatures follow the pressure increase with a Psat/Tsat relationship.

RCS Th SCM spikes to approximately 90* r then drops with pzr pressure decrease to approximately 10 F then increases as pzr pressure recovers. The RVLMS will not indicate a vessel head problem unless HPSI flow is unavailable or inadequate.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

"Pzr Press. Lo-Lo A(B,C,D)" l "Stm Gen. Press. Lo-Lo A(B,C,D)" I "SIAS Actuation Sig. CH 1 (2) Trip" "CSAS Actuation Sig. CH 1 (2) Trip" "MSI Actuation Sig. CH 1 (2) Trip" "Pzr CH X (Y) Level Lo-Lo"

" Steam Generator 1 Level Hi/Lo"

" Steam Generator 2 Level Hi/Lo" i

operator action required to mitigate the accident includes securing 2 RCP's at 1600 psia pzr pressure, preventing auto aux feed addition to j g) the affected SG and securing the remaining 2 RCP's if SCM decreases

(,,e below 30 F. Operator action will be required to prevent PTS, l I

including the following:

- Prevent RCS reheat by opening the ADV on the intact SG.

Securing or throttling HPSI as conditions permit.

Restoring letdown.

- Reestablishing pzr pressure control.

This malfunction is unrecoverable. Simulator reinitialization will be i required to clear its effects.

Introduction of MS01A(B) at lesser severities will cause similar effects with the following exceptiens:

- SG blowdown will take longer which will cause greater RCS cooldown at intermediate severities.

At low severities, reactivity feedbacks and the turbine throttle j pressure limiter will prevent excessive RCS cooldown and depres- j surization. RPS trip and SIAS actuation will occur on CTMT pressure.

REFERENCES:

P&ID 26002, CEN 128 Case A4D.

[~)

Rev: 0 L/ Date: 3/1/89 1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i

e~s MALFUNCTION CAUSE AND EFFECTS

(_)

Plant: 'MP2 Malfunction #: MS02A(B)

Malfuncti$nTitle: Unisolable main steam line rupture on the aff'ected steam header outside CTMT.

MS02A SG #1 ,

MS02B SG #2 i

Malfunction Type: Variable, 0-100%, 100% equals 1.9 x 10' lbm/hr at 1000 psia. ,

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Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in a rupture outside CTMT on the steam header from the affected SG.

At 100% severity, level in the affected SG spikes upward due to swell then rapidly drops to offscale low in approximately one minute. A reactor trip is generated on SG level. Level in the intact SG drops O. rapidly post-trip to <20%.

1 l

Pressure in the affected SG drops to <100 psia in approximately 2 l minutes then slowly ramps toward CTMT pressure. An MSIS is generated 1 as the pressure decreases below 500 psia.

Pressure in the intact SG drops rapidly until MSI occurs then  !

decreases steadily to approximately 500 psia. l All RCS Th and Tc temperatures rapidly decrease to approximately 460 F with Tc from the affected SG leading and spiking-lower than Tc from 4 the intact SG. If RCP's are secured, a large delta T will develop- l with Tc from the affected SG being significantly lower than all other RCS temperatures.

RCS shrinkage drops pzr level to 0% indicated in approximately one minute and will remain offscale for approximately 2 minutes, then rapidly increases.

i' Pzr pressure drops rapidly during the SG blowdown phase (approximately 1 1/2 minutes) to bottom out approximately 600 psia then slowly recovers.

Enclosure building 6P spikes off-scale high and remains high throughout the event.

Rev: 0 O. Date: 3/1/89

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l RCS Th SCM spikes to;approximately 90 F then drops with pzr pressure q decrease to approximately 10 F then increases as pzr pressure i recovers. The RVLMS will not indicate a vessel head problem unless HPSI flow is unavailable or inadequate.

The'fo11owing alarms, key to event diagnosis, will occur as their setpoints are exceeded:

"Pzr Press. Lo-Lo A(B,C,D)"

"Stm Gen. Press. Lo-Lo A(B,C,D)"

'"SIAS Actuation Sig. CH 1 (2) Trip" "MSI Actuation Sig. CH 1 (2) Trip" q "Pzr CH X (Y) Level Lo-Lo" ,

" Steam Generator 1 Level Hi/Lo"

" Steam Generator 2 Level Hi/Lo" Operator action required to mitigate the accident. includes securing 2 i RCP's at 1600 psia pzr pressure, preventing auto aux feed addition to 1 the affected SG and securing the remaining 2 RCP's if SCM decreases f below 30 F. operator action will be required to prevent PTS, including the following: 3

- Prevent RCS reheat by opening the ADV on the intact SG.

Securing or throttling HPSI as conditions permit. l Restoring letdown.

- Reestablishing pzr pressure control. ]

?. \

Removal of MS02A(B) will stop steam leakage from the affected header.

Pressure in the affected SG will increase if the SG has not fully emptied.

Introduction of MS02A(B) at lesser severities will cause similar effects with the following exceptions:

SG blowdown will take longer which will cause greater RCS cooldown at intermediate severities.

- At low severities, reactivity feedbacks and the turbine throttle pressure limiter will prevent excessive RCS cooldown and depressurization.

REFERENCES:

' P&ID 26002, CEN 128 Case A4D.

Rev: 0 Date: 3/1/89

a i

I

. ,r y MALFUNCTION CAUSE AND EFFECTS

\

Plant: MP2 Malfunction #: MS03 Malfunction

Title:

Main steam line rupture in the turbine building.

Malfunction Type: Variable, 0-100%, 100% equals 1 x 10' lbm/hr. at

.1000 psig.

)

Plant Status: Normal full power operation.

1 Malfunction Effects: This malfunction results in a rupture on the-main steam header in the turbine building. The location of the break makes the effects common to both SG's.

Reactivity feedback from the cooldown and the increased aT cause ,

Q-power to increase to the RPS trip setpoint in ~30 seconds. The value of Q-power remains relatively high until MSI occurs.

At 100% severity, level in both SG's. ramp downward then drop to-off-scale low ~30 seconds post-trip.

Both SG pressures ramp down to the MSIS setpoint in ~4 minutes, bottoming out < 500 psia, then slowly recovering after MSI occurs.

RCS temperatures rapidly drop, led by Tc, to bottom out ~470 F Tc and

~490 F Th. All temperatures recover slowly after MSI occurs.

Pzr level ramps off-scale low in ~3 minutes as the RCS contracts due to overcooling. Approximately one minute later, pzr level rapidly increases as HPSI injects.

Pzr pressure decreases pre-trip, then drops sharply post-trip to ~1000 ,

psia. SIAS is initiated as the low pzr pressure setpoint is exceeded. l Pzr pressure will recover' slowly after MSI occurs and HPSI injects.  !

Th SCM slowly increases pre-trip, spikes up when the plant trip occurs, then rapidly drops to ~0 F. SCM slowly increases as pzr pressure recovers.

The RVLMS will briefly indicate the presence of a vessel head bubble while the SCM is ~0 F, then return to 100% indicated as pzr pressure increases.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded: I Rev: 0 Date: 3/1/89

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( 4 "Pzr Press. Lo-Lo A(B,C,D)" l "Stm Gen. Press. Lo-Lo A(B,C,D)"

"SIAS Actuation Sig. CH l (2) Trip"

" Condenser Pit A (B) Sump Level Hi" l "MSI Actuation Sig. CH 1 (2) Trip" "Pzr CH X (Y) Level Lo-Lo"

" Steam Generator 1 Level Hi/Lo"

" Steam Generator 2 Level Hi/Lo" Operator action required to mitigate the accident includes securing 2 RCP's at 1600 psia pzr pressure, and securing the remaining 2 RCP's if )

SCM decreases below 30 F. Operator action will be required to prevent PTS, including the following-1

- Prevent RCS reheat by opening the ADV's.

- Securing or throttling HPSI as conditions permit.

Restoring letdown.

- Reestablishing pzr pressure contcol.

Introduction of MS03 at lesser severities will cause similar effects of a lesser magnitude, with the following exceptions:

g

(_) -

At lesser severities the RVLMS will not indicate a vessel head level problem unless HPSI is inadequate or unavailable.

- At low severities the turbine throttle pressure limiter will maintain SG pressure above the MSIS setpoint by throttling closed on the CV's and SG levels will stabilize at lower values due to the FRV control system response.

Closure of the MSIV's effectively terminates the RCS and SG cooldown.

Removal of the malfunction stops leakage from the main steam header.

This may be used at low severities to simulate isolation of a ruptured steam drain, vent, or other isolable, connected line.

REFERENCES:

P&ID 26002, CEN 128 Case A4H

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[(_/') Rev:

Date:

0 3/1/89

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1 j"*wg MALFUNCTION CAUSE'AND EFFECTS V

' Plant: MP2 ' Malfunction #: MSO4:

A - 2MS79A B - 2MS79B Malfunction

Title:

- MSR Second Stage Pressure Control Valve Failure.

Malfunction Type: Generic. ,

Malfunction'Cause: valve mechanically failed open. j i

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will fail open'the' moisture separator reheater lA second stage 1 pressure control valve. Second _;

stage steam flow, temperature, and pressure .will : increase.  ;

s_,

Moisture separator. reheater 1A outlet ~ temperatures and-pressures to the' low pressure turbines will increase.

The increased steam flow will cause steam header pressures .

and temperatures to decrease leading to-a drop in the RCS l average temperature. With a negative 1MTC this-is a  !

positive reactivity addition and power will increase.- ,

The effects of this malfunction will decrease at higher l power levels as this valve is normally open. If the valve is failed open and the MSR steam supply isolation fails to shut following a plant trip, excessive.cooldown may occur. j The following alarm may be received:

LP Turb A/B Stm Hi Delta T.

Malf B - . Effects similar to Malf A except MSR 1B second stage pressure control valve will be.the major component affected- -

Malfunction removal will restore proper operationLof the selected failed MSR second stage pressure control valve.

L l-f- .

REFERENCES:

26002, OP-2317.

( Rev: 0-Date: 1/31/89 l 1

r~' MALFUNCTION CAUSE AND EFFECTS i N~)N Plant: MP2 Malfunction #: MS 0 5 -

A - 2MS2A I B- 2MS2B i

'l Malfunction

Title:

2nd Stage MSR Steam Supply Isolation Valves Fail  !

Open. ]

i Malfunction Type:- Generic.

l.

Malfunction cause: Valve mechanically failed open.

Plant Status: Plant Trip from Full. Power.

i Malfunction Effects

  • Malf A - This malfunction will prevent the reheater steam source valve to MSR #1 (2-MS-2A) from shutting'once it is.in its fully open position. The valve will not fail open if it  ;

starts out shut.  ;

(~)T

%. i When the plant is tripped this valve will remain open (usually closes automatically at less than 10 psig in MSR No. 1B) resulting in continued steam flow through MSR No.

lA second stage tube bundle. MSR No. lA high load valve J will shut and its low load valve will shut.

This malfunction by-itself will not lead-to any signif-icant cooldown. If the MS malfunction to fail a second stage drain tank level control valve open is utilized blow through of steam to the condenser after the 2nd stage drain tank empties out will cause additional plant cooldown. l Malf B - Effects similar to Malf A except that the reheat steam source valve to MSR No. 1B (2-MS-2B) will be the major affected component.

The effects of this malfunction will be dependent on mode of low and high load control valves and their valve position. If the low load valves is placed in manual control it may be fully shut to stop the steam flow.

REFERENCES:

32020 SH. 3, 6, 37, 38, System Dese, OP-2317 l

Rev: 0 Date: 1/31/89 .;

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MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: MS06 A - 2MS64A' B - 2MS64B Malfunction

Title:

. Spurious MSI Closure.

Malfunction Type: Generic.

I

. . l Malfunction Cause: Spurious MSI Signal.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - The main steam isolation valve on the #1. header will-immediately shut.on malfunction insertion resulting.in an .

immediate stop in steam flow from S/G #1. Its pressure ]

O- will rise and be limited by its associated safety valve actuating. Its level will shrink and'its feedwater control valve will shut in response to.the reduced steam flow.

The steam flow from S/G #2 will increase in an attempt to maintain the same total steam flow. This will cause a drop in its pressure with resulting level swell.

l The RCS average temperatures will increase due to the warmer water in the isolated steam generator loop.

.The initial increase in RCS avarage temperature will cause pressurizer level and pressure to increase. The' net turbine electrical load will decrease due-to lower main steam line g essures and the turbine-control makes closing due to the throttle pressure limiter operation.

The following alarms will actuate when their setpoints are exceeded:

Steam Generator 1/2 Hi/Lo Level Tave-Tref Hi/Lo.

TM/LP High Pzr Press High Rev: 0 O- Date: 1/31/89 c--____---____-__________-__- -__ __- - _ _ _. ._ _ _ _ _ - _

1

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() Control board indications are:

Steam Generator 1 Steam Flow Decreases Steam Generator 2 Steam Flow Increases j RCS Average Temperature Decrease Reactor Power Levels Initially Increases Pressurizer Level and Pressure Decrease Main Steam Line Pressure Decreases

' Turbine Electrical Output' Decreases.

The reactor will trip due to high pressurizer pressure or j an TM/LP. TM/LP setpoint increase is due to the high RCS 1 cold leg temperature and~the high pressure is due to the i high RCS Tavg and resulted RCS swell.

Malf B - The effects of this malfunction will.be similar to Malf A with the main steam isolation valve on the #2r header being the affected component. .

Malfunction removal will allow.the-selected failed MSIV to be opened provided an actual MSI does not exist ~and the.  !

differential pressure across the valve is minimized.

i

REFERENCES:

26002, 32020 SH. 18, FSAR Vol. 14 Para. 14.8.  !

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MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: MS07.

A - 2MS247 B - 2MS239 i Malfunction T'itle: Main Steam Generator Safety Valve Failure. l l

Malfunction Type: Generic / Variable. 100% equals 795,000 lbm/hr.at: j 1000 psia. l

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Malfunction Cause: Safety Valve Spring Failure.

Plant Status: Normal full power. 'i Malfunction Effects:

Malf A - This malfunction will. result in steam genera' tor.#1 leakage i

(~' to atmosphere from a. spring loaded safety valve. The resulting leakage will cause an increase in. steam flow by

(

both steam generators, causing a decrease in their 4 pressure. Instantaneous high severity leaks will cause swell characteristics to be observed within the steam generator. S/G Safety Valve Tech specs will be impacted. j i

The increased steam flow will cause-a reduction in the RCS average temperature leading to lower pressurizer level and pressure. The reactor power level will increase possibly ,

leading to a variable over power reactor trip. The ~j reduced steam line pressure will cause the generator electrical output to decrease.

Control board indications are:

Increased Steam Flow Decreased Steam Generator Levels and Pressures Decreased RCS Average Temperatures Reactor Power Change Decreased Pressurizer Level and Pressure Decreased Electrical Power Output.

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-O\d Rev: 0 l Date: 1/31/89

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The increased steam flow'after a trip will cause a cooldown rate as'a function of the malfunction severity.

Malf B - The effects of this malfunction.will be similar to Malf A with 2-MS-239 being'the affected component on main steam generator #2.

Malfunction removal will allow the' selected failed safety'  : l relief valve to operate properly.

REFERENCES:

26002, MS Sys Desc.

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1 MALFUNCTION.CAUSE AND EFFECTS l

-l Plant: MP2 Malfunction #: MS08 Malfunction

Title:

Gland Seal Regulator Failure. j l

Malfunction Type: Variable. 100% equals 20 psig setpoint. ,

I Malfunction cause:- Valve controller failure.

l Plant Status: Hot Standby.

Malfunction Effects:

This malfunction, depending on severity level, will either' cut off  ;

the main steam supply to_the gland seal supply header or continue to supply steam at a higher pressure than needed.

At minimum severities of this malfunction, the steam seal feed regulating valve will shut causing gland steam pressure to decrease. i The loss of gland sealing steam will cause a loss of condenser vacuum. The effects may be limited by operation of the steam seal motor operated bypass valve.

With this malfunction inserted at high severities, steam pressure will increase and be limited by the direct acting steam seal dump l valves. The rise in presnure will be limited to 5 psig. Steam seal i exhaust vacuum will decrease but may be controlled by starting an additional gland seal exhauster or throttling open a gland seal exhauster discharge valve.

The following alarms will actuate when their setpoints is exceeded:

Steam Seal Header Press.Hi/Lo Steam Packing Exhauster Press Hi.

Control board indications are:

Steam Seal Header Pressure Steam Seal Exhaust Header Vacuum.

() Rev:

Date:

0 1/31/89

_-_- __--______._ _ a

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l At power levels greater than approximately 50%.this malfunction will have'no effect on gland seal steam pressure, i

Malfunction removal will restere the operation of the gland seal regulator to normal.

REFERENCES:

26006, 32016 SH. 1 thru 7,'28500 SH. 520 l

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i Rev: 0 Date: 1/31/89 .

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.e"'s MALFUNCTION CAUSE AND EFFECTS l V

Plant: MP2 Malfunction #: MSll A-2-ES-77B (4A) D-2-ES-77C (3B) G-2-ES-80B (lA)

B-2-ES-77A (4B) E-2-ES-77F (2A) H-2-ES-92 (lB) l C-2-ES-77D (3A) F-2-ES-77E (2B) l Malfunction

Title:

Extraction Steam Motor Operated Isolation Valve  !

Inadvertently Shuts. j 1

l Malfunction Type: Generic. l I

Malfunction Cause: FW Heater High Level Contact Fails. .

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1 Plant Status: Normal full power.

Malfunction Effects:

/~} Malf A - This malfunction when inserted will cause a loss of i

(_) extraction steam to low pressure feedwater heater 4A. Its I motor operated extraction steam supply valve will shut.

Its extraction steam bypass valve to the condenser will  ;

open and associated bleeder trip valve will shut on l turbine trip or high heater level. l I

Loss of extraction steam will result in a decrease in the temperature of the feedwater leaving this heater.

Pressure on the shell side of the heater will decrease. l the lower feedwater temperature will be fed through the j rest of the feed train and into the steam generators. l This will result in reactor power level increasing '

depending on the amount of feed temperature reduction. l Loss of heater drains flow ' rom heater 4A into heaters SA, 6A and the drains cooler wi4 . result in lower feedwater '

outlet temperatures on these heaters.

Malf B Effects similar to Malf A except that the extraction steam through source valves and respective heaters as listed above in H- the generic components may be individually affected.

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[) Rev: 0 1/31/89

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Malfunction removal will allow the selected failed feedwater level switch to operate. properly. If-the respective heater level is low enough the bleeder-trip valve will reopen and the steam bypass valve will shut.

REFERENCES:

26004, 26003, 32010 SH. 1-20.

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1 MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: MS12 l

i Malfunction

Title:

Steam Leak into Containment.

Malfunction Type: Variable. 100% - 5 x 10' ***/hr at 1000 psid.  !

i Malfunction Cause: Main Steam Generator-#1 Vent Line Leak.

Plant Status: Normal full power.

Malfunction Effects:

Insertion of this malfunction will result in a relatively small steam line leak to the containment from #1 main steam header.- The increased steam flow will cause containment pressure, temperature, and humidity to slowly rise. The containment sump level will ,

increase to reflect the accumulation of the condensed steam by 1'

('N containment air cooling units. Plant overall efficiency will be reduced as indicated by an increase in net thermal output to maintain the same generated electrical output. Reactor trip on high j containment pressure is ~ 20 minutes at 100% severity. 1 Control board-indications are: l Containment Pressure, Temperature and Humidity Rise Slowly Containment Normal Sump Level Increases, Plant Efficiency Reduced Malfunction removal will stop the. steam leak on #1 main steam header.

REFERENCES:

26002  ;

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f Rev: 0 Date: 1/31/89 iI

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: MS13

.. A-MSRDT 1A C-MSR1DT 1A E-MSR2DT 1A B-MSRDT 1B D-MSRIDT 1B F-MSR2DT 1B Malfunction

Title:

MSR Operator Drain Tank Normal Level Control Failure. )

Malfunction Type: Generic / Variable. 100% equals 100% open.

Malfunction cause: Valve positioner fails valve at selected severity. 1 Plant Status: Normal full power.

l Malfunction Effects:

Malf A - Insertion of this malfunction will fail the normal level ,

A control valve on MSR drain tank No. lA at the selected j severity. I If the valve is failed shut the drains flow to LP I feedwater heater 2A from this tank-will stop, resulting in f a loss of efficiency of the heater. reedwater temperature will decrease slightly. The drain tank level will increase to cause its level to be controlled by its high  !

level dump.

If the valve is failed open MSR drain tank No. lA will empty resulting in steam passing directly through to LP.

feedwater heater 2A. Overall turbine efficiency should decrease slightly as less steam is produced for LP turbine usage. Feedwater outlet temperature from heater 2A will increase slightly.

The following alarm (s) will be received:

MOIST SEP Drn Tk 1A Lvl Lo.

Malf B - Effects similar to Malf A except that MSR drain tank No.

1B normal level control valve and drains flow to heater 2B will be the major affected components.

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() Rev:

Date:

0 1/31/89

(d s Malf C - Effects similar to Malf A except that moisture separator first stage reheater drain tank No. lA normal level control valve and drains flow to feedwater heater lA will be the major affected components and the steam isolation valve will close on high level.

Malf D - Effects similar to Malf A except that moisture separator first. stage reheater drain tank No. 1B normal level control valve and drains flow-to feedwater heater 1B will be the major affected components.

Malf E - Effects similar to Malf A except that moisture separator second stage reheater drain tank No. lA normal level control valve and drains flow to feedwater heater lA will be the major affected components.

Malf F - Effects similar to Malf A except that moisture separator second stage reheater drain tank No. 1B normal level control valve and drains flow to feedwater heater 1B will be the major affected components.

Malfunction removal will restore normal control of the selected failed MSR drain tank level control valve.

REFERENCES:

26003 l

t l

i I

A U Rev:

Date:

0 1/31/89 i

q

]

l

(

[G') MALFUNCTION CAUSE AND EFFECTS 1

Plant: MP2 Malfunction #: MS14 A - MSR1A i B - MSRIB  ;

1 I

i Malfunction

Title:

Moisture Separator Second Stage Tube Rupture.

1 Malfunction Type: Generic / Variable. 100% equals IX10(') lbm/hr at )

4 300 psid.

Malfunction Cause: Tube Rupture. ,f l

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will result in a tube leak from the (j second stage tube bundle (supplied by main steam) to the shell side of the MSR No. lA at the selected severity.

Second stage steam flow to MSR No. lA will increase ,  !

resulting in an increase in the reactor power level. Hot  !

reheat temperatures and pressures out of this MSR will j also increase. The overall effect will be a decrease in I plant efficiency. j Reheat steam pressure to both feed pump turbines may also j increase slightly.

Malf B - Effects similar to Malf A except that second stage steam to MSR No. 1B will be the major affected component. Feed pump turbine steam supply pressure is not directly-affected by this malfunction.

Malfunction removal will stop the second stage tube leak on the selected failed moisture separator reheater.

REFERENCES:

26002, 26003, OP-2317, System Description.

n Rev: 0 k_) Date: 1/31/89

1 i

MALFUNCTION CAUSE AND EFFECTS l

Plant: MP2 Malfunction #: MS15 A - MSRIA B - MSRlB l

1 Malfunction

Title:

Moisture Separator First Stage Tube Rupture.

l Malfunction Type: Generic / Variable. 100% equals- 500,000 lbm/hr at 250 psid.

Malfunction Cause: Tube Rupture.

Plant Status: Normal full power.

Malfunction Effects:

l Malf A - This malfunction will result in a tube leak from the first )

() stage tube bundle (HP turbine second stage extraction) to the shell side of the MSR No. lA at the selected severity.

First stage steam flow will-increase-resulting-in an ,

increaso in reactor power level. The steam leak will cause ,ot reheat steam temperature and pressure out of MSR No. lA 'o increase slightly. The overall effect will be a i

decrease in plant efficiency.

Reheat steam pressure to both feed pump turbines may also increase slightly.

Malf B - Effects similar to Malf A except that first stage steam to MSR No. 1B will be the major affected component. Feed pump turbine steam supply pressure is not directly affected by this malfunction.

Malfunction removal will stop the first stage tube leak on the selected failed moisture separator.

REFERENCES:

26002, 26003, OP-2317, System Description.

() Rev:

Date:

0 1/31/80

MALFUNCTION CAUSE AND EFFECTS

(}

Plant: MP2 Malfunction #: MS16 A-MSRDT 1A C-MSRlDT 1A E-MSR2DT 1A B-MSRDT.1B D-MRS1DT 1B F-MSR2DT 1B Malfunction

Title:

Moisture Separator Drain Tank High Level Control Valve Failure.

Malfunction Type: Generic / Variable. 100% equals 100% open.

Malfunction Cause: Level control valve fails at selected position.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will fail the high level dump valve on the moisture separator drain tank at the desired position.

f( )

If this valve is failed shut and the normal level control valve cannot handle the drains flow, the level in this-tank will rise eventually causing a turbine trip on high MSR water level.

If this valve is failed open, MSR drain tank level will decrease resulting in loss of a drains flow to LP heater 2A (MSR drain tank normal level control valve throttles shut). When the drain tank is empty the drains flow will go directly to the condenser. This blowby results in a drop in reheater outlet pressure and overall decrease in plant efficiency.

Malf B - Effects similar to Malf A except that MSR drain tank 1B high level control valve is the major affected componer' along with drains flow to LP heater 28.

Malf C - This malfunction will affect the high level dump valve position on first stage reheater drain tank 1A. If the tank level increases beyond the capacity of the normal level control, the first stage scavenging steam isolation valve will automatically be shut. As water rises into the l (\d9 Rev:

Date:

0 1/31/89

1

(' tube bundle region first stage extraction steam flow will decrease. This will cause a reduction in MSR No..lA steam production ability and an overall reduction in plant efficiency.

If the level in the first stage drain tank goes empty, due to the high level control valve failing open, drains flow th HP heater lA will decrease. Drains flow will then blowby directly to the condenser. The blowby: will cause first stage steam flow to increase resulting in overall decreased plant performance.

Malf D - Effects similar to Malf C except that MSR first stage reheater drain tank 1B high level dump and drains flow to HP heater 1B will be the major affected components.

Malf E - This malfunction will affect-the high level dump valve '

position of second stage reheater drain tank 1A. If the tank level increases beyond the capacity of the normal level control, the second stage scavenging steam isolation valve will automatically shut on high level. As the water rises into the tube bundle region second stage extraction steam flow will decrease. This will cause a reduction in MSR No. lA steam production ability and an overall reduction in plant efficiency.

If the level in the second stage drain tank goes empty, 7- due to the high level control valve failing open, drains q-flow to HP heater lA will decrease. Drains flow will then blowby directly to the condenser. The blowby will cause second stage steam flow to increase resulting in an overall decrease in plant performance.

Malf F - Effects similar to Malf E except that the high level dump on MSR second stage reheater drain tank 1B and drains flow to HP heater 1B will be the major affected components.

Note: Malfunction removal will allow the tanks level to be controlled by the HLDV.

REFERENCES:

26002, 26003,.OP-2317.

O Rev: 0

(_s/

Date: 1/31/89

~.

MALFUNCTION CAUSE AND EFFECTS Plant: ' MP2 Malfunction #: PC01 Malfunction

Title:

Loss of Plant Computer.

Malfunction Type: Generic.

Malfunction Cause: ' Central Processing Failure.

Plant Status: As desired.

Malfunction Effects: .

Malfunction ~ insertion will cause failure of the central processing units to transfer or accept data. This will cause-all digital and-analog outputs from the process computer to freeze. Therefore,Jall displays from the computer will not update and any' computer; driven annunciators will freeze in their last state. The.coputer-clock will continue to operate and update. After ~2 minutes, annunciator

'- O on CO8 " Computer Inop/Hi Temp" will alarm. The CRT's printers and keyboards will still be operable. . Tech specs will be impacted, since Linear Heat Rate monitoring will no longer be available from the PPC.

i Malfunction removal will restore the functions,of the central processing units and will allow all peripherals to be operational.

REFERENCES:

OP 2349B Plant Process Computer.

Rev: 0

'O. Date: 1/31/89

. MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RC01 Malfunction

Title:

RCS Crud Burst.

Malfunction Type: Variable. 100% equals maximum microcurie release l relative to maximum letdown radiation monitor indication.

Malfunction Cause: Chemical shock.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will increase the gross activity level of the reactor coolant system to a maximum of IE6 counts per minute as displayed by the letdown activity monitor. The increased reactor coolant system

,_s activity will also be reflected within any system that reactor coolant

( system leakage may exist.

V)

Area radiation levels in the containment and charging and letdown line vicinity will increase.

Radiation monitors affected are as follows:

RM-202 Letdown Radiation Monitor RM 7805 Primary Sample Sink Area RM-7896 Aux Bldg - 25' The simulator will have to be re-initialized to recover from this malfunction.

REFERENCES:

FSAR.

+g.

g,) Rev: 0 Date: 1/31/89 l

w_____________.______

- MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RCO2A(B)

Malfunction

Title:

RCS hot leg break (Th LOCA).

RCO2A #1 RCS Hot Leg RCO2B #2 RCS Hot Leg Malfunction Type: Variable, 0-100%, 100% equals 180,000' lbm/sec at 2250 pria.

Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in a rupture of the affected RCS hot leg. At 100% severity the malfunction is equivalent to a double-ended guillotine shear of the affected hot leg.

At 100% severity, pzr level immediately drops off-scale low. . RCS pressure drops to < 200 psia within several seconds causing a plant trip on TM/LP and SIAS on low pzr pressure. The RVLMS drops to 0%

indicated level as the RCS flashes and blows down. During the core p),

(_ recovery and injection phase, the RVLMS will rise to >19% indicating core coverage above the bottom of the hot leg.

CTMT pressure exceeds 40 psig within 15 secs and peaks at approximately one minute. CSAS occurs as its setpoint is exceeded.

CTMT temperature rises rapidly, peaking greater than 260 F within the first'two minutes.

CTMT area radmonitors increase sharply to peak at < 500 R/hr, (without fuel failure), then slowly decrease with time.

CTMT emergency sump. level indicators rise slowly during the injection phase to be approximately 5 1/2 feet when SRAS occurs.

As RCS pressure drops below SIT pressure, ('225 psig), the SIT's empty to recover the core. The SIT's will indicate empty within 4 minutes.

HPSI flow starts and exceeds 1200 gpm total within 1 minute. LPSI pumps start injecting as RCS pressure decreases below 200 psia. Total LPSI flow exceeds 4500 gpm within 2 minutes.

CTMT spray initiates on CSAS with header flows approximately 1400 gpm within 1 minute.

Rev: 0

( Date: 3/1/89

RWST level starts dropping when HPSI pumps start anc will decrease approximately 2% per minute when full SI and CS flows are established.

Core CET's decrease to < 250 F during the first several minutes of.the accident, then slowly decrease as the decay heat load drops off.

During the RCS blowdown phase, RCP amps and loop DP's oscillate due to cavitation.

Approximately 44 minutes after the initiating event, RWST level will have decreased to the SRAS setpoint.

When SRAS occurs, both LPSI purps will trip; the minimum flow recirc.

valves, (2-SI-659 and 2-SI-660), will close if their associated keylock switches'are placed in "OPER", both CTMT sump. suctions will open; and the SDC Hx RBCCW outlets will open. .

Due to reduced core flows and the hotter sump water, core CET temperatures will rise to stabilize at a higher temperature.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

"Pzr Press. Lo-Lo A(B,C,D)"

"CTM Press. Hi A(B,C,D)"

"CTM Press. Hi-Hi A(B,C,D)"

, " SIT 1(2,3,4) Level Lo" s "RWST CH A(B,C,D) Level Lo-Lo" "SIAS Actuation Sig CH 1(2) Trip" "CIAS Actuation Sig CH 1(2) Trip" "EBFAS Actuation Sig CH 1(2) Trip" "CSAS Actuation Sig CH lt2) Trip" "SRAS Actuation Sig CH 1(2) Trip" Operator action in response to this accident should be to trip all RCP's and monitor for proper actuation of SIAS, CIAS, EBFAS, CSAS, and SRAS. Operator action is required to place the minimum flow SI recirc. valve keylock switches to "OPER" prior to SRAS.

This malfunction is unrecoverable. Simulator reinitilization will be required to clear its effects.

Introduction of RCO2A(B) at lesser severities will cause similar l effects with the following exceptions:

l -

RCS depressurization will take longer.

CTMT pressure increase will take longer.

- ~n dicated RVLMS level may stabilize at higher values.

RWST level decrease will be slower with SRAG delayed proportion-fs ately.

' Rev: 0 Date: 3/1/89 L_________.____.____.

.)

) - At successively lower severities, RCS pressure will stabilize at successively higher values which will successively prevent LPSI' injection, SIT injection,'and HPSI injection.

- At very low severities, RCS pressure and pzr: level will' stabilize on charging pumps alone'.

Diagnosis of a #1 hot leg break versus a #2 hot leg break is not possible and has no. affect on operator response.

REFERENCES:

P&ID 26014, 26015, 26022, SH 1, FSAS 14.15.

I i

J 3

J 1

1 k

i I

l I

(). Rev:

Date:

0 3/1/89

)

1 j

f- MALFUNCTION CAUSE AND EFFECTS N].I l

Plant: MP2 Malfunction #: RCO3A(B,C,D)

Malfunction

Title:

RCS cold leg break (Tc LOCA).

RCO3A #1A RCS Cold Leg RCO3B #1B_RCS Cold Leg RCO3C #2A RCS Cold Leg RC03D #2B RCS Cold Leg Malfunction Type: Variable, 0-100%, 100% equals 100,000 lbm/sec at 2250 psia.

Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in a rupture of the affected RCS colH Teg. At 100% severity the malfunction is equivalent to a double-ended-guillotine shear of the'affected cold leg.

At 100% severity, pzr level immediately drops off-scale low. RCS pressure drops to < 200 psia within several seconds causing a plant trip on TM/LP and SIAS on low pzr pressure. The RVLMS drops to 0%

/~N indicated level as the RCS flashes and blows down. After the core i recovery and injection phase, the RVLMS will rise to 7% indicating core coverage just above t.he fuel alignment plate.

CTMT pressure exceeds 45 psig within 15 secs and peaks at approximately one minute. CSAS occurs as its setpoint is exceeded.

CTMT temperature rises rapidly, peaking greater than 270 F within the first two minutes.

CTMT area radmonitors increase sharply to peak at < 500 R/hr, (without fuel failure), then slowly decrease with time.

CTMT emergency sump level indicators rise slowly during the injection phase to be approximately 5 1/2 feet when SRAS occurs.'

As RCS pressure drops below SIT pressure, (~225 psig), the SIT's empty to recover the core. The SIT's will indicate empty within 4 minutes.

HPSI flow starts and exceeds 1200 gpm total within 1 minute. LPSI pumps start injecting as RCS pressure decreases below 200 psia. Total LPSI flow exceeds 4500 gpm within 2 minutes.

CTMT spray initiates on CSAS with header flows approximately 1400 gpm within 1 minute.

RWST level starts dropping when HPSI pumps start and will dectease approximately 2% per minute when full SI and CS flows are established.

6 Rev: 0 Date: 3/1/89

l l

l 1

l Core CET's decrease to < 280'f during the first several minutes of the accident, then ramp up to indicate ~100'F of superheat, (~380 F),

during the core recovery phase. Approximately 12 minutes into the event, core level reaches the upper 10% of the fuel. CET's ramp down j to Tsat, (~270 F), over the next 3 minutes. j During the RCS blowdown phase, RCP amps and loop DP's oscillate due to cavitation.

l Approximately 44 minutes after the initiating event, RWST level will j I

have decreased to the SRAS setpoint.

When SRAS occurs, both LPSI pumps will trip; the minimum flow recire.

valves, (2-s1-659 and 2-SI-660), will close if their associated keylock switches are placed in "OPER"; both CTMT sump suctions will ,

open; and the SDC HX RBCCW outlets will open.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded: l l

"Pzr Press. Lo-Lo A(B,C,D)"

"CTM Press. Hi A(B,C,D)"

"CTM Press. Hi-Hi A(B,C,D)"

" SIT 1(2,3,4) Level Lo" "RWST CH A(B,C,D) Level Lo-Lo" "SIAS Actuation Sig CH 1(2) Trip"

[~N "CIAS Actuation Sig CH 1(2) Trip" (s- "EBFAS Actuation Sig CH 1(2) Trip" "CSAS Actuation Sig CH 1(2) Trip" "SRAS Actuation Sig CH 1(2) Trip" Operator action in response to this accident should be to trip all RCP's and monitor for proper actuation of SIAS, CIAS, EBFAS, CSAS, and SRAS. Operator action is required to place the minimum flow SI recire. valve keylock switches to "OPER" prior to SRAS.

This malfunction is unrecoverable. Simulator reinitialization will be required to clear its effects.

Introduction of RC03A(B,C,D) at lesser severities will cause similar effects with the following exceptions:

RCS depressurization will take longer.

CTMT pressure increase will take longer.

- Indicated RVLMS level may stabilize at higher values.

- RWST level decrease will De slower with SRAS delayed proportionately.

/

Rev: 0

Date: 3/1/89

At successively. lower severities, RCS pressure will stabilize at

~

1 successively higher values which.will successively prevent'LPSI injection, SIT injection, and HPSI. injection.

- At.very low severities, RCS pressure and pzr level will stabilize.

on charging pumps alone.

Diagnosis of a #1A or B cold. leg break versus a #2A or B cold leg i break.is not possible and has no affect on operator response.

REFERENCES:

P&ID 26014, 26015, 26022 SH 1, FSAR 14.15.

J l

l 4

1

)

i l

Rev: 0

' Date: 3/1/89

. J I

l s ,

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RC04 1

Malfunction

Title:

Unisolable RCS leak on the Rx vessel head-vent.- I Malfunction Type: Variable, 0-100%, 100% equals 170 gpm at 2250 psid.  ;

l 1

Malfunction Cause: Socket weld or body to bonnet failure of the Rx head vent valve.

i Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in an unisolable RCS leak in CTMT from the Rx head vent line. Indications associated with this malfunction are non-specific as to'its location. Diagnosis beyond "a small unisolable RCS leak in CTMT" is not possible.

At 100% severity, the leak causes an initial rapid decrease in pzr level. The letdown flow control valve throttles back to minimum

,o letdown (~29 gpm) in'less than one minute. As pzr level continues to

() decrease, the first then'the second backup charging pumps start. At maximum charging and minimum letdown, pzr level will continue-to decrease approximately 1% per minute. VCT level will decrease approximately 3% per minute. The PPC program for RCS leak rate will indicate RCS leakage approaching 170 gpm as data is accumulated.

Pzr pressure will decrease slowly to ~2200 psia. The proportional heaters will maintain pzr pressure with their output at maximum until pzr level decreases to 20% and all heaters deneergize.

Containment conditions slowly change to indicate a small'RCS leak.

CTMT normal sump level, CTMT temperatures, dewpoint, narrow range l pressure, CTMT particulate and gaseous radmonitors all increase to a j

indicate a release of high energy fluid, with activity, inside CTMT.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

"Pzr Pressure Selected Channel Deviation Hi/Lo" "Pzr Ch 'X' Level Hi/Lo" "Pzr Ch 'Y' Level Hi/Lo" l i Rev: 0 x Date: 3/1/89

Due to the leak being unisolable, Tech. Specs. will require an orderly shutdown for unidentified leakage exceeding limits and AOP 2568 requires a manual reactor trip for RCS leakage exceeding the capability of CVCS to maintain pzr level. RCS cooldown and depressurization will be required to minimize the leakage.

Removal of RC04 will stop the leakage and pzr level and pressure control systems will respond to restore normal pzr level and pressure.

Introduction of RC04 at lesser severities will cause similar effects of proportionally smaller magnitudes with the following exception:  !

I

- Pzr level will be maintained with two backup charging pumps, one backup charging pump, or letdown flow decrease as severity is decreased. j

REFERENCES:

P&ID 26014, CEN 128 Case E2.

i Rev: 0 Date: 3/1/89

- MALFUNCTION CAUSE AND EFFECTS l

Plan $: MP2 Malfunction #: RC05A(B)

Malfunction

Title:

Pzr safety valve (sv) failure.

RCOSA Safety valve 2-RC-200 RC05B Safety valve 2-RC-201 Malfunction Type: Variable, 0-100%, 100% equals full open, steam flow through a full open SV at NOT/NOP is approximately 250,000 lbm/hr.

Plant Status: Normal full power operation.

Malfunction Effects: This malfunction causes the affected pzr SV to fail in the open position. At 100% severity, the affected valve fails full open which passes approximately 250,000 lbm/hr steam flow (at NOT/NOP) to the RCS quench tank.

Pzr pressure decreases to the TM/LP trip setpoint in approximately one minute.

m

(_) Post-trip, pzr level drops to < 30% due to RCS cooldown on the SD + By system then steadily increases 12-15% per minute as HPSI injects, i With no operator action the RCS will go solid. I Pzr pressure, post-trip, drops to the SIAS setpoint in approximately 35 seconds and continues to drop, bottoming out at 950-1000 psia.

Pressure slowly increases as HPSI injection recovers pzr level.

Discharge to the Quench Tank (OT) causes level, temperature, and pressure to rise rapidly until the rupture disk blows out at 100 psig.

QT pressure then drops to O psig and level ramps to 100%. Safety i valve tailpipe temperatures will drop from approximately 300 F to j about 215 F after the rupture disk blows. j RCS Th and Tc temperatures respond as on a normal trip then continue a i slow decrease. l RCS Th SCM decreases ~10 F pre-trip, spikes up ~30 F post-trip, then undergoes a ramp decrease to < 10 F as the RCS depressurizes. SCM then slowly increases as HPSI injection recovers RCS pressure.

The RVLMS will not indicate a vessel head level problem unless HPSI I flow is inadequate or unavailable.

1

[~h Rev: 0 (l Date: 3/1/89 i

.i

1 1

/'*

(,,)g After the QT rupture disk blows out, CTMT temperature, pressure, j humidity, and normal sump level will change to indicate a small RCS l leak in CTMT.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

"Pzr Safety VV RC-200 (201) Dis Temp. Hi" "QT Level Hi/Lo" "QT Press. Hi" "QT Temp. Hi" "TM/LP Trip CH A(B,C,D)"

"Pzr Pressure Selected Channel Deviation Hi/Lo" "SIAS Actuation Sig CH 1(2) Trip"

" Safety VV RC-200 (201) Open" Operator action in response to this event should be to verify the SV open and manually trip the plant and/or carry out EOP 2525 in response to the TM/LP trip. All RCP's should be tripped when SIAS occurs. RCS cooldown and depressurization will be required to stop the leak.

Removal of the malfunction will cause the affected SV to reclose allowing recovery of pzr level and pressure control.

Introduction of RC05A(B) at lesser severities will cause similar effects of a lesser magnitude, with the following exceptions:

i - Due to the slower depressurization and feedwater addition, pzr pressure will bottom out at successively lower values as severity is decreased toward median values.

- At successively lower severities, the combination of charging and reduced leakage will stabilize the RCS at successively higher pressures. HPSI injection and SIAS actuation will be precluded as pressure stabilizes above their respective values.

- At very low severities, RCS pressure will be maintained by the heaters. Tech. Specs. must be consulted regarding RCS leakage specifications and/or SV operability and a controlled shutdown may be required.

REFERENCES:

P&ID 26014, Retran/Nulap analysis.

l l,-~l Rev: 0 Date: 3/1/89

-- MALFUNCTION CAUSE AND EFFECTS

'\

Plant: MP2 Malfunction #: RCO6A(B)

Malfunction

Title:

Pzr PORV Failure.

RCO6A PORV 2-RC-402 F.C06B PORV 2-RC-404 Malfunction Type: Variable, 0-100%, 100% equals full open, steam flow through a full open PORV at NOT/NOP is approximately 130,000 lbm/hr.

Plant Status: Normal full power operation.

Malfunction Effects: This malfunction causes the affected pzr PORV to fail in the open position. At 100% severity, the affected valve fails full open which passes approximately 130,000 lbm/hr steam flow (at NOT/NOP) to the RCS quench tank.

Pzr pressure decreases to the TM/LP trip setpoint in approximately 1/2 minute.

Post-trip, pzr level drops to < 30% due to RCS cooldown on the.SD + BV system then steadily increases 4-8% per minute as HPSI injects. With '

no operator action the RCS will go solid. ,

Pzr pressure, post-trip, drops to the SIAS setpoint in approximately 2 minutes and continues to drop, bottoming out at ~800 psia when the pzr fills.

Discharge to the Quench Tank (OT) causes level, temperature, and ,

pressure to rise rapidly until the rupture disk blows out at-100 psig.

QT pressure then drops to O psig and level ramps'to 100% and remains. 1 PORV tailpipe temperature will drop from approximately 300 F to about  ;

215 F after the rupture disk blows.

RCS Th and Tc temperatures respond as on a normal trip then continue ,

to decrease as excessive feedwater addition cools the RCS. i RCS Th SCM decreases ~10* F pre-trip, spikes up ~30 F post-trip, then undergoes a ramp decrease to < 1 F as the RCS depressurizes and the pzr fills.

The RVLMS will not indicate a vessel head level prob,lem unless HPSI flow is inadequate or unavailable.

+ Rev: 0 5 Date: 3/1/89 i.

() After the QT rupture disk blows out, CTMT temperature, pressure, humidity, and normal sump level will increase to indicate a small RCS leak in CTMT.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

"Pzr Relief Valves Dis Temp. Hi" "QT Level Hi/Lo" "QT Press. Hi" "QT Temp. Hi" "TM/LP Trip CH A(B,C,D)"

"Pzt Pressure Selected Channel Deviation Hi/Lo" "SIAS Actuation Sig CH 1(2) Trip" "PORV RC-402 (404) Open" Operator action in response to this event should be to determine which PORV is leaking and close, deenergize, and tag the respective block valve in accordance with Tech. Spec. requirements. Inability to close the block valve will require a manual reactor trip or orderly shutdown depending on severity.

Removal of the malfunction will cause the affected FORV to reclose allowing recovery of pzr level and pressure control.

Introduction of RC06A(B) at lesser severities will cause similar effects of a lesser magnitude, with the following exceptions: 1 Pzr pressure will bottom out at successively higher values as severity is decreased.

- At successively lower severities, the combination of charging and reduced leakage will stabilize the RCS at successively higher pressures. HPSI injection and SIAS actuation will be precluded as pressure stabilizes above their respective values.

At very low severities, RCS pressure will be maintained by the heaters. Tech. Specs. must be consulted regarding RCS leakage specifications and/or PORV operability and a controlled shutdown may be required if the PORV block valve cannot be closed.

REFERENCES:

P&ID 26014, Retran/Nulap analysis.

1 O Rev:

Date:

0 3/1/89 i

f- MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RC07A RCPA l RC07B RCPB RC07C RCPC RC07D RCPD Malfunction

Title:

RCP Lower Mechanical Seal Failure.

Malfunction Type: Variable / Generic. 100% equals no pressure drop across the seal.

Malfunction Cause: Worn out seal. ,

I Plant Status: Normal full power.

Malfunction Effects:

Malf A - Malfunction insertion will reduce the lower mechanical seals

(~'

t ability to provide its normal pressure drop (approx 700 psi) on reactor coolant pump A. As the malfunction severity  !

s level is increased the middle seal pressure will approach i reactor coolant system pressure and the differential J

pressures across the middle and upper seals will increase.

Controlled bleed off flow from pump A will increase slightly as will its lower seal temperature. ,

1 The pump will continue to run with the failed seal. {

Malf B - Effects similar to Malf A except that RCP B lower seal is the major affected component.

Malf C - Effects similar to Malf A except that RCP C lower seal is the major affected component.

Malf D - Effects similar to Malf A except that RCP D lower seal is the major affected component.

Malfunction removal will restore the selected pump lower mechanical seal performance to normal.

REFERENCES:

26032

[^)

N-Rev:

Date:

0 1/31/89

1 i

i

l; MALFUNCTION CAUSE AND EFFECTS ,

(s s_

~)g' l

)

1 Plant: MP2 Malfunction #: RC08A -RCPA RC08B RCPB ,

RC08C RCPC  :)

RC08D RCPD j j

j Malfunction-Title: -RCP Middle Mechanical Seal Failure.  !

l Malfunction Type: Generic / Variable. 100% equals no pressure drop q across the seal.  ;

i j

Malfunction Cause: Worn out seal.

Plant Status: Normal full power. l 1

Malfunction Effects:

4 Malf A - Malfunction insertion will reduce the middle mechanical  !

(~T seals ability to provide its normal pressure drop-(approx- l'

(_/ 700 psi) on reactor coolant pump A. As the malfunction severity level is increased the upper seal pressure will approach the middle seal pressure. The differential pressures developed across the lower and upper seals will increase. Controlled bleedoff flow from pump A will increase slightly as will its lower seal temperature.

The pump will continue to run with.the' failed' seal.

Malf B - Effects similar to Malf A except that RCP B middle seal is the major affected component.

Malf C - Effects similar to Malf A except that RCP C-middle seal is the major affected component.

Malf D - Effects similar to Malf A except that RCP D middle seal is the major affected component.

Malfunction removal will restore the selected pump middle mechanical seal performance to normal.

REFERENCES:

26032

(~ Rev: 0'

(_)/ Date: 1/31/89

1

+

.]

1 1

l MALFUNCTION CAUSE AND EFFECTS or Plant: MP2 Malfunction #: RC09A RCPA RC09B RCPB RC09C RCPC j RC09D RCPD

_ Malfunction

Title:

RCP Upper Mechanical Seal Failure. ]

1 Malfunction Type: Generic / Variable. 100% equals no pressure drop across the sea 7 -

i Malfunction cause: Worn out' seal.

I l Plant Status: Normal full power.  !

l Malfunction Effects:

Malf A - Malfunction insertion will reduce the upper mechanical seals ability to provide its normal pressure drop (approx 700 psi) g, on reactor coolant pump A. As the malfunction severity level is increased the differential pressures developed across the lower a.1d middle mechanical seals will increase.

Controlled bleedoff flow from pump A will increase slightly as will its lower seal temperature.

The pump will contitaue to run with the failed seal.

Malf B - Effects similar to Malf A except that RCP B upper seal is  ;

the major affected component.  ;

Malf C - Effects similar to Malf A except that RCP C upper seal is i the major affected component.

Malf D - Effects similar to Malf A except that RCP D upper seal is the major affected component.

Malfunction removal will restore the selected pump middle mechanical seal performance to normal,

REFERENCES:

26032 Rev: 0

\'- Date: 1/31/89

MALFUNCTION CAUSE'AND EFFECTS Plant: MP2 Malfunction #: RC10A RCPA RC10B RCPB

.RC10C RCPC RC10D RCPD

\

Malfunction

Title:

RCP Vapor Seal Failure.

. Malfunction Type: Generic / Variable. 100% equals no pressure' drop j across the seal.

Malfunction Cause: Worn out seal.

I Plant Status: Normal full power, i

)

l Malfunction Effects:

i Malf A - This malfunction will result in RCP A seal leakage into the primary drain tank. As.the malfunction severity is in- 1 creased RCP A seal bleedoff flow return to the volume i control tank will decrease, also bleedoff pressure will O

decrease if in manual control.  !

Primary coolant system mass loss will be seen as a decrease-in volume control tank inventory and an increase in primary .

I drain tank level.

The following alarm will be received:  ;

l RCP A Bleedoff Flow Low, i Malf B - Effects similar to Malf A except that RCP'B vapor seal will be the major affected component.  !

Malf C - Effects similar to Malf A except that RCP C vapor seal will' be the major affected component.

Malf D - Effects similar to Malf A except that RCP D vapor. seal will be the major affected component.

i Malfunction removal will restore the selected pump vapor seal performance to normal.

REFERENCES:

26032 Rev: 0 Date: 1/31/89

_ ._ _ j

q j

l 1

MALFUNCTION CAUSE AND EFFECTS f

Plant: MP2 Malfunction #: RC 11 A(B,C,D)

Malfunction

Title:

Locked RCP rotor.

RC 11 A RCP A RC llc RCP C RC 11 B RCP B RC llD RCP D l

Malfunction Type: Generic ]

i Plant Status: Normal full power operation.

i Malfunction Effects: This malfunction results in the instantaneous i seizure of the affected RCP shaft. Overcurrent trips the breaker for the affected RCP. Indicated loop flows-drop to ~75% of normal.

Reduced flow through the core causes Th to rise above 600 F pre-trip.

The resultant RCS thermal expansion causes.a pzr insurge of ~5% which causes pzr pressure to increase to the PORV setpoint (pre-trip).

~T Trip setpoint for RCS high pressure and low flow are reached almost

/ simultaneously. 1 Post-trip primary and secondary response is similar to normal j uncomplicated trip response.  ;

The following alarms, key to event diagnosis, will occur as their 4 setpoints are exceeded:

"RCP A (B,C,D) Motor Trip" "Pzr Pressure Selected Channel Deviation Hi/Lo"  ;

"RCP Underspeed Trip CH A (B,C,D)"

"RC Lo Flow Trip CH A,B,C,D" Operator action in response to this malfunction should be to perform Standard Post Trip Actions, identify the seized RCP, and commence a plant cooldown in preparation for repairs.

This malfunction is unrecoverable. Simulator initialization will be '

required to unlock the affected RCP.

REFERENCES:

P&ID 26014, FSAR Section 14.6 (h

'/

Rev:

Date:

0 3/1/89 1

e


a--------.----___n__A

i i

e's MALFUNCTION CAUSE AND EFFECTS i j

( )

N_/ j Plant: MP2 Malfunction #: RC12A RCPA RC12B RCPB )

RC12C RCPC )

RC12D RCPD Malfunction

Title:

Upper Oil Reservoir Leak.

Malfunction Type: Generic / Variable. 100% equals 100 gpm leak.

Malfunction Cause: Upper Oil Reservoir Leak.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will result in the loss of oil from the RCP A upper oil reservoir. Pump bearings supplied by oil in the upper reservoir will not show any effect of loss of oil ,

(~)N

(_ until the reservoir level is less than 65% full. Normally it will be at the 85% level point with approximately 170 l

i gallons of oil. Rate of heatup on the thrust and upper guide bearings will be dependent on the upper sump level.

Maximum heatup will be 25 deg F/ minute at less than 20%

level.

When the pump bearing temperature increases above 250 deg F it will begin to draw more operating current and its vibration levels will increase. The pump will trip on overcurrent leading to a plant trip on low RCS flow.

If pump bearing temperature exceeds 350 deg F its roto'r will seize, after coastdown, preventing the pump from being i restarted. Instantaneous seizure will not occur with this malfunction.

Malf B - Effects similar to Malf A except RCP B upper reservoir will be the major affected component.

Rev: 0 O) k Date: 1/31/89

____ _ a

1 l

l .

T . Malf'C - Effects similar to Malf A except RCP-C upper reservoir will be the major affected component.

Malf D - Effects similar to Malf A except RCP D upper reservoir will j be the major affected component. 1 Malfunction removal will only stop the oil leak on the reservoir.

REFERENCES:

26032 1

l )

i l

O l

i l l l

l i

i l

l I

i t Rev: 0 l Date: 1/31/89 l l

t i

w-_.- _.______._-:__-._-.__-. _ - _ _ _ _ _

I i

I 1

e'N -MALFUNCTION CAUSE AND EFFECTS  !

y,)

Plant: MP2 Malfunction #: RCl3A RCPA RCl3B RCPB RCl3C RCPC RCl3D RCPD Malfunction

Title:

RCP Shaft Break. 3 i

Malfunction Type: Generic.

Malfunction Cause: Clean Mechanical Shear.

Plant Status: Normal full power.

i Malfunction Effects: j Malf A - This malfunction will result in a shaft separation between the motor and pump of RCP A. The pump motor will continue j

/,_'i to run at its no load value. RCS flow in loop 1A will i

(/ decrease to cause a low flow trip to be generated by RPS.

Total core flow will drop to less than that for normal three pump operation due to the increased reverse flow through loop 1A. Pump B running current and associated loop flow values will be higher than those for the other operating

, RCP's as it will be supplying most of the reverse flow to loop 1A.

I Malf B - Effects similar to Malf A except RCP B will be the major I affected component.

Malf C - Effects similar to Malf A except RCP C will be the major affected component.

Malf D - Effects similar to Malf A except RCP D will be the maj t affected component.

This malfunction is not recoverable. The simulator will have to be reinitialized to restore the selected failed RCP to normal operation.

REFERENCES:

26014 i Rev: 0

'- Date: 1/31/89

l 1

("'g MALFUNCTION CAUSE AND EFFECTS V

Plant: MP2 Malfunction #: RCl4A RCPA

~RCl4B RCPB RCl4C RCPC RCl4D RCPD Malfunction

Title:

RCP Speed Sensing Circuit Failure.

1 Malfunction Type: Generic.

Malfunction Cause: Speed Probe Failure.

Plant Status: Normal full power.

l Malfunction Effects:

Malf A - This malfunction will initiate an RPS trip on channel A RCP speed sensing circuit. RCP A operation will not be

/_ ' affected. Only channel A will show a trip status. RPS Tech

\ Specs will be affected.

4 If 2/4 trips exist the RPS will develop a trip signal to j trip the reactor / turbine. j l

The following alarm will be received: )

RCP Underspeed Trip CH A  !

Malf B - Effects similar to Malf A except RCP B speed sensing probe will be affected.

Malf C - Effects similar to Malf A except RCP C speed sensing probe will be affected.

Malf D - Effects similar to Malf A except RCP D speed sensing probe will be affected.

Malfunction removal will restore the function of the RCP speed sensing circuit which was failed to normal.

REFERENCES:

- 26032, 28500 SH. 120

{

l i Rev: 0  ;

Date: 1/31/89

i t

/ MALFUNCTION CAUSE AND EFFECTS

.\

Plant: MP2 Malfunction #: RC15A RCPA RC15B RCPB RC15C RCPC RC15D RCPD Malfunction

Title:

RCP Seal Pressure Oscillation.

Malfunction Type: Generic / variable. 100% equals +/- 300 psi on lower seal.

Malfunction Cause: Seal Failure.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will cause RCP A lower seal pressure to 6)

\_/

oscillate at a 10 pound per second rate'over a 600 psi range at maximum severity. Middle, upper and vapor seal pressures will reflect the oscillating pressure as transferred f rom the lower seal. Seal temperature and flow will not be visibly affected.

The following alarms may be received:

RCP Mid Seal Press Lo/Hi RCP Upper Seal Press Lo/Hi Malf B - Effects similar to Malf A except RCP B seal pressures will  ;

oscillate. 1 Malf C - Effects similar to Malf A except RCP C seal pressures will oscillate.

Malf D - Effects similar to Malf A except RCP D seal pressures will oscillate.

Malfunction removal will restore the selected failed RCP .

seal function to. normal. I

REFERENCES:

26032

() Rev:

Date:

0 1/31/89 i

j

.- _ _-._2. - _ . _ - - _ . _

j

(~

MALFUNCTION CAUSE AND EFFECTS

\~ i l

Plant: MP2 -~Ma' ~anction #: RC20A RCPA  ;

RC20B RCPB j RC20C RCPC

  • RC20D RCPD Malfunction

Title:

RCP Thermal Barrier. Tube Rupture.

i Malfunction Type: Generic / Variable. 100% equals 50 gpm @ normal DP within the HX (2100 psid).

Malfunction Cause: Tube Failure.

I Plant Status: Normal-full power.

Malfunction Effects:

Malf A - This malfunction will cause reactor coolant system leakage

(~ from the thermal barrier of RCP A to the reactor building

\- closed cooling water system. Seal temperatures and flows will not be affected by this malfunction. The reactor coolant entering the RBCCW system will cause the pump RBCCW return temperature to increase.  ;

RBCCW surge tank level will increase as will the systems activity level as monitored by RIT-6038.

RBCCW heat exchanger inlet temperatures will increase due to the injection of primary coolant resulting in opening of their service water outlet valves to maintain its outlet temperature.

Malf B - Effects similar to Malf A except that RCP B thermal barrier is the major affected component.

Malf C - Effects similar to Malf A except that RCP C thermal barrier is the major affected component.  :

Malf D - Effects similar sa, Malf A except that RCP D thermal barrier is the major affected component.

Malfunction removal will restore the selected failed RCP '

thermal barrier performance to normal which will stop the RCS leakage.  ;

REFERENCES:

26022 Rev: 0 Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RD01 **

Malfunction

Title:

Dropped CEA.

01-CEA #1(RG7) 20-CEA #20(RG2) 39-CEA #39(RG7) 55-CEA #55(RG4) 02-CEA #2(RG5) 21-CEA #21(RG2) 40-CEA #40(RG7) 56-CEA #56(RG4) 03-CEA #3(RG5) 22-CEA #22(RG2) 41-CEA #41(RG7) 57-CEA #57(RG4) 04-CEA #4(RG5) 23-CEA #23(RG2) 42-CEA #42(SDA) 58-CEA #58(RG3) 05-CEA #5(RGS) 24-CEA #24(RG2) 43-CEA #43(SDA) 59-CEA #59(RG7) 06-CEA #6(SDB) 25-CEA #25(RG2) 44-CEA #44(SDA) 60-CEA #60(RG3) ,

07-CEA #7(SDB) 26-CEA #26(RGl) 45-CEA #45(SDA) 61-CEA #61(RG3) l 08-CEA #8(SDB) 27-CEA #27(RG1) 46-CEA #46(SDA) 62-CEA #62(RG7) /

09-CEA #9(SDB) 28-CEA #28(RG1) 47-CEA #47(SDA) 63-CEA #63(RG3) 10-13 P1 N/A 29-CEA #29(RG1) 48-CEA #48(SDA) 64-CEA #64(RG3) 14-CEA #14(RG6) 30-CEA #30(RG1) 49-CEA #49(SDA) 65-CEA #65(RG7) 15-CEA #15(RG6) 31-CEA #31(RG1) 50-CEA #50(RG4) 66-CEA #66(RG3) 16-CEA #16(RG6) 32-CEA #32(RG1) 51-CEA #51(RG4) 67-CEA #67(RG3) 17-CEA #17(RG6) 33-CEA #33(RG1) 52-CEA #52(RG4) 68-CEA #68(RG7) 18-CEA #18(RG2) 34-37 P2 N/A 53-CEA #53(RG4) 69-CEA #69(RG3) 19-CEA #19(RG2) 38-CEA #38(RG7) 54-CEA #54(RG4)

\- s Malfunction Type: Generic Plant Status: Normal full power operation.

Malfunction Effects: This malfunction results in the selected CEA Bropping to the fully inserted position in the core. The negative reactivity inserted causes reactor power to decrease sharply.

Reactivity feedbacks from fuel and RCS temperature decrease will null reactivity and stabilize reactor power lower than pre-drop values.

The decrease in RCS temperature causes SG pressures to decrease and pzr level and pressure drop as the RCS volume contracts. All parameters decrease in proportion to the amount of power decrease.

The degree of power decrease is dependent on the relative worth of the dropped CEA and the time in core life (MTC). Under the worst case, (high worth dual CEA, BOL, and no operator action), average reactor power will decrease ~8%. Pzr level drops ~8%, pzr pressure ~65 psia, Tc ~7 F, and SG pressures drop ~50 psia. Effects will be proportion-ately smaller for lesser worth CEA's and/or later times in core life.

l l

T Rev: 0

( ,) Date: 3/1/89 E-_--- - - _ _ _ - - - - - _ . _ _ _ _ _

/g Besides a decrease in average core power, a dropped CEA will cause localized power depression (tilt). This is reflected by a larger than

( ,/

avera9o decrease in the ex-core detector (s) closest to the dropped CEA. An INCA printout will also show the depression in the in-core detectors in close proximity to the dropped CEA. INCA values for Tg, FR T

, and Fxy* will increase proportional to the degree of flux shift.

The various rod position indication systems will respond to indicate the dropped CEA:

o The Metrascope flashes, with the group containing the dropped CEA flashing brightly and the bar depicting the affected CEA pulses as a solid, vice dotted line.

o The Metrascope digital meter indicates 000 when the cursor is used to select the dropped CEA.

o Dialed in on the backup scanner, the dropped CEA will indicate 000.

o Core mimic lights for the dropped CEA change,to indicate the CEA fully inserted.

o Position for the dropped CEA on the P?C position display shifts to l 0.

l I

(~') The initial negative rate of change of power will cause the " Rod Drop" I (m,/ bistable to light on one or more RPS channels. This effect will not I occur in a limited number of conditions; such as dropping of the i center CEA or very low power level at the time of drop.

The following alarms, key to diagnosis, will occur as their setpoints are exceeded: i "CEA Dropped NIS"  ;

"CEA Dropped Reed Switch"  ;

"CEA Group Out of Seq."  ;

"CEA Group Out of Seq. Bkup" "CEA Group Dev. Bkup" "CEA Motion Prohibit" "FRT/TQ" ,

I c

In addition, alarms specific to the group containing the dropped CEA will occur i

"CEA SD Gp A (B) Dev."  !

I "CEA SD Gp A (B) Gross Dev."

i "CEA Reg. Gp 1 (2,3,4,5,6,7) Dev." l "CEA Reg. GP 1 (2,3,4,5,6,7) Gross Dev." l "CEA Reg. Gp 1 (2,3,4,5,6,7) PDI Limit"  ;

"CEA Reg. Gp 1 (2,3,4,5,6,7) PPDI Limit" Rev: 0

() Date: 3/1/89

operator response to a'c.ropped CEA, at power, should be to balanceTech turbine load to reactor power thereby halting the RCS cooldown.

Specs. dictates further response dependent on power level. If initially >70%, power mt st be reduced to <70% thermal power prior to CEA recovery. If >50% tut <70%, power must be held _less than initial during CEA recovery. If initially <50%, power may be increased to 50%

during CEA recovery.

After the CEA has been recovered, core flux distribution must-be assessed by

  • running the INCA program. _ Dependent on tne value of Tq, FRT, and Fxy ; Tech. SpEcv.. may require further action or a limit may be imposed on maximum a]lowable power.

If a CEA cannot be realigned with its group or if more than one CEA drops, an orderly plant shutdown must be initiated.

Removal of the malfunction allows the CEA to be latched and withdrawn.

Leaving the malfunction active precludes latching and withdrawing the {

affected CEA.

REFERENCES:

Reference Ilant Data Book, Event #40 and #42.

O Rev: 0 O Date: 3/1/89

l

-l f-s MALFUNCTION CAUSE AND EFFECTS lv/

Plant: MP2 Malfunction #: RD02.01 + 69 i

j Malfunction

Title:

Stuck CEA.  !

Malfunction Type: Generic.

Malfunction cause: Mechanical failure as positioned, untrippable, 61 CEDMS total.

I Plant Status: Normal full power.

Malfunction Effects:

Malf 01 - Movement of CEA number 1 will be totally prohibited.with this malfunction inserted. Rod position demand signals j from the-control element drive system or loss of power to-its coil power programmer will not reposition.the CEA. l Rod. bank worth will be affected by the' stuck rod. CEA  :

( Tech specs will be impacted.  ;

Rod position indication (secondary) for the selected failed rod will not change, leading to CEA deviation alarms if other CEA's in its group are moved. Pulse counting (primary position ind) will;still function- .

Core physics effects as observed on excore and incore nuclear instrumentation will be affected by the stuck CEA.

Malf 02 Effects similar to Malf 01 except that the number sel-through ected affects the associated CEA. Selection of a power 69 - shaping CEA will yield an error from the PCM as these CEA's have been removed'from the reference plant.

Malfunction removal will allow the CEA to be positioned-or to drop if its upper gripper coil is deenergized.

REFERENCES:

CEDS Manual. ,

/~' Rev: 0 Date: 1/31/89

l l

l

,f-- ,

MALFUNCTION CAUSE AND EFFECTS i

Plant: MP2 Malfunction #: RD03 01 - 69 Malfunction

Title:

.-CEA Partial Drop.

Malfunction Type: Generic / Variable. 100% equals 100 steps drop (61-total CEAs).

Malfunction cause: Worn out gripper causes slippage. 1

\.

Plant Status: Normal. full power.

Malfunction Effects:

Malf 01.- This malfunction will result ta the inward slippage of: '

CEA number 1 0f 100 steps at maximum severity. Secondary reed switch indication as displayed by the core map, backup scanner,.and the metrascope will indicate the actual rod position. The primary pulse counting position

( indication will not show the actual position until the position is manually updated through the computer or the CEA acivates its rod bottom reed switch. CEA Tech specs will be impacted.

Reactivity effects due to the dropped rod will be observed on core parameters and excore instrumentation as a function of the rods' worth and malfunction severity level.

The rod may be repositioned with its group without removal of the malfunction.

CEA deviation alarms as a function of the maximum and minimum position of rods within the sarae group. Other CEA position alarms are possible depending on malfunction severity.

Malf 02 Effects similar to Malf 01 except that the number through selected affects the associated CEA.

69 -

Malfunction remov61 will have no visible effect on simulator operation.

REFERENCES:

AOP 2556

-(

Rev: 0 Date: 1/31/89

r~3 MALFUNCTION CAUSE AND EFFECTS Y]

Plant: MP2 Malfunction #: RD04 *

  • Malfunction

Title:

Ejected CEA.

01 CEA #1 Reg. Group 7 41 CEA #41 Reg. Group 7 62 CEA #62 Reg. Group 7 '

65 CEA #65 Reg. Group 7 Malfunction Type: Generic Plant Status: Hot zero power (HZP), reactor critical at 10-'%, Group 4 CEA's @ 109 steps.

i Malfunction Effects: This malfunction results in a mechanical failure j of the affected CEDM drive housing. The affected CEA ejects from the core in ~0.1 seconds.

O(_/ The worth of the ejected CEA, fron the fully inserted position is

~0.5% reactivity. This rapid instrtion of positive reactivity, from below the POAH, causes an instantaneous power spike of ~1 decade followed by a rapid power escalatiou ~ 1/2 decade per second. Power j rises to the variable high power trip setpoint in ~5 seconds. Power 4 drops rapidly after the reactor trips.

The RCS leakage through the ruptured housing is initially 275 gpm at 2250 psia. Level drops rapidly, causing letdown to throttle to minimum and starting the backup charging pumps. Level continues to drop ~3% per minute after maximum charging and minimum letdown.

Pzr pressure decreases rapidly to <2200 psia then slows due to the pzr backup heaters energizing. Pressure drops rapidly after all the heaters deenergize due to low level.

The CEA reed switches carry away when the housing blows off. This results in all of the core mimic lights associated with the CEA going off. The reed switch ladder assembly open circuits. The Metrascope digital indicator and backup scanner interpret this as 0 steps withdrawn. The PPC CEA position remains at the pre-ejection value.

l [)

\/

Rev:

Date:

0 3/1/89

The following alarms, key to event' diagnosis occur as their setpoints are exceeded:

"NIS.Hi Pwr Trip.CH A.(B,C,D)"

I Operator response to this event should be to cooldown and depressurize in preparation for repairs.

REFERENCES:

Cycle 9 NDR, Ketran/Nulap.

I 1

0 1

Rev: 0 Date: 3/1/89

4 I

i q MALFUNCTION CAUSE AND EFFECTS i

i Plant: MP2 Malfunction #: RDOS 01 - 69 l

Malfunction

Title:

CEA Sequence Failure.

Malfunction Type: Generic / Variable. 100% equals 10 second delay between demand signals.

Malfunction Cause: Timer module failure - selected CEA does not receive motion demand signal at proper time.

Plant Status: Normal full power. I Malfunction Effects:

Malf 01 - This malfunction will cause a delay in the individual I raise or lower signal sent to CEA number 1. The CEA will  ;

appear to move slower than its normal rate, as the 1 severity level is increased, causing it to lag behind'the rest of the group as it is moved. The malfunction will 1 only have an effect on a rod if it is moved in a group l control mode. CEA position deviation alarms will be.

developed as a function of the maximum and minimum positions of rods within a group. CEA Tech Specs may be i impacted.  !

The misalignment of the CEA will have an effect on core  ;

flux patterns and excore instrumentation response. =

The following alarms may be received:

CEA Position Dev Alarms CEA Group Dev i CEA Group Out of Seq  !

Malf 02 Effects similar to Malf 01 except that the number sel-through ected affects the associated CEA. Selection of a' power i 69 - shaping CEA will yield an error from the PCM as these l CEA's have been removed from the reference plant.

1 Malfunction removal will restore the normal sequential timing to the selected failed CEA.

REFERENCES:

AOP 2556.

tO. Rev: 0-Date: 1/31/89

KALTUNCTION CAUSE AND EFFECTS l

Plant: MP2 Malfunction #: RD06 1

i l

Malfunction

Title:

In-Hold-Out Switch Failure. j Malfunction Type: Generic. l i

Malfunction cause: Wiring problems _ inhibit switch function.

Plant Status: Normal full power.

Malfunction Effects:

Insertion of this malfunction will inhibit all functions.of the CEDS in-hold-out switch at C04 in all modes of rod control. It will not impair any other functions of the system. If rod motion is in i progress, due to control switch operation, it will be stopped when  !

the malfunction goes active.

Malfunction removal will restore operability to the in-hold-out switch. J

REFERENCES:

CEDS Manual.

l l

i l

Rev: 0 l Date: 1/31/89 i

/~N MALFUNCTION CAUSE AND EFFECTS L)

Plant: MP2 Malfunction #: RD08 01-69 Malfunction

Title:

CEA Pulce Counter Failure.

i Generic / Variable. 100% equals 10 step lag in 1

Malfunction Type:

pulse computation (done only in 10% increments).

Malfunction cause: Demand motion pulse signal intermittent failure.

Plant Status: Normal full power.

Malfunction Effects:

Malf 01 - This malfunction will cause the indicated position of CEA number 1, as displayed by its primary position indica- l tion, to lag behind its true CEA position. At a 10%

,_ severity level the CEA pulse signal to the computers

/D primary position indicating circuit will receive a pulse

\s / at half the rate that it should. 100% severity will decrease the rate to one-tenth the normal time. Actual CEA demand pulses to the coil power programmer will not be affected.

Alarm and control signals as developed by the process computer will be affected by the erroneous CEA position calculation.

Secondary CEA positions ar displayed by the metrascope, backup scanner and core map display will not be affected by this malfunction. CEA Losition indication Tech Specs will be impacted.

Malf 02 Effects similar to Mnif 01 e.: cept that the number through selected affects the associa.ed CEA. Selection of a 69 - power shaping CEA will yield an error from the PCM as these CEA's have been removed from the reference plant.

Malfunction removal will allow pulse signals from the CEDS to be received by the computer at their normal rate.

l Primary position indication from the computer will have to be manually updated to restore the CEA's calculated position indication to the CEA's actual position.

, p

REFERENCES:

CEDS Manual.

Rev: 0 Date: 1/31/89 i

- MALFUNCTION CAUSE-AND EFFECTS Plant: MP2 Malfunction #: RD09 ** i Malfunction

Title:

Uncoupled CEA.

01-CEA #1(RG7) 20-CEA #20(RG2) 39-CEA #39(RG7) 55-CEA #55(RG4) 02-CEA #2(RG5) 21-CEA #21(RG2) '40-CEA #40(RG7) 56-CEA #56(RG4) 03-CEA #3(RG5) 22-CEA #22(RG2) 41-CEA #41(RG7) 57-CEA #57(RG4) 04-CEA #4(RG5) 23-CEA #23(RG2)- 42-CEA #42(SDA). 58-CEA #58(RG3) 05-CEA #5(RG5) 24-CEA #24(RG2) 43-CEA #43(SDA) 59-CEA #59(RG7) 06-CEA #6(SDB) 25-CEA #25(RG2) 44-CEA #44(SDA) 60-CEA #60(RG3) 07-CEA #7(SDB) 26-CEA #26(RG1) 45-CEA #45(SDA) 61-CEA #61(RG3) 08-CEA #8(SDB) 27-CEA #27(RG1) 46-CEA #46(SDA) 62-CEA #62(RG7) 09-CEA #9(SDB) 28-CEA #28(RG1) 47-CEA #47(SDA) 63-CEA #63(RG3) 10-13 P1 N/A 29-CEA #29(RG1) 48-CEA #48(SDA) 64-CEA #64(RG3) 14-CEA #14(RG6) 30-CEA #30(RG1) 49-CEA #49(SDA) 65-CEA #65(RG7) 15-CEA #15(RG6) 31-CEA #31(RG1) 50-CEA #50(RG4) 66-CEA #66(RG3) 16-CEA #16(RG6) 32-CEA #32(RG1) 51-CEA #51(RG4) 67-CEA #67(RG3) 17-CEA #17(RG6) 33-CEA #33(RG1) 52-CEA #52(RG4) 68-CEA #68(RG7) 18-CEA #18(RG2) 34-37 P2 N/A 53-CEA #53(RG4) 69-CEA #69(RG3) 19-CEA #19(RG2) 38-CEA #38(RG7) 54-CEA #54(RG4)

Malfunction Type: Generic Plant Status: NOT/NOP, ready to pull critical.

1 Malfunction Effects: This malfunction results in the selected CEA being uncoupled. During CEA withdrawal for critical approach, the selected CEA extension shaft will be withdrawn, thereby causing the rod position indication systems to indicate that the CEA is being withdrawn. However, the active CEA, and the associated negative, reactivity, will not be withdrawn from the core. This will cause the estimated critical position (ECP) to be inaccurate. _The degree of inaccuracy will be equal to the worth of the uncoupled CEA(s).

There are no alarms associated with or caused by this malfunction when active during a reactor startup.

Diagnosis of this problem would be done by the Reactor Engineer during post-refuel low power physics testing.

An ECP inaccuracy large enough to be diagnosed by operators during a routine startup would require uncoupling more than one high worth CEA.

/D Rev: 0

\/ Date: 3/1/89

Operator-response to this event should be to seek' confirmation, of an O uncoupled CEA, from Reactor Engineering. Once confirmed, Tech. Specs.

would require a plant cooldown for repairs.

This malfunction is unrecoverable. The simulator must be reinitialized to re-couple the CEA.

REFERENCES:

Plant data, i

1 i

i l

Rev: 0 Date: 3/1/89 l

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

.i MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RD10A - SDA RD10G - RG5 RD10B - SDB RD10H - RG6 RD10C - RG1 RD10I - RG7 RD10D - RG2 RD10E - RG3 RD10F - RG4 Malfunction

Title:

Continuous Bank Insertion.

Malfunction Type: Generic.

Malfunction Cause: Hot shorts (all Rod Groups) only turning off rod control system stops rod motion.

Plant Status: Normal full power.

Malfunction Effects:

O Malf A - This malfunction will result in the continuous insertion of shutdown bank A to its fully (mechanical) inserted position of zero inches. The inward rod motion of this group will only be stopped if power is lost to the coil power programmers by reactor trip or deenergization of the CEDS by selecting the off mode at C04. CEA Tech Specs may be impacted.

Primary and secondary CEA position indication will show the rod motion. Core reactivity effects and excore instrument response will occur as appropriate to the worth of the CEA's being inserted.

Malf B Effects similar to Malf A except the selected rod groups through noted above as the generic components may be indiv-I - idually affected.

Malfunction removal will stop the selected failed group inadvertent inward motion.

REFERENCES:

CEDS Manual.

() Rev:

Date:

0 1/31/89

MALFUNCTION CAUSE AND EFFECTS x},.

[~

Plant: MP2 Malfunction #: RDllA - SDA RDilG - RGS RD11B - SDB RD11H - RG6 RDilC - RG1 RD11I - RG7 RD11D - RG2 RD11E - RG3 RDllF'- RG4 Malfunction

Title:

. Continuous Bank Withdrawal.

Malfunction Type: Generic.

Malfunction Cause: Hot Shorts (all rod groups) only turning off rod l control system stops rod motion.

Plant Status: Preparation for Reactor Startup.

Malfunction Effects:

(

Malf A - This malfunction will result in the continuous withdrawal of shutdown bank A to its fully.(mechanical) withdrawn j position of 137 inches (183 steps). The outward rod i motion of this group will only be stopped if power is lost to the coil power programmers by reactor trip or l deenergization of the CEDS by selecting the off mode at C04. CEA Tech Specs may be impacted.

Primary and secondary CEA position indication will show i the rod motion. Core reactivity effects will occur as appropriate to the worth of the CEA's being withdrawn.

Malf B Effects similar to Malf A except the selected rod groups through noted above as the generic components may be indiv-I - idually affected.

l Malfunction removal will stop the selected failed group inadvertent outward.

REFERENCES:

CEDS Manual. ,

Rev: 0 Date: 1/31/89 '

E________

i l

l

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MALFUNCTION CAUSE AND EFFECTS l

Plant: MP2 Malfunction #: RD12  !

l Malfunction

Title:

CMI Failure.

Malfunction Type: Generic.

Malfunction Cause: CMI relay fails in its energized position.

.q 1

Plant Status: Normal full power. i 1

Malfunction Effects:  !

This malfunction will not-stop rod motion if a CMI is generated.

CMI would normally be generated when any one of the following conditions exists:

CEA Group Out of Sequence O violation of Shutdown Group Insertion Permissive violation of Regulating Group Withdrawal Permissive CEA Group Deviation PDIL Violation Alarms associated with the CMI initiating devices will work properly. The CMI alarm "CEA motion prohibit" and associated CMI functions will not work. CEA Tech specs will be impacted. j Malfunction removal will restore all alarm and CEA motion blocking functions to normal.

)

I

REFERENCES:

CEDS Manual. l 1

Rev: 0 Date: 1/31/89 i

i i

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RHOlA(B)

Malfunction

Title:

LPSI Pump Breaker Trip RHOlA LPSI Pp A RHOlB LPSI Pp B Malfunction Type: Non-variable Plant Status: RCS ~120 F, vented, shutdown cooling in operation with the RCS drainad approximately to the hot leg centerline.

Malfunction Effects: This malfunction causes an overload trip of the' breaker for the affected LPSI pump. If inserted on a running LPSI pump, the breaker trips immediately. If inserted on an idle LPSI.

pump, the breaker will trip when a start is attempted.

If the affected LPSI pump was being used to supply SDC flow, (1 pump l operation), the reactor vessel water will start to heatup on core decay heat.

As indicated SDC flow drops to O gpm, CET's start increasing from

~120" F to 210-230 F at ~ll F per minute. Boiling occurs in the core, which stabilizes CET temperatures.

Wide range loop Th temperatures follow the CET increase above their low value of 150 F. Wide range loop Tc temperatures are not in the affected areas and do not respond.

SDCS suction and discharge temperatures remain at their pre-trip values.

Restoring SDC flow causes the CET's to spike upwards, then trend downward as cooler Tc water mixes with the heated water in the core region.

As heated water from the core region is transported to the SDC suction piping, the SDCS suction temperature trends up followed by the SDCS discharge temperature. The peak value for the suction temperature is significantly lower than the CET temperatures due to mixing and the discharge temperature peaks lower still, due to cooling in the SDC heat exchanger.

LI Rev: 0 l- Date: 3/1/89 l

() The following alarms, key to event diagnosis, will occur:

"LPSI Pump A (B) Overload / Trip" operator action in response to this malfunction should be to restore SDC flow using the unaffected LPSI pump. The cause of the breaker trip should be investigated and repairs initiated. Tech Specs should be consulted regarding SDC loop operability.

ReL3 val of the malfunction removes the cause of the breaker trip. The LPSI pump does not automatically restart. Its handswitch must be taken to the " Trip" position to reset the overload, amber trip light, and alarm. The pump may then be restarted by turning its handswitch to " Start".

REFERENCES:

P&ID 26015, 26014, 32008 sh. 4 O

Rev: 0 O- Date: 3/1/89

?

\

Malfunction removal will reopen the pump suction isolation valve to restore pump suction head. l 1

REFERENCES:

26017 j

?

l i

i-l l

1h Rev: 0 i v Date: .1/31/89 l l

1 i

I i

MALFUNCTION CAUSE AND EFFECTS  !

l t ) J Plant: MP2 Malfunction #: RH03 ,

l Malfunction

Title:

Shutdown Cooling Flow Control Failure.

Malfunction Type: Variable. 100% equals indicated flow 1000 gpm greater than actual flow. j l

Malfunction Cause: Flow transmitter FT 306 failure.

I Plant Status: Shutdown Cooling Operations.

Malfunction Effects:

This malfunction will cause the flow value transmitted to FIC-306 and its associated computer point to be higher than the actual flow. As the severity level is increased indicated shutdown cooling flow will increase causing the shutdown cooling flow controller output to increase. As the controller output increases its flow control valve ,

r~% will be further shut. The difference between the actual flow entering

( the RCS (as measured by the total LPSI loop. flows) and shutdown cooling flow indicated values will be greater at higher-severity levels.

Reduced shutdown cooling flow through the shutdown heat exchangers may result in upward trending of RCS return temperature. This will be dependent on core decay heat levels and flow through 2-SI-657.

As the low pressure pump flow is reduced the pumps running current will decrease and its discharge pressure will increase.

Malfunction removal will restore proper shutdown cooling flow indication.

REFERENCES:

26015.

l O

Rev:

Date:

0 1/31/89

' MALFUNCTION CAUSE AND EFFECTS i .O Plant: MP2 Malfunction #: RH04A P42A' RH04B P42B Malfunction

Title:

LPSI Pump Seal Failure.

Malfunction Type Generic / Variable. 100% equals 20 gpm 0.30 psig.-

suction pressure.

Malfunction Cause: Worn out mechanical seal on pump.

Plant Status: : Shutdown Cooling Operations.

Malfunction Effects:

Malf A - This malfunction will result in the leakage of mass.from the reactor coolant system via the low pressure safety injection pump A mechanical seal. The-leakage will be collected and pumped from safety injection room "A" sump to the aerated O waste drain tank.

The leakage will stop if the pumps suction source is isolated.

The following alarm may be' received:

SI Rm A Sump Level Hi j j Malf B - Effects similar to Malf A except the seal leakage will be from low pressure safety injection pump B. Leakage will be collected in SI' room B sump.

Malfunction removal will stop the seal leakage from the selected failed pump seal.

REFERENCES:

26015, 26024 O Rev:

Date:

0 1/31/89 -

w-- L-- - --- --

-y

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i l

/~N- MALFUNCTION CAUSE AND EFFECTS lQ ,

i Plant: MP2 Malfunction #: RH05A SDC Hx'A RH05B SDC Mx B Malfunction-Title: SDC Heat Exchanger TV'oe Rupture.

Malfunction Type: Generic / Variable. 100% equals 100 gpm at 100 psid.

i Malfunction cause: Tube failure. .)

Plant Status: Shutdown cooling operations. >

Malfunction Effects:

Malf A - This malfunction will result in a loss of reactor coolant system mass via shutdown cooling heat exchanger to the  :

reactor building closed cooling water system. i

) As the severity level is increased the operating LPSI pump (J

N discharge pressure will decrease slightly. The shutdown cooling flow control valve will open to maintain its ,

controlled setpoint (3000 gpm for 1 pump operation). The j loss of mass from the reactor coolant system will be .

observed by the decrease in pressurizer level. l 1

The leakage into the RBCCW system will cause an increase in its surge tank level. Overflow from this tank will be collected in the aerated waste tank. Activity levels as monitored by RIT-6038 will reflect the radioactive inleakage.

Malf B - Effects similar to Malt A except shutdown coolir.g heat exchanger B will be the major affected component.

Malfunction removal will restore the integrity of the tubes on the selected shutdown cooling heat exchanger.

REFERENCES:

26015, 26022

() Rev.

Date:

O 1/31/89

i J

a

' /'\- MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RH06A P43A' RH06B. P43B

.)

.i Malfunction

Title:

Containment Spray Pump Trip. 1

(

1 Malfunction Type: Generic j

Malfunction Cause: Faulty' Load Shed Contact. l Plant Status: Containment spray pump operations.

Malfunction Effects:

Malf A - This malfunction will cause containment spray pump A's motor supply breaker to trip open if'it is shut and prevent it from being shut if.open. The pumps motor running current will decrease to zero and its discharge pressure will drop

. to its suction head value. Flow developed by the pump will decrease as a function of the. pump D/P.- ECCS Tech Specs will be impacted.

Pump breaker status at the evntrol panel and computer i display will show that it' ins tripped (amber HS light on as. 1 a function of HS and' breaker position). ,

Malf B - Effects similar to Malf A except that. containment spray pump ,

B is the affected component.

Malfunction removal will restore-the function of the-selected failed. containment spray pump load shedding. contact to normal. j

REFERENCES:

26015, 32008 SH. 6, 7 l l

l l

4 l

Rev: 0 Date: 1/31/89 1

w_-_____-___

~

1 1

MALFUNCTION CAUSE AND EFFECTS. ,

' Plants: MP2 Malfunction #: RH07A 2-SI-615-RH07B 2-SI-625 i RH07C 2-SI-635 J RH07D 2-SI-645 j Mal'ynction

Title:

LPSI Flow Control Valve Failure.

Mal # unction Type: Generic.

Malfunction'Cause:' Valve mechanically failed' shut.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will mechanically fail the low pressure safety injection flow control MOV to loop 1A-in its shut

-position. It will not shut the valve if it is open. If the O> malfunction is inserted and-the valve is shut, opening of the valve with its associated handswitch or SIAS: signal will be inhibited. ECCS Tech specs will be impacted.

Malf B through D -

Effvets similar to Malf'A except that the low pressure a safety injection flow control valves listed above as. generic ]

components may be individually affected.

Malfunction removal will remove the .eahanical failure on  ;

the selected valve to allow its normal operation.

REFERENCES:

26015, 32008 SH. 21, 22, 23, 24.

l 1 i l

l Rev: 0 Date: 1/31/89 l

7 MALFUNCTION CAUSE AND EFFECTS 1

Plant: MP2 Malfunction #: RM01 A .RIT-7890 Ctmt Personal Access K RIT-8241'Ctmt High Range B RIT-7891 Service Platform L RIT-8142 Spent Fuel Pool NW.

C RIT-7892 Drumming Area M RIT-8156 Spent Fuel Pool NE D RIT-7894 Safeguard' Area O RIT-9799A Control Room Vent E RIT-7895 Sample Sink- P RIT-9799B Control Room Vent F RIT-7896 14'6" Area Q RIT-4299A #1 Main Steam Line G RIT-7897 -45'6" Area R RIT-42998 #1 Main Stm Atm Dump H RIT-7899 Control Room 5 RIT-4299C #2 Main Stm.Line I RIT-8139 Spent Fuel ~ Pool SW J RIT-8248 Ctat High Range l

Malfunction

Title:

Area Radiation Monitor Failure.

Malfunction Type: Generic / Variable. 100% equals. meter full scale deflection.

Malfunction Cause: Instrument Failure.

) Plant Status: As desired.

Malfunction Effects:

Malf A - Range: 10-2 to 10+4 mr/hr. Malfunction insertion will cause the indicated value of RIT-7890 (CTMT personnel access) to fail'at.a fixed position on scale at the selected severity.(50% severity fails the meter at midscale). Alarm functions will occur as appropriate to the severity. level in respect to the alarm setpoints. Acutal radiation-levels l will not affect the metered output. Module test functions will appear to operate properly.

The following alarms may actuate:

Area Monitor Radiation Hi Area Moniter Module Fail Malfunction removal will restore the selected failed channel to normal.

l Malf B Affects monitors as listed in generic components above.

through General area monitor range will be .1 to lE4 MR/HR while the N- post accident monitors RIT-8240 and RIT-8241 read from 1.0 to lE7 R/HR. Tech Specs may be impacted.

Rev: 0 O: Date: 1/31/89

?

i i

i e I

()- Malfunction removal will restore the selected failed channel- 1 indication to normal, d Malf O and P - '(

Range: 10~

  • to 10' mr/hr. Malfunction insertion'will.cause:

the indicated value of RIT-9799A(B) (Control Room intake-duct) to fail at a fixed position on. scale at the selected severity (50% severity fails the meter at midscale).

Control Room ventilation automatic recirculation function will occur as appropriate to the severity level with respect to the alarm setpoints. Tech specs may.be impacted.

The following alarms may actuate:

Control Room AC System In Auto'Recirc Malfunction removal will restore the selected failed channel indication to normal. -Control Room Ventilation System will remain.in recirculation mode.

Malf 0 through S - )

I 105 to 10' R/hr. Malfunction' insertion will'cause Range:

the indicated value of RIT-4299A (B,C) (Main' steam line radiation monitorc) to fail.at a. fixed position on scale at i the selected severityf(50% severity fails the meter at I O midscale). Alarm functions will occur as appropriate to the severity level in respect to the alarm s(4tpoints. Actual i radiation levels will not affect the~ metered' output. Tech specs may be impacted.

The following alarm may actuate:

Main Steam Line Hi Rad / Inst. Fail" l Malfunction removal will restore the selected: failed channel indication to normal.

REFERENCES:

OP 2383B 1

i i

y Rev: 0 .

j Date: 1/31/89 j i

j l

1 1

J

l r - MALFUNCTION CAUSE AND EFFECTS l

l Plant: MP2 Malfunction #: RM02 A RIT-5099 Steam Jet Air Ejector J RIT-8262B Ctmt Gaseous 1 i

B RIT-80ll Control Room Vent K RIT-8434A Rad Area Vent Partet C RIT-8123A Ctmt Particulate L RIT-8434B Rad Aren Vent Gaseous D RIT-8123B Ctmt Gaseous M RIT-8997 Charging Pump & Degas l E RIT-8132A Unit 2 Stk Particult N RIT-8998 VCT-Sample Room I F RIT-8132B Unit 2 Stk Gaseous O RIT-8999 SFP Pump & HX G RIT-8145A Fuel Hdling Partic P RIT-9895 Waste Gas Discharge H RIT-8145B Fuel Hdling Gaseous Q RIT-8168 Unit 2 Stk High Range I- RIT-8262A Ctmt Particulate Malfunction

Title:

Airborne / Process Radiation Monitor Failure.

Malfunction Type: Generic / Variable. 100% equals meter full scale I 1

deflection.

Malfunction Cause: Instrument Failure.

(~ Plant Status: As desired. l

\_

Malfunction Effects Malf A - Malfunction insertion will cause the indicated value of RIT-5099 (condenser air ejector discharge) to fail at a i fixed position on scale at the selected severity 1pvel (Sp%  ;

severity fails the meter at midscale). Range: 10 to 10 I CPM. Tech specs maybe impacted.

Alarm and control functions will occur as appropriate to the severity level in respect to the alarm setpoints. Actual radiation levels will not affect the metered output. Module test functions will appear to operate properly.

The following alarms may be actuated:

Process Mon Hi/ Fail Process Mon Radiation Hi.

Malf B Affects the airborne process radiation monitors as listed through in generic components above. Indicated instrument range i

P- will be from 10 to 1E6 CPM.

e Rev: 0 i \~ Date: 1/31/89

/~N

() Malfunction removal will retlore the selected failed channel indication to normal.

Malf Q - Af fects vent stack radmonitor range is 10-' to 10 5

pci/cc.

l l

l I

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)

O l

i Rev: 0 g

Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RM03 A RIT-201 Failed Fuel Gross E RIT-9049 Clean Waste Discharge B RIT-202A Failed Fuel ~ Linear F RIT-9116 Aer Waste Discharge C RIT-4262 S/G Blowdown G RIT-9327 Condensate Recovery-D RIT-6038 RBCCW Malfunction

Title:

Liquid Process Radiation Monitor Failure.

Malfunction Type: Generic / Variable. 100%' equals meter full scale deflection.

Malfunction Cause: Instrument Failure.

plant States: As desired. -

Malfunction Effects:

O Malf A - Malfunction insertion will cause the indicated value.of RIT-202 (letdown total activity monitor) to fail at a fixed position on scale at the selected severity,(e.g. p0%

severity fails the meter at midscale). 10 -to 10- CPM.

Alarm and control functions will occur as appropriate to the severity level in respect to the alarm setpoints. Actual radiation levels will not affect the metered output. Module test functions will appear to operate properly.

The following alarm may actuate:

Letdown Line Radiation Hi/ Failure.

Malf B - Effects similar to Malf A except that the failed fuel letdown radiation monitor is the affected instrument. The meter failure will by independent of its multiplier switch range selection.

i 10 to 10 selected in decades.

l l Malf C Affects liquid process monitors as listed in generic through components above g Except E & F which have high alarms G- only. 10 to 10 CPM.

1 Malfunction removal will restore the selected failed channel indication to normal.

l) Date:

Rev: 0 1/31/89 l

j l

l MALFUNCTION CAUSE AND EPFECTSc f

)

Plant: MP2. ' Malfunction #: RM04-i 1

Malfunction

Title:

Tank Rupture of T19A. l Malfunction Type: Variable. 100% equals.16,000 curies.

Malfunction Cause: Tank Rupture.

Plant Status:' Norial full-power..

Malfunction Effects:

Insertion'of this malfunction will result in theLre'.'. ease of a waste. ,

gas decay tank into the auxiliary building ventilation system.- The' '

flow of the radioactive gas from the tank.into the room will be carried by the ventilation system past the-following process monitors:

() RIT-8434A/B Radwaste Area Vent Exhaust RIT-8999 SFP Pump and Hx Vent ~ Exhaust-RIT-8168 Unit 2 Stack Exhaust RIT-8132A/B Unit 2 Stack Exhaust.

The magnitude of effect of the indication of these instruments will be dependent on severity selection. Cleanup of the air in the auxiliary building will not occur by the ventilation systems..

At 100% severity the above listed radiation monitors will alarm in less than 2 minutes.

This malfunction is nonrecoverable. The simulator must be  ;

reinitialized to restore normal background levels"on ventilation process radiation monitors.

i

REFERENCES:

26029, 26028, 26506 i

i I

L Rev: 0 Date: 1/31/89

.)

_ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . M

MALFUNCTION CAUSE AND EFFECTS.

{}

l MP2 Malfunction #: RP01 j Pl a}t_:

A-TE-112HA I-TE-122HA B-TE-112HB J-TE-122HB C-TE-112HC K-TE-122HC D-TE-1123D L-TE-122HD E-TE-112CA M-TE-122CA F-TE-112CB N-TE-122CB G-TE-112CC 0-TE-122CC H-TE-11'CD P-TE-122CD '

Malfunction

Title:

RPS Noisy Temperature Input.

Malfunction Tyoe: Generic / Variable. 100% equals +/- 25

Oscillation. j l

Malfunction Cause: High frequency cable noise on transmitter. l 1

-, Plant Status: Normal full power.

O Malfunction Effects:

Malf A - Insertion of this malfunction will cause a high frequency oscillation from loop one hot leg transmitter TE-112-HA at the selected severity. The oscillation will be transmitted l to its computer point and control board indicator which will display a visible variance in the value. The averaged hot leg temperature signal from the channel A instruments being l

used by the core protection calculator will also-be affected. AT power will be affected which would cause alarms and trips on High Power, TM/LP or LPD for channel A l

i depending on malfunction severity. RPS Tech Specs will be-i impacted.

Malf B Effects similar to Malf A except that the temperature through elements as noted in the generic listing above may be P- individually affected, as will RFS AT power for that channel.

Malfunction removal will restore the selected failed in.t ument transmitter value to normal.

REFERENCES:

28500~SH. 79, 85 D\j Rev: 0 Date: 1/31/89 l

1 L____________._____

R 1

1 MALFUNCTION CAUSE-AND EFFECTS O '

Plant: MP2 Malfunction #:- RP02 Malfunction

Title:

Spurious Reactor Trip (Momentary at. Manual Pushbuttons).

Malfunction Type: Generic. l Malfunction Cause: Momentary actuation of manual trip pushbuttons. q I

i Plant Status: Normal full power.

Malfunction Effects:

Malfunction initiation will cause the reactor trip circuit breakers to open as if a manual trip from C04 had been initiated. This will cause an immediate reactor / turbine trip. The coil power programmers will be deenergized causing the CEAS to insert into the core. A normal turbine trip will occur due to undervoltage on the CEDM power supply buses which will in turn cause the generator output and field' breakers to open. Station loads will fast transfer to the RSST.

Malfunction removal will have no visible effect on simulator operation. l l

REFERENCES:

CEDM Manual, Reference Plant Data Book, Evunt #36. j I

i l

Rev: 0 Date: 1/31/89 l(

l L_____--_-_-__---_------ - - - - -- o

l

, MALFUNCTION CAUSE AND EFFECTS I

Plant: MP2 Malfunction #: RPO4 )

Malfunction

Title:

Manual Reactor Trip' Failure. ,

i 2

Malfunction Type: Generic.

1

~

Malfunction Cause: Manual Trip PB Contacts Inoperable.

Plant Status: Normal full power.

l Malfunction Effects:

I i

Malf A - This malfunction will prevent the left #1 ' reactor trip  !

pushbutton on C04-from tripping TCB1 and TCBS if it is j depressed. TCB operation will not be prohibited if an automatic breaker trip occurs due to_ actuation of its

()

\_)

undervoltage device.

Malf B - Effects similar to Malf A except the right #1 reactor trip _

pushbutton and TCB's 2 and 6 will be affected.

Malf C - Effects similar to Malf A except the left #2 reactor trip pushbutton and TCB's 3 and 7 will be affected.

Malf D - Effects similar to Malf A except the right #2 reactor trip pushbutton and TCB's 4 and 8 vill be-.affected.

Note: Manual Reactor' Trip is inhibited only if Malf A or B is inserted and Malf C or D is inserted. If one of these combinations are used RPS Tech Specs will be impacted.

Malfunction removal will restore proper operability of the selected failed manual reactor trip pushbutton.

REFERENCES:

32045.

[ Rev: 0 Date: 1/31/89 L______________._ _ _ _ _ _ _ _

MALFUNCTION CAUSE AND EFFECTS 7-s Y

Plant: MP2 Malfunction #: RP05 A-PS 5 E-PS 9 I-PS 13 B-PS 6 F-PS 10 J-PS 14 C-PS 7 G-PS 11 K-PS 15 D-PS-8 H-PS 12 L-PS 16 Malfunction

Title:

RPS Matrix Power Supply Failure.

Malfunction Type: Generic.

Malfunction Cause: Transformer failure, loss of associated 28 VDC output.

Plant Status: Normal full power.

Malfunction Effects:

(3

('~j Malf A - Insertion of this malfunction will cause the deenergization of power supply 5 feeding the AB RPS matrix logic. The indicating light for this power supply located on RC05 will be extinguished.

The AB-1 and AB-2 matrix relays will deenergize causing the K1 and K2 relays to deenergize. With this occurring, TCB's 1, 2, 5, and 6 will trip open. The reactor will not trip as power will be maintained through TCB's 3, 4, 7, 8, and 9.

i Trip matrix ladder lights and trip matrix relay lights will be inoperable on that half of a ladder that is deenergized.

The following alarm will be received: ,

RX Scram Bkr TCB Trip.

i Malf B - Effects similar to Malf A except that PS6, CD-1, and CD-2 j matrix relays will be the major components affected. i Malf C - Effects similar to Malf A except that PS7, AC-1, and AC-2 l

! matrix relays will be the major components affected.  !

l Malf D - Effects similar to Malf A except that PS8, AC-3, and AC-4  ;

matrix relays will be the major components affected. i

/\ Rev: 0  !

(_) Date: 1/31/89 1 i

O)

N, s Malf E - Effects similar to Malf A except that PS9, AD-1, and AD-2 matrix relays will be the major components affected.

Malf F - Effects.similar to Malf A except that PS10, AD-3, and AD-4 matrix relays will be the major components affected.

Malf G - Effects similar to Malf A except that PS11, BC-1, and BC-2 matrix relays will be the major components affected.

Malf H - Effects similar to Malf A except that PS12, BC-3, and BC-4 matrix relays will be the major components affected.

Malf I - Effects similar to Mr.if A except that PS13, BD-1, and BD-2 matrix relays will be the major components affected.

Malf J - Effects similar to Malf A except that PS14, BD-3, and BD-4 matrix relays will be the major components affected.

Malf K - Effects similar to Malf A except that PS15, AB-3, and AB-4 matrix relays will be the major components affected.

-Malf L - Effects similar to Malf A except that PS16, CD-3, and CD-4 matrix rela's j will be the major components affected.

Simultaneous deenergization of power supplies which_will cause all eight TCB's to open will cause a reactor trip.

TCB's 3, 4, 7, and 8 will trip open if any combination of the #3 and #4 matrix relays are deenergized.

Malfunction removal will restore transformer operability to the selected failed matrix power supply.

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! Rev: 0 l Date: 1/31/89 c---__---- -

fg MALFUNCTION CAUSE AND EFFECTS Y_/]

Plant: MP2 Malfunction #: RP06 A - Channel A B - Channel B C - Channel C D - Channel D Malfunction

Title:

TM/LP Calculator Failure.

Malfunction Type: Generic / variable. 0-100% equals 1500 to 2500 psia.

Malfunction cause: Calculator output failure at selected severity. )

1 Plant Status: Normal full power.

l Malfunction Effects:

l Malf A - ' Insertion of this malfunction will fail the thermal

("'N margin / low pressure calculated in channel A at the selected

(_)

i severity level. This will be displayed as the P-VAR variable on the RP5 cal and ind panel. Severity selection of a value greater than the primary system pressure will result in TM/LP channel trip actuation. The minimum TM/LP trip value of 1750 psia will provide protection if a low severity selection is made. RPS Tech Specs will be  ;

impacted. l I

The TM/LP computer and CO3 display will also reflect the i erronecus calculated value.

Malf B Effects similar to Malf A except that the respective through channels TM/LP calculation may be individually failed.

D-Malfunction removal will restore the selected failed channels TM/LP calculated value to normal.

REFERENCES:

39069 SH. 40 l

('T 3 Rev: 0 k> Date: 1/31/89 u_______ . _ _ _ _ _ _ _ _ _ _ _ _ _

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction # RP07 A - Channel A' B - Channel B C - Channel C D Channel D Malfunction

Title:

LPD Calculator Failure.

Malfunction Type: Generic / Variable. 100% severity equals 20%-power down shift on operating curve.

Malfunction Cause: Curve envelope shift due to erroneous calculated power.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - Insertion of this malfunction will result in the shifting of the predetermined axial shape .index operating li'mits used in the calculation of local power density trip and prttrip setpoints. The shape of this envelope will not be chaaged. There will be an increare in ASI limits..

This Malfunction will not affect the calculated axial offset value. RPS Tech specs will be impacted.

Computer, C04, and axial offset limits as displayed on RC05 will reflect the erroneous trip setpoints.

Malf B Effects similar to Malf A except that the respective

! through channels LPD calculation may be individually failed.

D-Malfunction removal will restore the selected failed  !

channels LPD calculated value to normal.

i

REFERENCES:

39069 SH. 41, Fig 2.2 in Tech Specs.

O Rev: 0 (m/ Date: 1/31/89

_ ___m_ . _

/ MALFUNCTION CAUSE AND EFFECT.5

~

Plant: Mr' Malfunction #: RP08 A - Channel A B - Channel B-C - Channel C.

D - Channel D Malfunction

Title:

Delta T Power Calculator Failure.

Malfunction Type: Generic / Variable. 100% equals 125% of Delta T Power Range.

Erroneous Power Calculator, M_alfunction'Cause:

plant Status: Normal full power.

Malfunction Effects:

Malf A - Insertion of this malfunction will set the calculated Delta T power value (B) from the. Delta T power calculator at the severity level. 'This output will also affect the calculations of the TM/LP trip, local power density trip, and Hi Power' Trip. RPS Tech-Specs will be impacted.

Malf B through D- Effects similar to Malf A except that the individual' channel Delta T power calculated values may be failed.

Malfunction removal will restore the selected failed channel Delta'T power calculated value to normal.

REFERENCES:

39069 SH. 40, Reactor Protection Manual.

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I Rev: 0 Date: 1/31/89

______-__-___a

i 1

(} MALFUNCTION CAUCE AND EFFECTS l

Plant: MP2 Malfunction #: RP09  ;

i A - PDT111A E - PDT121A ')

B - PDT111B F - PDT121B {

C - PDTillC G - PDT121C  ;

D - PDTillD H - PDT121D Malfunction

Title:

RCS Flow Transmitter Failure.

Malfunction Type: Generic / Variable. 0-100% equals -8 to +64 psid. ~ 1 l

Malfunction Cause: Transmitter failure.

.i Plant Status: Normal full power.

Malfunction Effects:

a p),

Malf A - Insertion of this malfunction will fail the transmitted D/P value from loop #1 channel A transmitter at the' selected

( severity. The transmitted value will affect the actual flow .

input value for the determination of RPS channel A low RCS '

flow trip and associated loop and steam generator D/P inputs to the computer and CO3 indication. RPS Tech Specs will be impacted. q Malf B through H- Effects similar to Malf A except that the individual loop l differential transmitters as listed in the generic  !

components above may be individually failed.

Malfunction removal will restore the selected failed transmitters output to normal.

REFERENCES:

28500 SH. 77, RPS Manual.

ON Rev: 0 Date: 1/31/89 i

s -

5

,q MALFUNCTION CAUSE AND EFFECTS-LJ Plant: MP2 Malfunction,_#: RP10 A - PT102A B - PT102B C - PT102C D - PT102D Malfunction

Title:

Pzr Pressure Transmitter Failure.

Malfunction Type: . Generic / Variable. 0-100% equals 1500:- 2500 psia.

Malfunction Cause: Transmitter fails at selected severity.

Plant Status: Normal full power.

I Malfunction Effects:

Malf A - Insertion of this malfunction will fail the transmitted

(~N value of the A safety channel of pressurizer pressure at the

( selected severity. The transmitted value will affect the pressurizer pressure inputs for TM/LP and hi-pressure trip generation, and safety. injection actuation. RPS and.ESAS Tech specs will be impacted.

Indicated values of this transmitter on CO3 and C21 will reflect the erroneous value.

Malf B - Effects similar to Malf A except that channel.B safety channel of pressurizer pressure will be the affected value.

Malf C - Effects similar to Malf A except that channel C safety channel of pressurizer pressure will be the affected value.

There is not any C21 indication.

Malf D - Effects similar to Malf A except that channel D safety channel of pressurizer pressure will be the affected value.

There is not any C21 indication.

Malfunction removal will restore the selected failed pressurizer pressure transmitted ~value to normal.

REFERENCES:

28500 SH. 53, 54, 56 and 57 Rev: 0 iso Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS i

)

Plant: MP2 Malfunction #: RP11 A-TE-ll2HA E-TE-122HA B-TE-112HB F-TE-122HB C-TE-ll2HC G-TE-122HC D-TE-112HD H-TE-122HD Malfunction

Title:

RCS Safety Channel Hot Leg Temperature-Transmitter:

Failure. ,

ll Malfunction Type: Generic / variable. 0-100% equals 515* F to 665 F. ]

Malfunction cause: Transmitter failure at selected severity.

Plant Status: Normal full power.

Malfunction Effects:

() Malf A - Insertion of this malfunction will fail the transmitted value of the loop #1 hot leg safety channel temperature  !

instrument at the selected severity. Computer point and CO3 i displays will show the faulty value from the instrument. .

RPS Tech Specs will be impacted. i This temperature input will also feed into the Delta T power  :'

calculator (average T-Hot value used) which will affect the TM/LP and LPD trip setpoints. The Delta T power value will also be compared with the linear'NI output for its respec-tive channel and the maximum value of the two is used as an input to the high power trip unit.

If the temperature selected is above the actual temperature, the Delta T power value will increase. This will raise the calculated TM/LP and possibly make more restrictive the LPD trip setpoints which may make their respective channels trip. The power level input to the VOP trip unit on Channel A will also increase, placing the unit closer to its trip setpoint.

Selection of a lower temperature will reduce the calculated Delta T power value. If the NI power and Delta T power values were initially equal, the LPD, TM/LP and VOPT setpoint and input values will not be affected.

Rev: 0

/]

\_s Date: 1/31/89

-)

.I

. .l

, , l Malf B Effects similar to Malf A except that the transmitters through listed above as generic components may be individually H- affected.

Malfunction removal will restore the selected failed hot leg transmitted value to normal'.

REFERENCES:

28500 SH. 84 i

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Rev: 0 Date: 1/31/89 )

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\~J MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RP12 A-TE-ll2CA E-TE-122CA B-TE-ll2CB F-TE-122CB C-TE-ll2CC G-TE-122CC D-TE-ll2CB H-TE-122CD Malfunction

Title:

RCS Safety Channel Cold Leg Temp' Transmitter Failure.

Malfunction Type: Generic / Variable. 0-100% equals 465 to 615* F.

Malfunction cause: Transmitter failure at selected severity.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - Insertion of this malfunction will fail the transmitted L value of the loop RPS #1 cold. leg safety channel temperature instrument at the selected severity. Computer-point and CO3 displays will also show the faulty value from the .!

instrument. RPS Tech Specs'will be impacted. j l

This temperature input will also feed into the Delta'T power  !

calculator (max loop cold leg value used) which will affect  !

the TM/LP and LPD trip-setpoints. The Delta T power value will also be compared with the linear NI output for its respective channel and the maximum value of the two is used l as an input to the high power trip unit. j If the T-cold value is decreased, but not below the other I cold leg, input to the RPS channel the calculated Delta power level will increase. This will raise the calculated TM/LP and make more restrictive the LPD trip setpoints which .

may make their respective channels trip. The power level  !

input to the VOP trip unit on channel A will also increase which will place the unit closer to its trip setpoint.

Selection of a higher temperature will reduce the calculated Delta T power value if the compared loop temperature is lower. This will reduce the TM/LP trip setpoint on channel A. If the NI power and Delta T power values were initially equal, the LPD and VOPT setpoint and input values will not be affected.

Rev: 0 O~- Date: 1/31/89 i

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/'

( )N -Malf B-through Effects similar to malf A except.that the transmitters listed above as generic-components may be individually H- affected.

. Malfunction removal.will= restore the selected failed.' cold leg transmitted value to normal.

1

.I

REFERENCES:

28500 SH. 79,7 80 i

)

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l Rev: 0 Date: 1/31/89  ;

i

t MALFUNCTION CAUSE AND EFFECTS Flant: MP2 Malfunction #: RP13 A-LT-1113A E-LT-1123A B-LT-1113B F-LT-1123B C-LT-1113C G-LT-1123C D-LT-1113D H-LT-1123D Malfunction

Title:

Safety Channel S/G Level Transmitter Failure.

Malfunction' Type: Generic / Variable. 100% equals maximum output. l Malfunction Cause: Transmitter failure at selected value.

Plant Status: Normal full power.

Malfunction Effects:

fs Malf A - Insertion of this malfunction will fail the A safety channel

/ level transmitter for #1 steam generator at the selected

's) severity. This value will effect the auctioneered low input to channel A low SG level trip, level indication on COS, C21, and automatic aux feedwater initiation logic. RPS Tech specs will be impacted.

Malf B through H- Effects similar to Malf A except that the level transmitters for both steam generators listed above as generic component may be individually affected. B, C, and D transmitter outputs are not used for display on C21.

Malfunction removal will restore the selected failed steam generator level transmitters output to normal.

REFERENCES:

28500 SH. 370, 371, 372, 373.

( Rev: 0 Date: 1/31/89 1

,.s MALFUNCTION CAUSE AND EFFECTS

G Plant: MP2 Malfunction #: RP14 A-PT-1013A E-PT-1023A B-PT-1013B F-PT-1023B C-PT-1013C G-PT-1023C D-PT-1013D H-PT-1023D Malfunction

Title:

Safety Channel S/G Pressure Transmitter Failure.

Malfunction Type: Generic / Variable. 100% equals 1000 psia.

Malfunction cause: Transmitter failure at selected severity.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - Insertion of this malfunction will fail the A safety channel gs pressure transmitter for #1 steam generator at the selected t

' ) severity. This value will affect the auctioneered low input to channel A low SG pressure reactor trip and ESAS developed MSI signals. The value will also be displayed as a computer point and indication on Co5. RPS and ESAS Tech Specs will be impacted.

A low failure below 500 psia will result in RPS channel A low pressure reactor trip and MSI signal development.

Malf B through H- Effects similar to Malf A except that the steam generator pressure transmitters as listed above in generic components may be individually failed. B, C, and D transmitter outputs do not go to the computer for display.

Malfunction removal will restore the selected failed '

transmitters output to normal. l

REFERENCES:

28500 SH. 340, 341, 342, 343.

/~T Rev: 0

(_) Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RPl5 A - Channel A B - Channel B C - Channel C D - Channel D Malfunction

Title:

Wide Range Channel Failure.

Malfunction Type: Generic / Variable. 0-100% equals 10 (-8) - 150%.

Malfunction Cause: Summing Amplifier Failure.

Plant Status: Normal full power.

Malfunction Effects:

O Malf A - This malfunction will fail the output of channel A wide range NI output at the severity selected. Rate of change of power, indicated power level at RC05A, C04, and computer displays will be affected. Audio countrate will not be affected, when in use, by this malfunction. Tech Specs may be impacted.

If a severity level which corresponds to less than 10E-4%

power level is selected, level 1 and 2 wide range bistable will deenergize which will permit functions of the zero power mode bypass circuitry to operate.

Calibrate and trip test functions of the wide range channel will not affect the displayed and output values.

Malf B Effects similar to malf A except that the wide range through channels listed above as generic components may be indiv-H- idually affected.

Malfunction removal will restore normal operation of the summing amplifier on the selected failed WR NI.

i

REFERENCES:

RPS Manual h Rev: 0 ,

Date: 1/31/89 '

MALFUNCTION CAUSE-AND EFFECTS Plant: MP2 Malfur ction #: RP16' A - Channel A B - Channel B C - Channel C D - Channel D Malfunction

Title:

Wide Range Channel Noisy.

Malfunction Type: Generic / Variable. 0-100% equals 0-1000 counts above background.

Malfunction Cause: Sporadic Electrical Interference.

Plant Status: Reactor Start-up.

Malfunction Effects:

() Malf A - This malfunction will cause channel A wide range logarithmic-channel to exhibit random spikes ~up to 1000 CPS higher:than an unaffected channel at full severity level. The rate of change of power circuitry on channel A will reflect the varying power level:due to the sporadic noise. If channel A is selected on the audio countrate monitor the noise will be

~

reflected. Tech Specs may be impacted. l Attempted calibration of the channels detector will'also be ,

affected by this malfunction, j Malf B Effects similar to malf A except that the wide range  ;

through channels listed above as generic components may be indiv-  ;

D- idually affected.  ;

Malfunction removal will restore the normal signal to the selected failed wide range channel, i

REFERENCES:

RPS Manual 1

i Rev: 0 ,

Date: 1/31/89 i

_ _ . _ _ . . _ . . _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ _m -_w 44L-

g- MALFUNCTION CAUSE AND EFFECTS V-Plant: MP2 Malfunction s: RPl7 A - Channel A-B - Channel B C - Channel C D - Channel D Malfunction

Title:

Wide Range High voltage Failure.

Malfunction Type: Generic.

Malfunction cause: High Voltage Power Supply Output Fails.

Plant Status: Normal full power / Reactor Startup.

Malfunction Effects:

(~s Malf A - This malfunction will cause a loss of high voltage to wide tj range logarithmic channel A. Power level indication on channel A percent power and CPS displays will decrease to minimum metered and computer output values. Its chamber voltage will decrease to zero and its associated high voltage bistable will trip. Startup rate indication will respond to the drop in indicated level. Level 1 and 2 bistable functions will be resettable. Tech Specs may be impacted.

Calibrate and trip test functions of power level indications will still be operable.

Malf B Effects similar to malf A except that the individual wide through range channels listed above as generic components are D- affected.

Malfunction removal will restore high voltage to the selected failed channel.

REFERENCES:

RPS Manual, NLW-3 (WR channel manual)

Rev: 0

% Date: 1/31/89

1

.l MALFUNCTION CAUSE ANDLEFFECTS

{-

Plant: MP2 Malfunction #: RP18.

A - Channel A B - Channel B C - Channel C a

-D - Channel D l 1

Malfunction

Title:

Power Range Channel Failure. ,

Malfunction Type: Generic / Variable. 0-100% equals 0-200% indication.

Malfunction Cause: Power summer failure.

Plant Status: Normal full power.

Malfunction Effects:

1 1

Malf A - This malfunction will fail the summed power output. signal from channel A linear range nuclear instrument. Individual i O- upper and lower linear range detector outputs will not be affected. Outputs of this summer which will be affected are:

Core protection calculator inputs for the determination of Q power, TM/LP and high power trip setpoints.

Level one bistable functions to inhibit LPD, loss of LPD, i and loss of load trips at less than 15% power.. ]

LPD trip setpoint determination.

Rod drop circuitry.

I Tech specs will be impacted.

Malf B Effects similar to malf A except that the power range '

through channel as listed in the generic components above may be D- individually affected.

Malfunction removal will restore the selected failed power range safety channel summer output to normal.

REFERENCES:

RPS Manual, Sys Desc

( ) Rev: 0 y Date: 1/31/89

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7 MALFUNCTION CAUSE AND EFFECTS- j i

Plant: MP2 Malfunction 0: RP19-A - LRLA j B - LRLB j C - LRLC i D - LRLD I 1

f Malfunction

Title:

Power Range Lower Detector Failure. j i

l Malfunction Type: Generic / Variable. 0-100% equals 0-100% indication.

f 1

Malfunction Cause: Lower detector amplifier failure. 1 i

Plant Status: Normal full power.  ;

Malfunction Effects:

Malf A - This malfunction will fail the lower detector output signal

('j

(

g from channel A linear range nuclear instrument at the selected severity level. RC05 and computer displayed outputs will reflect the subchannel failure. Outputs which j

J will be affected are as follows: i I

RPS LPD trip setpoint and reference input ]

I Comparator averager input and assoc alarm functions ')t Core protection calculator inputs for the determination of Q power, TM/LP trip setpoint, and high power trip Level one bistable function to inhibit LPD and loses of load trips 1

Rod drop circuitry l

Calibration and channel trip test functions will have no effect on the channel's output or display.

RPS Tech Specs will be impacted, l.

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('

Date: 1/31/89  !

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1 Malf B Effects similar to malf A except that the lower power range ,

through detector as listed in the generic components above may be 1 D- individually affected.- I Malfunction removal will' restore. the selected f ailed lower power range safety channel amplifiers output to normal.

i

REFERENCES:

RPS Manual, Sys Desc i

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Rev: 0 Date: 1/31/89 i

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MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RP20*

a A - LRU A B - LRU B C - LRU C D - LRU D Malfunction

Title:

Power Range Upper Detector Failure. j 1

Malfunction Type: Generic / Variable. 0-100% equals 0-100% indication.

-) 4 Malfunction cause: Upper detector amplifier failure.

1 Plant Status: Normal full power.

)

I Malfunction Effects: j Malf A - This malfunction will fail the upper detector output signal 1 g' from channel A linear range' nuclear instrument at the selected severity level. RC05 and computer displayed )

outputs will reflect the subchannel failure. Outputs.which will be affected are as follows:

RPS LPD trip setpoint and reference input 1

Comparator averager input and assoc alarm functions Core Protection calculator inputs for the determination .

of Q power, TM/LP trip setpoint, and high power trip ]

Level one bistable function to inhibit LPD and loss of I load trips 1

Rod drop circuitry.

RPS Tech specs will be impacted. j Calibration and channel trip test functions will have no effect on the channel's output or display.

l l

Rev: 0 Date: 1/31/89 I

__-._____-__-__---__________O

a l

Malf B Effects similar to malf A except that the upper power range j through detector as listed in the' generic components.above may be-D- individually.affected.  !

Malfunction removal will-restore the selected failed upper

)

power range safety channe1~ amplifiers output to normal.

REFERENCES:

RPS Manual, Sys Desc.

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Date:

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i MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RP21 j A - Channel A I B - Channel B C - Channel C D - Channel D l Malfunction

Title:

Power Range Channel Noisy.

l 100% equals +/--5% ..(10% of total Malfunction Type: Generic / Variable.  !

band width)

Malfunction Cause: Noisy amplifier causes high frequency oscillation around indicated power level. -j Plant Status: Normal full power. .

Malfunction Effects:

Malf A - This malfunction will cause a high frequency oscillation in the summed power. output signal of linear power range channel A at the selected severity. Upper and lower-detector outputs and displays will.not be affected:by this i malfunction The following outputs will show the effects.of I the power level oscillation:

Summed channel power level output indication'on RPSCIP. l l

CPC inputs for the determination of Q power, TM/LP trip setpoint, and high power trip'

- Level one bistable functions to inhibit.LPD, and loss of load-trips LPD trip setpoint determination l

L -

Rod drop circuitry.

l RPS Tech specs will be impacted.

Rev: 0

-\

Date: 1/31/89

Malf B Effects similar to Malf A'except that the power range through. channels as listed above in generic components may be D- individually affected.

Malfunction. removal will restore the selected failed-power.

range safety channels output to normal.

REFERENCES:

RPS Manual, Sys Desc O

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Rev: 0 1/31/89 l

MALFUNCTION CAUSE AND EFFECTS

(

Plant: MP2 Malfunction #: RP22 A-LRA B-LRB-C-LRC D-LRD Malfunction

Title:

Power Trip Test Interlock Failure.

Malfunction Type: Generic.

Malfunction-Cause: High voltage bistable failure causes false power trip test interlock.

Plant Status: Normal full power.

Malfunction Effecte:

( Malf A - This malfunction will cause inadvertent operation of the power trip test interlock on channel A of the RPS. It will cause the bistable units for high power, TM/LP, and local power density to trip. The LPD trip will not occur if power is less than 15%. None of these channels.will trip if they are bypassed with their trip bypass keys. RPS Tech-specs will be impacted.

Q-met to the metrascope and Q-PRC to the power ratio calculator will also be blocked.

The power trip test-interlock feature is normally activated if the delta T power calculator test switch is moved from its operate position or high voltage is lost to the linear range NI for the respective channel.

The following alarms will be received:

NIS Hi Pwr Trip Ch A TM-LP Trip Ch A LCL Pwr Dense Trip Ch A.

Rev: 0 Date: 1/31/89

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I ~Malf B Effects similar to malf A except that the power trip test through interlock failure will affect the associated RPS channel l D- listed in the generic components above.  !

Malfunction removal will restore the selectedLfailed high j voltage bistable operation to normal. 1

REFERENCES:

RPS Manual, Sys Desc

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Date:

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(~'N MALFUNCTION CAUSE AND EFFECTS

'tsE ,

i Plant: MP2 Malfunction #: RP23 )

A - LR Channel A I B - LR Channel B j C - LR Channel C l D - LR Channel D l I

Malfunction

Title:

Power Range Random Noise. l I

Malfunction Type: Generic / Variable. 100% equals 2 minute delay between 10% spike.

Malfunction cause: Electrical interference within calorimetric adjustment circuitry causes variable delay with a fixed momentary power spike.

1 Plant Status: Normal full power.

(

k/ Malfunction Effects:

Malf A - This malfunction will cause the summed power output of linear range NI channel A to show a 10% spike in power at the frequency as selected by malfunc. ion severity. The rise in power will be of sufficient magnitude and duration to ,

cause a VOP trip on channel A. The signal returning to )

normal will cause the associated rod drop bistable to trip.

Upper and lower sub-channel detector power values will not reflect the power spike. RRS Tech specs will be impacted.

Malf B Effects similar to malf A except that the random spike will through appear on the selected linear range channel as listed above D- in generic components.

Malfunction removal will stop the power spike on the l selected failed linear range NI.

REFERENCES:

RPS Manual I

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Rev: 0 Date: 1/31/89 l

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l MALFUNCTION CAUSE AND EFFECTS i

RP24 Plant: MP2 Malfunction #: i A - PT8113 B - PT8114 i C - PT8115 1 D - PT8116 Malfunction

Title:

Safety Channel Containment Pressure Transmitter  ;

Failure.

Malfunction Type: Generic / Variable. 100% equals 60 psig.

Malfunction Cause: Transmitter failure at selected severity.

Plant Status: Normal full power. ]

Malfunction Effects:

Malf A - This malfunction will fail the contair.'ent pressure transmitted value to RPS channel A and ESF sensor cabinet A.

The faulty value will be displayed as a computer point, meter / recorder displays on C01/C01R and ESF sensor. cabinet A, and RPS metered input from its respective. bistable trip unit. If this pressure exceeds 3.8 psig bistable BA101 on-ESF sensor cabinet "A" will trip placing both actuation cabinets in 1/3 logic for SIAS, CIAS, and EBFAS development.

If the pressure from this transmitter exceeds 3.3 psig the high containment pressure bistable on RPS channel A will )i trip placing the RPS in 1/3 logic for a reactor trip on high containment pressure.

If the pressure from this transmitter exceeds 25.8 psig bistable BA102 on ESF sensor cabinet "A" will trip placing both actuation cabinets in 1/3 logic for CSAS development.  ;

i The following alarms may be received:

CTM Press Hi A l CTM Press Hi Hi A CTM Hi Press Trip Ch A.

1

() Date:

Rev: 0 1/31/89 l

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_a ESAS an'd RPS Tech Specs will be' impacted.

Malf B Effects similar to Malf A except'that the pressure trans-through mitters listed above as generic components may be indiv- j D- idually affected. There is no recorder display on ColR. j j

REFERENCES:

28500 SH. 840, 841, 842, 843 I

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Rev: 0 Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS

[~

Plant: MP2 Me.1 function #: RP25 l i

A-TCB-1 E-TCB-5 {

B-TCB-2 T-TCB-6 j C-TCB-3 G-TCB-7 D-TCB-4 H-TCB-8 Malfunction

Title:

Inadvertent Reactor Trip Circuit Breaker Opening.

1 Malfunction Type: Generic, j I

Malfunction Cause: Loss of Trip Control Power.

Plant Status: Normal full power.

Malfunction Effects:

4 g Malf A - This malfunction will cause reactor trip circuit N breaker #1 to be opened by actuation of its under-voltage device. Circuit breaker status indication at C04 and RC05 will be lost. A digital computer point and associated C04 panel alarm will annunciate on the .

opening of the breaker.

The breaker will not he able to be reset and shut.

The following alarm will be received:

RX Scram Bkr TCB-1 Trip.

Malf B Effects similar to malf A except that the reactor trip.

through circuit breakers listed above as generic components may H- be affected' individually.

1

, If the proper breakers are opened to cause a loss of a CEDM power supply bus A turbine trip will occur on l reactor trip bus undervoltage. All of the remaining i closed Tcs's will then open as a result of a reactor trip on loss of load.

() Rev:

Date:

0 1/31/89

1 I

Malfunction removal will restore proper operation of the selected failed TCB undervoltage device. Thus,

. allowing the breaker to be reset.

4 1

REFERENCES:

39069 SH. 32, 61, 32045 SH. 1-8 )

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Rev: 0 Date: 1/31/89 i

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MALFUNCTION CAUSE AND EFFECTS O

Plant: MP2 Malfunction #: RX0lA RC-100E RX0lB RC-100F Malfunction

Title:

Pzr Spray Valve Controller Failure.

)

Malfunction Type: Generic / Variable. 100% equals valve full open.

Malfunction Cause: Controller output failure in Auto and Manual Mode.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will fail the automatic and manual output of HIC-100E which will directly affect the operation of 2-RC-100E. If this valve is failed open pressurizer pressure will decrease. The selected pressurizer pressure 9 controller will energize proportional heaters in an attempt to maintain pressure. Backup heaters will energize if pressure drops below 2200 psia. If the ability of the spray system to lower the pressure exceeds the heater capacity, pressure will decrease to cause the RPS and possibly the engineered safeguards systems to actuate.

The effects of this malfunction can not be mitigated by taking manual control of HIC-100E or HIC-100E2 at C21 to operate the spray valve.

The valve may also be failed shut which will reduce the systems ability to lower system pressure automatically.

Malf B - Effects similar to Malf A except that HIC-100F and 2-RC-100F will be the major affected components.

Malfunction removal will restore automatic and manual control of the selected failed spray valve to normal.

REFERENCES:

Reference Plant Data Book, Events #27 and #33.

Rev: 0 O Date: 1/31/89 1

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RX02A - Prop Grp 1 RX02B - Prop Grp 2 RX02C - B/U Grp 1 RX02D - B/U Grp 2 RX02E - B/U Grp 3 RX02F - B/U Grp 4 Malfunction

Title:

Loss of Pzr Heaters.

Malfunction Type: Generic / Variable. 100% equals minimum (zero) output.

Malfunction Cause: Open Heater Elements.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - Insertion of this malfunction will reduce the capacity of proportional heater bank #1 from its rated output value of 160 KW. Pressurizer Heater Tech Specs will be impacted for RX02A and RX028.

Bus 22E current will reflect the effects of the reduced electrical current drawn by the failed heater.

As the severity level is increased, pressurizer pressure will decrease, resulting in a higher heater demand signal from the pressure controller in service.

Malf B Effects similar to Malf A except that the heater group through failed will be as listed in the generic components above.

F- Note that the selected failed group must be operating for this malfunction to have any effect. Proportional heaters will have an individual bank capacity of 160 KW each.

Back-up heater banks will be rated at 320 KW each.

Malfunction removal will restore full capacity to the selected failed heater group.

REFERENCES:

System Description.

h Rev: 0 Date: 1/31/89

,3 MALFUNCTION CAUSE AND EFFECTS J

Plant: MP2 Malfuncti n #:

~~~

RXO3A PT100X RX03B PT100Y Malfunction

Title:

Pzt Pressure Control Transmitter Failure.

Malfunction Type: Generic / Variable. 0-100% equals 1500-2500 psia.

Malfunction Cause: Pressure transmitter fails at selected severity.

)

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will fail the pressurizer pressure transmitter value from the channel X control transmitter at the selected severity.

rs If it is failed above the actual pressure and channel X is

'- ) in control system, RCS pressure will be reduced in an attempt to make the transmitted value equal to the  ;

controlled setpoint. The faulty transmitter output will i be displayed as a computer point, controller meter output, and recorder point (PR-100).

1 If failed below the actual pressure, the pzr backup heater j will energize, the proportional heater output will go to maximum and the spray valves will close.

The following alarms will operate:

Pzr Press Channel X (Y) Hi/Lo Pzr Deviation l Effects of this malfunction may be mitigated by taking manual control of pressurizer pressure controller PIC-100X ,

and/or its associated controlled components or shifting l control to channel Y.  !

l Malf B - Effects similar to Malf A except that the Channel X l pressure control transmitter PT-100Y will be affected.  !

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Rev: 0 I(\_]- Date: 1/31/89 i

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I Malfunction removal will restore the transmitted value I

from the selected failed pressurizer pressure centrol i transmitter to normal.

REFERENCES:

28500 SH. 50, Sys Desc.

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('~ Rev: 0 4

Date: 1/31/89

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i

- . MALFUNCTION CAUSE AND EFFECTS J

Plant: MP2 Malfunction #: RX04A .LT110X RXO4B LT110Y -

Malfunction

Title:

1 Pzr Level Transmitter Failure.  ;

Malfunction Type: Generic / Variable. 0-100% equals 0-100% indicated level. l 1

Malfunction Cause: Level Control Transmitter Fails at Selected- ,

Severity.  :

Plant Status: Mormal full power.

j Malfunction Effects:

Malf A - This malfunction will fail the channel X transmitted value ]

i

(~)

(_/

for pressurizer level control at-the selected severity.

The faulty transmitted value will be displayed as a computer point, controller metered output, recorder point (LR-110) and a C21 meter display. Tech Specs may be impacted.

If channel X is selected as the controlling channel and the level selected is below the actual level the following actions will occur to cause the-actual level to increase:

- B/U Charging Pumps Start to Restore Level

- Letdown Valve (s) Shut to Minimum Position

- Heater (all) Deenergize if Less Than 22% Level (Dependent on Channel Defeat Switch Pos)

- Low Level Alarm (-4.2% Deviation Between Setpoint and Level).

If the level selected is above the. actual level the following actions will occur to cause the actual level to decrease:

- Any B/U Charging Pumps Running Will Stop

- etdown Valve (s) Open

- All Heaters Energize (+3.6% Deviation Between Setpoint and Level).

Rev: 0 Date: 1/31/89

i The effects of this malfunction may be mitigated by taking manual control of LIC-110X and/or manual control of its associated controlled components. Selection of the  ;

nonaffected channel'(Y) may be used to restore pressurizer i level.

Malf B - Effects similar to Malfunction A except Channel Y will be affected.

Malfunction removal will restore the transmitted value  !

from the selected failed pressurizer level control transmitter to normal. j

REFERENCES:

28500 SH. 69, Sys Desc. I

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4 1

l O Rev:

Date:

0 1/31/89

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[ [ MALFUNCTION CAUSE AND EFFECTS-Plant: MP2 Malfunction 4: RX05A - PT.4298 l RX05B - PT 4300 ,

i Malfunction

Title:

Turbine First Stage Press Trans Failure.

Malfunction Type: . Generic / Variable. ~0-100% equals 0-750 psig. y

.1 Malfunction Cause: Transmitter failure at selected severity.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will fail the turbine first stage pressure transmitted value to RRS Unit 1 (X channel)'at the selected severity. The failed value will be indicated )

as a computer point, recorder point (TR-lll), and as a I

() selectable output display point in RRS cabinet #1.

The following alarm may be received:

l T-avg - T-ref Hi/Lo (dependent on RRS channel selected). ]

Malf B - Effects similar to Malf A except that the first stage pressure transmitted to RRS' Unit 2 (Y Channel) will be the affected component.

1 Malfunction removal will restore the selected failed first stage pressure transmitter output to normal.

REFERENCES:

28500 SH. 510, RRS Manual.

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() Rev:

Date:

0 1/31/89

{

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction'4: RX06A RRS#1 RXO6B RRS#2 l

Malfunction

Title:

Tavg Program Calculator Failure.

Malfunction Type: Generic / Variable. 0-100% equals 515-615'r.

Malfunction Cause: Tavg output from RRS Tavg calc fails at selected severity.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - Insertion of this malfunction will result in failure of the Tavg output, as calculated in RRS unit #1, at the selected severity level. The failed value will be directly indicated as a computer point, recorder point O display (TR-111), and as a selectable output display point on RRS cabinet #1.

Pressurizer level programmed setpoint from RRS #1 will vary directly with the erroneous Tavg signal. The CVCS system will respond in an attempt to match the controlled level setpoint.

The steam dump demand signal will be held at a fixed value if a trip occurs. Depending on the severity level, this may inhibit the quick open signal, and hold the bypass and ATM steam dumps open when the actual temperature has dropped low enough for them to shut the atmospheric and steam dump valves from opening (less than 535 F).

Effects may be mitigated by switching to other RRS channel or taking manual control of CVCS functions.

Malf B - Similar to Malf A except that the calculated Tavg value in RRS #2 will be the affected component. '

Malfunction removal will restore the selected failed calculated program value to normal.

i RRS Manual.

REFERENCES:

Date: 1/31/89

-MALFUNCTION CAUSE AND EFFECTS

{ }.

Plant: MP2 Malfunction #: ' RXO7A TE'111X RX07B TE 121X-Malfunction

Title:

RCS Control Channel Hot Leg Temperature Transmitter Failure.

Malfunction Type: Generic / Variable. 0-100% equals 515-615*r.

Malfunction cause: Transmitter failure at selected severity.

Plant Status: Normal full power.

Malfunction Effectst.

Malf A - This malfunction will fail the loop fl hot leg temperature transmitters output for.the control channels at the selected severity. The faulty value will be transmitted O as an input value to both reactor regulating control cabinets for Tavg calculation, computer point, and CO3 metered display.

If the temperature is failed high, the average calculated temperature within both RRS units will increase. The remote functions may be used to deselect faulty TH and TC inputs to the RRS units. The higher TH value will also cause the calculated SMM temperature to decrease.

If the temperature is failed low, the average calculated temperature within both RRS units will decrease. This decrease will cause a' decrease-in Pressurizer Level Setpoint with resultant change in control of the letdown and charging system.

Operate actions, through remote functions, will remove the effected TE from the RRS.

The following alarm may be received:

RC Loop 1 Hot Leg Temp Hi Tavg - Tref Hi/Lo.

O\ Rev:

Date:

0 1/31/89

i I

() Malf B -- Effects similar to MalfEA except that loop #2 hot' leg control' channel temperature transmitters' output.will be the major affected component.

Malfunction removal will restore the-selected failed control channel TH transmitters output to normal.

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REFERENCES:

28500 SH. 73, RRS Manual.

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Rev: 0 Date: '1/31/89  ;

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r' . MALFUNCTION CAUSE AND EFFECTS

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Plant: MP2 Malfunction #: RXO8A - TE111Y q RX08B - TE115 I RXO8C - TE121Y  !

RXO8D - TE125 Malfunction

Title:

RCS Cold Leg Temperature Transmitter Failure.

Malfunction' Type: Generic / Variable. 0-100% equals 0-1000 deg. F.

- Malfunction Cause: Temperature transmitter fails at selected I i

severity.

l Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will fail loop 1A cold leg transmitters

/T'N control channel temperature output at the selected

\ severity. Effects of this malfunction will be dependent  !

on which TC value is selected to RRS through HS-111 at-CO3by operator actions. J If TE-111Y is selected to be received ~by RRS, the following functions / displays will be affected:

Computer Point and Temperature Indication (on TI-111Y) at CO3 (515 to 615 F)

RRS TC Input from Loop #1 Hi TC Alarm Development.

l If TE-115 is selected to be received by RRS, the following function / displays will be affected if TE-111Y is failed:

i Recorder point (TR-115), and metered temperature indi-cation on TI-115 at co3 (0-750* F) i Generation of low temperature over pressure protection l alarms and PORV operation which are HS-1402 dependent. i Computer point (0-750 F)

() Rev:

Date:

0 1/31/89 i

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() Malf B - Effects similar to Malf A except that loop 1B cold leg control transmitters output will be the major affected component.

Malf C - Effects similar to Malf A except that loop 2B cold leg control transmitters output will be the major affected component.

Malf D - Effects similar to Malf A except that loop 2A cold leg control transmitters output will be the n.ajor affected component.

Malfunction removal will restore the selected failed control channel TC transmitters output to normal.

REFERENCES:

28500 SH. 75A, B, 99A, B.

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() .Rev:

Date:

0 1/31/89 l I

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,-s MALFUNCTION CAUSE AND EFFECTS ks Plant: MP2 Malfunction #: RXO9A PT103 RXO9B PT103-1 Malfunction

Title:

RCS Low Range Press Transmitter Failure. l Malfunction Type: Generic / Variable. 0-100% equals 0-1600 psia.

Malfunction cause: Transmitter failure at selected severity.

Plant Status: Shutdown Cooling Operations.

Malfunction Effects:

Malf A - This malfunction will fail the pressurizer pressure transmitted value from PT103 at the selected severity.

The faulty value will be displayed on meters located at e CO3 and C21, and as a computer point. Tech specs will be  !

. s impacted.

If the output is failed at a value greater than 450 psia with temperature less than 280 deg F, the over pressure protection circuit will open PORV 2-RC-404 in an attempt to lower the pressure. Arming of this circuit will be dependent on TC-125 output and HS-1404 position.

If the output is failed at a value greater than 280 psia, shutdown cooling isolation MOV-652 will shut and will not be able to be reopened.

The value from this transmitter will affect the calculated pressure and temperature values from the subcooled margin monitor and the operation of the SI tank outlet valves SI-634 and SI-644.

The following alarms are affected by this transmitter's output:

Reset HS-1404 to Low Low Temp Over Press T-125 P-103.

Rev: 0 O' Date: 1/31/89.

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' () Malf B - Effects similar to Malf A except that the. output'of PT-103-1 will~be affected. 'It has similar output displays

.but controls PORV-402, its associated alarms, the function.

of SI tank outlet MOV's SI-614 and 624, and SDC isol valve-SI-651.

Malfunction removal will restore the transmitted output of.

the selected failed low range pressure transmitter to 1 normal. )

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REFERENCES:

28500 SH. 99A, 99B,.32007 SH. 24, 32008, SH. 33, 39, 40, 28500 SH. 75A, 75B.

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(). Rev:

Date:

0 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RX10A FT5268 RX10B FT5266 RX10C FT5269 RX10D FT5267 Malfunction

Title:

S/G Feed Flow Transmitter Failure. j i

i Malfunction Type: Generic / Variable. 0-100% equals 0-6.3 E6 lbm/hr.

Malfunction Cause: Transmitter Failure.

I Plant Status: Normal full power.

Malfunction Effects:

Malf A - Malfunction insertion will fail the feed flow transmitted value as measured by the #1 feed line primary transmitter

, at the selected severity. Displays of the faulty value will consist of computer and recorder point.(FR-5301).

This flow is averaged with the backup flow.

,l If the value of flow is failed so that it is lower than i the steam flow, the feed regulating valve to #1. steam generator will open, causing the steam generator level to rise. If the level error equals or exceeds the flow .

error, steam generator level will be maintained (assuming high level turbine trip setpoint is not i.. ached).

If the value of flow is failed so that it.is higher than the actual steam flow, the feed regulating valve to #1 steam generator will close causing the steam generator level to decrease. If the level error equals or exceeds the flow error, steam generator level will be maintained l (assuming low level reactor trip setpoint is not reached).

The following alarm may be received:

"S/G Level Deviation: I 1

The' operator can mitigate the problem either by deselected at C05, or going to manual on the feed controller.

Rev: 0 i Date: 1/31/89 l

1 l

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() Malf B - Effects similar to Malf A except that the backup feedwater flow transmitter on the #1 feedwater line will be the major affected component.

3

{

Malf C - Effects similar to'Malf A except that the' primary feedwater flow transmitter on the #2 feedwater line will  !

be the major affected component.

Malf D - Effects-similar to Malf A except that the backup feedwater f flow transmitter on the #2 feedwater line will be the major affected component.

Malfunction removal will restore the output of the '

selected f ailed feedwater flow transmitter to normal.

REFERENCES:

26005, 82N56704 (Feedwater control System), 28500 SH. )

588, 589 .

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Rev: 0 O'.

Date: 1/31/89

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j MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RX11A FT4243 I RX11B FT4244 RX11C FT4241 RX11D FT4242 i Malfunction

Title:

Main Steam Flow Transmitter Failure.

Malfunction Type: Generic / Variable. 0-100% equals 0-6.3 E6 lbm/hr.

I Malfunction Cause: Transmitter Failure.

Plant Status: Normal full power. l Malfunction Effects:

)

Malf A - Malfunction insertion will fail the steam flow transmitted )

value as measured by the #1 steam line primary transmitter l at the selected severity. Displays of the faulty value j

(_/ will be by computer and recorder point (FR-5301). This i flow is averaged with the backup flow.

If the value of the flow is failed so that it is lower I than the feed flow, the feed regulating valve to #1 steam ,

generator will close, causing the steam generator level to i decrease. If the level error equals or exceeds the flow  !

error, the steam generator level will be maintained '

(assuming that the low level trip setpoint is not reached).

If the value of flow is failed so that it is higher than the feed flow, the feed regulating valve to #1 steam generator will open, causing the steam generator level to  :

increase. If the level error equals or exceeds the flow error, steam generator level will be maintained (assuming that high level turbine trip setpoint is not reached).

The following alarm may be received:

"S/G Level Deviation" i

The operator may mitigate the problem by deselecting at Co-5 the faulty detector or going to manual at the feed reg station.

( Rev: 0 Date: 1/31/89

i I

g~ Malf B - Effects similar to Malf A except that the backup steam j flow transmitter on the #1 main steam line will be the affected component.

Malf C - Effects similar to Malf A except that the primary steam flow transmitter on the #2 main steam line will be the affected component. i Malf D - Effects similar to Malf A except that the backup steam flow transmitter on the #2 main steam line will be the affected component. i Malfunction removal will restore the faulty transmitters' output to normal.

REFERENCES:

26002, 82N56704 (Feedwater Control System), 28500 SH. 495, 496 4

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() Rev:

Date:

0 1/31/89

1 1

(~ MALFUNCTION CAUSE AND EFFECTS

\m, ,

Plant: MP2 Malfunction #: RX12A LT5271 l RX12B LT5272 >

RX12C LT5273 )

RX12D LT5274 j Malfunction

Title:

S/G Level Transmitter Failure (Rx Control Channel)

Malfunction Types Generic / Variable. 0-100% equals 0-100% Indicated Level.

Malfunction Cause: Transmitter Failure.

Plant Status: Normal full power.

)

1 Malfunction Effects: I Malf A - This malfunction will fail the primary level transmitter  !

l for feedwater level control on #1 steam generator at the N selected severity. The selected lower level between the primary and backup level transmitted will be displayed at COS on LI-5271. .

Failing this level low will cause the feed regulating valve to #1 steam generator to open, causing the actual  !

level to increase. The high downcomer level override will not activate if this level is failed at a value of less than 90%. If the level in the steam generator rises .

sufficiently high enough to cause carryover to the turbine, a turbine trip will be developed.

Failing this level high (greater than 90%) will cause the feed regulating valve to #1 steam generator to shut-and the turbine to trip (if the high level trip feature is not defeated).

If the high level trip feature is defeated, steam generator level will decrease to cause a reactor trip on the low steam generator water level.

The following alarms may actuate:

Steam Generator Level Hi/Lo Steam Generator Level Hi/Hi f S/G Level Deviation.

Rev: 0 Date: 1/31/89

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) The operator can mitigate this event by deselecting the 1 I

faulty transmitter input to the level control system at C05 or going to manual on the feed station.

Malf B - Effects similar to malf A except that the backup #1 steam generator level transmitter will be the affected component.

I Malf C - Effects similar to Malf A except that the primary #2 steam generator level transmitter will be the affected component.

Malf D - Effects similar to Malf A except that the backup #2 steam generator level transmitter will be the -ffected component.

Malfunction removal will restore the selected failed steam generator level transmitters' output to normal.

REFERENCES:

28500 SH. 591, 592, 82N56704 (Feedwater Control System), 32012 SH. 31, 32, 32006 SH. 4A (1)

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1 Rev: 0 Date: 1/31/89

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(~~ -

' MALFUNCTION CAUSE AND EFFECTS

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Plant: MP2 Malfunction #: RX13A 2MS190A 1 RX13B 2MS190B ]

)

1

~ Malfunction

Title:

Atmospheric Dump Valve Failure.

Malfunction Type: Generic / Variable. 100% equals valve fully open ]

(885, 000 lbm/hr). j i

Malfunction Cause: E/P Controller Failure.

1 Plant Status: Normal full power.

i Malfunction Effects:

)

Malf A - This malfunction will result in a steam' leak to the l atmosphere from #1 main steam header through its respective atmospheric dump valve. The leakage will cause O an increase in steam flow from both steam generators, causing a decrease in their steam pressure. Instantaneous high severity leaks will cause swell characteristics to be q

1 observed.

The increased steam flow will cause the RCS average temperatures to decrease leading to lower pressurizer ,

levels and pressures. The reactor power level will-increase possibly leading to a variable overpower reactor trip. The reduced steam line pressure will cause the generator electrical output to decrease, i

The atmospheric dump valve pcsition indication will show l that the valve is not fully closed. j The following alarm will be received: i Atmospheric Dump Valve Not Closed.

Control board indications are:

Increased Steam Flow Decreased Steam Generator Levels and Pressures i Decreased RCS Average Temperatures Increased Reactor Power Decreased Pressurizer Level and Pressure Decreased Electrical Power Output. '

Date: 1/31/89

The failed atmospheric dump valve will not be able to be reposition 0d by its associated hand or pressure controller. The steam. leak may be isolated by shutting l off an associated manual isolation valve through the use of an individual remote function.

Malf B - The effects of this malfunction will be similar to Malf A with the atmospheric dump valve on #2 main steam header being the affected component.

REFERENCES:

26002, 28500 SH. 489, 490,.32020 SH. B, 25, 44.

l O Rev: 0 Date: 1/31/89

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\J MALFUNCTION CAUSE'AND EFFECTS '

)

Plant: MP2 Malfunction #: RX14A 2MS209  :

RX14B '2MS208.

RX14C .2MS207 RX14D- 2MS206 Malfunction

Title:

Main Steam Dump Valve Failure.  !

Malfunction Type: Generic / Variable. 100% equals valve fully open. j

.I Malfunction.Cause: E/P Converter Failure. q I

Plant Status: Hot Standby.

Malfunction Effects: ,

Malf A - This malfunction will result in uncontrolled steam flow i through 2-MS-209 to condenser lA. The resulting steam

/T k/

flow will cause the RCS average temperature-to decrease. i Pressurizer level and pressure will decrease.with their  !

appropriate control systems responding in an attempt to i restore them. Neither controller will effect the MS dump valve position. l If leak rates less than the required flow rate to maintain l the steam line pressure (RCS average temp)'are selected, ,

the average temperature of the RCS will increase until a l demand signal to operate the unaffected. steam dump valve  :

(approx. 540 deg F) is initiated. The average temperature of the RCS will then be maintained between 535 and 540 i deg F. {

The steam dump quick opening signal to 2-MS-209 will not be inhibited by this malfunction. 1 The following alarm will be received:

l Condenser Bypass Valve Not Closed.  :

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Date:

0 1/31/89  ;

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Malf B - This malfunction will produce the same flow rates for severities as selected by Malf A with 2-MS-208 being the affected component.

The leakage will also include condenser 1A. Failing this valve open will cause the RCS average temperature to drop, resultino in a closing of the turbine bypass valve. If severity levels above the necessary flow rate to maintain tave are selected, the RCS temperature will continue to decrease.

The steam dump quick opening signal will not be inhibited by this malfunction.

The following alarm will actuate:

Condenser Steam Dump Valve Not Closed.

Malf C - Effects similar to Malf B with 2-MS-207 the affected component and the steam leakage entering condenser is an exception.

Malf D - Effects similar to Malf C with 2-MS-206 the arfected component.

Malfunction removal will restore normal operation of the selected failed steam dump E/P converter.

(s)

~~REF' +2CES: 26002, 26004, 28500 SH. 488A, 488B, 32020 SH. 44, RRS Manual CE #18167-ICE-6403 O

' () Rev:

Date:

0 1/31/89

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. MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: RX15A PT4215 (0-1000 psia)

RX15B PT4216 (800-1000 psia)

Malfunction

Title:

Main Steam Line Pressure Transmitter Failure.

Malfunction Type: Generic / Variable. 100% equals maximum transmitter range.

Malfunction Cause: Transmitter railure.

1 Plant Status: Normal full power.

I Malfunction Effects:

Malf A - This malfunction fails the transmitted value of the main steam pressure as displayed on PR-4215 at C05 and on the i process computer. It will display the indicated value at j the severity level and cause no other system dynamic

[w effect.

Malf B - This malfunction will. fail the transmitted value of the main steam pressure as displayed and controlled by PIC-4216 at C05. At full malfunction severity, the turbine bypass valve will open to reduce the steam pressure. This will result in greater steam flow, reduced ,

average RCS temperatures and an increase in reactor power. i At minimum severities the effects of this malfunction will not be noticeable except for the failed indicated value,  ;

until a plant trip occurs and temperature control is via the steam dump controller. The turbine bypass valve will remain shut with RCS temperatures maintained at elevated values (535 to 540 deg r) by the steam dump demand signal.

The following alarm will actuate if their setpoint is exceeded:  ;

Condenser Bypass Valve Not Close.

Control board indications are:

Main Steam Header Pressure Indication.

() Rev:

Date:

0 1/31/89 I

P

. Malfunction removal will restore the-displayed and controlled selected failed' main steam pressure transmitted

-output to normal.

I

REFERENCES:

- 26002, 28500 SH. 487, 488A, B, RRS Manual CE

  1. 18767-ICE-6403.

O 1 I

J i

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~i O Rev:

Date:

0 1/31/89 i

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: SG01A S/G1 SG01B S/G2 Malfunction

Title:

Steam Generator Tube Leak (Small)

Malfunction Type: Generic /variabla. 100% equals 10 gpm at 1250 psid.

Malfunction Cause: Steam Generator Tube Failure.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will result in a small primary to secondary leak in the number one steam generator. The leakage will be within the charging pumps capacity to maintain pressurizer level as it initially drops. VCT level will decrease. Tech specs will be impacted. Plant Shutdown will be necessary at 9 most severities by Tech Specs.

Radiation levels will increase on the following monitors:

SJAE Discharge RIT-5099 S/G Blowdown Monitor RIT-4262.

If either of the above monitor levels reach high alarm setpoints, steam generator blowdown will be isolated automatically.

The following alarms will actuate if their setpoints are exceeded:

Process Monitor Rad Hi Process Monitor Rad Hi/Hi.

Control board indications are:

SJAE Rad Levels Increasing Blowdown Monitor Rad Levels Increasing Charging Flow and Makeup Requirements Increase.

O Rev:

Date:

0 1/31/89

i . Malf B - This malfunction will be siinilar to- Malf A with. Steam.

Generator 2 being the affected component.

Malfunction removal will stop~the Steam Generator tube leakage on tne selected failed Steam Generator.

REFERENCES:

26002, 26012, 26028, 29103 SH. 13,.32031 SH. 32, 37006 SH. 4 O

0

'O Rev:

bate: 1/31/89

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: SG02A(B) j i

Malfunction

Title:

Steam Generator Tube Rupture (SGTR) ')

SG02A #1 SG Tube Rupture j SG02B #2 SG Tube Rupture j l

Malfunction Type: Variable, 0-100%, 100% equals 3000 gpm at 1250 psid. 1 Plant Status: Normal full power operation.

Malfunction Effects: This malfunction causes leakage of RCS inventory to the affected SG through one or more ruptured SG tubes. . 100%

severity is equivalent to 5-6 sheared SG tubes and will result in RCS leakage to the affected SG of 3000 gpm at 1250 psid. 20% severity is the equivalent of one sheared SG tube.  ;

At 100% severity, level in the affected SG increases ~12% per minute

>)

7-

\'

pre-trip.- Post-trip, the affected SG level drops to ~30% then increases at 8-12% per minute until RCS and SG pressures equalize.

Level in the intact SG drops to ~15% post-trip then increases at ~6%

per minute on main feed.

Pzr pressure drops to the TM/LP trip setpoint in ~35 seconds then rapidly drops through the SIAS setpoint to 1000 psia at ~2 minutes, .

then slowly decreases toward SG pressure. Pzr level drops to empty in

~1 1/2 minutes.

The SJAE radmonitor rapidly rises through its alarm setpoint to

>30,000 epm. The rate of rise tapers off with time. The SJAE radmonitor alarm isolates SGBD. Early isolation of SGBD sample valves prevents transport of activity to the SGBD radmonitor and no increase is indicated.

The RVLMS will not indicate a vessel head level problem unless HPSI is inadequate or unavailable.

All RCS Th and Tc temperatures undergo standard post-trip response, ramping down to no-load Tave values of 534-536 F on the SD + BV l system. Temperatures then will decrease ~1*F per minute due to excess feedwater addition and HPSI injection.

l When each SG level reaches 85%, its associated FRV and bypass will shut on the SG High-Level Downcomer override' signal.

Rev: 0  !

Date: 3/1/89  !

e

l The following alarms, key to event diagnosis, will occur as their

()

7-. setpoints are exceeded:

"S/G Level Setpoint. Deviation Hi/Lo" l

" Process Mon. Rad. Hi-Hi/ Fail" "Pzr CH X (Y) Level Lo-Lo" "TM/LP Trip CH A(B,C,D)"

"Pzr Press. Lo-Lo A(B,C,D)"

"SIAS Actuation Sig CH 1(2) Trip" Operator action in response to this event should be to manually trip and/or respond to an automatic trip in accordance with EOP 2525. RCS pressure should.be decreased to minimize pri-sec. leakage and a plant cooldown initiated to <520 F in the affected hot leg. The.SG is then bottled up. Two RCP's are tripped at 1600 psia and the remaining RCP's should be tripped if SCM decreases below 30 F. Affected SG 1evel should be minimized by securing or minimizing its feed addition.

Removal of the malfunction will stop the RCS leakage to the affected SG. However, the effects of mass and activity already transferred will still exist.

Introduction of SG02A(B) at lesser severities will cause similar effects, of lesser magnitude, with the following exceptions:

Pzr level and pressure decrease will be slower, extending the time to reach the TM/LP trip setpoint and SIAS.

As the severity is successively decreased, pzr pressure will bottom out at successively higher values.

SJAE radmonitor response will be slower and lesser values will be reached.

At very low severities, pzr level and pressure will be maintained by their respective control systems and the feed regulating system will respond to stabilize the affected SG level at an elevated value. Tech Specs for RCS leakage will require an orderly plant shutdown.

REFERENCES:

P&ID 26002, 26005, 26014, Retran/Nulap analysis.

[N Rev: 0

(_) Date: 3/1/89

b I

MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: SIO1A - SI Loop 1A (2-SI-217)

SIOlB - SI Loop 1B (2-SI-227)

SIOlC - SI Loop 2A (2-SI-237) i SIO1D - SI Loop 2B (2-SI-247) l Malfunction

Title:

Safety Injection-Loop Check valve Leakage.

Variable: 100% = 10 gpm @ 2000 psid.

Malfunction Type: Generic, Variable i

Malfunction Cause: Leakage from RCS to SI across check valve.

Plant Status: Normal full power operation.

Malfunction Effects:

1 This malfunction results in leakage through check valve 2-SI-217, (227, )

237, 247), causing the pressure to increase in the loop 1A, (1B, 2A,

( 2B), safety injection header piping. This header pressure PI-319, (329,

339, 349) will be displayed as a computer point and at Col. The pressure may be bled down through 2-SI-618 (628, 638, 648) and 2-ST-661 J to the primary drain tank. The reactor coolant system will reflect the l loss of mass. If the section of piping is isolated after being l depressurized it will repressurize.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

SIS to Loop 1A Press Hi SIS to Loop 1B Press Hi SIS to Loop 2A Press Hi SIS to Loop 2B Press Hi Removal of malfunction will seat the selected failed loop check volve properly to stop the leakage.

References:

P&ID 26015.

Rev: 0 Date: 1/31/89 1

_. _ _ _ _-_-__-______D

I MALFUNCTION CAUSE AND EFFECTS O

Plant: MP2 Malfunction #: SIO2A - SI Tank 1 SIO2B - SI Tank 2 1 SIO2C - SI Tank 3 l SIO2D - SI Tank ~4 1 Malfunction

Title:

Safety Irajection Tank Level Low. '

Variable 100% = 10 gpm 0 200 psid.

Malfunction Type: Generic, Variable Malfunction Cause: Fill and drain valve leakage simultaneously with leakage out break in fill and drain header pipe. j l

Plant Status: Normal full power operation.

Malfunction Effects:

This malfunction results in a loss of mass from safety injection tank )

  1. 1 (#2, #3, #4) through its fill and drain' valve 2-SI-611, (612, 613, i

(}/

(, 614) and out break in fill-and drain header pipe to the ctmt sump.

The fill and drain. valve position indication will not show that it is j l

open. Drain header pressure (PI-305 @ Col) will not increase unless flow into the header is greater than the full malfunction severity  ;

flow.

As level in the affected SI tank decreases so will its pressure.

I The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

i Safety Injection Tank Level Lo Safety Injection Tank Press Lo Ctmt Sump Level Hi/Lo Due to the SIT low level or low pressure, tech. specs. will require restoring SIT level, or proceed to Hot Shutdown.

l Removal of malfunction will stop the leakage through the selected failed fill and drain valve and restore the fill and drain header operability to normal.

1 l~

References:

P&ID 26015.

O Rev:

Date:

0 1/31/89 t

T l

i MALFUNCTION CAUSE AND EFFECTS

. ["'

\

Plant: MP2 Malfunction #: SIO3A - SI Tank #1 SIO3B - SI Tank #2 SIO3C'- SI Tank #3 SIO3D - SI Tank #4 Malfunction

Title:

Safety Injection Tank Low Pressure. 100% = 20 psia decrease / minute from Nitrogen Over Pressure in tank.

Malfunction Type: Generic, Variable.

Malfunction cause: Unisolable tank leak to containment.

Plant Status: Normal full power operation.

Malfunction Effects:

This malfunction results in a loss of nitrogen mass from Safety Injection Tank A (B,C,D) to the containment at the severity selected.

s. Nitrogen make-up may be used to restore the tank pressure as necessary. The decrease in tank pressure will be displayed by its computer point and CO-1 metered outputs. Safety injection loop pressure will also decrease as the head of tank decreases.

The following alarms, key to event diagnosis, will occur as their setpoints are exceeded:

Safety Injection Tank Press Lo Due to SIT low pressure, tech. specs. w!11 require restoration of pressure or proceed to Hot Shutdown.

Malfunction removal will stop the nitrogen leakage from the selected failed safety injection tank.

REFERENCES:

P&ID 26015.

O Rev:

Date:

0 1/31/89

l

-t MALFUNCTION CAUSE AND EFFECTS

-Fiant: MP2 Malfunction #: SIO4A - P41A  ;

SIO4B - P41B l SIO4C - P41C j l

l i

1

[slfunction

Title:

High Pressure Safety Injection Pump Trip i

[slfunction Type: Generic, Non-variable l

[sifunction Cause: Faulty Load Shed Contact l l

FLant Status: Normal full power operation. {

1

[s1 function Effects:

711s malfunctzen results in high pressure safety injection pump A's (3's, c's) motor supply breaker to trip open if it is shut and prevent i: from being shut if open. The pumps motor running current will 6acrease to zero and its discharge pressure will drop to its suction  ;

trad value. Flow developed by the pump will decrease as a function of C tie pump D/P.

l Eamp breaker status at the control panel, Col, and computer display l s'.11 show that it has tripped (amber HS light on as a function of HS  ;

eid breaker position). j 1le following alarms, key to event diagnosis, will occur as their setpoints are exceeded: None E2e to inoperability of one HPSI pump, tech. specs. will require Iestoring ECCS subsystem operability or proceed to Hot Shutdown.

Malfunction removal will permit closure of the selected failed high pressure safety injection pump breaker by restoring the faulty load shedding contact to normal operation.  !

R:FERENCES: 32008 SH. 1, 2, 3.

i Rev: 0 l

\ Date: 1/31/89 '

5

MALFUNCTION CAUSE AND EFFECTS'

-P. ant: MP2 Malfunction #: SIO7A 2-SI-616 - C 2-SI-626 SIO7B 2-SI-617 - D 2-SI-627 SIO7E 2-SI-636 - G 2-SI-646 SIO7F 2-SI-637 - H 2-SI-647 Malfunction

Title:

HPSI Flow Control Valve Failure (8 total valves)

Malfunction Type: Generic, Non-variable Ms1 function cause: Valve mechanically failed shut.

P ant Status: Normal full power operation.

Malfunction Effects:

T11s malfunction will mechanically fail the high pressure safety 11jection header A, B flow control MOV to loop 1A, (lB, 2A, 2B), in i:s shut position.

O I. will not shut the valve if it is open. If the malfunction is 11serted and then the valve.is shut, opening of the valve with its associated handswitch or SIAS signal will be inhibited. Note that H2SI injection valves are normally kept in the throttled position and tsis malfunction will have no effect unless the valves are manually s lut.

Tie following alarms, key to event diagnosis, will occur as their sitpoints are exceeded: None D ie to the inoperable injection valve, tech. specs. will require restoring the ECCS subsystem to operable status or proceed to Hot Slutdown.

Malfunction removal will remove the mechanical failure on the selected vslve to allow its normal operation.

RSTERENCES: 26015, 32008 SH. 13-20.

l

() Rev:

Date:

0 1/31/89

MALFUNCTION CAUSE AND EFFECTS b

-P. ant: MP2 Malfunction #: SI12A - SI Tank 1 (2-SI-215)

SI12B - SI Tank 2 (2-SI-225)

SI12C - SI Tank 3 (2-SI-235)

SI12D - SI Tank 4 (2-SI-245)

Mt1 function

Title:

SI Tank Check valve Leakage.

Viriable: 100% = 10 gpm 0 2000 psid.

M ilfunction Type: Generic, variable Malfunction cause: Leakage from RCS to SI Tank.

P. ant Status: Normal full power operation.

Malfunction Effects:

T11s malfunction will cause leakage into Safety Injection Tank A

( 3, C, D), through its associated tank outlet check valve 2-SI-215, (125, 235, 245),^if the loop header pressure is higher than the tank O- . . p ressure. This malfunction, when used in conjunction with the SI.

malfunction for RCS loop check valve leakage will result in a loss of miss from the reactor coolant system. Safety Injection Tank level w.ll rise depending on severity with a corresponding increase in its p ressure.

Stutting of the tanks outlet isolation valve will stop the leakage.

Tie following alarms, key to event diagnosis, will occur as their sitpoints are exceeded: None D2e to the malfunction, tech. specs. will required restoring o>erability of the affected SIT, or proceeding to Hot Shutdown.

Malfunction removal will stop the leakage through the selected failed Sifety Injection Tank outlet check valve.

R IFERENCES : P&ID 26015.

Rev: 0 Or Date: 1/31/89

l MALFUNCTION CAUSE AND EFFECTS l

-Plant: MP2 Malfunction #: SWOlA P5A SWOlB P5B SWG1C P5C l Malfunction

Title:

Service' Water Pump Trip.

l Malfunction Type: Generic Malfunction cause: Overcurrent Relay (51) Failure Plant Status: Normal full power.

Malfunction Effects:

Malf A - Service water pump A will trip and not be able to be restarted. Service water flow to the "A" header components will stop. Tech specs may be impacted.

Major SW supplied component in the "A" header _are:

)

TBCCW Heat Exchanger C RBCCW Heat Exchanger A D/G A Heat Exchangers Chiller A Vital SWGR Cooling Coils j

The following alarms will actuate:

l SW Pump A Overload / Trip Vital AC SWGR Rm Clg Coil Lo Dis Press.

l Malf B - Effects similar to Malf A except SW pump B is the major affected component. Affected header will depend on pump alignment.

Malf C - Effects similar to Malf A except SW pump B is the major affected component. With only pump C supplying header B, the following major components will lose SW cooling:

TBCCW Heat Exchanger A RBCCW Heat' Exchanger C D/G B Heat Exchangers Chiller B Non-Vital Chiller Vital SWGR Cooling Coil 183.

  • Rev: 0 Date: 1/31/89 1

l

I i

1

)

i Malfunction removal will restore the selected failed SW pump i overcurrent device to normal which will then allow the pump i to be started.

REFERENCES:

26008, 26027, SH. 2, 32013 SH. 5, 6 and 7 j l

l l

l Rev: 0 O' Date: 1/31/89 l

l

MALFUNCTION CAUSE AND EFFECTS ;i

\r"' J

_l l Plant: MP2. Malfunction #: SWO2A HX17A SWO2B HX17B SWO2C HX17C-Malfunction

Title:

Service Water Side of TBCCW Heat Exchanger Fouling.

I Malfunction Type: Generic / Variable. 100% equals total' flow blockage.

with appropriate loss of heat transfer.

Malfunction Cause: Tube Fouling.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will reduce the heat transfer ability and Q flow through TBCCW heat exchanger A. As the severity level k) m is increased the service water outlet temperature control valve will open in an attempt to maintain the controlled setpoint as set through a variable remote. function.

Malfur ction . severity will also be . dependent on service water supply temperature. Service water' header "A" pressure will increase when the severity level exceeds the ability of_the 1 heat exchangers' outlet valve to maintain its controlling setpoint (full open). TBCCW heat load will shift to the "C" heat exchanger. ,

If the inservice TBCCW heat exchangers cannot handle'the i plant heat load, the TBCCW supply water temperature will increase. Components supplied by the TBCCW system will show the effects dynamically as their cooling supply temperature rises leading to a possible turbine trip.

The following alarm (s) will actuate when their setpoints are exceeded:

TBCCW HDR Temp Hi.

5 Rev: 0 Date: 1/31/89

1 I

i 1

1 l

()- Malf B - Effects similar to Malf A TBCCW heat exchanger B being the affected component. SW header affects will be dependent on heat exchanger alignment.

Malf C - Effects similar tO Malf A with TBCCW beat exchanger C being the affected component.

Malfunction removal will restore the selected failed TBCCW l heat exchanger heat removal.and flow capabilities to normal. i

REFERENCES:

26007, 26008

)

4 O I

)

l 1

l

() Rev:

Date:

0 1/31/89

l

)

"w g

MALFUNCTION CAUSE AND EFFECTS j s /' I Plant: MP2 Malfunction #: SWO3A HX18A  !

SWO3B HX18B SWO3C HX18C j i

Malfunction

Title:

Service Water Side of RBCCW Heat Exchanger Fouling. l l

Malfunction Type: Generic / Variable. 100% equals total flow blockage with appropriate loss of heat transfer. ,

Malfunction cause: Tube Fouling.

Plant Status: Normal full power. l Malfunction Effects:

Malf A - This malfunction will reduce the heat transfer ability and 1

(~} flow through RBCCW heat exchanger A. As the severity level is increased the service water outlet temperature control i

l

(_/

valve will open in an attempt to maintain the controlled  ;

setpoint as set through a variable remote function.

Malfunction severity will-also be dependent on service water  !

supply temperature. Service water header "A" pressure will increase when the malfunction severity level exceeds the i ability of the heat exchangers' outlet valve to maintain its  ;

controlling setpoint (full open). Components supplied by RBCCW header "A" will show the effects dynamically as their cooling supply temperature rises.. Tech specs may be impacted. RCr Hi Temp Alarms likely, if uncorrected, reactor manual trip possible. Operator action would be to place another HX in service.

The following alarm will actuate:

RBCCW Hx Temp Hi.

Malf B - Effects similar to Malf A except RBCCW heat exchanger B is the major affected component.

O Rev: 0 Date: 1/31/89

4

?

Malf C - Effects similar to Malf A except RBCCW heat exchanger C is the. major component affected. '

Malfunction removal will restore the selected fa!. led RBCCW heat exchanger heat removal and flow capabilities to normal.

REFERENCES:

26008, 26022 ]

l i

1 I

i 1

O 1 l

a.

l i

O Rev: 0 Date: 1/31/89

k l

l fs MALFUNCTION CAUSE AND EFFECTS ,

~s i

Plant: MP2 Malfunction #: SWO4A 'D/G_120 Hx l SWO4B D/G 13U Hx i Malfunction

Title:

Diesel Generator Heat' Exchanger / Strainer Fouling.

i Malfunction Type: Generic / Variable. 100% equals total flow blockage l i

with appropriate loss of heat transfer.

Malfunction cause: Tube Fouling, j i

l Plant Status: Diesel' Generator Operations.

J Malfunction Effects: I Malf A - This malfunction will reduce the heat transfer ability and l flow through emergency diesel generator H-7A exchangers. As i the malfunction severity level is increases service water 1 outlet temperature (computer point only) will increase at a

(~')

(,f rate depending on the generator load and service water supply temperature.

If service water outlet temperature exceeds 150 deg F and an emergency start signal does not exist,.the diesel will trip.

If jacket cooling water outlet' temperature exceeds 200 deg.F with an emergency start signal present the diesel will trip (assume oil pressure low enough to complete 2/3 trip circuitry). At this point, diesel operation will be nonrecoverable.

The diesels will run at least 3 minutes at full load without any service water flow. A remote function for each diesel generator will be provided to reset its shutdown relay if it had been energized. If the diesel generator is indepen-dently supplying bus 24C when it trips the bus will be de-energized. Tech specs will be impacted.

The following alarm will actuate, when service water flow to the D/G goes below its minimum setpoint:

Diesel Gen 12U Trouble.

' () Rev:

Date:

0 1/31/89

?

Malf B - Effects similar to Malf A except diesel generator 13U is.the major affected component.

I Malfunction removal will restore the selected failed diesel generator heat exchanger heat removal ability to normal.

I

REFERENCES:

26009, OP 2346A l

I O

J 1

i i

Rev: 0 Date: 1/31/89 1

i-MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: SWO5A Located Upstream of ,

2-SW-3.2B  :

SWO5B ' Located Upstream of i 2-SW-3.2A

'i Malfunction

Title:

Unisolatable Service Water Header Rupture in Turbine Building.

Malfunction Type: Generic / Variable. 100% equals 5,000 gpm leak i rate at 50 psid, j Malfunction Cause: Piping Weld Failure.

Plant Status: Normal full power.

Malfunction Effects: ,

i r- Malf A - The rupture on service water header "A" within the turbine building will cause leakage into the condenser pit area.

(_3j Leakage will initially be collected in the "B". pit sump with overflow going into the "A" pit sump and condenser pit area.

If condenser pit level exceeds 6 inches, a trip signal for the circulating water pumps will be generated.

Service water header "A" pressure will decrease resulting in i reduced flow to its associated components. Service water l pump running current will increase as the flow through the j pump rises. Service Water Tech specs will be impacted.

Major' components supplied by SW header "A" are: j TBCCW Heat Exchanger C RBCCW Heat Exchanger A D/G A Heat Exchangers Chiller A Vital SWGR Cooling Coils i l Logic and dynamic effects of reduced heat removal ability of the associated heat exchangers will occur as appropriate.

l Leakage on the header will continue until the pump (s) l supplying that header are stopped.

1 Rev: 0 1

(_ Date: 1/31/89 )

i

)

1

)

_ _ _ _ - _ _ _ _ _ - _ _ s

]
1 j

i

. r~ .

Malf B - Effects similar to Malf A except' service-water header "B" is the major affected component'.

Malfunction removal will restore the integrity.of the selected failed SW header.

l'

REFERENCES:

26008 SH. 1, 2. ,

i 1

1 i

i I

i O 1 i

l O Rev:

Date:

0 1/31/89

MALFUNCTION CAUSE AND EFFECTS

(~s

\ i l

Plant: MP2 Malfunction #: SWO6A - Located downstream I i

of 2-SW-3.2B SWO6B - Located downstream of 2-SW-3.2A

]

Malfunction

Title:

Isolatable service water rupture in Turbine-  ;

Building. ,

i 1

l Malfunction Type: Generic / Variable. 100% equals 5,000 gpm leak rate at 50 psid.

Malfunction Cause: Piping Weld Failure.

Plant Status: Normal full power, i

Malfunction Effects:

Malf A - The rupture on service water header "A" within the turbine building will cause leakage into the condenser pit area.

Leakage will. initially be collected in the "B" pit sump with overflow going into the "A" pit sump and condenser pit area.

If condenser pit level exceeds 6 inches, a trip; signal for the circulating water pumps will be generated.

Service water header "A" pressure will decrease.resulting in j reduced flow to its associated components. Service water '

pump running current will increase as the flow through the pump rises.

Major components supplied by SW header "A" are:

TBCCW Heat Exchanger C ]

RBCCW Heat Exchanger A 1 D/G A Heat Exchangers Chiller A )

Vital SWGR Cooling Coils j Logic and dynamic effects of reduced heat removal ability of the associated heat exchangers will occur as appropriate.

I 1

, Rev: 0 I 1/31/89

~

Date:

1 1

i i

This leak may be isolated by shutting the "A" SW supply isolation valve (2-SW-3.2B) to the TBCCW heat exchangers. 1 Malf B - Effects similar to Malf A except service water header "B" is the major affected component. Leak isolation is .

accomplished by shutting off the "B" SW supply isolation j valve (2-SW-3.2A) to the TBCCW heat exchangers. c Malfunction removal will restore the integrity of the selected' failed SW header.

REFERENCES:

26008 SH. 1, 2.

i 1

I l

1 l

l a

i Rev: 0 Date: 1/31/09

MALFUNCTION CAUSE AND EFFECTS

\

Plant: MP2 Malfunction #: SWO7A 2-SW-88A SWO7B 2-SW-88B )

SWO7C 2-SW-88C Malfunction'

Title:

Service Water TBCCW Temperature Control Valve Failure. I i

Malfunction Type: Generic / Variable. 100% equals valve full open.

1 Malfunction Cause: Positioner / Valve Coupling Failure.

Plant Status: Normal full power.

I Malfunction Effects:

Malf A - This malfunction will override the ability of the TBCCW HX A outlet temperature control valve positioner to position 8 2-SW-88A. Failing the valve at a position less open than required to maintain the controlled temperature setpoint

\ (variable remote function) will cause actual TBCCW outlet temperature to increase. Heat load will shift to TBCCW HX "C" when in service. Service water flow to TBCCW HX "A" will decrease causing lower pump running currents and higher header pressures on the SW header.

Valve position failure at positions greater than that required to maintain the controlled temperatures will cause reduced TBCCW temperatures. The higher SW flow will reduce SW header pressure and increased SW pump-running current.

Malf B - Effects similar to Malf A except TBCCW HX B SW outlet valve is the major affected component. SW header dynamic effects will depend on heat exchanger alignment as controlled through inlet isolation valve remote functions.

Malf C - Effects similar to Malf A except TBCCW HX C SW outlet valve is the major affected component.

l l Malfunction removal will allow proper positioning of the selected failed TBCCW SW outlet valve through its associated temperature controller.

REFERENCES:

26008.

() Date:

Rev: 0 1/31/89

i

("' -

MALFUNCTION CAUSE AND EFFECTS

(' I J

Plant: MP2 Malfunction #: SWO8A 2-SW-8.lA SWOBB 2-SW-8.lB SWO8C 2-SW-8.lc SWO8D 2-SW-247 SWO8E 2-SW-246 SWO8F 2-SW-245  !

l Malfunction

Title:

Service Water RBCCW Temperature Control Valve j Failure. l l

1 Malfunction Type: Generic / Variable. 100% equals valve fully open. l l

j Malfunction Cause: Positioner / Valve Coupling Failure.

l Plant Status: Normal full power.

1 Malfunction Effects: J 1

f~) Malf A/D - This malfunction will fail the-outlet temperature control 1

(/ valve of RBCCW HX A. The. malfunction will override the ability of outlet temperature control valve to position  ;

either 2-SW-8.1A or 2-SW-247. A remote function valve, i 2-SW-8.lA or 2-SW-247 is in service. Failing of the valve at a position less open than required to maintain the controlled temperature setpoint (variable remote function) 1 will cause the actual RBCCW HX "A" outlet temperature and 'l supply temperatures for associated components to increase.

This will also result in less SW flow through HX A, causing higher service water pressure and lower SW pump running currents. Associated components supplied by RBCCW header "A" will reflect the change in cooling water supply i temperature.

Valve failure at positions greater than that required to maintain the controlled temperature will cause reduced RBCCW temperatures. The higher SW flow will reduce SW header A pressure and increase SW pump running current.

Tech specs may be impacted..

Malf B/E - Effects similar to Malf A except RBCCW HX B SW outlet temperature control valves are the major affected components. SW header and RBCCW header dynamic effects will depend on heat exchanger alignment as controlled through inlet isolation valve remote functions and control panel valve positioning respectively.

f Rev: 0

\- Date: 1/31/89

o 1

Malf C/r - Effects similar to Malf A except RBCCW HX C SW outlet.

temperature control. valves.are the major.affected j components. g Malfunctiort . ?n wal will allow proper positioning of the.

selected fa!J!d RBCCW SW outlet valve through its associated temperature controller.

REFERENCES:

26008 i

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MALFUNCTION CAUSE'AND EFFECTS 1

Plant: MP2 Malfunction-#: SWO9A P5A i

-SWO9B .P5B SWO9C -PSC j l

Malfunction

Title:

Reduced Service Water Pump Capability. j Malfunction Type: Generic / Variable. 100% equals total flow blockage.

Clogged Service Water Strainer at the Pumps' Malfunction Cause: j Discharge.

.l Plant Status: Normal full power. -)

h Malfunction Effects:

Malf A - This malfunction will cause a decrease in the head developed ]

by service water pump "A". Flow through associated heat' 1 exchangers supplied by the "A" service water header will . 1 Os decrease. Temperature control valves on the outlet of the TBCCW and RBCCW heat exchangers;will open up in an attempt to maintain their' respective system control .emperature setpoint.

As the severity level is increased the temperature control valves will have to open fully. TBCCW and RBCCW. supply temperature will then.begin to increase with the:effect seen on their associated components. Tech ~ specs may be impacted.

The following alarm will actuate:

SW Pump A Strain DP Hi.

Malf B - Effects similar to Malf A except service water pump "B" is

! the major affected component. SW header affects will be L dependent on pump alignment.

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Date:

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Malf C - Effects similar tofMalf A except service water pump "C" and the "B" service. water heater will~be.the major affected components.

Malfunction removal-will restore the. selected failed service water strainer:to normal.

REFERENCES:

26008 i

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i MALFUNCTION CAUSE AND EFFECTS l [~^h i

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i Plant: MP2 Malfunction #: TC01 2

Malfunction-Title: Turbine Trip.

i Malfunction Type: Generic  !

Malfunction Cause: Momentary closure of Turbine Trip Pushbutton.

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will result in a turbine trip due to energization of the mechanical trip solenoid and master trip bus. At greater than 15%

power level, a reactor trip due to loss of load trip actuation (low EHC oil pressure) will occur.

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. The turbine trip will cause the main stop, control, and intermediate l

\ reheat intercept and stop valves to close. This will stop steam flow to the turbine. Turbine speed will then begin to decrease.

Main generator output breakers (15G-8T-2 and 15G-9T-2) trip and the ]

field breakers trip and lock out. Auto transfer of station service  ;

loads from the normal station service transformer to the reserve station service transformer occurs.

The steam dump and bypass system initially causes the dump valve to quick open to limit the rise in the RCS average temperature. It then ;

modulates the turbine bypass valve to control steam generator pressure <

and, thus, the average temperature'at 532*F.

The bleeder trip valves will shut and the main feed regulating valves will be ramped shut. The feedwater bypass valves will be opened to approximately 75%.

The following alarms will be received:

Turbine Master Relay Trip EHC Emergency Pressure Switches Turbine Trip Turbine Generator Lockout Trip Channel I/II Reactor / Generator Prot Turbine Trip.

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Malfunction removal will have no visible effect on simulator operation. j d

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REFERENCES:

32005 SH. 4A, 19, 23  ;

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l MALFUNCTION CAUSE AND EFFECTS

($$)

Plant: MP2 Malfunction #: TCO2  !

l Malfunction

Title:

Turbine Throttle Pressure Limiter Failure. l l

Malfunction Type: Variable. 0-100% equals 0-1000 psig, l

.i Malfunction Cause: Limiter Failure at Desired Range Setting. (

)

Plant Status: Normal full power.

k Malfunction Effects:

This malfunction will override the function of the throttle pressure limiter when it is selected for operation at the turbine control  !

panel. Normally the limiter is set at 90% during turbine operation 4 with a full range of 0 to 815 psia. Extending the range is necessary to obtain an effect from this malfunction without the need of addit- 1 ional malfunctions to lower the main steam pressure.

O- If the severity level selected 's above the actual throttle pressure, the control valves will close to increase the pressure to the desired value. A 10% error will result in control valve closure to'their no 1 load opening. If severity level selected is less than actual throttle  !

J pressure, there will be no effect. . -j

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As the control valves close the generated electrical load will decrease and heat will be backed up in the primary system.

Malfunction removal will restore control of the throttle pressure, limiting setpoint to its associated potentiometer at the-turbine control panel.

REFERENCES:

System Description, OP-2323A, GE Turbine Tech. Manual, Reference Plant Data Book, Event #30.

Rev: 0 iO Date: 1/31/89 l

l MALFUNCTION CAUSE AND EFFECTS f

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I Plant: MP2 Malfunction #: TC04 q

Malfunction

Title:

Load shed.

8 Malfunction Type: Variable. 0-100% equals 0-100% Load Setpoint.

(0-920 MWE).

Malfunction Cause: Load Set. Rundown. ]

Plant Status: Normal full power.

Malfunction Effects:

This malfunction will override the function of the turbine load' set controls. The manual increase and decrease load selector controls-will not have any effect on changing the selected load setoint. The severity selected will correspond to the load set setpoint.

() With a severity selected below the load limit control, the control valves will close and the turbine will go off load limit control. As j

the control valves shut, generated electrical load will decrease and j heat will be backed up in the primary system.

j Steam generator pressure will increase resulting in its level q shrinking. RCS average temperature will. increase causing pressurizer '

level and system pressure to increase. i Steam generator atmosphere relief valves may open to limit the secondary side pressure.

The reactor would most likely be tripped on an RCS high pressure trip function during large loss of loads.

Malfunction removal will restore control of the load set setpoint at the turbine control panel. The setpoint will have to be repositioned to the desired value to return to normal.

REFERENCES:

System Description, GE Turbine Tech Manual O Rev:

Date:

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MALFUNCTION CAUSE AND EFFECTS

'O-Plant: MP2 Malfunction-#: TC05A MSV1 TC05B MSV2 6 l- TC05C MSV3 TC05D MSV4 l- Malfunction

Title:

Turbine Stop Valve Failure.

]

1 Malfunction Type: Generic / Variable. 100% equals valve fully open.

Malfunction cause: Mechanical failure of stop valve.at the malfunction position. )

Plant Status: Normal full power.

Malfunction Effects:

l Malf A-- This malfunction will fail the number one main turbine stop 4 valve at the desired position by severity selection. The j

("j'T s turbine control system will have no effect.on operation of the valve. Its position will depend solely.on the severity level inserted.

valve position will be displayed on the turbine control' panel (analog) and computer (digital).

Shutting of a single stop valve while at full power.will not result in reduction in steam flow-to the. turbine.

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Failure of the stop valve to close will inhibit generator trip logic as a direct result of a turbine trip. 3 Malf B - This malfunction will fail the number two turbine stop valve )

at the desired position as determined by severity level.

When severities of 95% or less are selected, the #1, #3, and

  1. 4 MSv's will close, due to their slavish relationship to #2 MSV. Severities greater than 95% will result in response similar to the effects of Malfunction A.

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A y ' Malf C Effects similar to Malf A except that the turbine stop and D - valves listed as generic components above may be individually affected.

I Malfunction removal will. allow positioning of the selected )

failed stop valve via'the EHC cystem.  ;

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REFERENCES:

32006 SH. A, 41, 320,05 SH. 23.

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h MALFUNCTION CAUSE AND EFFECTS i

Plant: MP2 Malfunction #: TC06A cv1 1 TC06B CV2 .i TC06C CV3 1 TC06D CV4

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Malfunction

Title:

Turbine control Valve Failure. q 1

Malfunction Type: Generic / Variable. 100%' equals valve fully open. ']

'i Malfunction cause: Mechanical failure of valve at the malfunction l position.

i Plant Status: Normal full power.

Malfunction Effects:

Malf A - This malfunction will fail the number one main turbine  ;

control valve at the desired position by severity selection.

O. The turbine control system will have no effect on operation of the valve. Its position will depend solely on the j

severity level inserted. j i

Valve position will be displayed on the turbine conttol ,

panel (analog) and computer (digital). ]

If first stage pressure feedback is in operation, the closure of the control valve will be compensated by the opening of the unaffected valves as they attempt to maintain ,

the desired load. With no feedback, the closure of a j control valve will result in a loss of steam flow to the turbine and thus reduced electrical output. Primary and secondary systems will respond as appropriate to the failure ,

1 of the valve.

Insertion of this malfunction in a speed. controlling mode will result in overspeed tripping if a control valve is failed open.

Malf B Effects similar to Malf A except that the turbine control through valves listed above as generic components may be indiv-  !

D- idually affected.

.j Rev: 0 Date: 1/31/89 i

Malfunction removal will restore control of the selected failed control valve to the EHC system. i

REFERENCES:

32006 SH. A, 45

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Date: 1/31/89

( MALFUNCTION CAUSE-AND EFFECTS Plant: MP2 Malfunction #: TC07 Malfunction

Title:

First Stage Pressure Feedback Failure.

Malfunction Type: Variable. 100% equals 1000% psig.

Malfunction Cause: First Stage Pressure Transmitter Failure.

Plant Status: Normal power for Control Valve Testing.

Malfunction Effects:

The malfunction when inserted with a severity level greater'than what is called for at the present load conditions will cause the-control valves to start closing causing the generator load to decrease.

If the malfunction is inserted at a lower severity level than the

/'- present load conditions, the control valves will start to open causing 5-) the generator load to increase. Either condition will cause RCS temperature and pressure swings due to changing steam-flow demand.

If the severity level is set less than 20% rated load the-first stage pressure feedback will be removed from service and have no effect on the control valves.

Malfunction removal will return the first stage pressure transmitter to operate normally.

REFERENCES:

Turbine Instruction Manual for EHC and ISI GEK 33809 Rev: 0

, Date: 1/31/89

[ MALFUNCTION CAUSE AND EFFECTS N,

Plant: MP2 Malfunction #: TC09A P81A TC09B P81B Malfunction

Title:

EHC Hydraulic Fluid Pump Failure.

Malfunction Type: Generic.

Malfunction cause: Overload Contact (49) Failure.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - Insertion of this malfunction will stop EHC pump P81A if running and prevent it from being automatically or manually started. The pump's motor contactor will operate properly,

f. '

but the pump will not build up a discharge pressure.  !

t

\') Hydraulic fluid system pressure will decrease to 1300 psi which will cause the standby EHC pump to start and restore system pressure.

The following alarm (s) will be received:

Hydraulic Fluid Pump A Overload / Temp Hi Hydraulic Fluid Pump B Auto Start Hydraulic Fluid Pressure Lo.

Malf B - Effects similar to Malf A except that EHC pump P81B will be the affected component.

Loss of both EHC pumps will result in a turbine trip on low EHC oil pressure at 1100 psi.

It will take approximately 10 minutes for pressure to bleed down to 1100 psi from the normal operating pressure of 1600 psi to cause a turbine trip due to accumulators if all EHC pumps are inoperable.

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Rev: 0 Date: 1/31/89

Malfunction removal will restore the selected failed pump overload contact to normal'. This will allow the pump to develop a discharge head if its motor contactor (42) is-shut.

REFERENCES:

32006 SH. 26, System Description,. Turbine Tech Manual I

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MALFUNCTION CAUSE AND ETTECTS MP2 Malfunction #: TP01A P7A j

~P. ant: TP 01B ' P7B i TP01C P7C Malfunction

Title:

TBCCW Pump Trip I

i Malfunction Type: Generic

_ Malfunction Cause: Thermal Overload contact Failure (49)

P'. ant Status: Normal full power.

M11 function Effects:

Milf A - Turbine building closed cooling water pump A will trip upon malfunction insertion if it is running. Its breaker position indication and associated breaker trip alarm will show the breaker has opened. Pump A current and the TBCCW header pressure will begin to decrease. The TBCCW pump in O

i standby will start to restore system pressure to normal.

The pump will not start if a manual start attempt is mede.

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The amber light on pump A handswitch will illuminate.

The follnwing alarm will actuate:

TBCCW PP Overload / Trip.

Control board indications are:

TBCCW Pump A Current Decreases TBCCW Header Pressure Decreases (momentarily).

i Milf B - The effects of this malfunction will be similar to Malf A i with pump B being the affected component. l 1

M ilf C - The effects of this malfunction will be similar to Malf A  !

with Pump C being the affected component. l Multiple pump failures will result in a turbine trip due to loss of TBCCW cooling to the following major pieces of equipment:

Rev: 0 <

Date: 1/31/89

l Heater Drain and Cond Pump Coolers j

Stator liquid coolers Exciter
Air and Generator Hydrogen Coolers Generator Iso Phase Bus Duct Coolers 'h Feed Pump and Main Turbine L.O. Coolers  :

EHC Oil Coolers .

1 A& B Instrument and Station Air Compressor Cooling.

Malfunction removal will restore the selected failed motor overload contact to normal. l RSFERENCES: 26007, 28107, 32014, 30051 SH. 2, 37006 SH. 4 1

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f- MALFUNCTION CAUSE AND EFFECTS  !

l P. ant: MP2 Malfunction #: TP02A HX 17A

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TP02B HX 17B TP02C HX 17C-

_ Malfunction

Title:

TBCCW Temperature Control Failure.

Malfunction Type: Generic / Variable.  ?

100% severity equals 100 F setpoint.

Malfunction Cause: Heat exchanger outlet temperature transmitter failure at fixed setpoint.

P. ant Status: Normal full power.

Malfunction Effects:

Milf A - This malfunction, if inserted at low severities, will cause l the service water outlet temperature control on TBCCW HX A J

,g to close in an attempt to maintain the desired 1TBCCW j (j temperature. This desired temperature will be sei as a remote function on each individual TBCCW heat exchat.ger. As i'

the service water temperature control valve shuts on HX A, the TBCCW heat load will shift to HX C causing its temperature to increase._ The C HX TCV will then open in an attempt to maintain its desired outlet temperature. HX A  !

l will receive its SW supply from-SW header B normally and HX C will receive its SW supply from SW header A. The service water pump running current indication will reflect flow requirements of its associated header. If the cooling capacity of the unaffected TBCCW heat exchanger is exceeded, "

TBCCW supply temperatures will continue to rise. The effects of this malfunction may be reduced by aligning the B TBCCW HX up for service.

At high severities of this malfunction the affected heat j exchangers outlet temperature will decrease causing an -

initial decrease in TBCCW temperatures.

The following alarm will actuate as its setpoint'is exceeded:

TBCCW Hdr Temp Hi.

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Control board indications are as'follows:

TBCCW Supply Temperatures may fecrease or increase.,SW-Header Heat Load may increase (1 decrease depending on selected severity.

Milf B - The effects of this' malfunction'will be similar to Malf A with HX B being the affected component.

Msif C -- The effects of this malfunction will be similar to Malf A with HX C being the affected component.

l Malfunction removal will restore the selected failed TBCCW l outlet temperature transmitter for its temperature control l to normal..

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REFERENCES:

26007, 26008.

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MALFUNCTION CAUSE AND EFFECTS

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P. ant: MP2 Malfunction #: TP03 l

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_ Malfunction T i tl e: TBCCW Leak i

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-M ilfunction Type: Variable 100% equals 1000 gpm leak rate at 80 psid.

M ilfunction cause: Rupture on common pump discharge line.

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P'. ant Status: Normal full power.

Malfunction Effects:

T11s malfunction will result in leakage from the TBCCW system to the .

raom in which the TBCCW pumps are located. As the severity-level.is 11 creased, the TBCCW system pressure will decrease. The running TBCCW  ;

p 2mps current indication will increase. Surge tank level will drop to j

, cause its associated low alarm. The surge tank will have the ability t) be filled via a remote function. As the NPSH provided by the surge tink decreases the pump discharge pressure will further drop. The rinning pumps will trip and the standby pump will not start if less tian 10 psig suction pressure exists. Leakage will be collected in tie condenser pit sumps.

L )ss of TBCCW cooling will affect the following major components:

Heat Drain and Condensate Pump Cooling Main Generator Stator Liquid and Exciter Air CLRS Generator Hydrogen CLRS Generator Isolated Phase Bus Duct CLRS Main and Steam Generator Feed Pump L.O. CLRS EIC Oils CLRS A& B Instrument and Station Air Compressor Cooling Tie following alarms will actuate when their setpoints are exceeded:

TICCW SRG Tk Level Lo T 3CCW Hdr Press Lo T 3CCW PP Overload /7 rip (s Rev: 0 Date: 1/31/89

t V) C mtrol board indications are:

T 3CCW Pump Running Current Increases T 3CCW Header Pressure Decreases M ilfunction removal will restore the ruptured pipe to normal.

REFERENCES:

26007, 32014, 28107, 37006.

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Date:

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r'% MALFUNCTION CAUSE AND EFFECTS' P'. ant: MP2 Malfunction #: TPO4 Malfunction

Title:

_ . Loss of Stator Cooling.

Msifunction Type: ~ riable I)0% equals complete loss'of stator liquid cooling flow.

Malfunction Cause: Clogged inlet strainer.

P. ant Status: Normal full power.

M ilfunction Ef fects:

As the severity of this malfunction is increased _ flow through the s:ator cooling bars of the main generator and the static rectifiers w.ll be reduced. Cooling water inlet pressure will also decrease.

Tte heat load on the generator hydrogen coolers will increase d!pending on the electrical load.

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5:ator cooling outlet temperatures will increase leading to a higher hrat load on the stator liquid coolers and the TBCCW system. Machine g is temperatures and pressure will increase.

I? the stator liquid temperature from the winding exceeds 81 deg. C, tie turbine will be tripped after a 70 second time delay.

Tie following alarms will actuate:

H'drogen S.O. Stator Clg Cabinet Trouble L)ss of Stator Coolant Trip Malfunction removal will restore the inlet strainer to the stator bars t) normal.

R$FERENCES: Sys Dese, OP-2324E, 32005 SH. 5, 6, 32006 SH. 1. 8.

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MALFUNCTION CAUSE AND EFFECTS Plant: MP2 Malfunction #: TUOlA BRGl TUOlF BRG6 TUOlB BRG2 TUO1G BRG7 TUOlC BRG3 TU0lH BRG8 TUOlD BRG4 TUOlI BRG9 TUO1E BRG5 TUOlJ BRG10 TUOlK THRUST Malfunction

Title:

Loss of Lube Oil to Turbine Bearing.

Malfunction Type: Generic / Variable. 100% equals total flow blockage.

Malfunction cause: Clogged Bearing Supply Line.

Plant Status: Normal full power.

Malfunction Effects:

Malf A - As the malfunction severity is increased, so will the bearing oil drain temperature on the number one bearing G (computer point T4401). When the actual bearing temperature (not displayed) exceeds 250 degrees F, the bearing will show an increase in its vibration level (UR-4502). If bearing failure does occur, it will affect the drag on the turbine when it coasts down after a trip. Bearing seizure will not occur.

Malf B Effects similar to Malf A except that the bearings listed through above as generic components may be individually affected.

J-Malf K - Effects similar to Malf A except that the thrust bearing is the major affected component. Bearing metal temperature is an active monitored computer point.

If thrust bearing metal temperature exceeds 300'F, a turbine trip will occur.

Malfunction removal will restore normal oil flow to the selected failed bearing. Bearing vibration levels will return to normal as the bearing temperature returns to normal.

REFERENCES:

Turbine / Generator Technical Manuals.

O Rev:

Date:

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I MALFUNCTION CAUSE AND EFFEC'fS

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Plant: MP2 Malfunction #: TUO2A HP TUO2B LP1 j TUQ2C LP2 j TUO2D Generator i TUO2E Exciter ,

I Malfunction

Title:

Turbine Bearing High Vibration.

l Malfunction Type: Generic / Variable. 100% equals 10 mil increase above baseline vibration.

Malfunction Cause: Rotor Imbalance. ]

Plant Status: Normal full power.

l Malfunction Effects: j 1'

Malf A - This malfunction will cause the vibration levels on bearings

(' number 1 and 2 to increase to the selected severity level.

( The increase in vibration will be added to the baseline vibration value. All other main turbine bearing vibration levels will increase to smaller values with respect to distance from the number 1 and 2 bearings.

The following alarms may actuate:

Turbine vibration Hi (7 mills)

Turbine Vibration Hi/Hi (12 mills)

There is no automatic turbine trip on high vibration.

Vibration levels will decrease as a function of turbine speed if the turbine is tripped.

Malf B Effects similar to Malf A except that the major turbine through components listed above as generic malfunction components E- may be individually affected.

REFERENCES:

32006 SH. 60 Rev: 0

-O' Date: 1/31/89

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1 g MALFUNCTION CAUSE AND EFFECTS j t i I

i Plant: MP2 Malfunction #: TUO3 4

i Malfunction

Title:

Shaft Driven Lube Oil Pump Reduced Capacity.

4 Malfunction Type: Variable. 100% equals no differential pressure developed by the pump.

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Malfunction cause: Worn Oil Impeller. i l

Plant Status: Normal full power.

l Malfunction Effects As the severity of this malfunction is increased the main shaft' oil pump discharge pressure will decrease (not a displayed parameter).

This will be observed as a decrease in bearing oil header supply pressure (PI-7210 at C07 and computer point display). i

() The turbine turning gear oil pump will start when bearing supply pressure decreases to 15 psi. The motor suction pump will start I

when main shaft pressure (not a displayed parameter) decreases to 10 psi.

The main turbine will trip on low shaft oil pressure if the turbine speed is 1300 rpm or greater.

The following alarms will be received:

Turbine Brg Oil Pressure Lo Turbine TGR Oil Pump Running Motor Suction Oil Pump Running Turbine Shaft Pump Press Lo-Lo Trip.

Malfunction removal will restore full capacity to the main turbine shaft driven lube oil pump.

REFERENCES:

26013, 32006 SH. 9, 12, 13, GE Turbine Tech Manual l

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Rev: 0 O- Date: 1/31/89

MALFUNCTION CAUSE AND EFFECTS v

Plant: MP2 Malfunction #: TUO4A - MSPp TUO4B - EBOPp TUO4C - TGOPp Malfunction

Title:

Failure of Turbine Lube Oil Pumps.

Malfunction Type: Generic /Non-Variable.

Malfunction cause: Motor Thermal Overload Failure.

Plant Status: Turbine on Turning Gear.

Malfunction Effects:

Malf A - This malfunction will stop the main turbine motor suction pump if running and prevent it from being automatically or manually started. Turbine roll up beyond 1300 rpm will fs not be accomplished without the motor suction pump in

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operation as the main oil pump does not become self-supplying until it is at approximately 90% rated speed (1620 rpm). The turbine trip will occur on low main shaft pump oil pressure. If this malfunction is inserted at less than 1300 rpm, bearing oil header pressure will decrease slightly. If this malfunction is inserted when the turbine speed is greater than 1620 rpm, it will have no effect on bearing oil pressure.

The following alarm will be received:

Motor Suction Oil Pump Overload / Temp Hi.

Malf B - This malfunction will stop the main turbine emergency bearing oil pump if it is running and prevent it from being automatically or manually started. If it is the only source of oil while the unit is on, the turning gear and bearing lift pumps will stop.

The following alarm will be received:

Turbine Brg Emer Oil Pump Overload.  !

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!s ,h/ Malf C - This malfunction will stop the main turbine turning gear  !

oil pump if it is running and prevent it from being automatically or manually started. If tripped while the i unit-is on the turning gear, the eeergency oil pump will i automatically start to restore bear.\ng oil pressure.

The' turning gear will momentarily stop while the' oil' I pressure is low. 1 The following alarm will be' received:

l Turbine Tgr oil Pump Overload / Temp Hi.

Malfunction removal will restore the faulty overload device ta) normal on the selected failed pump.

REFERENCES:

26013, 32006 SH. 11, llA, 12, 13, 21, 28, GE Turbine Tech Manual i

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! Rev: 0 Date: 1/31/89

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() MALFUNCTION CAUSE AND EFFECTS:

I Plant: MP2 Malfunction #: TUO5A- Lift Pump A TUO5B Lift Pump B TUO5C Lift Pump C TUO5D Lift Pump D TUO5E. Lift Pump E TUO5F Lif.. Fump F

-1 Malfunction

Title:

Turbine Bearing _ Lift Pump Failure. '

.l Malfunction Type: Generic /Non-Variable.

Malfunction Cause: Pressure Switch Failure.

Plant Status: Turbine Turning Gear Operations.

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Malfunction Effects:

Malf A - This malfunction will stop bearing lift pump A if it is in l (7-s) operation and prevent it from being automatically or j manually started. The loss of supply pressure from the i lift pump will not cause the turning gear to stop. It  !

will cause more drag on the turbine shaft. The pump low '

pressure indicating light on C07 will illuminate.

The following alarm will be received: j Turbine Brg Lift Pump Pressure Lo (if all lost).

Malf B Effects similar to Malf A except that the bearing lift 4 through pumps listed above as generic components may be F- individually affected.-

Malfunction removal will allow proper operation of the j selected failed lift pump pressure switch, after the reset  ;

pushbutton located on C06R is depressed. l 1

REFERENCES:

32006 SH. 21, 28-32 Rev: 0 Date: 1/31/89 ,

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. MALFUNCTION CAUSE AND EFFECTS f-s Plant: MP2 Malfunction #: WD01A 2-SSP-16.1 )

WD01B 2-SSP-16.2 l 4

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Malfunction

Title:

Containment Sump. Discharge valve ~ Failure (Shut). i Malfunction Type: Generic Malfunction Cause: Sump Discharge valve Auto Open Contact Failure.

Plant Status: Normal full power. )

Malfunction Effects:

Malf A - This malfunction will fail 2-SSP-16.1 in its closed l position. If either containment sump pump is started, the 4 valve will not automatically open. The contents of the containment sump will not be able to be pumped'out. If the containment sump pump.is started and the sumpLvalve remains j 7- shut, an associated high sump pump discharge pressure alarm

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will annunciate.

The following alarm will actuate as its setpoint is exceeded:

CTM Norm Sump Dis Press Hi.

Control board indications are:

2-SSP-16.1 Valve Position Containment Sump Level Ind.

l Malf B - Effect similar to Malf A with 2-SSP-16.2 being the affected component.

Malfunction removal will restore the selected failed t l

containment sump valve control to normal.

REFERENCES:

26024, 28124, 32030 SH. 3, 4.

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,1 Rev: 0 f((\j' Date: 1/31/89 ,

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I e MALFUNCTION CAUSE AND EFFECTS i .

Plant: MP2 Malfunction #: WD02A 2-SSP-16.1 l

WD02B .2-SSP-16.2 l

Malfunction

Title:

Containment Sump Discharge Valve Failure (Open). l

-J 4

Malfunction Type: Generic.

Malfunction cause: Mechanical Failure in Full'Open Position.

1 l

Plant Status: Normal full power. j i

j Malfunction Effects: ]

i Malf A - This malfunction will fail 2-SSP-16.1 in the open position i only after the valve has been fully opened. The valve will )

not be able to be shut by any associated electrical or air  !'

controlled. mechanism. Tech specs ~will be impacted.

<' control board indication is:

1 2-SSP-16.1 remains open, i

Malf B - Effects similar to Malf A with 2-SSP-16.2 being'the affected I component.  ;

Malfunction removal will restore the selected failed containment-sump valve control to normal.

REFERENCES:

26024, 28124, 32030 SH. 3, 4. 1 i

O Rev:

Date:

0 1/31/89 O_ __ _ _ _ __ _ _