ML20136E591
| ML20136E591 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/30/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20136E589 | List: |
| References | |
| FOIA-85-696 NUDOCS 8511210530 | |
| Download: ML20136E591 (136) | |
Text
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i.. - PALO VERDE UNIT I - REACTOR TRIP, SAFETY INJECTION,
- . LOSS OF PRESSURIZER AUXILIARY SPRAY SYSTEM SEPTEMBER 12, 1985 (E. A. LICITRA, NRR) .
PROBLEM - DURING LOSS OF LOAD TEST PLANT EXPERIE TRIP, REACTOR TRIP, SAFETY INJECTION, CONTAINMENT ISOLATION AND LOSS OF PRESSURIZER AUXILIARY SPRAY SYSTEM-4 SAFETY SIGNIFICANCE - THE PRESSURIZER AUXILIARY S WAS NOT AVAILABLE, IF REQUIRED, FOR RAPID C00LDOWN AND 1 DEPRESSURIZATION OF REACTOR COOLANT SYSTEM (PLANT DOE NOT HAVE PORVS) ' 1 1
* ~
~.
, DISCUSSION I .
t PLANT AT 55% POWER FOR LOSS OF LOAD TEST WITH . GENERATOR SUPPLYING ONSITE LOADS, INCLUDING RCP'S i - 4 ON LOSS OF LOAD, GENERATOR FAILED TO PROVIDE POWER
- TO'ONSITE LOADS; RCP TRIPPED ON UNDERVOLTAGE REACTOR TRIPPED ON PROJECTED LOW DNBR' .
AUTOMATICLTRANSFER TO OFFSITE POWER FOR NON-E LOADS DID NOT OCCUR I' AUXILIARY FEEDWATER SYSTEM WAS MANUALLY ACTUATED LOW RCS PRESSURE CAUSED SI INITIATION PLANT STABILIZED !N HOT STANDBY; RCPS RESTORED IN. 1
'ABOUT ONE HOUP i -
#EST WAS'PE-RUN WITHOUT INCIDENT ON SEPTEMBER ,16.
1985, WITH A MODIFIED TEST PROCEDUPE 8511210530 851030
- PDR FOIA S-1
- . GARDE 85-696 PDR lI
NRC FOLLOWUP ACTION (1) CONFERENCE CALL WITH LICENSEE ON SEPTEMBER 16, 1985 (2) EVALUATING SINGLE FAILURE VULNERABILITY OF AUXIL SPRAY SYSTEM FOR PRESSURIZER PROBLEMS BEING EVALUATED A. DOES PRESSURIZER AUXILIARY SPRAY SYSTEM MEET SING FAILURE CRITERION? B. IN RESTARTING THE PLAtlT, DID THEY VIOLATE TECHNICAL SPECIFICATIONS?. - C. WHY DID TURBINE TRIP ON LOSS OF LOAD AT 55% POWEP? (SUPPOSED TO STAY ON TO HANDLE HOUSE LOADS) D. WHY WAS TEST INITIALLY RUN BEFORE CHECKING WHETHE AUTOMATIC TRANSFER TO OFFSITE POWER FOR THE NONESSENTIAL LOADS COULD TAKE PLACE? (AUTO TRANSFER DID NOT OCCUR) E. REPORTING OF INCIDENT WAS INCOMPLETE AND INACCU 0
+i ,- .
PALO VERDE UNIT 1 - REACTOR TRIP, SAFETY INJECTION, LOSS OF PRESSURIZER AUXILIARY SPRAY SYSTEM SEPTEMBER 12, 1985 (E. A. LICITRA, NRR) PROBLEM - DURING LOSS OF LOAD TEST, PLANT EXPERIENCED TURBINE TRIP, REACTOR TRIP, SAFETY INJECTION, CONTAINMENT ISOLATION AND GAS BINDING OF ALL CHARGING PUMPS. SAFETY SIGNIFICANCE - THE PRESSURIZER AUXILIARY SPRAY SYSTEM WOULD NOT HAVE BEEN AVAILABLE, IF REQUIRED, FOR RAPID DEPRESSURIZATION OF REACTOR COOLANT SYSTEM (PLANT DOES NOT HAVE PORVS). SYSTEM NOT INSTALLED TO SAME SAFETY GRADE AS LICENSING BASIS. GENERAL CONCERNS ; I TURBINE CONTROLS DESIGN FAULTY (RU'NBACK). PLANNING FOR TEST INADEQUATE (TRANSFER). . INSTRUMENTATION PROBLEM (VCT LEVEL). ELECTRICAL DESIGN FLAW (SHEDDING MCC-72). E0PS WEAK. - REPORTING INCOMPLETE.
~
POST-TRIP REVIEW WEAK. CORRECTIVE ACTIONS
-- PLANT SHUTDOWN ON SEPTEMBER 16, 1985 (CONFIRMATORY ACTION LETTER ON SEPTEMBER 17, 1985). -
SHORT TERM COMPENSATORY MEASURES ESTABLISHED FOR CONTINUED OPERATION: DAILY CHECK OF VCT LEVEL INSTRUMENTATION REVISE PROCEDURES FOR MANUAL ALIGNMENT OF RWT TO CHARGING PUMPS UPON LOSS OF OFFSITE POWER. INSTITUTE PROCEDURAL CAUTIONS ON RESTART OF CHARGING PUMPS. S-2
- .. c . .s
^
/
RE-EXAMINE POST-TRIP REVIEW PROCESS. FOR REMAINING TEST PROGRAM, EXAMINE PROCESS FOR VENDOR REVIEWS. REVIEW SHIFT COMPLEMENT FOR REMAINING TEST PROGRAM. RELEASED FOR RESTART SEPTEMBER 20, 1985 (NRR/R-V LETTER), LONGER TERM ACTIONS BY LICENSEE. INCLUDE REVIEW OF AUXILIARY SPRAY SYSTEM TO DETERMINE: WHETHER SYSTEM NEEDS TO BE SAFETY GRADE. WHAT CHANGES ARE REQUIRED TO MAKE IT SAFETY GRADE. STAFF PREPARING 50.54(F) LETTER CONCERNING RELIABILITY OF AUXILIARY SPRAY SYSTEM e
s . 9 AGENDA PRESSURIZER AUXILIARY SPRAY DESIGN REVIEW OCTOBER 8, 1985 INTRODUCTION R.M. BUTLER DIRECTOR OF TECHNICAL. SERVICES, ANPP
' DESIGN HISTORY G.A. DAVIS MANAGER, STANDARD PLANT LICENSING, CE SGTR USE OF AUX SPRAY G.W. S0WERS SUPERVISOR OF SAFETY ANALYSIS, ANPP EXISTING DESIGN B.K. MCOVOID SYSTEM ENGINEER, CE DESIGN MODIFICATIONS M.A. RADSPINNER MECHANICAL ENGINEER, ANPP
SUMMARY
T.F. QUAN LICENSING SUPERVISOR, ANPP E5 '7
~
DEFINITION OF SYSTEMS THAT ARE SAFETY RELATED FROM 10CFR100, APPENDIX A:
"CERTAIN STRUCTURES, SYSTEMS, AND COMPONENTS ARE DESIGNED TO REMAIN FUNCTIONAL [AFTER A SAFE SHUTDOWN EARTH 00AKEl. THESE STRUCTURES, SYSTEMS, AND COMPONENTS ARE THOSE NECESSARY TO ASSURE:
(1) THE INTEGRITY OF THE REACTOR COOLANT PRESSURE B0UNDARY, (2) THE CAPABILITY TO SHUT DOWN THE REACTOR AND MAINTAIN IT IN A SAFE SHUTDOWN CONDITION, OR , (3) THE CAPABILITY TO PREVENT OR MITIGATE THE CONSEQUENCES OF ACCIDENTS WHICH COULD RESULT IN POTENTIAL OFFSITE EXPOSURES COMPARABLE TO THE GUIDELINE EXPOSURES OF THIS PART." i l
..#- s a.L. wc,. 1. , -
-:s.. ~ s
'. 8.' .
REQUIREMENTS FOR SAFETY RELATED SYSTEMS o MINIMUM REQUIREMENTS ARE SPECIFIED IN 10CFR50, APPENDIX A - GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS o GDC'S RECOGNIZE THAT SPECIFIC REQUIREMENTS FOR EACH SYSTEM DEPEND ON FUNCTION PERFORMED o ACCEPTABLE METHODS FOR MEETING GDC'S PROVIDED IN: REGULATORY GUIDES STANDARD REVIEW PLANS BRANCH TECHNICAL POSITIONS s l
1 . COLD VS. HOT SHUTDOWN o PRIOR TO 1978, SAFE SHUTDOWN WAS TAKEN TO MEAN HOT SHUTDOWN
,~
o IN 1978, NRC ISSUED NEW GUIDANCE ON GDC'S WHICH EFFECTIVELY DEFINED SAFE SHUTDOWN AS COLD SHUTDOWN (BRANCH TECHNICAL POSITION RSB 5-1) o RSB 5-1 SPECIFIES THAT:
"THE DESIGN SHALL BE SUCH THAT THE REACTOR CAN BE TAKEN FROM NORMAL OPERATING CONDITIONS TO COLD SHUTDOWN USING ONLY SAFETY-GRADE SYSTEMS."
o RSB 5-1 IDENTIFIES THREE CLASSES OF PLANTS FOR
, IMPLEMENTATION:
CLASS 1, (NEW PLANTS) FULL COMPLIANCE CLASS 2, (PLANTS UNDER CONSTRUCTION) PARTIAL IMPLEMENTATION CLASS 3, (OPERATING PLANTS) BACKFIT o CESSAR AND PALO VERDE ARE IN CLASS 2 1 i 1 L _ .. . _.
~.
RECOMMENDED IMPLEMENTATION FOR CLASS 7 PLANTS o CONCERNING AUXILIARY PRESSURIZER SPRAY, TABLE 1 0F BTP RSB 5-1 STATES:
- RECOMMENDED IMPLEMENTATION FOR 1 POSSIBLE SOLUTION FOR CLASS 2 PLANTS FULL COMPLIANCE l
f COMPLIANCE WILL'NOT BE REQUIRED IF "l PROVIDE UPGRADING AND ADDIT 0NAL VALVES TO ENSURE OPERATION OF A) DEPENDENCE ON MANUAL ACTIONS
! INSIDE CONTAINMENT AFTER SSE OR
- AUXILIARY PRESSURIZER SPRAY SINGLE FAILURE OR B) REMAINING AT USING ONLY SAFETY-GRADE SUB-HOT STANDBY UNTIL MANUAL ACTION
- SYSTEM MEETING SINGLE FAILURE.
POSSIBLE ALTERNATIVE MAY INVOLVE REPAIRS ARE COMPLETE ARE FOUND TO
!! BE ACCEPTABLE FOR THE INDIVIDUAL USING PRESSURIZER POWER-0PERATED PLANT.
RELIEF VALVES WHICH HAVE BEEN
! UPGRADED. MEET SSE AND SINGLE
'FALURE WITHOUT MANUAL OPERATION INSIDE CONTAINMENT.
l 1
~ .. ~ , . .
1 SCOPE OF AUXILIARY PRESSURIZER SPRAY SYSTEM o AUXILIARY PRESSURIZER SPRAY SYSTEM BEGINS AT BRANCH FROM CHARGING SYSTEM AND ENDS AT PRESSURIZER SPRAY N0ZZLES
- o. MECHANICAL COMPONENTS CONSIST OF:
PIPING TWO SOLEN 0ID OPERATED VALVES (CH-203 & CH-205) Cl!ECK VALVE o SCHEMATIC 0F AUXILIARY PRESSURIZER SPRAY SYSTEM AND SOURCES OF B0 RATED WATER (VIA CHARGING SYSTEM) SHOWN IN: i FIGURE 2 1-4 0F CEN-239, AND FIGURES 5 & 6 0F APPENDIX B IN NUREG-1044 t 1
d ,# MIGURE 2.1-4 . SIMPLIFIED SCHEMATIC 0F PNLO VERDE CVCS SHOWING AUXILIARY SPRAY PORTION AND SOURCES OF B0 RATED WATER FrutlotlC MID Mffitiff. INIK l
><- w DURIC Min (pCM lull 81CAfiftl y M 8 ION MMRS ,
O WIGils N P 3 6 I"" O PflGC OP512 vutut r3 t-CONTROL 756 IME Fr4CPt REACIGI
#wxttp mitR,- r
, m .
r' g.
) (-- %
4 33 Oe%30
,r CN.527 Deso W~ OwicirG Fue ?
Cell 0f aL
. RJftlC MID
,N' 55 **Ill * *Il E 1 01 TIC M8U L 51( tit p e T)G 8, ty g- 6 l l PACE
,, , CWtlGilo N P I
Mi to xt %
sio(( t ins .E Al Cnenste 1 4
FIGdRE 2.1-4 (CONT.) SIMPLIFIED SCliEMATIC 0F PALO VERDE CVCS SHOWING AUXILIARY P0RTION AND SOURCES OF B0 RATED WATER , i i Atal!LIARY $ PRAY
, f_ =_"*' '_" $
1 .l _$__ ! ro Lp Cm!03 l ,W rLOW l g' l SPRAT ($) + TO CWS T, I VALWS I g L_ .ettb_5__ _ _ _J
=
Oe524 7 229 A
# A,",'r. 'I '
'I O
,1 ,,
a a g I u-o vton R
- FR0rt RCS i
4 e i ,
- l. -
l
HISTORY OF AUXILIARY PRESSURIZER SPRAY SYSTEM o PRIOR TO BTP RSB 5-1 (1978), NO SAFETY RELATED FUNCTION o QUESTION 440 6 (ISSUED AND ANSWERED IN 1981), ADDRESSED SY, STEM 80 CONFORMANCE WITH BTP RSB 5-1 o COMBUSTION ENGINEERING'S RESPONSE TO QUESTION 440 6 DESCRIBES OPERATION OF SPRAY SYSTEM AND THE PORTION OF CHARGING SYSTEM WHICH PROVIDES WATER TO SPRAY SYSTEM o REQUIREMENT TO CONFORM TO BTP RSB 5-1 MADE THE AUXILIARY PRESURIZER SPRAY SYSTEM (AND A PORTION OF THE CHARGING SYSTEM) SAFETY RELATED i o AFTER REVIEWING C-E'S RESPONSE TO QUESTION 440 6, RSB ( TOOK POSITION THAT OPERATOR ACTIONS OUTSIDE OF CONTROL ROOM COULD ONLY BE USED TO MITIGATE SINGLE FAILURES 1
- o. FOLLOWING APPEAL MEETING WITH DIRECTOR OF SYSTEMS INTEGRATION ON SEPTEMBER 17, 1981, SYSTEM 80 DESIGN WAS MODIFIED TO PROVIDE A MOTOR OPERATOR ON VALVE CH-141 (LATER RENUMBERED TO CH-536) AND TO PROVIDE EMERGENCY POWER TO CH-536 AND CH-501 FOLLOWING A LOP EVENT 1
i
HISTORY (CONT.) o SUPPLEMENT N0 1 0F THE CESSAR SAFETY EVALUATION REPORT (ISSUED MARCH 1983) CONCLUDED THAT "THE GUIDELINES OF BTP RSB 5-1 HAVE, THEREFORE, BEEN SATISFIED AND THIS 1SSUE IS RESOLVED." o IN CEN-239, COMBUSTION ENGINEERING AND ARIZONA PUBLIC
- SERVICE RESPONDED TO NRC REQUEST FOR ADDITIONAL l
INFORMATION ON THE DESIGN AND OPERATION OF THE ! AUXILIARY PRESSURIZER SPRAY SYSTEM o CEN-239 STATED THAT " AUXILIARY SPRAY PROVIDES THE [ SAFETY-RELATED METHOD FOR RELATIVELY RAPID AND
, CONTROLLED DEPRESSURIZATION OF THE RCS TO COLD SHUTDOWN
! CONDITIONS. AS SUCH THE SYSTEM HAS A DEGREE OF i PERFORMANCE CONSISTENT WITH THE NRC BRANCH TECHNICAL f ,- POSITION RSB 5-1." 4 o IN NUREG-1044, NRC STAFF EXPRESSED CONCERN ABOUT SINGLE FAILURE VULNERABILITY OF VALVE CH-240 CONCERN WAS RESOLVED BY ADDING VALVE CH-239, IN SERIES WITH CH-240
8 l STEAM GENERATOR TUBE RUPTURE (SGTR) ANALYSES o ORIGINAL ANALYSIS INCLUDED IN CESSAR-F (TENDERED IN 1978): 1 BASED ON CATEGORIZATION MATRIX OF CHAPTER 15 (IN ACCORDANCE WITH REG. GUIDE 1 70, REV.2) i 1 TUBE RUPTURE ONLY AUXILIARY PRESSURIZER SPRAY WAS NOT CREDITED FOR ANALYSIS TO CALCULATE OFFSITE DOSES l I
} o ANALYSIS REVISED TO BE CONSISTENT WITH STANDARD REVIEW i PLANS (1981/1982):
i SGTR WITH AND WITHOUT LOSS OF 0FFSITE POWER AUXILIARY PRESSURIZER SPRAY WAS NOT CREDITED FOR ANALYSIS TO CALCULATE OFFSITE DOSES , CREDIT WAS TAKEN FOR THREE SECOND TIME DELAY BETWEEN REACTOR TRIP AND LOSS OF 0FFSITE POWER
~! o NRC STAFF REQUIRED RE-ANALYSIS WITH ADDED SINGLE FAILURE AND RECOGNITION OF EMERGENCY OPERATING PROCEDURES PER CEN-152 (APRIL 1983) o SEPARATE ANALYSES WERE PERFORMED FOR CESSAR AND PALO VERDE (1984). BOTH ANALYSES RECOGNIZED USE OF AUX 1LIARY PRESSURIZER SPRAY (AS'AN OPERATOR ACTION) o NEW PALO VERDE ANALYSIS IS BEING PERFORMED, WHICH DOES NOT USE AUXILIARY PRESSURIZER SPRAY IN THE FIRST TWO HOURS
..~ - .
SUMMARY
'o AUXILIARY PRESSURIZER SPRAY SYSTEM AND PORTION OF CHARGING SYSTEM ARE SAFETY GRADE, AS REQUIRED BY NRC TO MEET BTP RSB 5-1 f
e 4
~ . . -
~. .
PVNGS-FSAR (APPENDIX 15A) SGTR ANALYSIS RESilLTS FSAR
- REVISED ANALYSIS
- EV$NT IIME THYROID DOSE TilV90lD DOSE (SECONDS) (REM) (REM)
SGTR & STUCK OPEN ADV 0 0 0 LOP 51 0 0 AFAS 132 0 0 i ADV OPENS 460 0 0 I MSIS 513
.I j SIAS 581 655 AFW OVERP.IDE AUX SPRAY 1015/7200 115 115 TUBES RECOVERED 1385/1347 182 186 2 HP DOSE a EAB 7200 200 208
- REGULATORY DOSE LIMIT IS 300 REM
2500 i i I . I i OPERATOR TAKES CONTROL OF PLANT-0 PENS ONE ADV IN EACH SG 2000 - OPERATOR INITIATES AUXILIARY SPRAY 1500
' ~~~' \
f OPERATOR CONTROLS AUXILIARY SPRAYFLOW, -
@ [BACKUPPRESSURIZERHEATEROUTPUT,AND y i HPSI FLOW IN ORDER TO KEEP THE RCS 20 7 0
W
- c. 1000 t
' 1 SUBC00 LED _
g U ce \
.[
\
\ RCS REACHES SHUTDOWN 500 \
COOLING ENTRY CONDITIONS k_ 0 I I I I I O 5.000 10000 15000 2000 25000 30000 TIME, SECONDS
.~
Palo Verde Nuclear Geerating Station A FSAR STEAM GENERATOR TUBE RUPTURE WITH I4SS OF OFFSITE POWER AND A FULLY STUCK OPEN ATMOSPHERIC DUMP VALVE RCS PRESSURE VS TIME Figure 15A-3 (Sheet 2 of 2)
1 4 70 i l I i
-\
/ \
. / \
/ \ -
60- -
)
AUXILIARY 6 PRAY INITIATED I I M 50 R
.x
\
-[ D s ~- \
$x 40 _. g _
M f s \
\
w E
- 30 )
OPERATOR ^ . si OPENS ADV o
'N(m v 4 smA^^e 20 0
0 5000 10000 15000 20000 25000 30000 TIME, SECONDS l Palo Verde Nuclear Generating Station
. FSAR STEAM GENERATOR TUBE RUPTURE WITH IDSS OF OFFSITE POWER AND A FULLY STUCK S
OPEN ATMOSPHERIC DUMP VALVE TUBE LEAK RATE VS TIME
- rigure 15A-11 (Sheet 2 of 2)
M S A, ' CONTAINMENT ATMOSPHERE
/\ s S l f F 7 V 7 s
4 k st - w r , 2 , . 1 7/32" l N/ h RDT PRESSURIZER j PRESSURIZER VENT PATHS
~
l PRESSURIZER VENT SYSTEM DEPRESSURIZATION DURING SGTR R'EDUNDANT CLASS 1E QUALIFIED VENT PATHS LIMITING PATH (7/32 INCH ORIFICE)
~
hifhkkbNfLfAkY R!hkIRkkEkShRA PROVIDES ACCEPTABLE DEPRESSURIZATION PERFORMANCE i EMERGENCY OPERATING PROCEDURES ADVISE OPERATOR OF AVAILABILITY OF VENT TO BACKUP PRESSURIZER AUXILIARY SPRAY
, - .,, - - - - >-,,,e. wr..,--
EXISTING DESIGN o PRIMARY PATH FOR SAFE SilVTDOWN o . VALVE BY VALVE FAILURE IN PRIMARY PATH - o
SUMMARY
- MANUAL ACTIONS OUTSIDE CONTROL ROOM
- z) t j 6 I
4 Y .
/
e l i
LETDOWN
~
0 A_40 _EJE ' 64
>4 E[% v0tuuE CONTPOL CHARGING h g 3
filter PUMPS (
~
O k
- 757 v O - Q' gh boric x ACID
@y)01
- s Q30 Yhhps <
k o 47 j - lif 3 E75'
\ k D v V
Q3) L r \
;;75, kEkL INJECTON k
g 2A P Q s 12] r, k g V SAFETY k INJECTION D h N u C - A ~tG N G A X _ A RY S NAY
't i OPERATOR ACTION
SUMMARY
FAILURE MANUAL ACTION V536 IN CLOSED POSITION MANUALLY OPEN V327 AND V757, V756 OR V755 V501 To CLOSE MANUALLY DEPRESSURIZE VCT,
! MANUALLY VENT THE CHARGING f
j PUMPS i l h
- ?
j ' ./ - -1 a 1 i l l
- . . = . . , .
7 .- . . . . . CVCS ENHANCEMENT o REPORT OF ACTIONS UNDERTAKEN TO ADDRESS SEPTEMBER 12, 1985
': EVENT ( PER SEPTEMBER 20, 1985 MEETING ) ,i o -THREE MODIFICATIONS PLANNED r
i ENSURE CONTINUED CONTROL OF V501 AND V536 2 FOLLOWING LOP AND SIAS
'l
- ADD SECOND, DIVERSE REFERENCE LEG FOR VCT
- ij LEVEL MONITORING WITH ALARM i NI
,j -
AUTOMATIC REALIGNMENT OF V501 AND V536
,n ,
j { -} l
.-. ~ -.
, - --,e - -,- .e - ,-- . ,.. -n ,--- ..a g-
VALVE POWER SUPPLY CHANGE . i l -EXISTING- .N0D.IFIED - IE 60.S -
/[ OUS l
l . Th P ) ! cw l Siff$ ) l
/E MCf '
NON /E A1CC. l
~
)i <
l 3 s i' 501 536 l t Sol. 53(o i i - i CilANGE ENSURES OPERABILITY FR0f1 CONTROL ROOM AFTER SI AS AND LOP SUCH l THAT SUCTION COULD BE ALIGNED TO Ri1T FR0f1 VCT. . i l
VOLUN CONTROL TANK LEVfl INDICATION MODIFIED EXISTING 1 6 I a VOLUME VOLUME CONTROL CONTROL II CONTROL CONTROL p- -ROOM TANK ROOM INDICATOR INDICATOR [ I
-226 LT-227 I ;. f,;, '
l, I I l
; ~
SIGNAL I LOW __ ,__ .1 LOW " LEVEL l COMPARATOR
' ' LEVEL SIGNAL ALARM ON SIGNN.
AND CONTROL '-- IEI LEVEL ROOM ALARM DIFFERENCE l i t IMPROVEMENTS
- 1. SEPERATE REFERENCE LEG TO EACH TRANSMITTER
- 2. ONE WET AND ONE DRY LEG TO PROVIDE DIVERSE REFERENCE
- 3. COMPARATOR ALARM PROVIDES INDICATION OF POSSIBLE LO CORRECT REFEREllCE TO ONE OF THE TRANSMITTERS 1
~
LETDOWN
^_ ^ _^ ^_^ _ _
0 bO - Dy H,
='-
1,6,4 , g4 "' CHARGING VOLUME
@e CONTR1 PUMPS
^ 4
%_ O filter I k(
l c- _ A lb l w mu m , x w
'6- - - -a j r
[ INJE N 12] r, 1 %f I N AUTOMATIC TRANSFER TO REFUELING WATER TANK
4 ENHANCEMENT EVALUATION .
~
o B0 RATED WATER SOURCE REMAINS AVAILABLE TO CONTROL ROOM OPERATOR FOLLOWING LOP AND SIAS i o INACCURATE VCT LEVEL IS ALARMED IN CONTROL ROOM I I
- o OPERATOR WORK LOAD REDUCED BY AUTO TRANSFER OF V501 AND V536 i
,i j _f
- l 4
- - . . . . . ~ . . . - _ . .. .. .
. e ,
ENHANCEMENT EVALUATION 4 o B0 RATED WATER SOURCE REMAINS AVAILABLE TO CONTROL ROOM OPERATOR FOLLOWING LOP AND SIAS j o INACCURATE VCT LEVEL IS ALARMED IN CONTROL ROOM i l o OPERATOR WORK LOAD REDUCED BY AUTO TRANSFER OF l V501 AND V536 I di .i j-
- 1 4
1 1 l i i i
* * , -. >$>;f PVNGR PORT TnTP REVTEU s' .'. . FORM Part I: Initial Conditions:
A) Event Dame / Time: #1 /.2 /6 2.206 B) Shift Personnel: SS Nicr/c[ Ass't. SS w on Prim. Op. F4reaee
, Sec. Op. O# Yd [e
$5 lt A r (r f m aam
*. wowy'
- STA Other
- i-
. C) Unit Conditions: Unit No. / Mode / Rx Pwr O%
Other Ae,efue f}n s l'8e.cl A . . ele- WkE
~
- ~,,y:. $b '2 ls JJ n '$ lon d 71 PA- /JP Off
*9- ~
4 .:n -
\ ,s,
. E M. :
P as'.'-C.
, f ..
l;# O D) Evolutions In Progress:
.~
Surveillance Testing .7 /J r-' 9 J s of r (a e- cu L% en e ]
.a T [ (' ~ a s/f /^C # 1
.+,..,- .
g p:. ,' . - i * 'f Haintenance Unit Startup/ Shutdown
- 9 Other 1
0-3 ti
.J r a; i s L -
e )E
, , b/ -- b u ^.t va bcsv166 Qu ? WM3 ^ .
, , CPC C F) Control System Status:
RRS h Test CEMCS h MS MG MI STBY FWCS Aut Man
-[' s SBCS Man PLCS Man
- PPCS Man RPCS 3 Man G) RPS/ESFAS Channels in Bypass / Trip Prior to the Event: C/a, . / C
. 5 loa. a ,
o sve Vola (vle o v e ,n .,a w . L bHB A, A: lFD e il
$ %/bt,P A S S./ W $ WLA fY
'I t
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g a '; { .',- s'
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e 4 9 9 9 l O e 8 .i
- iPart II: N_o tifi cation /D_e s crip tion _nf_ Event :
A) Event Classification (EPIP-02): //14,'[/ , .. N,. - o [ /L r, to o / 6 g4 f
- 1) Time Delcared: 222f Time Terminated: o/o.2
- 2) Were all required notifications made?
Yes t/ No If No, Reasons: ,A//4
- 3) Subsequent Reclassifications Time Declared: A/// Time Terminated:
B) Event
Description:
k,,,,_-b,r ' r, o vi Eb [031 er [ dre c</ e I e ea (o isn an d rle.,e.a..frA e lcc4e ie a l r.. rA$l >^ 1 l e(Jo rr, Any und NJP a c $ u o'b o'on .
.s
.C) Plant Response:
- 1) Rx First Out: /,, /) A/// g
- 2) Turbine First Out: A Erfl/ /bn Te/o <
- 3) ESFAS Status: a , L., frj h AFAS-2 o ,%-(ff h CPIAS i HSIS FBEVAS CSAS CRVIAS RAS CREFAS .,.
AFAS-1 LOP d T i
'M
.i; e . 4) Annunciator Status Check: (List any (1) Unusual or unexpected alarms for the event and (2) any expected alarms that were not received)
Bol: Alar n r ,. r r , - l ,, la 0 L,:Yb, l,3 i ,n . . w r ~ oa sv.d e ~J,, I sJ A/AA,!'YA m1 B02:
- B03: Is C T Lue / is -l., a .14 re e- eived . (8.u..L UC *r
.w. .
a o enn,db suaf A aa < B04: FC T !.[ B05: B06: "Ia' riin o us . fee Jw,,4,,, . a 4 'lr. ;;, r 507: bsr a/ Pk/ c w trc,. T C si e i,3 u N' d loss
^ o$ ,ns u en ~{o A/AA/-Ja / we ~Jo3 RMS/EP: Rn] .. A c~f Jui. ute.'e ,L, 4, laji n d .>n - cAuj s, we,-
SESS: ])'r,j,1 1.I n;/ s a-u ,, f,u ,,, la,a r (Lit, 9%:ai) ,
- . En J:e i r4 //w A f* t A Afs .
Comments: h >'c je f ./. . { r, { .ra nnl . un fu e a 3,4Irja l,. d?rh M Er nowemd '
. L' / /
fe., ,, a u . cl.<< n e c sd:J u-r ab - -s ar;> rsef. < a a9
Abe >A~d~,,aM% ,,1- .
F,i e 4h I ci:/la A L:., n ! ,, , 1, ret >'.n A + ~,s -s h (l .l A J ..,, [ b . D . , l N: , L L, ~,. :~1 + da L ea Jn,J , N4 Ic.n. he . : . .a ~ .L.,e. L, , -L. L i l.1/i.,%. ucr ~-xt Li> L.t u t .1:- a ,.,.a s t hat./:u A ik r ~ J rlh ~ :t- d ( II ,,, , n a4:n L ILes PJ [hil d , w e~
& t, n ,a n , L #a f n
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g ,.
- r4;;
t j .. a *
. Part III: Event Analysis:
A) Was 'the Rx trip setpoint within the allowable value for trip ' generation as listed in Table 2.2-1 of the Technical Specifi- : cations? . Yes No i If No, Explain: /A. i 1
' B) Were reactor trip signals generated for all trip values exceeded as shown in Table 2.2-1 of the Technical Specifica-l tions?
Yes ! No
, , If No, Explain: N,/4
} i . 4 C) Were all ESFAS signals generated as required for trip values i i exceeded per Table 3.3-4 of the Technical Specifications? , Yes I/ No , 4 is If No, Explain: a>/A
- i i
i D) Was any Safety Limit Violated? ' 1
- Yes No V j'
1 If Yes, list Safety Limit (s) y /W 4 - , l .c. -Max / Min Parameter Value Hastheapplicableactionstatementbeenmet?p[A Yes No . a If No, Explain: i i i
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E) Have any of the RCS Pressure / Temperature Limits as listed l
' ' in Section 3.4.8.1 of the Technical Specifications been l violated?
Yes No IfYes,hastheActionStatementbeenmet?g[ Yes No , If No, Explain: u/4 N . F) Verify the proper bparation of all safety-related equipment actuated as a result of the ESFAS signals' identified in Part II.C.3 of this procedure. This verification shall be performed utilizing'the applicable appendix of 41EP-1ZZO1, Emergency Operations. Explain, in detail, any discrepancies below and attach the appendix tp this report. Lu cp-tnacst Comments:fD ,WAJ,/ eT4] vad ~(led ,n e A ,.i .- 1 l,.. r .T t k . (D Fn dai d :ll , A 4r ; a so;f - l. w re-$ % a,_d 4v u o 4 ID F L~, L, .n . . ,
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(* $ ' G) Explain i'n detail, the sequence of events which led to the initiation of the event and the actions performed to place the plant in a stable condition. Include the observations and -
.v.? actions of specific individuals and comment'on the adequacy of the procedures used. Attach additional pages as required.
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Part IV: Restart Determination / Recommendation: A) Did all required safety-related systems / components operate as designed? Yes _ No / If No, explain in Detail:(O Find; I cL'II,n A .L :, n , A n /w
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i! M r t2 RA nati em 4#=a d %# . . (2ch;?gy.la L ~ 7. u L a ~ Lg*'Itc7- /<, a t B) Is there any equipment out-of-service which would prevent
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the unit from being returned to service? i Yes No / , If Yes, explain 19 Detai1: a /A
. C) Are there any Technical Specification Action Statements in effect which would prevent the unit from returning to service?
Yes No / If Yes, list below.
\ .
Tech Specs u/J
- ,4 D) Are there any corrective actions which should be performed before returning the unit to service, such as repairs which should be performed?
Yes / No If Yes, explain. Provide specific recommendations as appropriate. (O ddernlm rasir
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FI Pn e r-T v-i n Rov 40u? Rov 4pu Php fnlloufng rInenments for any inconsistencies or ambituities. Identify these
* . problems and explain them, in detail, in the remarks section below and include a statement concerning their resolution.
These documents need not be reviewed prior to restart except as indicated. Attach a copy of these documents to this report. Initial /Date
- 1) Sequence of Events Printout [ 9 r3 rfr
- 2) Post-Trip Review Printout B
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- 3) CPC Post Trip Printout 3-)S* 85
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- 4) Unit Log f (* A f-/)-/i~
'- . 5) Control Room Log Ir 2 T-r7 ef3-
- 6) Shif t Technical Advisor Log M\ Tr f
- 7) Alarm Typer Printout /C2 /-/7 <PJ' (Applicable time only)
- 8) SS Diagnostic (copy) . Ec'# f-/ ? - d*>-
- 9) Trend Recorder Charts _ f(p r/~r3 -d T
- 10) Strip Chart Recorders Ecd T-t7-d'5'
- 11) Other (List) tu ep-/ s-Pdt A-a I?//
Tih41 e en, i r ,,4 ,,, ,.l., a > 'E,,,,, As-
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- 12) Remarks:
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DC Signdmd. E.seds hkhut d \0 4 .
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', F) Restart Recommendation:
O All required safety-related systems operated as designed. l The plant did not exhibit any anomalous behavior during the course of this event. Based upon this evaluation, it has been determined that the plant can be restarted safely. Restart Recommended. All problems and/or anomalous plant behavior identified in section A through E of this part have been resolved and all
. required resolutions and/or retests have been performed and i documented. Restart recommended upon receipt of verbal !
concurrence from the Operatio s Manager.
' ' "OperationsMayge concurrence received." \
^
/
/hN SlYO lND c =
Shift Supervisor
' Dat/ Time D All problems identified in sections A through E of this part have not been resolved and/or the anomalous behav r exhibited by the plant in the course of this event M not
- be explained. An independent review of this event should be performed prior to u it. restart. Restart not ecpmmended.
< Jy'/Cl W Prepared By: k , [ .'2, 1, id [ v1 M - / 7 -d'f 2 cm c>
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Date/ Time Revbewed I}p: f ,c> u 7-M8
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Date/316e Comments:
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Operations M er's Appr v Startup: Granted _ IC /77 D' ate / Time h
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Denied / Date/ Time Obtained: M In-Person Per Telecon (written followup required) i N. .
'. Part V Rsview and Followup:
A) PRB and Manager of Nuclear Operations Review This section will be used only when (1) the initial approval for startup is denied by the Operations Manager and/or (2) subsequent reviews of the event are required. MAJOR FINDINGS OF SUBSEQUENT INVESTIGATIONS S Ec' h kcktY\69\ Actach other sheets as necessary. DETERMINATIONS BY PRB 3 CY b W 3 A Attach other sheets as necessary. STARTUP APPROVAL PRB Chairman [ (((([/[ / [ Manager of Nucle Op lons ~
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. B) OPERATIONS MANAGER FOLLOWUP:
Corrective actions required to prevent reoccyrrence of this M, fkh MC07311l81 @@ N _ , (n p 5' ptera4.c5Ac<w&n phch^$ . x PQB Aentansc0<t& l Note any changes to this document which may improve its effectiveness.
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l . Report Reviewed By 0 ons Manager Q ??M An i 7by d 9l'Il Ifate#/ Time NOTE: Operations Manager review is not required prior to authorizing startup. A copy of the report sent to the Training Department. Date Nuclear Safety Group Review
.. I NSG. Supervisor Date .
- - IrI
* ' 2200 --
n E R n i 2208:29--OPEN CDERATOR BREAKER 918 2208:53--REACTOR TRIP (RCP SPEED 901) 2210 -- (TUR.BINE UNABLE TO MAINTAIN FREQUENCT) 2210:53--LOST STAT 10M 1,OAD EOST POWER T0 sol. W2 RCFS TRIP LOST VCT MAKEUP 2214 --MTV PLMP LOW SUCTIONS PRESSURE TRIP 2213 --$ TARTS M AFW FUMP 2217 --CPENED 1 ADV CN #2 SC
--RESTORED F0WER TO $0! AND $02
, (MAIN STEAM LINE DRAIN VALVES RE0FD) 2218 w
2220 -- n g 1 -%. , 5 AFW PUMP N TRIPS
- 2222 -- SIAS CIAS LOST POWER TO 501 4 536 g 2224 -- EFSI STOPS ., ,
k. 2230 --OFERATOR SECURES ALL 3 CHARCING PLMPS 2320 --tESTORED POVER TO BAM PLMPS c 3 xN M E E 4 2345 --POJERED $14 DOWN TO PREVENT CLOSURE DUE k TO 501 INTERLOCR.0PENED 514 g U t 0000 -- STARTED BAM FUMPS 0002 --$ TARTED CHARCING FLMPS $ AND C (A WOULD h0T MAINTAIM SUCTION) 0102 -- RESET $*.AS & CIAS RESTART 2 RCP's l
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r , a 1 SEQUENCE OF EVENTS 22:08:29 Generator output BKR 918 opened to initiate test. Steam bypass control system performed as designed maintaining steam generator pressure. Turbine speed increased due to loss of load turbine supervisory instrument-ation fast closed turbine control valves to limit overspeed condition.
, 22:08,:31 A turbine trip occurred causing the turbine step valves to close and turbine speed to decrease. The generator and plant loads remained connected and generator output frequency decreased with turbine speed.
Pressurizer pressure increased to approximately 2309 PSIA as expected by test predictions. . 22:08:53 Reactor trip occu'rred due to RCP's at 905 of rated speed. RCP slowdown was a result of decreasing bus frequency as the generator coasted down. As the generator continued to slow the RCP breakers opened as designed. The house loads were shed and then the aux trans breakers opened dropping NAN-S01 and NAN-S02 from the bus.
~
Shutdown margin was checked per procedure and found to be greater than 6%.
, Xe concentrations and B10 concentrations prior to trip were used in calcula-
,.e., ( tions. No credit was taken for HPSt injection.
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22:15:00 - Aux feedwater pump AFN-P01 was started to provide fed flow to the steam generators. . 22:17:00
, Atmospheric ump valve was manually opened 2-3% t ump steam and to prevent degradation o ondensor vacuum with less of circ wa er and to insure adequate BT for natural circulation.
22:18:00 Mainsteam line low point drains opened due to restoration of power. This caused an RCS cooldown rate increase due to low decay heat and leak of PCP heat input _to the RCS.
~
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a - B 22:22:00 Cooldown resulting from mainsteam line drain valves reopening. (These valves had previously been manually closed) and initiation of aux feedwater to maintain steam generator level, caused a safety injection actuation signal. The RCS reached a low of 1819 psia (sias at 1837 psia) and SI worked as designed. HPSI pumped to all 4 loops providing approx 75 GPM to each for approx. 2 min. The SI signal initiated a concurrent containment isolation signal and stripped the NON-ESS AF pump. The ESS aux feed pump B auto start-ed by was not used immediately to feed the SG's due to adequate level in the SG's. The charging pumps failed due to H2 in the suction lines when the VCT was drained. VCT drained due to the lack of Auto makeup caused by the loss of power. 22:23:00 Mainsteam drain line valves closed cooldown stepped. e gg* g ,2
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e Turbine Trip 9/12/85 during RPCs Testing 1). Breaker 918 was manually opened, all load except approximately 55 MW was dropped from the generator. 2). With this loss of load the entrained energy in the turbine began accelerating the turbine-generator above 1800 rpm. 3). The turbine control system sensed this acceleration and ordered a fast closing of the control valves and intercept valves by opening the " fast acting solenoid valves". k). Almost immediately the control system ordered the intercept valves
's - back open to bleed the extra steam from the high pressure section of the turbine to the low pressure sections.
5). All six " fast acting solenoid valves" on the intercept valves popped close. Now EHC fluid needed to fill the dish dump valves on all six intercept valves. This is more than the "ETS" section of the control oil system could supply (ETS-emerging trip system). 6). ETS pressure dropped below 400 psig bringing in two pressure switches whose function is to send trip signals to the turbine control system even though the turbine has not tripped. 7). With the loss of ETS pressure, the main stop valves and intermedi-ate stop valves also closed even though they still were receiving open signals from the turbine control system. 8). Now all the valves are closed, the control oil system is pumping the ETS pressure back to 1600 psig and that takes 10-15 seconds. Meanwhile with all the valves closed the turbine cannot maintain 1800 rpm.
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9). The combination of the trip signals sent to turbine controls and the signal of open breakers sent to the controls now causes the control system to deselect 1800 rpm set speed and select " valves close selected". 10). The turbine has not been tripped but " Valves Close Selected" now sends a close signal to the main stop valves, control valves and intercept valves. They will not reopen to maintain turbine speed at 1800 rpm even though the house load is now dragging the turbine generator speed below 1800 rpm. 11). The control system now is able to get "ETS" back to 1600 psig and reopens the only set of valves not receiving a close signal - the intermediate stop valves. However this has no effect on tur-bine speed since the other valves are still closed. 12). The turbine-generator speed continues to slow down due to house load. 13). The RCPs trip on low speed, trip the reactor which in turn finally trips the turbine. sn
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1 i Turbine and EHC Action on leading up to trip on 9/12/85, PVNGS #1
- The removal of the load from the Main Generator, accomplished by the manual opening of the Main Breaker 918, . started the following sequence in the EHC System and on the Main Turbine Valves:
4 The turbine-generator accelerated rapidly due to the loss of load, bringing in , the overspeed protection circuits. Because the difference was less than 40 percent of rated electrical load, between the load at the start of the test and the house load which remained connected to the generator, the Power / Load Unbalance circuitry did not activate. i ! The first overspeed circuit to come into action was Fast Closing IV's (Intercept Valves) at approximately 1/4 second after the main breaker was opened. This cirucit fully closed the Intercept Valves within an additional 1/4 second. The Fast closing IV's indication cleared quickly indicating the acceleration of the turbine was rapidly reduced.
' After the Intercept Valves had been closed for approximately 1/3 second. they were released to begin reopening. The turbine-generator speed had reached its peak by that point in time and speed was decreasing. The six Intercept Valves started to reopen slaultaneously, and the volume of fluid necessary to reseat the disk dusp valves on the six Intercept Valve became more than the hydraulic i pumping unit could supply.
The hydraulic pressure began to drop, alarming first as NO ETSV PRESSURE TRIP i TRIPPED on the sequence of events recorder. The next alarm was LO ETS PRESSURE TRIP TRIPPED, closely followed by the NO ETV PRESSURE TRIP TRIPPED. A pressure drop sufficient to bring in the LO ETS PRESSURE TRIP TRIPPED alarm would have caused all the Turbine Valves to fast close. The Alarm Typer printout 1 indicated all turbine valves had closed. When'the contacts on the.two ETS pressure switches, PS-4 and PS-5, both closed, 125 volts was fed through to Relay contact X50-1. as shown on the on the Trip and Monitoring Schematic (Document No. 03-10407-M400-3.17-542-1, co-ordinates
@ C-6), and to TM/15 (octagon-shaped symbol, co-ordinates A-6, same document),
i > which sent the LO ETS PRESSURE TRIP TRIPPED signal to the computer and to the j 4 EHC First Hit circuitry. The 125 volts was fed through relay contact X50-1, which had been previously i closed by circuitry sensing the opened Main Generator Breaker, to Relay X46 (Trip and Monitoring Schematic, co-ordinates C-6), energl=ing it.' Relay j ' contact K46-1 (Trip and Monitoring Schematic, co-ordinates E-10) then opened removing the +24 volta from the output point of that circuit labelled TM/601
- (co-ordinates E-10, aame document). '
l' The +24 volts removed from TM/601 input to the Speed Control Logic, shown on
- the Speed Control Logic Schematic (Document No. 03-10407-M400-3.17-460-2, at i co-ordinate B-11), allowed Relay X9 (Speed Control Logic Schematic, co-ordinates C-10), to de-energize.
That relay de-energizing closed .the contacts X9-1 (Speed Controi Logic Schematic, co-ordinates D-3) allowing +24 volta fed from circutry sensing the opened Main Generator Bre.ker with the EHC trip system still reset (octagon labelled ,52/125, same document, co-ordinates A-2), to feed through all the closed contacts (other speed holds not selected) to the relays X1 and X2 (co-ordinates N-4, same document) which energized, picking up the CLOSE VALVES speed selection.
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Turbina cnd EHC Actiin cn 10 ding up to trip cn 9/12/85, PVNGS C1 CLOSE VALVES being activated put a closing signal on all Turbine Valves except the Intermediate Stop Valves. This voltage algnal also fed out to the Load Set Motor circuitry driving it down to 2 percent of load. With all turbine valves except the Intermediate Stop Valves held closed, the proper hydraulic pressure was reatored, the three indications of low hydraulic pressure then cleared,.and the Intermediate Stop Valves reopened. The turbine-generator continued to coast down until the trip was received from the reactor trip, which tripped the turbine and shut the Intermediate Stop Valves. 4 e N I e
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OUTLINE OF SIGNIFICANT EVENTS
- 1. Description of abnormal RCS cooldown and subsequent SIAS/CIAS
- 2. Failure of Essential Chiller "A"
- 3. Charging pump "A" failure due to Gas Binding
- 4. Declaration of Unusual Event i 4 5. Ioss of Remote Monitoring System and Chem Lab sample analysis capabilities.
- 6. Failure of Fast Transfer of House Loads to off-site power.
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RCS C00LDOWN
- 1. Immediately after the turbine / reactor trip primary pressure peaked and then decreased rapidly to approximately 1900 psia pressure then in-creased slightly and stabilized at 1923 psia where it remained for approxi-mately 2 minutes. At that point a number of things happened to cause RCS Cooldown:
A. SG Feed The Non-ESS Aux feed pump was put into service manually to supply feed water to the steam generators. SG #1 was fed at a rate of 450 gpm for approximately 1.5 minutes. At which time flow was stopped. SG #2 was fed between 450 gpm and 625 gpm for an additional 4 minute aux flow was s then reduced to 200 gpm. Aux feed flow continued with 4 sins was received which resulted in the downcomer valves going fully closed.and preventing any further flow. B. Atmospheric Dump Valves SG #2 line 1 ADV was partially opened at 2217 and closed at 2219 when the steam drain valves opened. At 2221 the ADV was partially opened to divert The ADV was steam from the condensor due to a loss of circ water flow. closed at 2223 after the sins had occurred. C. Steam Drain Valves The main steam line lowpoint drain valves opened. These eight two inch valves are designed to remove water from the main steam lines prior to turbine startup. The valves automatically open on a turbine trip and dump steam directly to the condensor. The valves were shut by operations follow-However, the ing the turbine trip to' prevent an excessive RCS Cooldown. e, - loss of power to the valves caused by the loss of power to the Non-ESS busses, reset the auto open circuit and the valves reopened when power was restored. The opening of the valves at the same time operations per-sonnel were restraint SG 1evels cause an excessive cooldown. This problem has been corrected by disabling the automatic open circuit of the mainsteam drain valves. Themp mod 1-85-MT-36 has been implementedAtoPlant prevent auto-Change matic opening of the drain valves after a turbine trip. Request has been initialed to implement this DCP in all three units. The combination of the aux feed flow, the opening of the ADV and the opening of the mainsteam low point drain lines resulted in RCS Cooldown and Depres-surization to a point where high presure safety injection was initiated.
- 2. FAILURE OF ESS CllILLER "A" ESS chiller "A" failed due to low refrigerant temperature which was caused by low refrigerant charge. Subsequently the chiller was restarted and tripped again. A bad solder joint was discovered on the line from the evaporator to the purge. The line was isolated and Ops directed ilVAC maint to refill chiller with refir8erant and chiller was restored to oper-ation. At no time during the evolution did the llPSI/CPSI/CS room temper-atures reach a level where chiller operaiton was required.
Isolation of the purge line will not ef fect operability of the chiller and the line is being repaired. _-- M
- 3. Loss of Charging Flow due to Erroneous VCT Level Indication The charging pumps became bound with hydrogen from the VCT resulting in charging flow decreasing to zero (as indicated by local control board indi-cations for charging header and seal injection flows) due to an erroneous VCT level indication in which the actual level decreased to zero but the indicated level did not. Thus, the charging pumps drained the VCT and became " gas bound" with hydrogen and continued to operate for an estimated duration of 5-10 minutes. The control room indication (LIZZ6) read approxi-mately 205 at the time the loss of charging flow was noted. Normally, a VCT level of 34% will initiate auto makeup to the VCT with the appropriate valve and pump actuations occurring and the VCT trouble alarm annunciating.
Auto makeup did not occur, however, due to a lose of non 1-E power to the valves and pumps which had occurred shortly before the loss of charging flow was noted (Instrument power was not lost at this time). Gravity feed
;% from the RW directly to the charging pumps (via CHV536) also did not initi-ate as it normally does on a 5% VCT LoLo Level (nor did the LoLo annuciator actuate) because of the erroneous 205 signal from LI 227. It should be noted that due to the pressure difference between the VCT hydrogen over--
pressure of approximately 20 psi and the usable head available for gravity feed from the RWT (approximately 10 psi), gravity feed could not have been established to the hydrogen bound charging pumps simply by an alignment of a flow path from the RWT. Once power had been restorad,
. the BAM Pumps were used to overcome VCT pressure and eventualy reestablish t charging flow; An alternate method could have been to vent the VCT to a . Iower pressure than the usable RW head (assuming the valves used for vent-ing have power and Radwaste can process the waste gas) and could possibly be accomplished faster than using BAMPS.
The charging pumps sustained no apparent damage and were determined to be mechanically sound and able to perform their intended function. To ensure no pump degredation, surveilliance test 41STICH06 was performed (satisfactory) on all 3 charging pumps. The packing seal tube system most likely prevented gross packing and plunger damage when the pumps were oper-ating gas bound.
'Ihe health and safety of the general public was not jeopardized since pres-surizer level and pressure could be maintained by the high pressure safety injection pumps with the charging pumps not operating until charging flow was reestablished and VCT level returned. Operations was aware of the gas binding problem and was also aware of their available options (i.e.
Boron Injection Flowpaths) to maintain safe plant conditions at all times. The cause of the transient was due to an incorrect level in the common reference leg of the VCT level transmitters (mainly LI226 on the main control board, but also LI227 and local LI227-1); a less than full reference log level produces on indicated level which is higher than actual 1cvel. '" The possible causes of the partially lost reference log could bet (1) Inadvertent opening of the equalizing valve at the transmitter (2) Leaking equalizer valve and/or fittings (3) Evaporation from the wet reference log Of the three possible causes, the second in the most likely, and the lack of boric acid crystals on the fittings indicates the equalizer volve is the problem. Evaporation seems unlikely due to the relatively low temper-4 mO E
o . 1 4 . i l r I atures and higher (than saturation) pressures usually present. Inadvertant I i equalizer valve opening should not be ruled out, although it would be much l were noticeable than a slow leak due to the sudden level change on the r
- control board indication.
! A similar problem occurred at St Lucie Unit I with essentially the same
! common reference log design as PVNGS; St Lucie opted to install a second i reference leg as the restoration to this problem. I should be noted that ' 1 each instrument must have its own refernce leg, not two reference legs serving each instrument. l ,
.. In the short term, the reference leg has been refilled and the transmitter l m- recalibrated. The long term resolution appears to be either to install 4
*. - a sec'ond reference leg similar to the St. Lucie resolution, or to install i a " head tank" or condensate pot to provide a fill volume to the existing I reference leg. In the interim, periodic checks will be made and the refer-l ence leg refilled as necessay until the long term modifications (s) is installed. Additional measures (such as warning tags on the equalizing valves) may be taken to ensure no inadvertant level inaccuracies are intro-
; duced. >
J This event will serve as the basis for any specific modifications proposed;
. however, it should be noted that the double failure scenario experienced (i.e.: loss of non IE power with simultaneous false VCT level indication) 2 .
was the cause of the changing pumps becoming gas bound, not the VCT level
- {dlatioplone.
f Richard W. Burge i 9/14/85 Ops Engineering
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- 4. Declaration of Unusual Event At 2223 an Unusual Event was declared due to the Reactor trip and the par-tial loss of power with a subsequent SIAS/CIAS. The Unit 2 S.S. was noti-fied to assume emergency coordinator duties. The STSC and OSC were acti-vated, and all notifications were made as required. The Unusual Event was terminated at 0102.
- 5. Loss of Radiation Monitoring System When NAN-S01,S02 were de-energized power was lost to all non-class power
.. Radiation Monitoring instrumenta and to the RMS computer. All R.U. units
'- required by Tech Specs to perform Safety Related actuations remained powered and capable of performing their safety function. In addition, although the PMS computer was not functional all class powered RU units could be monitored using the Remote Indicating Modules-(RICS) located in the Control Room area. During a loss of power the plant vent is not a off-site release pathway, all releases are through the Fuel Building. This pathway is moni-tored by a class powered R.U. monitor which can be monitored in the control room area.
- 6. Breaker Fast Transfer The testing performed was to include verification of the reactor power cutback system and the Stcom Bypass Control Valves. The house loads were powered thru the Auxiliary Transformer with a load of approximately 50 megawatts with the reactor at 50% power. The test was to start by opening
; the output breakers 915 and 918. The turbine / generator was to reduce speed and maintain house loads. Below is the sequence of events which followed the opening of breakers 915 and 918. The generator speed increased there-fore, the frequency increased. The steam valves closed and turbine speed decreased. The grid was at 60HZ and the generator was still maintaining the house loads until the frequency dropped 57.4HZ. By design the differ-ences in frequencies of the house load using the turbine / generator through the auxiliary transformer and the grid did not allow transfer. Breaker contacts NANS01 and ANAS02 were opened and fast bus transfer signal was ,
generated. Sequenzation check relays would not allow the transfer due
- to frequency mismatch, which is in accordance with the transfer design.
The transfer must be instantaneously. O * ,o s J- _
4.- PALO VERDE NUCLEAR GENERATING STATION UNIT I PLANT REVIEW BOARD MINITTES OF MEETING #85-123 SEPTEMBER 14. 1985 I. Verification of PRB Quorum (Tech Spec 6.5.1.5)
. MEMBERS:
0.J. Zeringue (Chairman)
- b. < - ? ?. L.G. Papworth s' ' .. '
R.E. Younger
- - J.M. Allen .
J.R. Bynum , W.F. Fernow J.F. Minnicks ALiERNATES: G. Waldrep CUESTS: R. Burge
- J. Taggart I. Review of Unit operations to detect potential nuclear safety hazards
* (Tech Spec 6.5.1.6e) ,
Post Trip Review Report #1-85-004 Unit I September 12, 1985 Reactor Trip with loss of forced circulation and degraded electrical conditions; also subsequent ESF actuation. Specific sections of the report were reviewed individually
- 1) Sequence of* Events ...
Board had minor editorial comments.
- 2) Essential Chiller Failure-Operations Engineering to initiate Preventive Maintenance Program
*- to refill refrigerant.
- 3) Reactor Coolant System Cooldown Two preliminary versions to be combined (Taggart/Waldrep)
- 4) Gas Binding of Charging Pumps ,
- Initiate Prevent Maintenance Program to refill Unit I Reference Log (one week completion).
- Design Change (PCR) to add second Reference 1,og or add
- Head Tank (i.e., Condensate Pot) to existing Log (one week complettor
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P'
Pcg'3 2 PRB Meeting Minutes #85-123
' September 14, 1985
- 4) Continued
- Temporary Modification to provide Class IE power directly to Valve 501 (one week completion).
- Procedural changes (Operations - prior to restart)
- All Shifts will review Post Trip Report.
- 5) Review of Chemistry Sampling / Analysis and RMS Power Sources Verify that procedures allow usage of Unit II analysis equipment
. in case of Unit I loss of power.
- 6) Unusual Event Report The referenced Post Trip Report has been reviewed with no unreviewed safety questions or unresolved comments.
Sub*nitted by: Approved by: 0.J. Zeringue L.A. Guerin PRB Secretary PRB Chairman s e 1 l l e 1 e A e t
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PRB RESTART RECONMENDATIONS Evaluate frequency of chiller periodic maintenance schedule to insure proper refrigerant level is maintained. Due 092185 OPS Eng. Add periodic maintenance for VCT level instrumentation to insure reference leg level is maintained (once/wk) and review PM's for all other Reference Legs. Due 092185
's . I&C Review VCT level instrumentation for possible design change.
Due 092185 OPS Eng. Change applicable operations procedures to insure Cil-UV-536 is opened and Cll-UV-501 is :losed during plant transients involving VCT Inventory Control Problems.
. Prior Unit 1 OPS Note: This may be handled on an interim basis using an operation 4 night order.
s Per Telecon
- 0. J. Zeringue ip; Each shift will be briefed on the changes made to the operations procedures and on items identified in the Post Trip Review.
OPS Superintendent Date Review operation / design of VCT discharge and chargin pump inlet valves for possible design change. Due 092185 OPS Eng. PRB also recommends a design change to provide class power to all Remote Monitoring System monitors and to the Remote Honitoring System computer and chemical analysis equipment / lighting. PRB also recommends that during subsequent performances of trannient tests additional operations personnel be on hand to cover any contingencies. l'HD Chairman UdLO
. ChWFA A INSIh? PERIODIC TEST CTSC ,
PUSH RETURN WHEM READY > SYS~E*1 TEST LAST RESTART - 30,33, SENSO7 STATUS WORDS
.- 1111 INgj'Y,..S. SF2 ..
S SFi t 0 0 .0 001110111 S SW3 : 0 0 00 0'00 0000 000 00 *
^
S SW4 0 00 0 000 010 F *. 'e .' SELECT TEST NUMBER A. * * ,
'l'-Ex2T SYSTEtt TEST :" .
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t .. 2-PERIODIC TEST - . 3-P AILTD SENSOR REPRT . 4-T RIPS SUFFER REPRT
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- 5-ADDR CONSTANT LOAD
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'. 4-ADDR C0KS' TANT CEN. .
t '. ENTER TEST NUMBER >3
>3-TAILED SENSOR REPRT* , )
l
*I
.PID TIME (HR) STATUS
)
049 ' +1:4 018E+2 4 , HT 1 1 p.M/049 '
+1440093+2 ox 4 1 t. ' gJg',.p* r..
049 +1:4009E+2 H7
' . h :,; . . . '
. f.P O 4 9 +144009E+2 -
'oK .
T.L~%8T049
+1J4 308E+ 2 H7
.$$IN2'
- *0 4 9 +1.400SE+2 ,
og ,
'. ,h,5:.. ENTER TEST NU!!STR>4
- D- *. . .
4-T RIPS EUTTER REPRT . ' '; e* P7D VALUE PID VALUE P7D VALUE 001 + 2. 3 010E + 3 002 +2 4 8 020E+ 3 003 + 2 410 20!+ 3 . 004 +2.8000E+3 005 +5.6287E+2 - 006 +546324T+2
- 007 +5. 9 2 5 0E+ 2 006 +5.9342E+2 009 +242440E+3 010 +4.2441E+1 011 +540535E+1 01'2 +5:0940r+1
-- - *013 + 1. 2 3 0 0E + 2 014 +1/2R00E+2 -
015 +145040E+2 016 +1. 5 0 467+ 2 , , 017 , ,+ 1 4 9 2 4 E + 2 . , ,, ,n ,, 018 ,,,+ 1.10 0 0E+ 2 ',
-"9 019 +1.4 8 9 3E+ 2 ~~l, 020 +1.5053E+2 021 +1.5000E+2 ,
.- 022 +145060E+2 -
023 +145030E+2 - 024 +1:50400+2 025 +1.4 9 31T+ 2 024 +1.4843E+2 027 +1:4 9 01E+ 2 028 ,41 4 9 24 E+ 2 029 +1. 4 0 R4 K+ 2 030 +145045!+2 031 +1.'4 916t+ 2 032 +1450373+2 033 +14 5 0 6 s!+ 2 -
..v 1.
434 +1 5 0 37E+ 2 , 035 +145051E+2 034 -+1:4...s....902E+2 ,'*
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.s* *np3 ol.0209E+0 044 +1.0690E+0 065 +
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, +1.4 0 0 0!+ 0 067 +2:0 000E+1 069 *+
. Od9 cl.10 0 0E+ 0 070 +7.4 9 0 0E+ 0 071 +14154C?'O 072 +1.2480E+1 073 +020000E+0 074 +1.091aE+0
.075 +1. 0 0 0 0!+ 0 076 + 1. 0 0 0 0 E+ 0 077 +1.0000E+0 074 +1.0000E+0 079 +14 0 010E+ 0 080 +1.0000!+0 081 + 6. 0 514E+ 0 032 -2. 7 6 24 E+ 0 093 +2.3750E-1 .
034 - 3.1013E+ 0 085 + 7. 9 216E+ 0 086 -2 4 7 R 7 6!+ 0 047 +5. 9 4 0 0E- 2 OSS -2.16 5 6E + 0 08a +5.5 5 98!+ 0 s 090 +14 0 0 0 0E+ 0 091 +1. 0 0 0 0E+ 0 092 +14 0 0 0 0E+ 0 093 +1. 0 0 0 0E+ 0 094 +1.0 0 0 0E+ 0 095 +140 0 0 0E+ 0 006 +1. 0 0 0 0!+ 0 . 097 +14 0 0 0 0!+ 4 099 +5.8000E-3 009 +1.18 3 0!- 2 100 +740 5 60E-2 101 +1. 0 3 90E-2 102 +4. 6 4 0 0E- 2 , 103 +2.0 0 00!+1 106 +2.9114E+0 . 120 > 9 4 6 7 62!-l 163 +1 0000!+0 166 +3. 0 0 20E+ 0 '/ . 170 +3 0 0 20E+ 0 171 + 5.18 9 6!+1 173 +54 6 34 5E+ 2 174 .. +1. 6 0 5 3E+ 0 '
*175 +0. 0 0 00E+ 4 177 +4 4 0 718!+1 173 +4. 9 7 8 8E+ 1 + 9. 9 7 91E+ 0 1183 + 64 0 4 9 9E+1 . , ,
'.g... i .',18 4 '.'+4.4 0 7 73E-1
.{[I 214~ 24 0 7 73! .1 ' .'d : ' 17 187 +1J964 9 6E-l 198 +1J0000E+0
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' 215 +1:0117E+0 216 +244 292E+2 M'"' /'
220 +1.12 5 4 E + 0 268 +146329E-1 333 +9:0 8 03E-1
- 334 +24 9 4 02E+ 0
* ' '}. ,.
335' -1495S4E-1 341 + 64 0 7 2 6E+ 2 ' 342 + 6. 515 3E+ 2 34 9 +1 6 0 4 9E+ 0 406 +2.a114!-l
. *414 +14 3 5 9 5E+ 2 415 -4 0 9 60!+ 3
- 416 +4e4 000K+1 417 + 0. 0 0 0 0E+ 0 418 +1. 2 8 0 0!+ 2 . 439 +1J0000!+0 440 +9.'08032-1 442 +2 4 24 59E+ 3 443 +5.6345E+2 444 +6 0 4 98E+1 445 +14 0 0 0 0!+ 0
ENTER TEST NU*iLER>l 1-EXIT SYcT!?! TEST, . RESET TEST SWITCH
- I END SYSTE:4 TEST 3
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.IMSIR" PERIODIC TECT DIEC PUS!! RETURN WHEN REACY>
SYSTI:t TEST LAST RISTART - 15/1R,30 S ENSOR STATUS WORDS SSFit 1111 SSW2: SSW3: -0 0 0000 1110111 000 00 0 0000 00000 S SW4 : 0 0000.00001 t SELECT TEST NU!!nER -
~ 1-EXIT SYSTZ:1 TES 4 :
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. 3-F AILID SENSOR REPRT , ,
e i 4-T RIPS BUFFER REPRT i, r 5-ADDR CONSTANT LOAD \ 6-ADDR CONSTANT OEN. '
- ENTER TEST NUfibER>3 . .
3-FAILED SENSOR
- REPRT .
PID " ' 77'lE ( H R) STATUS *
,g, 010 . +.3 4 8 7 21E + 2 LO
.s 011 +3 8710E+2 '
LO f.e y' 012 +3.8719E+2 * , *
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,,. , 999 +3J8717E+2
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OK .
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998
.* +3.8717E+2 OK 10.-
999 + 3 8 717E+ 2 H7 . ENTER TEST NUllLER>4 4-TRIPS .B .UTTER. REPRT ' PID VALUE PID .f. VALUE P7D VALUE M1WII2Yt0'0~0ry 3 'WnAJ 11~002'TlFf23 8 0 60 E+ 3*WW Co O T.W2 f 8~5 2'of+3 W po % (00 4'1.*At2 t 8 0 0 0E+3 wgAW 005 .
+ 5. 6 2 8 3E+ 2 006 007 +5. 9 3 6 8E+ 2 008 + 5 4 4 4 31T+ 2 .
010 +4 2 617E+1 +549521E&2 009 +2:2 3 52E+ 3 ' s 011 +5/9535E+1 012 +54 0 94 0E+1
. %W..'#17YfD'ot'CM*l 41'4'7.TITf8 00EFr! PFt. 015
.. 016 +1s4 911E+ 2 017
+1 e 5 0 5 3E+ 2 019 +145675E+2
+1. 5 0 00E+ 2 020
. 022 +1 5 4 093+ 2
+1.4 0 54f+ 2 M 021P,"7Jti +144 9v54E+ i r742 E'.E2 G rg.,.j 5 (.up 4 .
+.023 +1. 510 6E+ 2 '"""' 024 '+145113E+2
- p. *,
025 +1.' 5 0 5 3E+ 2 026 +1. 5 0 64M+ 2 028 . 027 +1!5 0 30E+ 2 "
+1. 5 0 0 0L + 2 029 41.502:!&2 031 +1 5 0 0 0!+ 2 430 +1 45415E+2
- 032 +145030E+2 033 434 +1 5022E+2' * +145 0 60E+ 2 0d0 035 +144 0 54 Y+ 2 036 .
+1.0 3 29E+ 0 041 +144 94 8E+2 '. " ' * . # *l.A'. >
+0 4 0 0 0 0E+ 0 462 + 0:0 0 00f+ 4
**i" * " L' ' - , pl. , .,_ - - - -.dJ, 4 4 't ',.
ti .4 2 9 4v+ n . edi M t_-.-__ ____ ._ 88'd***f ' * *
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u se .o . . ...-- 466 +14 4 0 0 0E+ 0 067 +2 40 0 00!+1 a 069
** . * ' 0 6'9 +141000E+0 49.0 0 00E+ 0 070 +7.4 0 0 0E+ 0 071
+141540E+0
, '072 +1. 2 4 GCE+1 073 +040 0 00E+0 074 075 +1. 0 0 0 0E+ 0 076
+1:0 919E+ 0
,07S
+1:0000E+0 077 +1:0000E+0
. +1. 0 0 0 0E + 0 079 +140 0 00E+ 0 ORO +1:0000E+0 081 + 6. 0 514E+ 0 082 -2. 7 6 24E+ 0 084 093 + 2 :3 7 5 0E-1
-341013E+ 0 085 +74 9 216E+ 0 086 -2 :7 8 76E+0 037 +5. 9 4 00E- 2 088 -241656E+0~
090 089 +5:5589E+0
+1.*0000E+0 091 +14 0 0 00E+ 0 092 +1.0000E+0 4
093 +1. 0 0 0 0E+ 0 .' 094 +1 0000E+0 095 +14 0 0 00E+ 0 096 +14 0 0 00E+ 0 097 +1. 0 0 0 0 E + 0 099 093 +5.9000E-3
+1.18 3 0E- 2 , 100 +740 5 60E-2 101 +1: 0390E-2 102
+4 4 6 4 00E- 2 103 +2:0 0 00E+1 EZQ.!5thv.W.mi.1 fM. 4.06 t.2:t2 tS O 92EED )(L 4IOm2:17T4E'f& G CEN'ItfE00ffdW 171 G.:6.9;It2:3.I34E4E yz, '.
+5:19 9 3E+1 173 +5 4 6 6 59E+2 174 +1s 6 0 2 9E+ 0 175 +0. 0 0 00E+ 0 178 177 +4. 9 21RE+1
.+4 9 5 2 0E+1 179 +9. 913 6E+ 0 1 *. 184 ' 183. + 6:0 0 91E+1
+3 9 4 67E-1 187 +1:6321E-1 $ m M '65bfliv ')R.iD
-1. 9 4 67E-1 215 +1 0118E+ 0 M)fS214,.;;. ', +3.' 9 2, 6[,2 5E+2 0 0 268 +1; 6 6 0 6E-1 216 +2:3 9 33E+ 2 '
334 SU32ITF94tT1*2GD F\. tot.ST",
+3e 0 4 74E+ 0 342 + 6 513 6E+ 2
- 335 -lt9070E-1 341 +6:0R29E+2 .
349 +1J 6 0 2 9E+ 0 RY6"ZF2YfD 42E*."'11) mwhntVt . 414 + 3.' 8 717E+ 2 415 -4 :0 9 60E+ 3 416 +6:4 000E+1 417 +010 0 00E+ 0 418 + 6:4 0 00E+1 439 +1:0 000E+ 0 440 + 9. 0 5 0 5E-1 442 +24 2 2 9 3E+ 3 . 443 444 4 6:1183E+1 +5 6 6 71E+ 2
- 445 +1:0 000E+0
- ENTER TEST NU:lBER>l .
1-IXIT SYSTE:t TIsT ,
, RESET TEST SWITCil '
. END SYSTE:4 TEST -
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s., cym64 V - INSERT PERIOOIC TEST DISC PUSH RETURN WHEN REA0Y> SYSTE*1 TEST ' LAST RESTART - 30,16,30 SENSOR STATUS WORDS , SSW1: 1 111 . .. S SV2,1 70 0 0~ 0 0 1.1 1 0 011
' ' - E .'T. .
S SW3 : * *d' 'O 0 'O O OOOO O0 0 0 0 00 S SW41 0 0 0 0 'O OO O O O
, SELECT TEST NUMLER ,
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.<st 1-EXIT SYSTE't TEST - ,
,.4, . . ,, ,
2-PERIOOIC TEST 3-TAILID SENSOR REPRT . l 4-TRIPS SUFFER REPRT
- 5-AOCR CON 3 TANT LOAD
, 6-ACDR CONSTANT GEN.
ENTER TEST NUMSER>i
~
l . 3-F AILED SENSOR RI?RT
- l 'PID s TIMZ (!!R) STATUS 999 + 6. 2 61 SE+ 0 OK *
;. , ,, . - ~
, 998 +6.26182+0 '
OK
,.,,, 999 + 6. 2 617E+ 0 HI ' '
....r... .
,. 999 +6.2617E+0, 11 7 (s , r.j 003 + 6. 2 5 6 3E+ 0, oX 002 *
+6.2563E+0 OX 1
, g ENTER "EST NU'IfiER>4 s ( '
4-T RIPS r30 FTIR REPRT , - PID VALUE PID 001 VALUE ' PID . VAL 4I
+ 2. 516 0! t 3 Wfth.h 002 004 +2 5170E & 3 wnMt. 0 0 3 *$ 2.'J 1700 + luJfLDol .,
' + 2 516 0E + 3 usRDa% 0 0 5 + 5.' 6 5 2 5I + 2 006 + 5 /6 3 2 0M+ 2 - -
007 +5. 9 4 70I+ 2 00s '
+ 5. 9 3 0 0E + 2 0 0 9 ' + 2. 2 4 74 E+ 1
.. . 010 -4.90392-2 011 + 1.' 3 0 2 7H- 1 012 + 4.* e 3 51E + 0 013
+1.2 0 00!+ 2 ?Ei 014 +1.2800E+2 PFL 015 +1. 4 011E+ 2
- 016 +1. 5 417!+ 2 017 -
019 + 1.' 4 9 7 9 E + 2 - 019 + 1. 4 e 6 3" + 2
+1.4 8 4 3E t 2 020 +1/ 5 0 07E+ 2 021 022 , +1 4 B R65+ 2 ;
+1 5022E+2 021 + 1.'4 8 7 A r + 2 024 025 +1 5 0 2 2E+ 2
+1/4 R 43E+ 2 029 '
024 +1s4 969f t 2 027 +1/4 R4 RE+ 2
+1.4 8 2 5E+ 2 029 + 1.' 4 8 4 RI + 2 030 031 +1 4 9 34r+ 2
, +1 4 3567+ 2 "
(* 3 4 032 +1.4 9 4 2E+ 2 , 033 +1. 4 916t+ 2 '
+1 4 9 94t+ 2 035 +1.4 914E+ 2
- 036
- +1/4 94 aE+ 2 ' ' . -- o '
~ ~. -_
~
463 +1.0 2 9 9E r v us4 +14 0 0 2 2E+ 0 065 +1..
. .. . ~. 'O k +1. 4 0 0 0E + 0 067 +2.0000E+1 069 +a.a.
069 +1.10 0 0E + 0 070 +744 R 00E+ 0 071 +14154G?+0 072, +1.2420E+1 073 +0.0000?&O 474 +1.0 alo?' O 075 +14 0 0 0 0E+ 0 076 +1e0000E+o 077 +1.0000?+0 G79 +1. 0 0 0 GE+ 0 079 +1. 0 0 0 0E+ 4 090 +1.1000?+4 GR1 & 6. 6 514E+ 4 032 - 2. 7 6 24 F+ 4 093 +243750E-1 084 -3.1013E+ 0 095 +7.0216E+0 096 - 2 . 7.17 6E + 0 087 +5. 9 4 0 05- 2 OSS -2.16 5 6E + 0 099 +5.5593E+0 090 +1. 0 0 0 0E+ 0 091 +140000F+0 092 +140400E+0 093 +1. 0 0 0 0E+ 0 694 +140 0 00E+ 4 Ca5 +1. 0 0 0 0E+ 0 096 +1. 0 0 0 0E+ 0 - 097 +140 0 0 0E+ 0 09' +549000E-3 099 +1.18 3 0E- 2 *100 +7. 0 5 60E-2 101 +1e0390E-2 102 +4 4 64 00E- 2 103 +2:0 000E+1 106 +143911E+0 %i 120 +1. 0 4 4 9E+ 0 mC. 168 +1.'10d9E+0 W 169 170 +1:2207F+0 tt..
+1. 2 2 0 7E+ 0 4 171 +1.9644E+0 173 +5.6609E+2 174 17b +0. 0 0 00E+ 0 177 + 5. 2 7 717'l 178 ,+ +5. 2.4 25700E+ 71E+10 179 +2:1912E+1 193 +6:194 0E+1 f .134 +2 e 3 89E-1 -
187 +2:0 5 39E-2 193 i
'a.g .- 214 -es 3 8 9 5E- 2 215 +1 0 5 67E+ 0 216
+1 e13 0 0E+'0 PFt.Pb ..- 4
# + 2 4 0174 F+ 2
' 0 - 220 +2 5 878E+ 0 268 +243R35E-2 333 +14 0 4 51E'O (%.ML T
' ~ '
334 +1:2 7 5 6E+ 0 335 -8 J 3 R R4 E-2 341 .+640770E+2 . 34 2 . + 64 5 2 53E+ 2 34a +2 s 4 5 09E* 0 406 +142207F40 minb e g,. 414 +5 6111E- 3 415 +0. 0 0 0 0E+ 0 416 +145344E'3 417 +04 0 0 00E+ 0 418 + 0. 0 0 0 0E+ 0 439 +140000E+0 440 +1 0 4 5 6E+ 0 / 442 + 2. 2 4 74E+ 3 *443 + 5. 6 612 E+ 2 - 444 + 6.18 4 6E+1 445 +1:10 9 9E+ 0 , ENTER TEST NUitSER>l , 1-EXIT SYSTE:t TEST RESET TEST SWITCll END SYSTE!! TEST . l , .., . s.
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SYSTEM TEST L AST RESTART - 30,16,30 - SENSOR STATUS W.OROS ., S SWl - 1 1.1 1 ' S SW2 : 0 00001110 111 SSW3: 0 000 0 000 0 000 0 0Q0 - S SW4 : 0 0 0 'O OO O010 -
., . SELECT TEST NUMBER -
,-. . ~. . - . .
i.". ~ 1-EXIT srSTEM TEST
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.2-PERIODIC TEST ,
, 3-F AILED SENSOR REPRT 4-TRIPS BUFFER REPN7 -
5-ALDR CONSTANT LOAD . 6-ADOR CONSTANT GEN.
' ENTER TEST NUMBER 3 .
3-F AILED SENSOR REPRT , FID TIME (H R) , STATUS 010 + 6.5 84 9E+ 2 LO j.. . .
'.4 ; ? 012 +6.5140E+2 LO T* .
i
'yn..t.
v, .
, i ldC.,. . . +6.5149E+2 OK 1
. ?# .- 012 pd: 012
+ 6. 5 34 9E+ 2 LO .
011
+ 6.* 5 34 9!+ 2 LO .
lA' , 999 .
+ 6 5 84 7E+ 2 Ox
- ENTER TEST NUMBER >4 4-TRIPS. LUFFER REPRT .
.[
PID VALVE PID VALUE PID VALUE 001 +2. 8 0 20E+ 3 t '. 002 +248000E+3 003 + 2. 9 0 0 0F t 1 . [5?t 004 +2 9030E+3 005 +5 44 72E+2 006 +5:4 64 6E+ 2 $ 007 +5. 9 5 4 5! t 2 008 + 5. 9 5 5 aE+ 2 009 +2:2 3 79F+ 3 *
'010 +4.2 5 39E t1 011 +5 0535E+1 012 +5/0142E+1
- 013 +1 2 0 00F+ 2 014 +1.2800Mt2 015 + 1. 5 0 00!+ 2 Old
+1 4 9 39E+ 2 017 +145075Y+2 018 +1410 07E+ 2 . "
019 +1. 5 0 4 9E t 2 020 +145069Ct2 . 021 +1. 5 0 6 8E+ 2 . 022 +1.5053E+2 023 +1. 4 916E+ 2 024 +1J5093E+2 s 025 +14 4 919F+ 2. 026 +1. 4 916E+ 2 027 +1:5045F+2 029 +1. 4 9 3 9E+ 2 029 +1. 5 0 5 3E+ 2 030
+1J4 924E+2 .. .
. . h2 031 +1. 5 0 41E + 2 ' 032 +1. 4
- 16M + 2 033 +1 f 4 914E+ 2
#*a 4, e.,a.. . .,s as e3<sv69 ,neae,s a @ _. I a$a 4, . .- . -
, .s 60
+ # . 0 3 4 6:.-r u
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vel +040 0 00E+0 +S .W, v 2 9.. -
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+1.0 2 9 9E+ 0 0 64 +14 0 62 2E+0 0 6 5 , +14 0 3'34E+ 0 '
I 066 +1.4 0 0 0E+ 0 067 +2';0 0 00E+1 069
=069 +1.1000E+0 070 +040000E+0
* +7.4 0 00E+ 0 071 +1.15 4 0F+ 0 072 +142480E+1 073 +04 0 0 0 0F+ 0 075 +1. 0 0 0 0E+ 0 074 +1.0919E+0 076 +140000E+0 077 +1 0000E+0 078 +14 0 0 0 0E+ 0 079 +1: 0000E+0 081 + 6. 0 514E+ 0 080 +1.0060E+0 092 -2. 7 6 24 E+ 0 -
083 +2.3750?-1 0.84 ~ 341013E+ 0 095 + 7. 9 216E+ 0 696 087
-2. 7 4 76E+ 0
+5. 9 4 0 03:- 2 OSS -2 s 16 5 6E+ 0 089 '
000 +5:5 5 S SE+0
+1 0 0 0 0E+ 0 091 +1. 0 0 0 0!+ 0 092 093 + 1. 0 0 0 0 E+ 0
+1. 0 0 0 0E+ 0 094 +1.0 0 0 0E+ 0 096 +1. 0 0 0 0E+ 0 095 +1 0000E+0
- 097 +14 0 0 0 0E+ 0 009 +5 4 9 0 00E- 3 099
+1. l S 30E- 2 100 + 7. 0 5 60E- 2 101 .*
102 +4.6400E-2 +1 0 3 00E-2 103 + 2:0 0 00E+ 1 106 +2t9021E+0 120 +9. 0 5 0 3E-1 168 +1:0000E+0 170 +2;9731E+0 169 +2;9731E+0 171 +541813F+1 173 +5 6 6 64E+ 2
. 174' +1J60462+0 .
175 +040000E+0 177 +4J9292E+1
+4c9292E+1 179 +949173E+0 183
'.)gh.mp[;178 i! 154 + 34 9 5 77E-1 187 +146305E-1 198
+549954E+1 '. If 2%34 214 ~~1.9577E-1 '
+1:0000E+0 . gyf 215 +140ll2E+0 216 +2:3 9 54E+2
~
220 +2418 0 6E+ 0 268 +1'46579E-1
** 334
' 333 + 0. 0 7 5 3E-1
+3.0854E+O 335 -1. 9 4 31E-1 341 +6. 0 8 6 5E+ 2 342 + 6 5175E+ 2 349 +1. 6 0 4 6E+ 0
~
414 406 + 2. 9 0 21E-1
+ 64 5 84 6E+ 2 415 -4 e0 9 60E+ 3 416 + 6:4 0 00E+1 417 +0. 0 0 0 0E+ 0 418 +142000E+2 440 +94 0 5 34E-1 439 +1:0 9 0 0E+ 0
- 442 +2. 2 3 54E+ 3 443 +5 s 6 6 66E+ 2 444 + 6. 0 3 3 5E+1
- 445 +14 0 0 00E+ 0 t'N"ER TEST NU:lBER>I. .
1-EXIT SYSTE:1 TEST . . .
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. END SYSTE!! TEST .
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WORMONG COPY ' PALO VERDE NUCLEAR GENERATING [ROCEDURE o ,pp ,, (* STATION MANUAL 41EP-1ZZ01 REVISION Page 1 of 9 EMERGENCY OPERATIONS '2 Page 154 of 171 STA RESPONSIBILITIES Although the STA has no actions in the RO, he is tasked with maintaining a high awareness of RCS conditions and expected trends. As a mini =um the STA will maintain an awareness of the following and report problems as neccessary to the Shif t Supervisor. . 1.0. . VERIFY TE FOLLCVING PARAETERS CAttrION *
' ' IF C0hTAINMEhT TEMPERA *I"JRE RISES ABOVE 200*F INCREASED INSTRUMENT INACCURACIES CAN BE EXPECTED. NOTIFY TE C0hTROL ROOM STAFF OF TE INCREASE IN INSTRUMEST INACCURACIES AND USE TE UNCERTAIhTIES LISTED IN STEP 4.0 TO EVALUATE
,, PLAST RESPONSE. ,
N RE CTIVITY CONTROL: TIME: b 4 h$
~ m fy tv N .
Reactor Pewer I l
/ l1 p I
# I >
I 010 l l IQ I 10 I YES(Y) l Q l( l l All C'r.A's Inserted NO (N) I/v lI 1 l I I I I[ I SI (S). ( l l 'l l l Emergency Boration CH (C) l l I l/g \- ll F ".,g;loel0ll-l6 l I I se ! s t l l 1 l l i Shutocun Margin Verified S l l l l I I "-~ per 72ST-1RXO9, Shutdown Margin .) l l l l I I I AEEOUATE CORE COOLING: . Highest CET *F #FI 5 I' .k$ , RVfl!S Indicates Core Covered 'O lV RCS 28'F Subcooled t' ? \I [* RCS Pressure (Psis) T I?.0 Ii'[ Ml l D l t% l N YES(Y) SI Flev Adecuate N0(N) ll IMl TN\
^4h'(M (64l W.'kll\'n@
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caouns PALO VERDE NUCLEAR GENERATING ["o APPENDIX BB STATION MANUAL 41EP-1ZZ01 Page 2 of 9 I REVISION EMERGENCY OPERATIONS 2 Page 155 of 171 STA RESPONSIBILITIES TIME: PRESSL'RE AND INVENTORY: q bh h
, Chareine Header Flev \ D. D SI Flet HPSI 1A b O b D d (-) lO HPSI IB D 0l0 !0 lDl0 ,
HPSI 2A 0lol6l0l0 HPSI2B.l l l0lol0l0 l0 LPSI LOOP 1 0 0 lDlhlDl0lg ( - LPSI LOOP 2 - b Pressure Level (*.) 1\ \ N b N ( D RVLMS Level (~,) l06 \D \0b ib 00 (00 RCS Pressure at OSPDS l1.D ! k ! kO b PZR Pressure (psia) Oh! @ !d N I N NN Md! M O HEAT REMOVAL: , , , Subceoline (*F)
- Ti (bb h -) \\1 lh
- SG #1 toy.1 . yg W he h N8 O (0 (p ()
Pressure (psia) l ion lLJ( l '? ) l LV lN41 b% l No SG 02 toyet a; ya Th 9 I Y# Pressure (osia) l Wr)I 1 % l % 3 Imd l M o l 61 O l wu I I I I 'I \1 l l ( . T bn g gj l8 l 0 I o lt)a0lg) gojwa l o WMPi '"2 l 0 l 0 Itmitolv)o!"l o Heat Re::: oval SBCS (S) l ll g{\l Y pd l AJ. yV+1 Atmosehere (A) l l l\k l l l
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WORKING COPY . PALO VERDE NUCLEAR GENERATING o [ROCEDURE APPENDIX BB 41EP-1ZZ01 Page 3 of 9 s STATION MANUAL - - - - REVISION EMERGENCY OPERATIONS 2 Page 156 or 171 STA RESPONSIBILITIES TIME: CNTMT: Isoihted YES (Y) l y' NO (N) l l IY l 4 l I .l l l l l l lg l Pressure e e e - ' ek (, I I I i i i I i I I I l l l
'\ff Te=cerature Su=ps A 0 l 0, l 9 lb ! b !O !)
B I DI v IO IO I o l I > l l l H l l ' 0
- ; O li Dli 0 iD i io i A l o 0 !o ! = !
S' 0 lO l O l
- lO l
{g . r SAS Flov B l 0 l B Radiation Alar =s
'O hD W Nb dATERINVENTORY:
- R'n , kb PMU * *)6 SD 0 D 3U
- O CST l%N( lT}[ 37.[ 3*J E$ $f Fuel Pool RAS A l0 l d !' l l"!-l' RAS B 0lD l'l~l-l-l, A l 611 1 4.p> l 8 b- l 4 Ul I ,,le o Hotve11s B ] '; . g l
,4 6 l V l W l lv l /-
1.1 Are any Safety Functions degraded? 1.2 Are safety function parameters trending as anticipated? 1.3 For degraded safety functions (if any), are the conditions , f causing degradation identified? 1.4 Vill any Recovery Operation Action have a negative impact on the subcooled margin? .
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WORK 0NG COPY cEwne PALO VERDE NUCLEAR GENERATING ["o APPENDIX BB C s STATION MANUAL 41EP-1ZZ01 REVISION Page 4 of 9 EMERGENCY OPERATIONS 2 Page 157 of 171 STA RESPONSIBILITIES 2.0 PROBLEM INDEhTIFICATION 2.1 Has a problem been identified?
. 2.2 Does the Onshift Organization need more support in identifying any problem (s), in order to take necessary corrective action?
3.0 PLAST RESPONSE - 2.1 Are plant parameters trending as expected?
/ 3.2 Do you anticipate a problem implementing upcoming Recovery Operation steps?
4.0 ADVERSE CONTAINMEST ENVIR0hMST. - [ 4.1 IF containment temperature increases to greater than 200*F, ( inform CRS and Control Room staff to conservatively a},, ly .tr following instrument errors. s, CHANNEL PARAMETER ERROR P-102 VI,de Range Pressuriser Pressure 240 psia
;,., " P-103,104,105,&l06 Narrow Range Pressurizer Pressure 1120 psia L-110 Pressurizer Level 16".
P-1013,1023 Steam Generator Pressure 225 psia L-1113,1123 Vide Range Steam Generator Level 13". T-112H,122H RCS Hot Leg Temperature 12*F T-112C,122C RCS Cold Leg Temperature , 112*F 4.2 IF contain=ent temperature increases to greater than 200*F, THEN 40*F subcooled margin should be used when assessing plant
- conditions.
-~~~~~ .
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". APPENDIX BB s
STATION MANUAL 41EP-12Z01 Page 5 of 9 REVISION EMERGENCY OPERATIONS 2 Page 158 of 171 5.0 DETERMINATION OF TIME REMAINING AT HOT STANDBY BEFORE INITIATION OF CCOI.DOW 5.1 Determine the following parameters: ' s "
. Available Condensate gal Current Clock Time Time Since Reactor Trip Hrs
'Cooldown Rate *F/HR
. NOTE k' hen the actual time since the trip falls J ~ between the two times that are plotted, use the lower ti=e. k' hen the actual time since the trip is longer than 16 hours, use the 16 hour -
curve. ss NOTE Curves assu=e 2 steam generators 'and 2 ADV are available for the entire cooldown. 1 NOTE - All curves repre'sent cooldown from 575'T to 350*F (225'Fdelta-T). For every 10*F less than a 225*F delta-T enter Figure 1 or 2 on the left hand margin with 2500 gallons more than is actually available. 5.1.1 IF cooling down by Natural Circulation, ENTER the left hand margin of Figure 1. '
. 5.1.2 IF cooling down by Forced Circulation ENTER the left hand margin of Figure 2.
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WORKING COPY . . PALO VERDE NUCLEAR GENERATING PROCEDURE f ". NO. APPE.NI)n* BB i STATION MANUAL 41EP-1ZZ01 Page 6 of 9 REVIStoN E.v.ERGENCY OPERATIONS - 2 Page 159 of 171 Co:iDE!! SATE CAPACITY VS. TIME REMAI tI::c AT hot STANDBY WITH NO RCP's 25 *F/HR cootooWN RATE
- Y -
ge, O 4 8 u m 570 540 I - I 510 l l . l i" 480
- <=0 1 -l
- b 420
- - 20 -
l- / O 3E0 - *
/
330 .
.W "
> 300 k@\
c \\$ 6" -
. l.- 5 270 I
s js # p/ /
+ g@f^
$ 2<0 l sf a- 210 I '
/ /r i ,,0
/ A' ,
l o 150 -
*f .
l-120
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90 l 30 0 - O 4 8 12 15 20 24 l . 75 *F/HR cootoown RATE ALLowAnt: TI:c: REMAI:tI:Io AT hot STA:iDBY (HRS) ,.
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PALO VERDE NUCLEAR GENERATING ["o cewns r '. APPENDIX BB 1 STATION MANUAL 41EP-1ZZ01 Page 7 of 9 f REVISION E'iERGENCY OPE?aTIONS 2 Page 160 of 171 l CONOENSATE CAPACITY VS. TI:1E RE.".AINING _,- AT HOT STANDBY WITH 2 RCP's .
. 25 'F/HR COOL::CWN RATE
. %, . 600 0 -
570 540 - 510 1 I V
,,0 I I V/ .
1 I
'/ X/ -
- 423
, %+ ' f/
350
- k' d; g 2,
. I I .pp/ +*"
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320
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t2 270 W g ,
* / J // - -
a o 210
// l
- i . 1,,
/ V/ -
I . gg, l U 120 ll
- SO f ,
60 l :* -
,, I i l
'I O I
. . 0 4 : 8 12 16 20 24
. l 75 *F/HRCOOLDOWN RATE ALLOWA3LE "II:2 RE"AINING AT HOT STANDBY (HRS) .
FIGURE 2 Pv214400 R(v.gi42 544 A *
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W' - -_ . - _ _ _ - _ - - _ _ _ _ - .
i
" ---m C APPCr1 DIX 00 qA a me,,nump %9h b h C b hL 'OtNCY OPCNAlloi13
-12Z01 NGE 8 0F 9 vV 596,900 gallons . REvis10N 2
*
- 584,200 gallons 571,500 gallons 558,800 gallons 546,100 gallons Q 533,400 gallons CST LEVEL 520,700 gallons g .; 508,000 gallons
; 495,300 gallons g;J. 482,600 gallons q 40 '=
I.: ' 469.900 goiion. C 457,200 gallons 444,500 gallons
- I ." 431,800 gallons
~
fj[ 419,100 gallons '
' g;~. 406,400 gallons 393,700 gallons 381,000 gallons
- g. 368,300 gallons y ;p' 355,600 gallons
. 30 4 342,900 gsHons
E 3N'500$ ' ASSUMPTIONS:
f;:
' 304,800 gallons 1)No tank inventory belc
- 2k00$!!$3 the bottom instrument
(( " 266,700 ge11ons 254 000 galloni tap will be assumed. [ '. 241,'300 gallons 2)12,700 gallons / foot. ( - 2v,. f(; - 228,600 gallons s' p 215,000 genons gf 203,200 gallons U.; 190,500 gallons b.' 177
- 165,,800 gallons 100 gallons
-l . . D 152,400 gallons fy:
139,700 qellons ~ 127,000 gallons ,
- I." 114,300 gallons 101,600 gallons 10 - 88,900 goiians.
f:. 76,200 qs11ons 63,500 gallons [ 50,800 gallons 38,100 gallons p: 25,400 gallons I '
~
12,700 gallons 3 ' ' O 9allons j ; . am aan '
, Off= M = 9 2 S220 L a -
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~*I ENCY OPERAll0N3 APPENDIX 00 Wim $9 X]NQ C{ tr1('R)'
496,000 gallons
!.O r 41EP-12Z01 PAGE 9 0F 9 REVisibN 2
.; 489,800 gallons 477,400 gallons
~ '465,000 gallons Q
(, _ 452,600 gallons 440,200 gallons 427,800 gallons 35 -- o; 4's 4
- S*"aa$
403,000 gallons RMWT LEVEL 390,600 gallons 4~. 378,200 gallons I ' 365,800 gallons
- 30 n 3 4
- 9*"aa' 341,000 gallons 328,600 gallons '
w j 316,200 gallons
- 303,800 gallons .
25 , L. 2si,4m gaues 279,000 gallons 266,600 gallons
'! 254,200 gallons
, 'y,- 241,8m ganons ASSUMPTIONS-20 229,4= g.u s 217,000 gallons 1)No tank inventory bel (-
h N$',$$$'a"1ons the bottom instrumen 179,800 gallons (gp gj)) be aggymed, ,
- 15 167.400 gaitons - -
2)12,400 gallons / foot. iS5,000 ganons g(r , 142,600 gallons , 130,200 gallons
!. 117,000 gallons jQ { ,
105,400 gallons 93,000 gallons
- I 80,600 gallor.-
I
. 68,200 gallons .
- IL 55,000 gallons 5 43.4* gan=s
[] g:- 31,000 gallons 18,600 gallons ' 6,200 gallons . 1.5 9 0 gaiions la orst ma l 093=13=900 l .
'h
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"qq f 2 WORKING COPY PALO VERDE NUCLEAR GENERATING $CEDURE C s STATION MANUAL 41EP-1ZZ01 APPENDIX K Page 1 of 4 REVISION EMERGENCY OPERATIONS 2 Page 65 of 171 VERIFICATION OF CIAS. A TRAIN AFTER HANDSVITCH DEVICE NUMBER NAME CIAS CONDITIO' HPA-HS-5 HPA-W-5 CONTROL SYSTEM A FR RECMB ISOL VLV HPA-HS-i HPA-W-1 CONT SYS A SPLY ISOL VLV HPA-HS-3 HPA-W-3 CONT SYS A TO RECMB ISOL VLV CHA-HS-380 CHA-W-580 MAKE-UP SPLY 70/REAC DRN 'IK VLV
, CHA-HS-560 CHA-W-560 REAC DRAIN TANK OUTLET ISOL VLV CHA-HS-516 CHA-W-516 I.ETDOWN TO REGN HX ISOL VLV h
4 WCA-HS-62 WCA-W-62 CHW RE*IURN HDR OUTSIDE CNIHT ISOL VLV HCA-ES-4S HCA-W-45 TO RAD MON OUTSIDE CNntf ISOL VLV HCA-HS-46 HCA-W-46 FROM RAD MON OUTSIDE CNIMT ISOL VLV (Q CPA-HS-4 - CPA-W-4A,4B CNTMT ACCESS PRG UPSTR ISOL VLVS CPA-HS-2 CPA-UV-2A,2B CNTNTREFUELPRGUPSTRISOLVLVS GAA-HS-1 GAA-W-1 NITROGEN TO SIT ISOL VLV GAA-HS-2 GAA-W-2 NITROGEN TO CNTMT LP HDR ISOL VLV CL SSA-HS-203A SSA-W-203 HOT LEG SAMPLE CNnff ISOL VLV SSA-HS-204A SSA-UV-204 / - PZR SURGE "INE SMPL CNn!T ISOL VLV y, Wb eh p ~ __
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WiORX]NG COPY . F PALO VERDE NUCLEAR GENER,ATING o [ROCEDURE ( STATION MANUAL 41EP-12Z01 REVISION APPENDIX K Page 2 of 4 EMERGENCY OPERATIONS 2 Page 66 of 171 VERIFICATION OF CIAS. A TRAIN (Cont'd) AFTER HANDSVITCH DEVICE NUMBER NAME CIAS CONDITION
.SSA-RS-205A SSA-W-205 PZR STEAM SPACE SMPL CNTMT ISOL VLV ,
GRA-HS-1 GRA-UV-1 WASTI GAS EDR INSIDE CMMT ISOL VLV RDA-HS-23 RDA-W-23 CONTAINMENT SUMPS IN3IDE'ISOL VLV
. SIi-HS-70S SIi-uv-20S RECIRC SUMP i vtv g
[t *SIA-HS-709 HPA-HS-24 SIA-UV-709 HPA-UV-24 HPSI PUMP A RECIRC VLV UV-709 2 H MON VLV CLOSED
~ 2 HPA-HS-23 HPA-W-23 ,H MON RETURN VLV CHA-HS-715 CHA-W-715 RETURN TO RDT VLV W-715 SED 2
( - WORK 91G COPY u .
J ../ WORK 0MG COPY PALO VERDE NUCLEAR GENERATING $ceouse ppggg g s STATION MANUAL 41EP-1ZZ01 Page 3 of 4 REVISION EERGENCY OPERATIONS 2 Page 67 of 171 VERIFICATION OF CIAS, B TRAIN
.HANDSk' ITCH DEVICE NUMBER AFTER NAME CIAS CONDITIC HPB-HS-6 HPB-W-6 C0hT SYS B FR RECMB ISOL VLV m .HS-2 m -uV-2 c0NT SzS B SmT 1So vtv .
gsD
'PB-HS-4
. HPP -W-4 CONT SYS B TO RECMB ISOL VLV Ca -HS-S61 CH3-W-361 aEiC DRiIN TiNx OWtET IS0t vtv 4
CHB-HS-S23 CHB-W-S23 r, REGEN HX OLTLET ISOLATION VLV SGB-HS-200 SGB-HV-200 SG 1 CEMICAL INJ SGB-HS-201 SGB-HV-201 SG 2 CEMCIAL INJ WCB-ES-61 WCB-W-61 , CHV RETURN HDR'INSIDE CNTMT ISOL VLV VCB-HS-63 WCB-W-63 CHV SUPPLY HDR OtJTSIDE CVTMT IS,0L VLV g@ ECB-HS-44 HCB-W-44 TO RAD MON INSIDE CSTMT ISOL VLV HCB-HS-47 HCB-UV-47 FROM RAD MON INSIDE ChTMT ISOL VLV N14400 REV.8/02 544 A , WORKOMG COPY A ,
~ WORKING COPY PALO VERDE NUCLEAR GENERATING [ROCENRE APPENDIX K STATION MANUAL 41EP-1ZZ01 Page 4 of 4 REVISION EMERGENCY OPERATIONS 2 Page 68 of 171 VERIFICATION OF CIAS, B TRAIN (Cont'd) AFTER HANDS'a' ITCH DEVICE NUMBER NAME CIAS CONDITION CPB-ES-5 CPB-W-5 A ,5 B ChTMT ACCESS PRG DWNSTR ISOL VLVS CPS-HS-3 ' CPB-W-3A,33 ChTMT REFUEL PRG DVNSTR ISOL VLVS SED SSB-HS-200A SSB-W-200 HOT LEG SAMPLE Ch'IMT ISOL VLV CLOS? SSB-HS-201A SSB-UV-201 PZR SURGE LINE SMPL ChTMT ISOL VLV
/
SSB-HS-202A SSB-W-202 PZR STEAM SPACE SMPL ChTMT ISOL VLV OS
!r GRB-HS-2 GRB-W-2
- WASTE GAS HDR OUISIDE ChTMT ISOL VLV RDB-HS-24 RDB -W-24 COSTAINMEhT SUMPS OUISIDE ISOL VLV RDB-HS-407 RDB-W-407 ChTMT RADVASTE SUMP OUILET VLV CHB-HS-924 CHB-W-924 LETDOWN LINE SAMPLE
%- =
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yf0RK]MG COPY PALO VERDE NUCLEAR GENERATING g cewas ! ppgg9xx , STATION MANUAL 41EP-1ZZ01 Page 1 of 9 REVISION EMERGENCY OPERATIONS 2 Page 56 of 171 NOTE If total HPSI, pump flow is less than 212 gps, consideration should be given to
~
stopping 1 pump when criteria can be met. VERIFICATION OF SIAS. A TRAIN
~
HANDSVITCH DEVICE NUMBER AFTER NAME SIAS CONDITIC - DGA-HS-1
- PEA-G~1 DIESEL GENERATOR A ST
, NHN-M71
, TRIPPED ,.
' NHN-M19 N f _
TRIPPED 4 - HJA-HS-81 HJA-J01A BATTERY ROOM A ESS EXH FAN
- m3 STARTED /
/
HJA-HS-83 HJA-J01B N' BATTERY ROOM C ESS EXH FAN
- - STARTED HJA-HS-97 HJA-M53/M54/M55 ESF SWGR A/EQPT ROOMS SMOKE DMPRS '
_ --3f NORM MODE m, ,. HJA-RS-96 HJA-M34 SVGR AREA RET DMPR TO ESS AHU A/ NORMLOSED HJA-HS-67
%NTN C HJA-ZO3 CONT BLDG EST SWGR RM ESS AHU FAN A T STARTED)
HJA-HS-10 HJA ,M38,M59 7 - COMM EQPT ROOM ISOL DAMPERS '
- CLOSED y .
HJA-HS-106 HJA-M23 ESF SVGR A NORM AHU SPLY ISOL DMPR CLOSED - HJA-HS-39 HJA-M56/M37 CO.NT ROOM SMOKE ISOL DAMPRS CLOSE k HJA-HS-41 % - HJA-M15/M16 CR KITCHEN / TOILET EXH FAN ISOL DMPRS CLD-V10RK3NG COPY ,e _
V10RX]NG COPY g PALO VERDE NUCLEAR GENERATING I @caouns q STATION MANUAL 41EP-1ZZ01 APPENDIX J Page 2 of 9 REVISION EMERGENCY OPERATIONS 2 Page 57 of 171 VERIFICATION OF SIAS. A TRAIN (Cont'd)' HANDSVITCH DEVICE NUMBER AFTER NAME STAS CONDITIC HJA-HS-61 HJA-M25/M28 CONTROL BLDG ESS ISOL DMPRS ) HJA-HS-28 HJA-F04, CR ESSTNTIAL AHU FAN A STARTED HJA-HS-7 HJA-M01/M52 CONT RM NORM AHU ISOL DMPRS CLOSE HJA-HS-38 HJA-M36,M51, \ M62,M66 CONTROL BLDG ESS ISOL DMPRS ESS MODE-M36/M51/M62/M66 HJA-HS-37 HJA-M03 CohT RM ESS AHU B OSA IhTAKE DAMPER N HJA-HS-36 HJA-M02 C0hT RM ESS AHU A OSA IhTAKE DAMPER OPEN HJA-HS-133 FAN A
, ESF DC EQUIP RM ESS AHU FAN A . k ARTED HAA-HS-112 HAA-M03 AUX BLDG PMP RM EXH ISOL DAMPER E l
HAA-HS-114
. AUX BLDG BASEMEhT PMP RM SPLY/EXH ISOL DMPRS SPLY HFA-HS-62 HTA-J01,M05,M06 AUX BLDG ESS AFU A STARTED HFA-HS-64 HFA-J01,M05,'M06 FUEL BLDG ESS AFU A ST ECA-HS-1A ECA-P01.E01 ESS CHLR/CHLD VTR PMP A STARTED
~~,
/ EVA-HS-1 EVA-Pol PUMP A Pol I STARTED EWA-HS-65 EVA-UV-65
\
CROSS-TIE VLV TO NCW UV-65 W24400 MVtitt $444 WORX]NG COPY ** ; kn.
WOP.X]NG C:OPY {( PALO VERDE NUCLEAR GENERATING [CEDURE APPENDIX J STATION MANUAL 41EP-1ZZ01 Page 3 of 9 REVISION EERGENCY OPERATIONS 2 Page 58 of 171 _ VERIFICATION OF SIAS, A TRAIN (Cont'd)
.HANDSWITCH DEVICE NUMBER AFIT.R NAME i' STAS CONDITIC
, EVA-HS-145 EVA-W-145
- .r CROSS-TIE VLV TO NCW W-145 CLOSED SPA-ES-1 SPA-Pol PUMP A Pol SIA-HS-635 SIA-W-635 LPSI EADER A TO RC LOOP 1A VLV SIA-HS-645 SIA-W-645 LPSI EADER A TO RC LOOP IB VLV ,
. SIA-HS-637 SIE-W-637 HPSI EADER A TO RC LOOP 1A VLV SIA-HS-647 SIA-W-647 HPSI HEADER A TO RC LOOP IB VLV SIA-HS-617 SI A-W-617 HPSI HEADER A TO RC LOOP 2A VLV SIA-HS-627 SIA-HS-627 HPSI HEADER A TO RC LOOP 2B VLV .
N SIA-HS-1 SIA-P02 HPSI PUMP A
, , TAR SIA-HS-3 SIA-P03 Co.NTAINMIST SPRAY PUMP A STARTED
~%
SIA-HS-3 SIA-Pol LPSI PUMP A h
, STARTED SIA-HS-634 ,SIA-W-634 SIT 1A OUILET TO RC LOOP 1A VLV OPE'N .
SIA-HS-644 SIA-W-644
- SIT 1B OUTLET TO RC LOOP IB VLV OPEN
( SIA-HS-682 SIA W-682
~
MISC DRAIN HEADER TO RDT VLV
. Cgo ,
CHA-HS-516 CHA-W-516 LE30VN TOpREGEN g yHX ISOL VLV
,, j . s a a g
. a . y,g 3
Pmemo prv.asar see A ' y- - m
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@CEWRE 41EP-12201 APPENDIX J Page 4 of 9 REVISION EMERGENCY OPERATIONS 2 Page 59 of 171
- VERIFICATION OF SIAS, A TRAIN (Cont'd)
HANDS'w' ITCH DEVICE NUMBER AFTER NAME - SIAS CohTITIO
. %. RCA-HS-100-4 BACKUP HEATERS BANK B01/B09/A14 , TRIPPED CTA-ES-15 CTA-P01 CONDENSATE XFR PUMP A STARTED WCA-HS-1A WCA-E01A 4
NORM CHLR A/ CIRC A TRIPPED 1 HCA-HS-11 HCA-A01A CNIMr NORMAL ACU FAN A , TRIPPED
, HCA-HS-13 HCA-A01C ENTMTNORMALACUFANC TRIPPED HCA-HS-49 HCA-A02A,'A02C CEDM ACU FANS A/C TRIPPED SGA-ES-500P SGA-W-500P SG 1 COMMON UPSTR ISOL VLV
. CLOSED SGA-HS-500S SGA-W-500S SG 2 COMMON DWSTR ISOL VLV
~
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WORK 0MG COPY . PALO VERDE NUCLEAR GENERATING @caouse APPENDIX J b STATION MANUAL 41EP-1Z201 Page 5 of 9 REVISION EMERGESCY OPERATIONS 2 Page 60 of 171 VERIFICATION OF SIAS. B TRAIN HANDSWITCH AFTER DEVICE NUMBER NAME SIAS CONDITIO' DGB-HS-2 PEB-G02 DIESEL GENERATOR B - START NHM-M72 - TRIPPED NHN-M20 TRIPPED HJB,-HS-82 HJB-J01B BATTERY ROOM B ESS EXH FAN , STARTED
. HE MIS-84 HJB-J01A BATTERY ROOM D ESS EXH FAN STARTED k HJB-HS-68 HJB-ZO3 CONT BLDG ESF SWGR RM ESS AHU FAN B STARTED HJB-HS-62 HJB-M31/M34 C0hT BLDG NORM /ESS ISOL DMPRS ESSENT M38/M58/M66 MODE HJB-HS-104 HJB-M28/M32/MS2 EST SVG B/EQPT ROOMS SMcKE DAMPERS NORM MODE HJB-HS-38 HJB-M56/M57 C0hT ROOM SMOKE ISOL* DAMPERS CLOSED HJB-H5-40 HJB-M23/M24 CR KITCFIN/ TOILET EXH FAN ISOL DMPRS CLOSED HJB-HS-11 HJB-M10/M13 CC D1 EQPT ROOM ISOL DAMPERS
- CLOSED HJB-HS-29 HJB-F04 CR ESSEhTIAL Alm FAN B STARTED HJB-HS-35 HJB-M03 C0hT R'1 ESS AIN A OSA IhTAKE DAMPER OPEN HJB-HS-34 HJB-M02 CohT RM ESS A]m A OSA IhTAKE DAMPER OPEN WORX]NG COPY -
WOEGNG COPY . PALO VERDE NUCLEAR GENERATING $etouse pp g9Ix , STATION MANUAL 41EP-12201 Page 6 of 9 REVISION EMERGENCY OPERATIONS 2 Page 61 of 171 VERIFICATION OF SIAS, B TRAIN (Cont'd)
"HANDSVITCH AITER DEVICE NUMBER NAME SIAS CONDITIO' S~ HJB-MS-8 HJB-M01/M55 CONT RM NORM AHU ISOL DNPERS CLOSED HJB-ES-136 HJB-ZO4 'EST EQUIP RM E'SS ANU FAN B STARTED HAB-HS-113 HAB-M03 AUX BLDG PMP RM EXE ISOL DAMPER
- CLO3ED HAB-HS-115
- AUX BLDG BASEMENT PUMP RM SPLY/EXE , CLOSED ISOL DAMPERS f
9 HFB-HS-63 HFB-J01 M05/M06 AUX BLDG ESS AFU B Q STARTED IdB-HS-65 HFB-J01 M05/M06 FUEL BLDG ESS AFU B STOPPED ECB-IkS-2A ICB-E01,P01 ESS CHLR/CHLD WTR PMP B . STARTED EWB-HS-2 EWB-Pol PUMP B Pol STARTED SPB-HS-2 SPB-Pol PUMP B P01 STARTED SIB-MS-322 SIB-W-322 HOT LEG INJ A CECK VLV LEAKOFF VLV CLOSE SIB-HS-332 SIB-W-332 HOT LEG INJ B CECK VLV LEAKOFF VLV - CLOSE SIB-HS-615 SIB-W-615 LPSI EADER B TO RC LOOP 2A VLV OPEN SIB-HS-625 SIB-W-625 LPSI IEADER B ,TO RC LOOP 2B VLV OPEN L ' SIB-HS-636 SIB-W-636 HPSI EADER B TO RC LOOP 1A VLV OPEN WORXWG COPY v.. :--- : L L
WORX]NG COPY - PALO VERDE NUCLEAR GENERATING C s STATION MANUAL [ROCEDURE o 41EP-1ZZ01 gppgg9 x , Page 7 of 9 REVISION EERGENCY OPERATIONS 2 Page 62 of 171 VERIPICATION OF SIAS, B TRAIN (Cent'd) HANDS'n' ITCH AFTER DEVICE NUMBER NAME SIAS CONDITIO?
% SIB-HS-646 SIB-W-646 HPSI EADER B TO RC LOOP 1B VLV OPEN SIB-HS-616 SIB-W-616 HPSI HEADER B TO RC LOOP'2A VLV OPEN SIB-HS-626 SIB-HS-626 HPSI EADER B TO RC LOOP 2B VLV OPEN
- SIB-HS.-J _ ,. _ SIB-P02 HPSI PUMP B STARTED
, SIB-HS-6 SIB-P03 COSTAINMEhT SPRAY PUMP B
' STARTED
[( SIB-HS-4 SIB-Pol . LPSI PUMP B l STARTED SIB-HS-614 SIB -W-614 SIT 2A OUTLET TO RC LOOP 2A VLV OPEN SIB-HS-624 SIB-W-624
, SIT 2B OUTLET TO RC LOOP 2B VLV OPEN SIB-HS-631 SIB-W-631 SIT 14 FILL AND DRN VALVE -
CLOSED SIB-HS-641 SIB-W-641 SIT 1B FILL AND DRN VALVE CLOSED SIB-HS-611 SIB-W-611 SIT 2A FILL AND DRN VALVE CLOSED SIB-MS-621 SIB-W-621 SIT 2B FILL AND DRN VALVE - CLOSED SIB-HS-638 SIB-W-638 SI LINE TO RC LOOP 1A DRAIN VLV W-638 CLOSED SIB-HS-648 SIB-W-648 SI LINE TO RC LOOP IB DRAIN VLV UV-648 CLOSED SIB-HS-618 SIB-UV-618 ' SI LINE TO RC LOOP 2A DPAIN VLV UV-618 CLOSED
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. VERIFICATION OF SIAS. B TRAIN (Cont'd)
HANDSWITCH DEVICE NUMBER AFER NAME SIAS CONDITIO: w SGB-HS'-222 SGB-UV-222 SG 2 COLD LEG BLODN UPSTR VLV CLOSED-SIB-HS-710 SIB-UV-710 HPSI PUMP B RECIRC VLV UV-710 CLOSED
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. Statecents should include the plant conditions prior to the trip, your indications that a problesexisted your actions as a result of those indications. noted equipment identified procedure malfunctions or inadequacies, and any deficiencies.
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To: "" M ' ( September 18, 1985 m d/M /4*e ANPP-33487-EEV3/WFQ C= , Mr. John 3. Martin, Regional Administrator Office of Inspection and Rafora.eaant U.S. Nuclear Eagulatory Commission Region V 1450 Maria Lane, Suite 210 ' Walnut Creek, CA 94596-5368
Subject:
Palo Verde Nuclear Generating Station (PVNGS) ' Unita 1, 2 and 3 Docket Nos. STN50-528 (License NPF-41)/329/530 Auxiliary Pressuriser Spray Pile: 85-056-026; G.1.01.10 References Confirmatory Action Intter from J. 3. Martin, NRC, to E. E. Van Brunt, Jr., ANPP, dated September 17, 1985 Dear Mr. Martin On September 17 1985, a conference call was bald between representatives of NRR, Region V and ANPP to discuss the unscheduled reactor shutdown of September 12, 1985 and its impact on the Chemical and Volume control Systema j (CVCS) design and operation. Daring this call, the following NRC concerns t related to the charging and auxiliary pressuriser spray were identified
- 1) Tht. non-IE Motor Control Centar (M-72) associated with motor-operated valves CH-501 and 536, is shed from the Class IE Electrical Bus on a Safety Injaction Actuation Signal (SIAS) and is not automatically resequenced outo the Class IE Bus. To reestablish remote manual control of valves CH-501 and 536 operator action outside of the control room is required (Imad Center panel located in the Auxiliary Building).'
- 2) The failure of non safety related Volume Control Tank (VCT) level instrumentation, could cause maloperation of the charging pumpe.
Specifically, the faulty instrument may provide a reading which would indicate higher than the actual level in the VCT. This would l lead to a loss of suction, if the VCT was eventually drained, and gas binding of the charging pumps could occur due to the hydrogen overpressure in the VCT. l 1
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Mr. John 3. Martin, Regional Administrator U.S. Nuclear Regulatory Commission ANPP-33487-EEV3/WFQ l September 18, 1985 Page 2 As discussed, ANpP evaluated the design and licensing basis', for the charging and auxiliary pressuriser spray, to determine the impact of the above described concerns. The result showed that use of the auxiliary pressuriser spray within 30 minutes of an initiating event, was assumed only for the PVNGS-specific Steam Generator Tube Rupture (SGT1) with a loss-of-offsite power and a full-open failed staospheric dump valve on the affected steam generator. For other event scenarios, only those which assume loss-of-offsite power, assume the operation of the auxiliary pressuriser spray. For these events, after the plant has stabilised and the accident has been aitigated, auxiliary spray is used to depressurise the reactor coolant system to allow entry into shutdown cooling as part of the post-accident recovery. As an interia resolution of the NRC concerns, ANPP proposes the following s teps:
' 1) The appropriate PVNGS operating procedures will be. changed to instruct the control roca operators to promptly switch the charging pump suction from the Volume Control Tank (VCT) to the Refueling Water Tank (RM), upon a loss-of-offsite power. This is done from the control room, by opening CH-536, to allan the RW, and by closing CH-501, to isolate the VCT.
l
- 2) A preventive maintenance (PM) procedure has been implemented to inspect the 7CT level instrument reference leg, and to fill, if necessary, on a weekly basis. 2his will provide assurance that the level instrucent will operate properly. In addition, a determination will be made if any additional surveillance or calibration to this instrument can be implemented without removing it from service.
l The changes to the operating procedures will assure alignment of the charging l pumps to the RWT, a safety grade source of suction, and provide early VCT isolation if a subsequent SIAS were to occur. The additional FM on the VCT level instrument will provide added assurance the operators have valid VCT level information, and that the VCT will isolate properly on low level. These measures will remain actions described in effectparagraph. in the following until this issue is resolved based on the l O
1 Mr. John B. Hartin, Regional Administrator U.S. Nuclear Regulatory Commission l ANPP-33487-EEYB/WFQ l September 18, 1985 l Page 3 l l Beyond the interia, ANPP proposes, to perform, in parallel,' (1) a reevaluation of the PVNGS specific SG11L accident analysis to determina if acceptable offsite does results are achieved assuming the auxiliary pressuriser spray is not available and (2) prelt=fn=ry engineering to establish the scope of work
- necessary to potentially upgrade the auxiliary pressuriser spray capability to
. meet safety grada design criteria should the SGTIL reevaluatin show that auxiliary spray is required to obtain acceptable results. By October 18, 1985, we will submit the results of our revised analysis, and if shown to be necessary by the revised analysis, a description of the design modifications for the auxiliary pressuriser spray upgrade, a schedule for implementation of the modifications, and a justification for continued operation if modifications are required.
As requested by the NRC staff, the loade fed by the non-IE Motor Control Center (M-72) are shown on the attached. , We believe these proposed actions adequately addrese the concerns of the ! referenced letter, and we anxiously await your concurrence. Very truly yours. [E b M I. E. Van Brunt, Jr. Executive Vice President ANPP. Project Director EEVB/TFQ/dla Attachment . cet C. W. Knighton (all w/s) R. P. Zimmerman A. C. Gehr ' E. A. Licitra l l l
4 . ATTACIDGDIT A 480V Non Class IE Motor Control Centsr E-N196-M72 The following non class IE loads are fed from HCC 72 and are shed on . SIAS (Raference Single Line Diagram 13-E-NHA-072 Rev. 4) Position Isad 1 - (inconing Feeder) 2 - Containment Normal ACU-B Discharge Damper (.13 hp) 3 - Containment Normal ACU-D Discharge Damper (.13hp) ; 4 - Backup Protection Breaker for positions 2 and 3 5 - spare - 6 - Space 7 - Space 8 - Volume Control Tank Outlet valve (W-501) (.33 hp) 9 - Refueling Water Tank Cravity Line to Charging' Pump Valve (HV-336)(.7 hp) 10 - Space 11 - Space 12 - Space 13 - Backup Protection Breaker for
- Position 14 14 - Pressuriser Normal cooling Fan (A063) (10 hp) 15 - space s
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- r. WALNUT $REEIC,CALIFOMNta 84Ess S$P 171985
- 1 Docket'No. 50-523 CONFIRMITORY ACTION LL'TTER s
Licana'No.NPf-y s' y . ~. . Arisona Nuclear Fever Project **
- l
' Post Office Boy 52034 '
Phoamir Aris 85072 2034 '- . Attoptdans' Mr. E. E. Va'n Brust i r y utive Vice Pr subject: Rattrrn of Palo Verde'l to Yawer Operations from Current Outage
, e; Centlemen: , ;
This refers to the'discusa!sson'hy tala$ hone on September .16,1985 between . Mr. J. L. Crews of this offich and Mr; J. G. Haynes, relating to the unscheduled reactor shutdown of .Palo Verde on September 12, 1985. ' i Mr. Haynes stated that prior to restart of the Unit from its current i shutdown, you will ensure that the issue of appropriate design criteria (in particular, single failure criteria) for the auxiliary spray system is resolved to the satisfaction of the NEC staff.
! T If our understanding concerning your r osed actions, as sumasarized above, is not correct, you should promptp otif this office in writing.
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J 3. Martin Regional Adminiatrator I Distribution: Standard * [
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,#g WALNUT CREEK, CALIFORNIA 9400s
...ee i SEP 201985 ;
Docket No. 50'-528 CONFIRMATORY ACTION LErrER_ License No. NPF-41 . Arizona Nuclear Power Project Post Office Box 52034 Phoenix, Arizona 85072-2034 Attention: Mr. E. E. Van Brunt, Jr. Executive Vice President
Subject:
Return of Palo Verde 1 to Power Operations from Current Outage Centlemen: In my letter. to you of September 17. 1985, I confirmed Arizona Nuclear Power Project's (ANFP) agreement that prior to restart of the Unit from its current shutdown; you would ensdre that the issue of appropriate design criteria for theauxiliaryspraysystemwasresolvedtothesatisfactionoftheNRCstaff. g By letter dated September 18, 1985, you discussed the unscheduled shutdown nf September 12. 1985 and briefly addressed NRC concerns relating to the auxiliary spray system and interfacing equipment. In response to these concerne, yod proposed certain short, term compensatory measures for continued operation af ! t'ae facility. . In a meeting with the NRC staff on September 20, 1985. you provided a more in-depth description of the Septanbar 12, 1985 event, including the sequence of events, design characteristics of the auxiliary spray system, and a further discussion of the short term compensatory measures for continued operation. ' At the conclusion of the meeting. Mr. J. Haynes. Vice President for Nuclear Production. ANPP cosumitted to the following short term compensatory measurest i (1) , Monitor the reference leg of the volume control tank level indicator on a daily basis. If the data obtained justify a less f requent ' monitoring interval, ANPP may propose a different interval to the NRC staff. (2) Revise the appropriate procedures to require elignment of'the refueling water tank to charging pump suction promptly on loss of offsite power... (3) Institute procedural cautions on restart of the charging pumps. l \ . (c.pn7/ W-40 [b - lo E00 Asa *0H s No!938 34Nin IP:st
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, (4) Examine the post-trip review process in light of the September 12 1985 1 event to assure that off-normal events are adequately evaluated, particularly with respect to their potential safety significance. (5) Examine the process for vendor reviews of the remaining power ascension tests to assure that, for equipment particularly senegive to the test being conducted, appropriate vendor input tas been provided in the test development. (6) Review the shift complement for the remaining power ascension tests to determine if additibnal staffing may be appropriate.
- On the basis of the above commitments, we are satisfied that adequate short-term compensatory measures are in place for restart of the Unit from its current <
shutdown. Long term asseures to assure the continued reliability of the auxiliary spray system will be the subject of future correspondence. If our understanding concerning the above measures is not correct. you-should promptly notify this office ita writing. ' W . J. B. Martin . [. Regional Administrator ; Distribution: $ 4 Standard . J. Axelrad. IE s { J. Lieberman, OELD 1
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