ML19207B725
| ML19207B725 | |
| Person / Time | |
|---|---|
| Site: | Crane, Davis Besse  |
| Issue date: | 06/28/1979 |
| From: | Chilk S NRC OFFICE OF THE SECRETARY (SECY) |
| To: | |
| Shared Package | |
| ML19207B717 | List: |
| References | |
| FOIA-79-98, REF-10CFR9.7 NUDOCS 7909050136 | |
| Download: ML19207B725 (20) | |
Text
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SLIDE 1 DAVIS BESSE - 1 COMPLIANCE WITH SHORT-TERM PROVISIONS OF ORDER OF 5-16-79 912059 7009050/ $ 1
SLIDE 2 FEATURES OF ORDER A.
UPGRADE AFWS B.
ELIMINATE ICS AS AFWS CONTROL OPTION C.
SECONDARY TRIPS D.
SB LOCA PROCEDURES, ANALYSES E.
TMI-2 SIMULATOR TRAINING FOR OPERATORS F.
DUAL LEVEL SET POINT IN OTSG G.
SEPTEMBER 24, 1977 EVENT AT DB-1 3.1 2060
I SLIDE 3 TE IE-1 AUXILI;RI FEE'.?.iER SYSTEM IS A SAFEIY GPME SYSE h' digi ltdS TE FOUEIMG FE"IFEEfiS:
- 1. EE SYSTEi IS MSIC:ED SEISilC CATEGCRY I. IHE SYSTE4 HAS SEIriIC CEGCRY I VAL'iS FCR ISCL;TICt1 IF INTERCCt;NECito TO NCtl-SEIS 11C SYSTd1S.
- 2. mE SYSTEi IS MISSILE PROTECTED
- 3. FE SYSTEi IS PROTECTED FRG4 FLCCDING.
- 4. THE SYSTEi IS SINGLE FAIL'JRE PRCCF
'79Qll pryran,,b u h u tio n w g
PRESSURE SW. (2)(1.0 psig) 1-OF-2 TO SitUTDOWN
^
PUMP 1-1 ON LOW DR VEN AUX. FEED
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PUMP 1-1 X
E PRESSURE SW. (2) (3.3 p:,ig) 2-OF-2 TO TRANS. TO SW. #1 ON LOW w>
PRESSURE SW. (2) 2-OF-2 TO TR ANS. TO SW. #2 ON L OW g
'$ y STEAM DRIVFN AUX. FEED
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Lf PUMP 1-2 4V C
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g PUMP 1-2 ON LOW r.s w
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- _::2 5 SIMPLIFIED DIAGRAM FOR INTERIM ANTICIPATORY REACTOR TRIP SYSTEM BLOCK HS X
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ALARM FOR PDS1 :
- - XKT T-G TRIP BYPASS w
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" ARTS" TRIP REACTOR cz:
LOGIC TRIP o
O UV TRIP COIL o<>
R if RPS TRIP 93.20G3 LOGIC
SLIDE 6 DAVIS-BESSE TMI TRAINING 1.
FACILITY REVIEW 0F TMI-2 ACCID.ENT 2.
IE REVIEW 0F TMI-2 ACCIDEt1T 3.
tMI-2 SIMULATOR TRAINING (BZW) 4.
ON-SHIFT PROCEDURE REVIEW 5.
ON-SHIFT SHIFT FOREMAN REVIEW 6.
FORT!AL CLASSROOM TRAINIllG 7.
Of1-SHIFT REVIEW 0F EMERGENCY PRCCEDURES 8.
FACILITY WRITTEN EXAMS 9,
i1RC AUDIT 10.
FOLLONUP TRAlf11NG 11.
ON-SliIFT REVIEW OF PROCEDURES 12.
FACILITY AUDIT 9,UiOG4
SLIDE 7 DAVIS-BESSE EXAM SUB-JECTS 1.
kEACTOR COOLANT SYSTEM A.
HEAT SINKS B.
PORY C.
REACTOR TRIPS D.
SUBC00 LING E.
PRESSURIZER LEVEL INDICATI0flS 2.
SFAS EQUIPMENT OPERATION /0VERRIDE 3.
PROCEDURE CHAtlGES 4.
AUXILIARY FEEDWATER SYSTEi1 31206b
SLIDE 8 TYPICAL EXAM QUESTION THEORY RELAT '
QUESTION WHAT THREE C0fDITIONS CAN BE VERIFIED TO ASSURE THAT THE PRIMARY AND SECONDARY SYSTEMS ARE BEST AVAILABLE TO REMOVE HEAT FROM THE CORE?
EXPECTED 2NSWER (3 POIilTS) 1.
RCS IS SUBCCOLED (3Y 50 F) 2.
RCS FLOW IS IN PROGRESS (RCP'S O'l FOR FORCED FLOW OR NATURAL CIRCUL2.T::N AVAILAELE) 3.
FEEDNATER TO OTSG'S AVAILABLE (EITHER NORFAL FEED OR AUX FEED)
ITEMS Iil (
) NOT ESSENTIAL, BUT NICE.
ANSWER RECEIVED / GRADE RCF FLOW WITH PRESSURE AND TEMPERATURE 2ELOW SATURATION RCS SUBC00 LED FEEDWATER FLOW GRALE:
2.7/3 91)::0G43
SLIDE 9 TYPICAL EXAf1 QUESTION SYSTEM RELATED QUESTION DESCRIBE HOW THE OPERATOR VERIFIES PROPER AUXILIARY FEEDWATER SYSTEN OPERATION IN THE EVENT OF AM SFRCS ACiUATiOM.
E'< ECTED li!SWER (2 ?0I:lTS)
SEVERAL I'lDICATIONS ??.E A'/AILAELE.
OTSG LEVEL IS 10ST I:!PCRTAilT.
.+UX FEED FL W IS THE liEXT SEST INDICATION.
AUX FEED PU"P DISCHARGE PRESSURE LEAST IMPORTAtli AUX FEED PUMP SPEED ANSWER RECEIVED / GRADE CHECKS SPEED DISCHARGE PRESSURE - GREATER thall OTSG PRESSURE AFW FLOW PROPER S/G LEVEL - 96" IN AUTO-ESSENTIAL 35" IN MAtl.
C,RADE:
2/2 3120G7
SLIDE 10 TYPICAL EXAi1 QUESTI0tl PROCEDURE RELATED QUESTIDH DAVIS-BESSE HAS A NEW ADMIi1ISTRATIVE PROCEDURE, AD 1839.02, CPERATION AtlD C0flTROL OF LOCKED VALVES.
PRIOR TO. MODE 4, VALVE VERIFICATI0fl OCCURS.
HOW IS THIS ACCOMPLISHED?
EXPECED ails'eiER (2 POINTS) 1.
CiiE CPERATCR C0i!PLETES A VALVE LIST TO VERIP PROPER POSITICil AilD THAT VALVES ARE LCCXED.
2.
A SECOND CPERATOR REVERIPIES VALVE POSITI0il CN TFE VALVE LIST.
3.
THE TAGGIBlG SUPERVISOR COMPARES THE VALVE LIST WITH THE LOCKED VALVE LOG FCR DISCREPANCIES AND RESOLVES ALL DISCREPANCIES.
ANSWER RECEIVED / GRADE PERFORI1ANCE OF THE LOCKED VALVE PT WITH THE INDEPEllDENT VERIFICATION AilD DISCREPAf!CTES RESOLVED.
GRADE:
1.8/2 31:20US
TMI SPECIAL EXAM SENIOR OPERATOR LICENSES SLIDE 11 EXAM 1 EXAM 2 95.4 95.6 90.2 98.7 93.1 95.6 98.7 81.3 97 79.5 93.5 X
98 X
91 X
95 TMI SPECIAL EXAM REACTOR OPERATOR LICENSES 94.6 97.2 92.7 90.5 94.6 72.5 97 73.2 37 71.5 99 74.4 95
'(
c1~
3120G9 X:
NOT AVAILABLE FOR EXAM 1
SLIDE 12 NRC AUDIT 1.
TMI-2 ACCIDEilT 2.
SMALL BREAK LOCA RESPONSE
- 3..
FACILITY CHANGES 4.
FROCEDURE CHANGES 5.
AUXILIARY /EMERGEllCY FEEDWATER SYSTEM G1..070
SLIDE 13 TMI-2 ACCIDENT 1.
SEQUE.'lCE OF EVEilTS 2.
OPERATOR ACTIOilS/ CONSEQUENCES E:1' 07L d
~
SLIDE 14 SMALL BREAX LOCA RESP 0i!SE 1.
PRESSURIZER LEAKS 2.
SATURATIGil/SUBC00LI lG 3.
NATURAL CIRCULTTI0fl 4.
TERilli!ATION OF HPI 5.
!iEAT sit!KS 3120'72
SLIDE 15 FACILITY C'dAtlGES
~
1.
REACTOR TRIPS A.
TURBli1E TRIP B.
LOSS OF FEEDWATER C.
3YPASSES 2.
PORV SET P0lili 3.
AUXILIARY /ENERGENCY FEEDWATER SYSTEM 912073
stice 16 PROCEDURE CHAtlGES 1.
LOSS OF C00LM!T 2.
LOSS OF FEED';!ATER 3.
LOSS OF ALL RCP'S 4.
OPERATIi!G PROCEDURES 5.
ADMIilISTRATIVE PROCEDURES
SLIDE 17
AUTC:'2 TIC STARTS /CO ! TROL 2.
lE'Uil ST;1RTS/C0iiTROL l
3.
SUCTIO:! SUPPLIES 4.
SUR'/EILLAi'CE TESTI !G D120%
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