ML20214L548
| ML20214L548 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/30/1987 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| TAC-60462, NUDOCS 8705300016 | |
| Download: ML20214L548 (48) | |
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oe_v6s "T% wf%* l l AGENDA l SMUD/NRC MEETIi1G 2/10/86 RANCHO SECO TRANSIENT OF 12/26/85 l I l
- 1. INTRODUCTI0fl RON RODRIGUEZ
- 2. ROOT CAUSE AflALYSIS STEVE CRUNK
- 3. HARDWARE " FIXES" DAN WHITNEY II . PLANT MODIFICATIONS DAN WHITNEY I
- 5. PROCEDURE CHAtlGES AliD TRAINING STEVE REDEKER
- 6. 100 DEGREE C00LDOWN LIMIT B0B DIETERICH
- 7. PRESSURIZED TiiERMAL SHOCK B0B DIETERICH
- 8. START-UP SCHEDULE RON RODRIGUEZ Sok"200ck$$000012 S PDR
i s e O ROOT CAUSE ANALYSIS STEVE CRUNK l
] DIRECT CAUSE: THE IMIATE TECHNICAL OR ENGINEERING EXPLANATION FOR THE FAILURE OBSERVED. ROOT CAUSE: THE PROGRAITIATIC SHORTFALL OR LACK THAT ALLOWED THE FAILURE TO OCCUR.
u ROOT CAUSE ANALYSIS COW LEX EVENT REQUIRED BREAKDOWN INTO FIVE " EVENT THEMES"
- 1. LOSS OF ICS
- 2. RAPID C00LDOWN
- 3. MAKEUP PUMP
- 4. HEALTH PHYSICS
- 5. EMERGENCY PLAN l
____ _ _ _ _ _ . _ _ --. _ _ -. .- , ,_. . . _ , , _ . , _ ~ . . . . , _
1 ISSUES REVIEWED BY IAG
- 1. PROCEDURAL ADEQUACY
- 2. DESIGN FEATURES
- 3. HUMAN FACTORS II . OTHER RELATED ISSUES INCLUDING ITEMS SUCH AS:
TRAINING PREVENTIVE MAINTENANCE PERSONNEL ACCESS ADDITIONAL TECHNICAL ANALYSIS BY B & W
q o 'j t.
~
ROOT CAUSES AND CONTRIBUTORY CAUSES (1) LOSS OF ICS MANUFACTURING ERROR
- DESIGN CHARACTERISTICS OF MODULE H
- S1, S2 SWITCH DELAY u
(2) RAPID C00LDOWN DELAY IN IMPLEMENTING
- PROCEDURES 1 DESIGN CHANGES TO
- TRAINING L MITIGATE EFFECTS OF LOSS OF ICS (3) MAKEUP PUFFS PROCEDURES TRAINING (11) HEALTH PHYSICS HUMAN PERFORMANCE
- TRAINING
,
- IMPRECISE DEFINITION OF HP RESPONSIBILITIES AUTHORITIES / DUTIES (5) EMERC{NCY PLAN TRAINING
- HUMAN PERFORMANCE
- PROCEDURES
AREAS FOR IMPROVEENT
- 1. PROCEDURAL ADEQUACY GUIDANCE FOR REC 0VERY FROM AFAS ICS CASUALTY PROCEDURE GUIDANCE E.05 C00LDOWN PROCEDURE CLARIFICATION AND/0R RE0RGANIZATION OF EERGENCY PLAN
- 2. DESIGN FEATURES
- AUX FW VALVES, TBVs, ADVs POSITION ON LOSS OF ICS
- 3. HUMAN FACTORS UNDERSTANDING 0F HP ASSIGNENT/INVOLVEENT VISIBILITY OF ICS POWER SWITCHES fl . HUMAN PERFORMANCE EERGENCY PLAN IMPLEENTATION LIMITING C00LDOWN BY SECURING AFW PUMPS ADHERENCE TO RAD-CON PROCEDURES
- 5. OTHER ISSUES TRAINING ,
PREVENTIVE MAINTENANCE
HARDWARE " FIXES" DAN WHITNEY 6
3 EQUIPENT REQUIRING REPAIR FOLLOWING EVENT
- 1. AFW FLOW CONTROL VALVE FV-20527
- 2. AFW ISOLATION VALVE FWS-063
- 3. MU PUMP P-236 SEAL / SHAFT DAMAGE
. I4 . ICS PSM
- 5. ICS WIRING CHANGE 00T
- 6. ICS S1/S2 TIE DELAY
- 7. RAD MONITOR R-15001 SAMPLE PUMP SEALS
- 8. WG COMPRESSOR
- 9. PRI/SEC LEAK l
-__-- . --- . - .- .- l
PLAflT MODIFICATIONS DAN WHITNEY
-j 8
f , l PLANT MODIFICATIONS TO PRECLUDE LOSS OF ICS POWER TO MITIGATE TRANSIENTS UNDER CONSIDERATION 'l O
MODIFICATIONS .i
- ICS CABINETS AND POWER SUPPLIES 4
ICS/AFW FLOW CONTROL VALVE INTERFACE ICS/ADV INTERFACE ICS/TBV INTERFACE TECHNICAL SUPPORT CENTER (TSC) SPRINKLER SYSTEM , MAIN STEAM LINE FAILURE LOGIC SETPOINT CHANGE. l ) f
- , , , , , - - - --en--v.--,--- ,--~ ,n.-- ----w--m--r, , , ,--------,<rn, - - . .,-e--,~.,---------,- -r - - - ~,,---w, n - ,y.. -- . - , - - - , - - - -n.,-.-
120 VAC S1 S2
- o o 24V 24V POWER POWER SUPPLY SUPPLY o <>
TRIP SIGNAL 32 57 AUCTIONEER BUS --] I V <i i POWER SUPPLY L _ ,, MONITOR h LOAD BUS "g , y y y VOLTAGE SIGNAL ' HIGH RESISTANCE CONNECTION LOADS l 1 ICS POWER DISTRIBUTION
SIMI-I l'20 VAC F- + -------------+ -----.e------., g
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' SUPPLY 1
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AUXILIARY FEEDWATER CONTROL INDEPENDENT OF I.C.S. FIGURE l e t l
e, ,gg NEW SCOPE - l - l lCS CLOSE
*
- CtDSE CtOSE i
' Rkb MJTO
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A4LO _ CONTACT SwtTCHON LDCAL OPEN ON DISABLE tt2SD SWITCH LOSSOF ICS POWER t
-o - -
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! 30 Atp~.u 6
i
- , SOLEN 0 i DEEHEIK,1 i
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i 1 . . 4 4
~
ADV MANUAL CONTROL . FIGURE 2
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4
_ - . - .=-_ ._ _ .
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,n ,y NOG, MAL,- ,
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, POWER -
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- - d.
hs AL$RM IDADS h 4 SO - SOLEN 010 DEENERGIZi TO CtDSE TBvS l TBV MANUAL CONTFOL - FIGURE 3 e
MODIFICATIONS CONSIDERED PFP TURBINE CONTROL ON LOICS POWER MAIN STEAM LINE ISOLATION WITHOUT ICS POWER INTERLOCKS ON MAKEUP /HPI PUMPS CR INSTRUENT FAILURES ON LOICS CR NOISE FROM ESSENTIAL HVAC RADIATION MONITOR BLOWER ISOLATION ON SFAS 4
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Sul9tARY IMPLEMENTING MODIFICATIONS TO REDUCE LIKELYH00D OF LOICS POWER IMPLFfE.HTING MODIFICATIONS TO ENHANCE THE EFFECTIVENESS OF THE OPERATOR FROM THE CR CR CONTROL. INDEPENDENT OF ICS FOR:
- AFW FLOW VALVES
- ADV's
- TBV's ,
SIMILAR TO OTHER B 3 W PLANTS i e j
POSITIO!!S OF KEY VAINES AND SYSTEMS - FOLIDWING IASS OF ICS DC POWER . RANCllO DAVIS CRYSTAL SEc0 RIVER MIQ-1 oCoNEE THI-l IlESSE BAILEY BAILEY BAILEY BAILEY BAILEY EQUIPHENT BAILEY 721 721 TYPE 820 820 020 820 TBPV 50% 0% 0% 50% H/A N/A ADV 50% on H/A N/A. H/A N/A EFW CONTROL ~ 50% H/A N/A N/A N/A N/A VALVES STARTUP FW 50% 50% 50% 50% H/A N/A FLOW PATil _ Hall 7W 0% 0% 0% 0% H/A N/A FID 0 ?ATH HF PUHP 2600 RPM 4690 RPH 4200 RPH HIH SPEED H/A N/A GOVERHOR , 5tOD CONTROL TO MANUAL TO HAHUAL TO HANUAL TO HAHUAL N/A H/A MAIN TURBINE AS IS AS IS AS IS AS IS N/A N/A GOV BRHOR DOES PLANT HO YES YES YES HO YES HAVE HSIVs? , ._ e
PROCEDURE CHANGES AND TRAINING STEVE REDEKER I l l I
PROCEDURES LOSS OF ICS RAPID C00LDOWN ABNORMAL TRANSIENT OPERATING GUIDELINE (AT0G) METHOD IS SOUND FOR LOSS OF ICS AND OVERC00 LING RANCHO SECO PROCEDURES CONFORMED TO AT0G TO TERMINATE OVERC00 LING CRITERIA WHEN TO TAKE CERTAIN ACTIONS TO TERMINATE OVERC00 LING HAVE BEEN DEVELOPED AND IMPLEMENTED CRITERIA FOR OTHER SYMPT 0MS WERE IN PLACE ICS REC 0VERY PROCEDURE HAS BEEN IMPLEMENTED MODIFICATIONS HAVE BEEN INCLUDED IN PROCEDURES 1
1 i i l l 1 MAKEUP PUFF EERGENCY PROCEDURES REVISED TO ASSURE SUCTION IS AVAILABLE 1 RECOVERY FROM SFAS ACTUATION PROCEDURE IMPLEMENTED I l 1 I
l i l l WATCHSTANDING i IMPROVED DIVISION OF RESPONSIBILITIES BETWEEN EERGENCY COORDINATOR AND SENIOR CONTROL ROOM OPERATOR I, l 1 j i 1 1
t 1 EERGENCY PLAN IPPROVEMENT TO ASSURE USE OF PROPER FORMS CORRECTIONS LONG TERM EFFORT TO SIMPLIFY
= _ _ -. . ..
HEALTH PHYSICS I
- IMPROVED PROCEDURE FOR ENTRY INTO AREAS OF UNKNOWN RADI0 ACTIVITY 1
i L i a l I 1
. _ _- __ . = - . . - .
i s , i i i PLANT TRIP RESPONSE TEAM i DOSE ASSESSENT i
! FOLLOWUP NOTIFICATIONS RESTART EVALUATION REPAIR ACTIVITIES 1
1 i e i
TRAINING EVENT AWARENESS PLANT MODIFICATIONS EERGENCY PROCEDURE,5 ICS RECOVERY PROCEDURE GENERAL PROCEDURES VALVE OPERATION t WATCHSTANDING HEALTH PHYSICS 4 EMERGENCY PLAN
100 DEGREE C00LDOWN LIMIT B0B DIETERICH
NORMAL C00LDOWN DEFILED AS 100 F/HR DESIGN 1 l l
1
. THE SASCOOC & WILCOX CO. .
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- reatuar un parttuar (arO XMl4G OF PL ANT LIFE) lOM4**-2 M e -_____
..{ . Table 2
.Cs,eratinst Transient Cycles _ ,
Design Cycles _ Transient Transient Descrietion. Number . Beatup and Cooldown 120
- 1. 8 100*F/hr hestup and cooldown 120_
8 35'7/hr heatup ,and 100'F/hr cooldo
- 2W Total '
, 1440 Power change O to 15% and.15 to 05 2
- k8.000 Power Loading 8% to 100% power 3 -
48,000 Power ala=Mns 100% to 85 power
% 8,000 105 Step Load Increase ,
5 .
. 3,000 1005 Step Load Decrease .
6 T Step Load Reduction (100% to 85 Power) 160 Resulting from turbine trip M Resulting from electrical load rejection 310 Tctal. , . 8 Besctor Trip k0 Type A 160 Type B - 88 Type C Trips included in transient numbers 11. 15 112 16, IT s 21 TOO Tetat .
~ 80 Rapid Depressurization
- 9 20 10 Change of Flow .
k0 11 Bod Withdrawal Accident 20 12 Hydrotests Steady State Power Variations 13 k0 ,
- 1%
- Control Rod Drop -
k0 15, Loss of Station Power , 1 16 Steen Line Failure 20 S ITA Loss of Feedvater to one Steam Generator
', 10
( Stuek open Turbine Bypass Valve 17B SERIAL CS(F)-3-92 FACE 2% . E DATE: 8/28/70 888-11/0670 D
APPENDIX G TO 10 CFR 50 REQUIRES CALCULATION OF P/T LIMIT
- HEATUP
- C00LDOWN
- VARIOUS VALUES OF DTT
- SPECIEN PROGRAM
- LARGE FACTORS OF SAFETY J
i
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RANDS SECO UNIT 1 TEDWICAL SPECIFICATION 5 I ," , Limiting Conditions for Operatica ( 3.1.2 MESSURIZATION, IEATIF, Als emu nem LIMITATIONS Specification 3.1.2.1 Inservice Leak and itydrostatic Tests: 55>4 pressure temperature limits for the first eight EFp years of inservice leak and lydmstatic tests are given in Figure 3.1.2-3. Meetup and coeldomer rates shall be restricted according to the rates. specified. in Figure 3.1.2-3. 3.1.2.2 M .e Coeldown: 55>< For the first eight EFp years of power operations, the reactor coolant pressure and the system heatup and coeldown rates (with the asception of the pressurizer) shall be limited in accordance with Figure 3.1.2-1 and Figure 3.1.2-2 mspectively. Heatup and cooldown rates shall not exceed the rates. stated on the associated figure. 3.1.2.3 The secondary side of the steam generator shall not be pressurized above 200 below 130,gsig . if the temperature of the steam generator shell is 3.1.2.4 The pressurizer heatup and cooldoun rates shall not exceed 100*F in any 1-hour period. l 3.1.2.5 The spray shall not be used if the temperatum diffannca between the l pewssurizer and spray fluid is greater than 410*F. j 55>4 3.1.2.6 prior to exceeding eight effective full power years of operation, 1 Figures 3.1.2-1, -2, and -3 shall be updated for the next service I period in accordance with 10 CFR 50 Appendix G. Section Y.8. The highest predicted ad,fusted reference temperature of all the beltline materials shall be used to determine the ad,1usted reference temperature at the end of the service period. The basis for this prediction shall be submitted for WtC staff review in accordance with Specification 3.1.2.7. 3.1.2.7 The updated proposed technical specifications referred to in 3.1.2.6 shall be submitted for MAC review at least 90 days prior to the end l of the service period. Appropriate additional MRC review time shall : be allowed for proposed technical specifications submitted in l accordance with 10 CFR 50. Appendix G. Section V.C. 55>4 3-3 Amendment No. 55 1
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RAacicSEC5trdIT1 TEcletICAL SPECIFICATIONS 55e> Limiting conditions for Operation x. v aw a Figure 3.1.2 2 gC e ea
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LINEAR C00LDOWN USED IN ANALYSIS
- THERMAL GRADIENT IS REAL LIMIT
- MANY WAYS TO COOL DOWN
- PRESENT INTERPRETATION l
FICTICIOUS Rx TRIP FOR EXPLANATION PURPOSES ONLY 600 000LDOWN CURVE STARTS AT 550*F 550 - C00LDOWN CURVE SLOPE - 100*F PER HOUR l c- ALLOWABLE 15*F BELOW C00LDOWN CURVE b ~ g 500 - -
),
e 's ' CURVE SHIFTS TO RIGHT Il '% O 450 - ~ s I ,A w 's E 's ~~ 400 - ACCEPTABLE UNACCEPTABLE ACCEPTABLE 350 - = , F 300 - 250 ............................... ..........,.. ...,.... . . . . . 00:00 10 20 30:00 40 50 60:00 70 80 90:00 t TIME - Minutes from Rx Trip
.. r DEC. 5, 1985 Rx TRIP RCS B-LOOP TEMPERATURE (Ave) 590 -
\
580 - C00LDOWN CURVE STARTS AT 550*F L1.
. 570 - C00LDOWN CURVE e
2 0 560 - e , O . y 550 - 4 D 540 - hJ G. 2 530 - N ! 520 - ALLOWABLE 15'F BELOW C00LDOWN CURVE 510 - 1 500................................................,............................... .a...... ..,... . . . . . . . . . . . . . 00:00 10:00 20:00 30:00 TIME - Minutes from Rx Trip 1
Rx TRIP DEC. 26, 1985 ROS B-LOOP TEMPERATURE (cold) 600 } C00LDOWN CURVE STAR 15 AT 550*F 550 - COOLDOWN CURVE SLOPE IS 100*F PER HOUR i J LOWABLE 15*F BELOW C00LDOWN CURVE g
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. TIME - Minutes from Rx Trip i
NEW P/T CURVE GENERATED
- STEP CHANGES ALLOWED
- TEMPERATURE SPECIFIED AB0VE WHICH l
ANY TRANSIENT ALLOWED 1
- TECHNICAL SPECIFICATION CHANGE WILL BE REQUESTED 1 l
l 1 i O j
PRESSURIZED THERMAL SH0CK BOB DIETERICH
SB LOCA ANALYSIS FOLLOWING TMI
- CORE COOLING
- RANGE OF BREAK SIZES
- HPI ONCE THROUGH COOLING FOR LOSS OF ALL FEEDWATER
- WITH " LOOP" COOL HPI WATER RAN DOWN VESSEL WALL
- THERMAL SHOCK
- PRESSURIZED THERMAL SHOCK 2
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4 B & W OWNERS GROUP ANALYSIS COMPLETED AUGUST 1982 BAW-1751
- MULTI-DISCIPLINED ANALYSIS e
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l l j PTS ANALYSIS ' - - i SB LOCA RCS TRANS1ENT* ~PRESSIIHE w
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/ HISTORY .
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\ .REPRESSIMIZATION--* PRESS / TEMP- -
- MIXING TRANSIENT HISTORY ANALYSIS
-~ > WALL -
THERMAL
= MECHANICS-* LIFE ANAL YSIS WFPY)
ANAL YSIS ANALYSIS
/
l0 VeSSet / MA TERIAL' PROPERTIES VESSEL & WELD
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- FLWNCE DETERMINA TION
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l i GUIDANCE TO OPERATORS
- BASED ON PTS STUDY
- CONSERVATIVE ASSUMPTIONS
- NO FORCED FLOW
- 32EFPY
- WORST FLAW
- C00LDOWN OVER 100 F/HR
-REPRESSURIZATION TO 2500 PSI l
l 1
'1 ENCLOSURE 8!1 l FIGIRE 1 i/ -
,REACTM COW. ANT SYSTEM INTERIM FRACTWE LIMIT l
l NO FMCED FLOW A M THERMAL SHOCK OPERATI N REGION i 3200' l" - - r nuit: Maintain'ng the reactor t M "
- coolant subcooled takes - --
i - precedence over the Interim N0 FORCED FLOW ! Brittle Fracture Curve OPERATING EANO
'(8&W 74-1122501 page.6) W/HPI
! 2800 _ EINTERIM 8RITTLE FRACTT= - i 2600 - i CURVE 8REAK POINTS VARIABLE i NN PRESSM E E E _ l . 2400 - E _ . 1 E 303 250 -
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