ML20138P008

Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007

ML20138P008
Person / Time
Site:	Millstone, Dresden, Davis Besse, Peach Bottom, Palo Verde, Fermi, Catawba, Point Beach, Oyster Creek, Sequoyah, Seabrook, Brunswick, Turkey Point, Crystal River, Robinson, Rancho Seco, 05000000, Fort Saint Vrain
Issue date:	10/21/1985
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Thompson H Office of Nuclear Reactor Regulation
References
NUDOCS 8511060282
Download: ML20138P008 (24)

Text

f, r 6 00T 211985 MEMORANDUM FOR: Hugh L. Thompson, Jr., Director Division of Licensing FROM: Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

SUMMARY

OF THE OPERATING REACTORS EVENTS l MEETING ON October 7, 1985 - MEETING 85-19 On October 7,1985, an Operating Reactor Events meeting (85-19) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on October 7,1985. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. In addition, the assignment of follow-up review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3. Each assignee should review Enclosure 3 with regard to their respective responsibilities.

Note that several assignees are approaching the due date. Please be responsive and advise ORAB (D. Tarnoff, x29526) if the target completion date cannot be met.

Dennis M. Crutchfield Assistant Director for Safety Assessment. DL 3

Enclosures:

DISTRIBUTION As Stated Central Files NRC PDR ORAB Rdg cc w/ enc 1: ORAB Members I

See next page I

or SL:0RAB:DL l0RAB:DL AD/SA:DL go \o ORAfl Dipnoff:cl[ RWessman ' GHolahan DCrutchfield 10/f/85 o / g/85 /g5/85 to /i$/85 9e lM88R 8%, f\Q[y) g gi

j. OCT 211985 I*

! MEMORANDUM FOR: Hugh L. Thompson, Jr. , Director Division of Licensing FROM: Dennis M. Crutchfield, Assistant Director for Safety Assessment DL i

SUMMARY

OF THE OPERATING REACTORS EVENTS

! MEETING ON October 7, 1985 - MEETING 85-19

On October 7, 1985, an Operating Reactor Events meeting (85-19) was held to l brief the Office Director, the Division Directors and their representatives on i

events which occurred since our last meeting on October 7,1985. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. In addition, the assignment of follow-up review responsibility i was discussed. The assignments made during this meeting and the status of 4

previous assignrents are presented in Enclosure 3.

l Completion dates have been assigned for items in Enclosure 3. Each assignee should review Enclosure 3 with regard to their respective responsibilities, i Note that several assignees are approaching the due date. Please be responsive

and advise ORAB (D. Tarnoff, x29526) if the target completion date cannot be met. l I

l .

Dennis M. Crutchfield, Assistant Director  :

for Safety Assessment, DL j

Enclosures:

DISTRIBUTION ,

} As Stated Central Files t NRC PDR l i ORAB Rdg i cc w/ encl: ORAB Members l See next page 1

r i

! rg .

I '

! ORA SL:0RAB:DL :0RAB:0L AD/SA@:DL N i DTpnoff:cl RWessman r GHolahan 0Crutchfield i

/p/f/85 o/gg/85 /g/85 to /s%/85 i

! t 1

)

1

y i

[ga nac Ic, UNITED STATES

!\ c /? NUCLE AR REGULATORY COMMISSION Y WASWNGTON, D. C. 20555 5s 4 af ,,5 i,

gw ,/

j GC 21 b.

l l j t i

I MEMORANDUM FOR: Hugh L. Thompson, Jr., Uirector i Division of Licensing l

l FROM: Dennis M. Crutchfield, Assistant Director  !

i for Safety Assessment, DL  :

l

SUMMARY

OF THE OPERATING REACTORS EVENTS  ;

MEETING ON October 7, 1985 - MEETING 85-19 l i

i

) On October 7,1985, an Operating Reactor Events meeting (85-19) was held to i l brief the Office Director, the Division Directors and their representatives on i

events which occurred since our last meeting on September 30, 1985. The list of i attendees is included as Enclosure 1. j 1 l 1 The events discussed and the significant elements of these events are presented i i in Enclosure 2. In addition, the assignment of follow-up review responsibility -

l was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3. '

1 l Completion dates have been assigned for items in Enclosure 3. Each assignee should review Enclosure 3 with recard to their respective responsibilities.

, Note that several assignees are approaching the due date. Please be responsive

! and advise ORAB (D. Tarnoff, x29526) if the target completion date cannot be met. i

( .1.h '\

Dennis M. Crutchfield, Assistant Director [

, for Safety Assessment, DL l

Enclosures:

) As stated l j cc w/ enc 1:  !

j See next page i i l l

1 i [

}  !

1

[

4  ;

I

Hugh L. Thompson, Jr. l cc: H. Denton E. Rossi IE R. Bernero R. Hernan J. Knight F. Schroeder T. Speis G. Knighton C. Heltemes D. Silver T. Novak J. Lyons W. Russell D. Brinkman J. Taylor E. Weiss E. Jordan R. Baer F. Rowsome G. Regna W. Minners H. Bailey L. Shao D. Lynch T. Ippolito K. Heitner G. Lainas S. Miner M. Grotenhuis R. Gilbert E. Sullivan D. Wigginton D. Beckhan M. Licitra G. Edison M. Ley j K. Seyfrit E. Butcher T. Murley, R-! J. Stolz J. Nelson Grace, R-II D. Vassallo J. Keppler, R-!!! S. Varga

! R. D. Martin, P-IV B. Youngblood j J. B. Martin, R-V J. Zwolinski R. Starostecki, R-! P. Baranowski R. Walker, R-!! D. Kirsch, R-V C. Norelius, R-!!! R. Denise, P-IV 4

1 f

i 4

j. -

ENCLOSURE 1 I  ;

j LIST OF ATTENDEES t i

OPERATING REACTORS EVENTS BRIEFING (85-19) l

] OCTOBER 7, 1985 i l I Name Division Name Division l f H. R. Denton NRR M. Grotenhuis NRR/DL/0RB2 4

i l D. Tarnoff NRR/DL/0RAB K. Heitner NRR/DL/0RB3 l

! W. H. Regan NRR DHFS J. Stone IE/DQAVT ,

i l D. Vassallo NRP/DL/ ORB 2 G. Requa NRR/ORBI 1

! M. Caruso NRR/0RAB W. Swenson NRR/0RAB

) R. V. Hernan NRR/PPAS E. J. Butcher NRR/DL i G. C. Lainas NRR/DL S. Black NRR/DL

} D. Crutchfield NRR/DL C. Miller NRR/DL f

i M. Chiramal AE00/ROAB G. Lanik EAB/IE J. Lazevnick NRR/DSI/PSB D. Lynch NRR/DL/LB1 ,

S. Rubin AEOD F. Manning AEOD I

! t j S. Miner NRR/DL/0RBA J. Stolz NRR/DL/0RB4 l H. Bailey I&E G. Kalman NRR l H. Ornstein AEOD K. Seyfrit AE00 i

! K. Eccleston NRR/TOSB B. Gilbert NRR/DL/0RBS E. Weiss IE/DEPER/EAB J. Beard NRR/DL/0RAB l F. Miraglia NRR/DL T. Speis NRR j l C. Rossi IE/DEPER/EAB R. Baer IE/DEPER/EGCB  ;

l l S. Schwartz IE/DEPER D. Humenansky OCM  !

l W. Minners NRR/ DST T. Novak NRR/DL J. Knight NRR/DE R. Houston NRR/DS!

, F. Schroeder NRR/ DST G. Holahan NRR/DL R. Wessman NPR/DL M. Licitra NRR/DL

4 j OPERATING REACTOR EVENTS BRIEFING (85-19)

OCTOBER 7, 1985 [

I PALO VERDE UNIT 1 LOSS OF 0FFSITE POWER EVENT  !

1  !

! l RANCHO SECO REACTOR TRIP a UNCONTROLLED C00LDOWN t

i BRUNSWICK UNIT 2 MSIVs FAILURE TO CLOSE i

)  ;

i j

i FERMI UNIT 2 RAPID C00LDOWN EVENT i

FORT ST, VRAIN START-UP OPERATIONAL PROBLEMS  !

l 'ca .

DRESDEN UNIT 3 SCRAM SOLEN 0ID PROBLEM INDUCED LEAKAGE (FOLLOW-UP)

]s .

I i

r l OTHER EVENTS OF INTEREST I

j ROBINSON UNIT 2 EXXON FUEL CODE INPUT ERROR -

i

l J l

I, .

l' i

I l PALO VERDE l-LOSS OF 0FFSITE POWER

< OCTOBER 3, 1985 (J. T. BEARD, NRR)  !

) -

PROBLEM I SIMULTANE0US LOSS OF BOTH 0FFSITE POWER CIRCUITS

! CAUSING PLANT TRIP l LOSS OF SWITCHYARD INSTRUMENTATION l J

LOSS OF CONTROL ROOM OPERATION OF SWITCHYARD

] ,

I BREAKERS SIGNIFICANCE

! EVENT MAY HAVE BEEN CAUSED BY MALFUNCTION I

0F A SINGLE COMMON MULTIPLEXING MONITOR SYSTEM:

STill UNDER INVESTIGATION i .

4 i

i I ,

} l 4

i 1 i I I l

i

4 CIRCUMSTANCES PLANT AT 82% POWER IN ABNORMAL ELECTRIC POWER CONFIGURATION (N0 LOADS ON AUX TRANSFORMER)

)

SIMULTANEOUS LOSS OF BOTH S/U TRANSFORMERS

] ,

EDGS AUTO STARTED, LOADED l

PLANT TRIP ON LOSS OF RCPs -- LO DNBR PROJECTION AFW AUTO STARTED, MAINTAINED PROPER S/G LEVEL SWITCHYARD MULTIPLEXER LOST CAUSED LOSS OF 4

INDICATIONS AND REMOTE CONTROL

OFFSITE POWER RESTORED LOCALLY IN 24 MINUTES

, REPEATED ATTEMPTS TO RE-START RCPs WERE UNSUCCESSFUL DESIGN REVIEW REVEALED A LOCK 0UT ON RCP RE-START

INTENDED TO ACCOMMODATE C0ASTDOWN OF THE MAIN ,

GENERATOR VOLTAGE, ALTHOUGH RCPs WERE NOT ON MAIN GENERATOR POWER AT THE TIME j AFTER RESET OF NEWLY-DISCOVERED LOCK 0UT FEATURES, RCPs WERE RE-STARTED SUCCESSFULLY j

FOLLOW-UP  ;

i

• UTILITY STILL EVALUATING I

• NRR/0RAB MONITORING 4

i l

l

i t l l' I j '

i I

F.

'l j rg gv ,  !  !  !

/

a g

, +

l i ,

.cweeuun + -

i g i  ! -

i ,

,  ; I i i

, .  ;  ; . t .  ! .

i

, i I

, i _ , _; _ _:_.--___,___ .

_ _ _ . ,_ _ .. i I  ;,

. i i  ;

i S a rr e

' l l l

s tu.J Ya '

tu->

• w .rpa g lsaw.d= w- w! as n;n e,n << mmE mm i

., j

, _. . < i, ,

gjg _j t-g  !

l l ,w __ __ __ _ _ _ _ _ . _ _ . . _ _ _ _ . _ _ _ _ ._ _ _

g l

l  ; F M IU4 1 *

, 6 .' 1 D -

o , , ,

I  ; ,

u.s u.' us u.,  ;  : ., ,

1

, i . .  ; ,

w i

W-l J us,e Aur  : I l.; i (w @)l

! . l - -  :

! . . 3 l l .: .

) i t

.i  ! . .

l l i l,! .

I i , .,, .

6 -

6 4 I i ,  ! l l

.Nf-0 V W N Y $ tllRI W 6 V ,

, .c 4

1 -

i i ' i, - , i-

! t -

I i

Ll : w' , l !-

I

~7'70 '

c ~ ~.:

l i

j

'M ' R h,

j i.

m as f  !!j"l:'

I j 8  ! '

i .

i l 3

i I f

} , ,

i t

i f

,l I .

2

' I l l

i -

?

l .

• , . . t I

• ll i

, e i l

f I i i * '

, l

1 RANCHO SECO-REACTOR TRIP AND UNCONTROLLED C00LDOWN OCTOBER 2, 1985 - (H, BAILEY, IE) i PROBLEM UNCONTROLLED C00LDOWN OF RCS SAFETY SIGNIFICANCE PERSONNEL ACTIONS WERE REQUIRED TO MITIGATE A FAIRLY COMPLEX EVENT TO PREVENT EXCEEDING THE MAXIMUM RCS C00LDOWN RATE ALLOWED BY TECHNICAL SPECIFICATIONS DISCUSSION UNIT AT 15% POWER WITH LOW DECAY HEAT WHEN A LOSS OF VACUUM CAUSED MAIN TURBINE TRIP

, BOTH MFPs TRIPPED WITHIN A FEW MINUTES AFTER TURBINE TRIP, MFPs ARE STEAM DRIVEN AND EXHAUST l TO LP CONDENSER.

REACTOR TRIP ON TURBINE TRIP AND MFP TRIP WAS

INOPERATIVE SINCE UNIT WAS BELOW 20% POWER REACTOR TRIPPED ON HIGH PRESSURE (2300 PSIG) AS THE OPERATOR WAS TRYING TO BRING THE STANDBY

MFP ON LINE.

A FW HEATER REllEF VALVE LIFTED AND STARTED A REACTOR C00LDOWN TRANSIENT. REACTOR COOLED FROM

) A TAVG OF 582*F TO 490*F IN ABOUT 1/2 HOUR, BASED ON INITIAL INFORMATION (TECH SPECS ALLOW 100*F i C00LDOWN IN ANY 1 HOUR PERIOD.

PRESSURIZER LEVEL DROPPED TO 35 INCHES FROM NORMAL  !

0F 220 INCHES. OPERATORS MANUALLY INITIATED HPl.

PRESSURIZER LEVEL RESTORED. FW HEATER STEAM SUPPLY SHUT OFF, SECURED HPI AND RESTARTED "B" MFWP.

CONTROLLED DEPRESSURIZATION AND SOAK FOR 3 HOURS AT 1400 PSI BECAUSE OF PRESSURIZED THERMAL SHOCK LIMIT FOLLOW-UP LICENSEE WILL REQUIRE TROUBLESHOOTING PROCEDURES TO BE APPRAISED BY MANAGEMENT PRIOR TO FURTHER i INVESTIGATION TO PRECLUDE DESTROYING EVIDENCE REGION V ISSUED CAL LICENSEE MEETING WITH NRC BEING SCHEDULED i;

e e

-,---,---,,+-,,,evn.-, ~. , ---~~ e- wn-=~m, - - -

i BRUNSWICK 2-MSIVs FAILURE TO CLOSE SEPTEMBER 27, 1985 -(M. GROTENHUIS, NRR) t t

PROBLEM 3 0F 8 MSIVs FAILED TO CLOSE IN TEST SIGNIFICANCE COMMON CODE LOSS OF CONTAINMENT INTEGRITY AND RCS ISOLATION CIRCUMSTANCES UNIT 2 SHUTDOWN FOR HURRICANE GLORIA 1

i * '

MSIV TEST BEFORE RESTART - 3 MSIVs FAILED TO CLOSE PROBLEM TRACED TO AIR OPERATED SOLEN 0ID ETHYLENE PROPYLENE" DISC DEGRADATION FOLLOW-UP ONE SOLEN 0ID SENT TO ASCO AND TWO SENT TO HARRIS 1 ENERGY CENTER FOR STUDY REGION II INSPECTOR ONSITE 10/2/85 l REGION II FOLLOW-UP l START-UP NOT PLANNED UNTIL PROBLEM IS UNDERSTOOD AND i CORRECTED i

4 i

.' l l

, FERMI 2 - RAPID C00LD0WN EVENT OCTOBER 1, 1985 (D, LYNCH, NRR)

~

PROBLEM INADVERTENT RAPID C00LDOWN IN EXCESS OF THE TS LIMITS SAFETY SIGNIFICANCE

, COMMON MODE FAILURE OF TURBINE BYPASS VALVES HIGH THERMAL STRESSES IN COMPONENTS OF PRIMARY COOLANT PRESSURE BOUNDARY DISCUSSION REACTOR IN STARTUP MODE AT 1% POWER ATTEMPTING TO RAISE REACTOR PRESSURE FROM 960 TO 980 PSIG PRIOR TO ROLLING TURBINE,

. CONTROL CIRCUITRY FAILED BOTH BYPASS VALVES IN FULL OPEN POSITION RESULTING IN 26% OPEN FLOW PATH.

(FAILURE RESULTED FROM DIRTY CONTACTS) 4 FLOW / POWER MISMATCH CAUSED A RAPID BLOWDOWN FROM 960 PSIG TO 340 PSIG IN ABOUT FIVE MINUTES, l TEMPERATURE DROPPED FROM 540*F TO 420*F 1

TRANSIENT TERMINATED BY OPERATOR ACTION (CLOSED BOTH BYPASS VALVES). MSIVs ALSO CLOSED BY OPERATORS, INITIAL VESSEL SWELL GAVE LEVEL 8 TRIP (MAIN '

FEEDWATER PUMP TRIPPED PLUS BLOCK ON HPCI & RCIC).

SUBSEQUENT SHRINK GAVE LEVEL 3 TRIP WITH MINIMUM WATER LEVEL AT 130" AB0VE TOP 0F FUEL.

STATUS OF RESOLUTION THERMAL STRESSES BEING EVALUATED PER TS REQUIREMENTS

1 FORT ST, VRAIN-STARTUP OPERATIONAL PROBLEMS OCTOBER 2 -4, 1985(K, L HEITNER, NRR)

PROBLEMS EXCESSIVE NOISE IN STARTUP CHANNELS LEADING TO R0D WITHDRAWAL PROHIBITS (RWPs)

I

• ERRATIC BEHAVIOR OF RWPs & ASSOCIATED ALARMS DIRTY CONTACTS IN CONTROLS FOR CONTROL R0D DRIVES 5

• OVER CURRENT TRIPS ON CONTROL R0D DRIVES SAFETY SIGNIFICANCE ,

NO TECH SPECS OR SAFETY LIMITS WERE EXCEEDED, THE RWPS G0 BEYOND THE SAFETY ANALYSIS REQUIREMENTS, INDICATIVE OF OPERATING a MAINTENANCE DIFFICULTIES FOLLOW-UP REGION IV IS FOLLOWING UP ON POTENTIAL DESIGN,

INSTRUMENTATION AND MAINTENANCE PROBLEMS i

l i

1

l DRESDEN 3 - SCRAM SOLENDID PROBLEM INDilCED LEAKAGE - FOLLOWilP SEPTEMBER 19, 1985 (ERIC WEISS)

PROBLEM RC? LEAKAGE TO REACTOR BUILDING DUE TO LEAKING SCRAM SOLENDIDS, LEAKAGE PATH FROM SCRAM OUTLET VALVES TO SCRAM DISCHARGE VOLifE VEhT AfD DRAIN VALVES, SAFETY SIGNIFICN CE DPESDEN PROBLEM MAY BE GEERIC TO BWR'S PRELIMItuRY CONCLUSIONS f0ST BWR'S WILL HAVE A LEAK OF PEACTOR WATER OUTSIDE DRWELL IF:

1. TEY HAVE A HALF SCRAM CONDITION (A CH RESET

& B CH TRIPPED)

2. TE HALF SCRAM FOLLOWS A FULL SCRAM ,

THE SOURCE OF THF IFAK IS NOT ORV!0ILS TO OPERATOPS UNLESS TRAINED TO RECOGNIZE TE PROBLEN TE LEAK IS EASILY TERMINATED AT DRESDEN WITH t'ANUAL CONTROL OF VENT AfD DRAIN VALVES THE EXHAUST DIAPHRAGM IN TE 117 VALVE IS NOT HOLDitG PRESSURE HEN AIR HEADER PRESSURE IS SLOWLY INCREASED TE LEAK WILL OCCUR WITH NEWLY REBUILT VALVES

I

)

ALTHOUGH TESTS IN SIIU SUGGEST THAT SYSTEM DESIGN IS ESPONSIBLE FOR THE LEAK 0F REACTOR WATER, INDIVIDUAL BENCH TEST SUGGEST VALVE CONDITION LEAK NE LIKELY, MAINTENANCE ECORDS SHOW THAT SOE OF THE WORST LEAKING VALVES WEE REBUILT ELATIVELY RECENTLY FOLLOWUP IE IS PURSUING MATTER WITH GEERAL ELECTRIC AN INFORMATION NOTICE IS IN PREPARATION 1

r. . , ..- , - . . . ,

e

. Ej.g ! e

~

e b

V$ NI

,.,. - -.. . e n . w .k.,,. ,es ,

I'#g g , p;y C

• h****' "

g 3g C

: * ^^ ****

f *osetnOL

,,,A IT g . ...

~

vin , ,iA . . .

O #

, , , 8 39e 3 39A

^

NOf t: SCR Aed lNLt T AND OUILif AC AC p l m edf h r/res .pse.a GSOL AflOst VALVE $1F.39A AND F 3901 ang age TO CLO1E WeenLE iCn Ane MPit RFSA '# 'N 081CatAnct VOLusst Vf MI AND scnAns Dot Alpe V A L Vi $ 17 3 7 A, 0, C1 <

SOLINoeO ARE Aln TO O,f M VALVil - 8'

1. AIER VENT VENT

. 8 SUC f Pse F 398 SCRA41OtSCHAAGE WOLutet

_1/  % '

/ ' "

Ym O -- SCRAa4 7 39A --

oggggy v N CnD VOttsnet HO 2 F'

pnons of te(n SCAA40 SCM Aae OUTL E F

() EE eMt t i VALVES ,

A k - *

' N

. J V 9er e><:.econea - - - - - - - - JL' N _ m _ =

-)

F 37 A motOf SCRAM VALVE ARRANGEMENT

• snee se son e seceo es

• actuas

• coa m e.s es o sseen ees ce po ese s t eoo Pose 9 swet t neue f C*e ross e soaes e

b o

W8

SUPPLY PRESSURE P P J d SCRAM PILOT VALVE

{v { 305-118 PRESSURE B RPS CHANNEL DIAPHRAGM P1

l. -

kag ,

, f EXHAUST DIAPHR AGM Et

,. f fl -

F 1

E da  :-

I. - 4  !.I Coll t

Mr_ '

E EXHAUST PRESSURE E e\, '

b PRESSURE DIAPHRAGM  ; SCRAM PILOT VALVE P2  ;; 3o3_gi7

> NORMAL

- +

,now reakos -

RPS CHANNEL A

] i <

EXHAUST OfAPHRAGM E2

• A-N -: X  ::

p.  :-

N '

N

, c , Coll I

m r

, ~

\ / \ /

SCRAM INLET SCRAM OUTLET VALVE DIAPHRAGM VALVE DLAPHRAGM figure .2- Serem Pifof Valve Configuration with A RPS Channel Reset and B RPS Channel Tripped l

OTHER EVENT OF INTEREST H._B. ROBINSON 2 - EXXON FUEL CODE INPUT ERROR-SEPTEMBER 28, 1985 (G. REQUA, NRR)

PROBLEM A NON-CONSERVATIVE ERROR WAS FOUND IN THE INPUT TO TRANSIENT HEAT TRANSFER CODE T00DEE 2 SIGNIFICANCE 10CFR 50.46 PEAK CLAD TEMPERATURE LIMIT OF 2200*F EXCEEDED IN ROBINSON 2 LOCA ANALYSIS

. RESULTS IN ERROR OF 8% IN PRESENT TECH SPEC LIMIT ON PEAKING FACTOR DISCUSSION JUNE '83 CP8L SUBMITTED ALL NEW LB8SB LOCA ANALYSIS FOR CYCLE 10 CORE RELOAD WHICH WAS REVIEWED AND APPROVED JULY '85 CP&L REQUESTED A CHANGE IN TECH SPEC K(Z) CURVE WITH ANALYSIS PENDING FOR OCT.'85 ERROR IN INPUT TO T00DEE 2 CODE WAS FOUND TO l

EXIST FOR CYCLE 10 ANALYSIS BY EXXON WHILE PERFORMING ANALYSIS FOR JULY '85 SUBMITTAL (FUEL R0D HEAT GENERATION) i i

FOLLOW-UP LICENSEE AN 8% POWER DERATE WAS ADMINISTRATIVELY IMPOSED TO ENSURE OPERATION BELOW CORRECTED CORE LIMITS SUBMITTING LETTER STATING: WHAT HAPPENED, WHAT THEY HAVE DONE TO CORRECT PROBLEM, AND WHY IT IS SAFE TO CONTINUE OPERATION UNDER ADMIN-ISTRATIVE CONTROLS ANALYSIS TO REMOVE DERATE IN PROGRESS NRR

, MANAGEMENT MEETING WITH EXXON SCHEDULED FOR OCT 11, 1985 TO DISCUSS ANALYSIS ERRORS CONTINUE DISCUSSIONS WITH CPal, EXXON INTERNALLY REGARDING SAFE OPERATIONS UNDER ADMINISTRATIVE CONTROLS REGION MONITOR HBR-2 FOR DERATE PARAMETERS GENERIC IMPLICATIONS f SAME INPUT ERROR IN D.C. COOK ANALYSIS, HOWEVER, APPARENTLY SUFFICIENT MARGIN IS STILL AVAILABLE IN STORED ENERGY AT E0L

NEITHER DERATE NOR T/S CHANGE REQUIRED, l

1

UNPLANNED REACTOR TRIPS

• i  :

AVERAGE WEEKLY. TRIP FRE0VENCY FOR PAST ONE WEEK IS ,

j APPROXIMATELY 17 TRIPS / WEEK, WHICH IS ABOUT TWICE  :

THE AVERAGE i

} -

BREAKDOWN OF REPORTED CAUSES:

AUTOMATIC EQUIPMENT FAILURES 47% l PERSONNEL ACTIVITIES 29%

i MANUAL 24%

i i

i

' BASED ON 10 CFR 50 72 REPORTS FOR PLANTS WITH LICENSES FOR ,

FULL POWER OPERATION i

a i

f 1

t

--,.-,r-,, . , , - - , . , - . - - - - - . , - < . , ~ - - , . , +-.w... - - - - - - . - - - - - - . . , . . . , - . , - . - _ . , - . , , , , , , _ _ , . _ , , , , , _ , ~ . .

Fa;e h:. I 10/16/55 CFEFATIN5 FEt.:TEF5 EVENT 5 MEETih5 FOLLCsJ' ITEa5

, AS CF MEEi!N5 E5-19 Ch 0:T0iEE 7 .1955 (IN A5CEN21%5 MEETi%$ [ ATE N555 VEhDOK. FACILI1( ORDER)

MEEilh5 FA:!L!it RE5F:%51 ELE TA56 IES:GIFTION 5MELULE CLC5ED LATE CCMMENTS hu~iER/ 4555 *Eh:~:0 EIVli!CN/ COMFLET. Et 00CLMENT, EEETI%5 EiENT IE531F. Ih:!VICUAL CATE(5) MEETING,ETC.

LATE Rt.N:r: SECO 1 IC55J 05A. F. 5.""A~ LIE ELW LIC. EE5FONSES TO 10/30/E5 0FEh / / STAFF FEilEs 0:

04/10/64 / CUESTIC%5 5;iSEGUENT TO RAN:FC 09/30/E5 ELW Cn%EF5 E':s*

in/MAINSEN]

bis; 5EN SECD LC55 0F NNI EVENT A%D OG/30/E5 50iMITTAL 0F Et:LC5IC% - FFE5E%T AT FCLLCh-bf CE EVENTS 1/11/E5 15 IN Fl.FTIAL LC55 CF ERIEFIh5 FF05FE55 (THIS NNI lrliiE4 EEACTIVATED-CEt5.RIV 3)

CE'5T;.. E! VEE 3 I:51/R:5A. F. C %5 ICE: NEEI F0E AO li!CNAL 12/0/E5 CFE4 e / 1:5E CCN5IIE:.IN5 01/C:/E5 la i TE*F. LC55 / FE;J:FE"Ehis ON ALARMS / (9/30/E5 CCCNEE 1 L055 0F CF %%: 12/:5,54 A%% M IATCf3 07/30/E5 A%N h:!A.

(4i:$iE5) Ih ANAL.

OF F.EGJIFEMENT5.

- MIL;57:%E 2 C: E M;;:rt. E. FEi:Es 55:5 LETTER Ch EIDt 11/30/25 0FEh / / OFN. CONTFACTE: TO 05i07, E5 CE / E::t EE / CON'AI, a. CU;FEhi TESTIN5 ISSUE, IN VIEW 10/0!iE5 EVALUATE EFFECT CF CL::E%T TEST 0 / 0: MILLST:NE : FIh0!N55. 02/07/E5 CFFER DN ED:V SIEA" EEN.

CUEFENT TEST!N TLIES. 4/!0:55 .IELAt3 IN CFh; TE5i!G CA N IA EL /Jais:L;. F. FULLCs UF ELIEFINE AFTER EVAL. 10/21/25 0 FEN / / FOLLCs UF ERIEFIh5 0507/E5 m / E:Ib R9 j / CF 0.ER:FE55. EFFECTS 0% 09/30/E5 SCHE:ULED CN IFAl%5 '

VAFICU5 SYSTEMS AND CCFFE:TIVE 08/07/25 10/07/65 CiE5F:155.EI:EL A TI G.

4/19/si E5-10 IAWIS EE5iE 1 C5: /FAR;. O. FE-EIA"!hE STAFF REVIEn CF 12/30/55 0 FEN / / IIT FEFORT Lh:ER Os/12/55 Es / LC55 CF A.L L /EEA5AIID A. A:CEFTA5!LITY/ DIVERSITY OF 05/ 0/E5 FEVIEe MAIN A%: AJf. CAVI5 EE55E AFn SYSTEM. 06/19/25 FEEEhATEF 6/9!E5 E!-10 It.VI5 EE55E 1 DL / LEA 5AIIO,A. FF: VIDE H. IE%iDN WITH 12/30/E5 0 FEN / / ITEM : IN 06/12/85 En / LD55 C' ALL / IsCta.FA'!!:% EETWEEN LAVIS 0E/30!E5  !TE"5 1.3 FF 5FE55.

MAIN A%: A;t.

EEEEE 1 A%! TMI-1 cr TM: ACTICh 06/19/E5 COMFLEiEL FEEIsaiER 6/9/E5 FLA% IMILEMEhiAT10N STATUS

2) C0'1FAF15:N OF MFW A%L AFW SYSTEM 5 AT IAVIS EESSE 1 &

TMI-1 31 STATUS CF STARTUF FW FUMP UFEFA:E.

E5-!! Of5iEF CREEr i Ef5/CLAviCN E. IETEEMINE EFFICA:Y 0F EFE/ 10/30/25 0 FEN / /

07/G1/E5 GE / / 0;EFATER A; Tith ANL EXCES5IVE 09/15/E5 UN ChiFO. LED o FE5'Ch5E TIME. 0E/30/E5 LEAFA5E CF FEACT;R CCOLANT CUTSILE

~ ~ ~

C0hTAlhMENT 6/l /55 l A

Fage ho. 2 10/16/E5

, CFE547!h5 REACT 0F5 EVEhT5 MEEilh5 FCLLCWJF ITEMS A5 0F MEET!h5 E5-19 DN OCT0EER 7 .1955 (th ASCEhDING MEETING LATE, N555 VEhDOR FACILITY ORIER)

MIETIN5 FA:!LITr RE58:h515LE Tait.IESCRIFi!CN SCHEDULE CLOSED IATE COMMEhis hQiERI h555 4Eh::R/ LIV!510N/ COMFLET. $Y COCUMEhi, GEETIh5 EVENT LES:RIF. ICIVIDUAL TATE (5) MEET!h6,ETC.

8 ATE E5-1: SEAERDCL E5!/ MAR 54 AN*LVIE SAFETY IMFLICATIONS OF 10/30/E5 0 FEN / /

07/23/55 h / CRDED mal % / VAJE FLCW IEFICIENCY 09/30/E5 STE&.SAFETV //

VALVE FLCh IEFICIEh:1

/.

12/54 E5-13 FCRE!6% IE /RC55!. E. C0h51LER ISSUAhCE OF IE 10/30/E5 0FEh / / IE h TICE lh 05/13/55 hA / MJLTIFLE / IhFORaAi!ON h0TICE. 07/30/95 CONCURRENCE FEEInATER / 09/03/95 FAILUFES E5-13 FCINTiEA:h IE iLON3. 5. IRAFI IE N0i!CE ON FT.EEACH 10/1E/E5 0 FEN / / LRAFT IE hui!CE Ik 05/13/E5 h / SAFEff 0:Li/CARU50. M. EVEhi. CON 5IDER TEMF.th5TR.FOR 09/30/85 CON:URRENCE lh!ECTICN / RES.IbiFECTCR REGARDIh5 09/13/E5 MINI-FiCdFECIEN COM?LIA4:E WITH AFF.K DE51EN IEFICIEN:t E5-13 TUR Et FCINT 3 EL /M;t;hALD,L. HAVE LICEh5EE INCORFORATE USE 10/13/25 0 FEN / /

05/13/E5 W / F:5T-iRIF LOSE Of AFW 0%

/ / Or MSTCR IRIVEN AFW FUMF5 IN EMEREEhtyFROCEDURES //

//

7/21/55 i 65-13 TLh Et FCIhi 3 L5!tFARE,D. FEVIEW ALEQUACY OF B0VERN3R 01/05/96 0FEh / /

06/13/05 t / FCET-TRIP / IES!E% CN TUE3INE LRIVEh AFW 10/13/95 LD55 CF AFW f Fe?.F5 -

//

E5-14 CATAt5A 1 I5! /5RINIVASA% M FEVIEh SEFA8AT!0N OF UNIT 1 AND 10/15/E5 0 FEN / /

02/26/E5 W /ILACCJi / / UNIT 2 Ah5 MEET WITH DUKE FRIOR 09/30/95 5154AL AC INTEUCTIC%

s'/ 10 LICEN5!hi 0F UNIT 2 / /

EEisEEh BIT 5 1 t AO 2 05-14 SEEJ0fAH E /STAdL t IhlTIATE STAFF REVIEW 0F TVA 12/30/E5 0 FEN / /  ;

00/26/95 W / Oli51 AV / SuiMitTALS 09/30/85 2 VOLUNTARY / /

SHUTEeN if TVA BECAUSE OF EDU!FMENT CUALIFICAT!0N j (EE)

INAEGUACIES j E5-15 LETERMINE kHAT FUTURE ACTION  !!/30/E5 0FEh / /

4 09/09/85 FEACH EDITOM

/ NEW FIFE 3 JLE/LIAWPD IE /HAZELTON W NEELED UN BENERIC BASIS 10/15/05 CRACK //

INLICAT10N5

1 Fe;e h:. 3

, 10/16!65 0FERATIh5 FEACT0F5 EVENTS MEETIh5 FOLLCCF ITEMS AS CF MEETIh3 E5-19 ON OCT05ER 7 .1955 (th ASCEN;1N5 MEETIN5 DATE. h555 VEh:0E, FACILITY 0FDER)

MEETIh5 FA:!LITt RESF055!iLE TAEA LE5: RIFT!0N SCHEDULE CLOSED CATE COMMENT 5 NE:ERI N555 VE4;C:.i LIVI5100 CC'tFLET. BY DOCUMENT.

MEETIN5 EVENT LES:KIF. Ih;!v1LUAL IATEtS) MEET!h5,ETC.

[ ATE E5-15 FEA:H 1:TTCM 3 / IE /LIAW B D FOLLCa-UF REQUALIFICATION OF 10/15/65 CLESED 10/07/65 05/0il55 / hen FIFE / DE /HAIELTON h th5FECTOR5 ISSUE / / CWNEES EE05 CRAtt / / MEET!h5 th21CATIchs 10/03/65 E3-16 IAV!5-iE55E IE / CCNSIDER IE h]TICE 11/01/G5 CLOSED 10/07/E5 09/16i55 / STEAM / / / IE h TICE WILL EEhE:t.iCR

'/

/ / h3T EE ISSUEt CVEEFEE55AIIATI 0%

C5-17 IFES:Eh 3 DL /In .!h561 J EETEFMI%E WHY SLV 15 NOT VENTED !!/CS/25 0FEh / /

09/23/E5 /5 FAM / TO GA5E0J5 RAL WASTE SiSTEM / /

5:LE%;!I FF:ELEM' / /

!%;;. E; FC5 LEA 6 ASE 55-17 LEES:En 3 .IE /hE!55 E LETERMIhE HEEL FOR lE b]TICE 11/0Ei65 CLOSED 10/07/55 09/23/E5 / 5:FA9 / / / / IE N3TICE Ik SCiEn;!! FR:P.EMJ .

/ / FFEFAEATION Ih:UEL F 5 LEAKAEE E5-17 FALOVEFIE*. CL n NIGHICN 5 CETEFMIhE W-EinER FACELEM 15  !!/02/E5 CFEN / /

09/23/55 / FEA:iCR / GEhERIL T0 hATERF0ED AN; SAN / /

TRIF.5ATETY 0%:FFE / /

Ih;ECTI h.LD55 y Or FEE 55JIZER AUI!LIAFV SFFA SYSTER E5-12 MULTI LST /RL'EIN A DST WILL FACTOR EIFEE!ENCE lhTO lu/30/65 0FEh / /

09/30/55 / HJ: FICA %E / CCMMISSION IFIEFIN5 ON STATION / /

ELCEIA FE5FCh5E ELAC60VT / /

E3-19 EEUN5s!K2 LL /EECTEkHul5 M FOLLCsUF BFIEFING WHEh CAUSE 12/15/05 0 FEN / /

10/07/55 / M3!Vs / AN3 IMPLICAi!CNS OF EVENT ARE / /

FAILURE TO CLC5E FULLY bh;ERSTOCD / /

L