ML20215J845
| ML20215J845 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/04/1987 |
| From: | Mark Miller Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8705080279 | |
| Download: ML20215J845 (54) | |
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Docket No.: 50-424 APPLICANT: Georgia Power Company FACILITY: Vogtle, Unit 1
SUBJECT:
SUMMARY
OF MEETING HELD ON APRIL 28, 1987 TO DISCUSS V0GTLE STARTUP HISTORY-The staff met with the licensee at the Vogtle site on April 28, 1987, to discuss the Vogtle startup history. The visit was a routine post-full power licensing visit but the staff was particularly interested in the licensee's discussion of the relatively high number of reactor trips and engineered safety feature (ESF) actuations. Participants are listed in Enclosure 1.
The licensee's slide presentation is included as Enclosure 2. At the time of the meeting, the unit was performing power ascension testing at the 75% power plateau. Convr.ercial operation is estimated for late May.
The licensee discussed its corrective actions to recent secruity problems.
These actions included establishing a security task force, daily management security meetings, added engineering support, and enhanced training for the security staff and all site employees. The licensee stated that daily security alarms have decreased to about 400 which is down from a peak of 1100.
While this progress represents a significant reduction, the licensee's goal is no more than 200 security alarms per day. The licensee indicated that lessons learned during implementation of the Unit 1 security system will be factored into the Unit 2 security program, and security will be included in the Unit 2 Readiness Review effort.
The licensee discussed problem areas and highlights of Each of the four phases of the startup testing program (fuel load, precritical, low power physics, and power ascension). During low power physics testing, the unit experienced a trip on high positive rate due to an overly conservative trip setting from Westinghouse to which the licensee had added additional margin. After this trip, the licensee incorporated revised Westinghouse data which has prevented recurrence of this type of trip.
The licensee is approximately 60% complete with the power ascension testing.
Between March 20 and April 11, the unit has experienced 8 reactor trips on 10-10 steam generator level. Besides some limited personnel errors (operators and technicians), the cause of these trips has been attributed to lack of plant-specific setpoints and needing additional tuning of the steam generator level and steam dump controllers. The utility indicated its belief that these items have been corrected. The lessons learned in tuning the Unit I controllers will be applied to Unit 2 startup.
M F
As of April 28, the utility stated that it had received 16 ESF actuations separate from a reactor trip.* The most prevalent types of ESF actuations are main feedwater isolation and control room isolation. Each control room isolation has been caused by failure high of a control room inlet radiation monitor. The utility has had limited success in resolving the continuing recurrence of actuation of the radiation monitor.
Prior to the meeting, the resident inspectors had informed the licensee that it should report control room isolations caused by actuation of a chlorine detector. At the meeting, the staff emphasized its position that isolation of the control room irrespective of the initiating event is considered an ESF actuation and should be reported as such. The licensee agreed to abide by the staff's position.
In closing, the staff comended the licensee for a thorough, well-prepared presentation. While interface with vendors and other utilities possibly should have occurred sooner on some recurring events, the staff concluded that the licensee appeared to be taking adequate corrective actions to address problems experienced during the Vogtle Unit I startup program.
% he b Melanie A. Miller, Project Manager Project Directorate II-3 Division of Reactor Projects I/II
Enclosures:
As stated cc: See next page
- This number differs from the NRC number in that the staff also includes a fuel handling building isolation and 3 control room isolations initiated by a chlorine detector as ESF actuations.
4 Mr. J. P. O'Reilly Georgia Power Company Vogtle Electric Generating Plant cc:
Mr. L. T. Gucwa Resident Inspector Chief Nuclear Engineer Nuclear Regulatory Commission Georgia Power Company P. O. Box 572 P.O. Box 4545 Waynesboro, Georgia 30830 Atlanta, Georgia 30302 Mr. Ruble A. Thomas Deppish Kirkland, III, Counsel Vice President - Licensing Office of the Consumers' Utility Vogtle Project Council Georgia Power Company / Suite 225 Southern Company Services, Inc. 32 Peachtree Street, N.W.
P.O. Box 2625 Atlanta, Georgia 30303 Birmingham, Alabama 35202 James E. Joiner Mr. Paul D. Rice Troutman, Sanders, Lockerman, Vice President & Project Director & Ashmore Georgia Power Company Candler Building Post Office Box 299A, Route 2 127 Peachtree Street, N.E.
Waynesboro, Georgia 30830 Atlanta, Georgia 30303 Danny Feig Mr. J. A. Bailey 1130 Alta Avenue Project Licensing Manager Atlanta, Georgia 30307 Southern Company Services, Inc.
P.O. Box 2625 Carol Stangler Birmingham, Alabama 35202 Georgians Against Nuclear Energy 425 Euclid Terrace Ernest L. Blake, Jr. Atlanta, Georgia 30307 '"
Bruce W. Churchill, Esq.
Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
l Washington, D. C. 20037 l
Mr. G. Bockhold, Jr.
Vogtle Plant Manager Georgia Power Company Route 2, Box 299-A Waynesboro, Georgia 30830 Regional Administrator, Region II
! U.S. Nuclear Regulatory Commission l
101 Marietta Street, N.W., Suite 2900 l
Atlanta, Georgia 30323 Mr. R. E. Conway Senior Vice President and Project Director Georgia Power Company Rt. 2, P. O. Box 299A Waynesboro, Georgia 30830
4 Enclosure 1 Participants NRC GEORGIA POWER COMPANY 1T31. Youngblood J. O'Reilly A. Gibson G. Bockhold V. Brownlee R. Thomas M. Miller T. Greene L. Crocker M. Bellamy J. Mauck A. Mosbaugh R. Dennig W. Burmeister J. Rogge R. Lide R. Schepens K. Holmes C. Burger M. Craven C. Belflower SOUTHERN COMPANY SERVICES L. Gucwa J. Bailey W. Burns M. Howard D. Smith C. Hayes H. Handfinger i
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- AGEbOA TIME ITEM NAME 8:30 AM NRC MANAGEMENT MEETS WITH RESIDENT INSPECTORS IN ADMINISTRATION BUILDING SMALL CONFERENCE ROOM 7
j 9:00 AM INTRODUCTIONS J.P. O'REILLY
, 9:15 AM PLANT VOGTLE OVERVIEW G.BOCKHOLD
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W.L. BURMEISTER o NUMBER / NATURE OF TESTS D o PROBLEMS / CORRECTIVE ACTIONS L o SUCCESSES AND COMPLETION OF TEST PROGRAM 10:40 AM RPS/ESFAS ACTUATIONS W.F. KITCHENS
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! 11:55 AM MANAGEMENT PHILOSOPHY G.BOCKHOLD l
12:00 AM WORKING LUNCH i a NRC COMMENTS AND QUESTIONS
- o CLOSING REMARKS J.P. O'REILLY i
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PLANT V0GTLE - NUCLEAR OPERATIONS PROJECTED UNIT i STAFFING PERSONNEL ,
f 2400 - ~ TOTAL STAFFING j; 2300 -
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STARTUP TESTING PROGRAM (66) ;
FUEL LOAD (5) - LOAD FUEL AND PERFORM FINAL' FUEL POSITION VERIFICATION.
PRECRITICAL (27) - ASSEMBLE REACTOR VESSEL, HEATUP REACTOR COOLANT SYSTEM AND PERFORM TESTS AT VARIOUS ,
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I LOW POWER PHYSICS (10) - ACHIEVE CRITICALITY IN A CONTROLLED MANNER AND PERFORM TESTS TO VERIFY REACTOR CORE ;
PERFORMS AS PREDICTED BY THE NUCLEAR FUEL ;
DESIGN REPORT.
i POWER ASCENSION (24) - RAISE REACTOR POWER AND TEST PLANT SYSTEMS l I
AND INTEGRATED PLANT RESPONSE AT POWER W PLATEAUS OF 5%, 30%, 50%, 75%, 90% AND 1001
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. f {- FUEL TRANSFER SYSTEM INSTALL DESIGN MODIFICATION O
SIGMA REFUELING MACHINE FUTURE REFUELINGS WILL BE PERFORMED UNDER "YET" CON-D DITIONS. TUNE SIGMA CAMERA.
'E li I HIGHLIGHTS MOVEMENT OF 193 FUEL ASSEMBLIES INTO REACTOR VESSEL SAFELY
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J ALL INCORE DETECTOR DRIVE PATHS WERE ACCESSIBLE DURING FLUX n MAPPING.
PHYSICS DATA COMPARED WELL TO PREDICTED VALUES IN FUEL DESIGN REPORT.
" f OUTAGE FROM MODE 2 DOWN TO COLD SHUTDOWN AND BACK UP TO MODE 2 CONDUCTED EXPEDITIOUSLY AND SUCCESSFULLY.
-~ _
^ -
. . _ _. _ __ ,.1 _ . ; . __ ._.. , u . _ . n.._-. . 2:, . _
POWER ASCENSION SEQUENCE ypu.60x & J W P~
c PROBLEM AREAS CORRECTIVE ACTIONS J REACTOR TRIPS ON STEAM CHANGED TESTING STRATEGY TO
- GENERATOR LOW LEVEL PERFORM TUNING OF S/G LEVEL AND STEAM DUMP CONTROLLERS I" PRIOR TO TESTING. -
D D HIGHLIGHTS LOSS OF OFFSITE POWER SUCCESSFULLY PERFORMED D W&P y M& wh
- h. .
J m
J
'l
-- + .,, - - - - - - , - - - . , . , , , , , _ . . _ - - . - . . . . - , , , . - - _ - - , , _ , - - - - . , - - - -- - - - . - - -
.= . . -
..=
1 1
- l g NRC INSPECTIONS
, FUEL LOAD: NO PROBLEMS IDENTIFIED OBSERVED PRACTICES TO BE I SAFE AND THOROUGH 1 i.
PRECRITICAL: IFI TO IMPROVE RCS LEAK M RATE SURVEILLANCE ACCURACY.
~
I
) INITIAL CRITICALITY i AND LOW POWER: NO PROBLEM IDENTIFIED
, OBSERVED PRACTICES TO BE SAFE AND THOROUGH t
_ POWER ASCENSION: OBSERVED LOSS OF OFFSITE i POWER TEST, NO PROBL' EMS
^i" IDENTIFIED.
- l. ~1 OBSERVED REMOTE SHUTDOWN l
" TEST. REQUEST MADE TO
. - PERFORM PARTIAL RETEST l_ USING ATMOSPHERIC RELIEFS.
/
l w asat i
4 4 p%%n ws a%a+
y%-
m 4
E
---. .. ________._.m_.. .--__,___._,_.._.m..,_._,____.,.___,_,_._____m., ____, , _ , _ _ _
REMAINING TESTING u
POWER COEFFICIENT 75% POWER: AFD FINAL CALIBRATION
~
4 10% LOAD SWING d b0 k 50% LOAD REDUCTION L
lt 7 CALORIMETRIC l 90% POWER: POWER COEFFICIENT ll ,
CALORIMETRIC q 100% POWER:
i S/G MOISTURE CARRYO 10% LOAD SWING 5~ 50% LOAD REDUCTION
' FULL POWER TRIP NATURAL CIRCULATION DEMONSTRATION l ;
I same O'UC )
l' l
l i
r 1
m__ < .m-..
, e a
RPS ACTUATIONS STATUS L
1 HIGH FLUX RATE TRIP 8 SG LO LO LEVEL TRIPS 9 TOTAL UNPLANNED REACTOR TRIPS 8
g m
9
ESF ACTUATIONS STATUS u
$. 1 AFW AUTO ACTUATION 3 CONTAINMENT ISOLATIONS 6 CONTROL ROOM ISOLATIONS
$ 11 (6)* FEEDWATER ISOLATIONS 21 (16)* TOTAL ACTUATIONS 2
- 5 FEEDWATER ISOLATIONS WERE IN CONJUNCTION WITH A REACTOR TRIP j
r l 4 % / / *W Y fus.ad (L J DeU t
4
. ~ . - .
VEGP FEEDWATER PIPING STEAM GENERATOR,.
8" _ m 16" t -
, N /
{
r-
- i. IRC 1RC ORC ORC
~
r r
/ k' f BYPAS$ 8" FE EDWATER M AIN 16" ISOLATION FEE 0 WATER 4" AUXILIARY ' ISOLATION FEEDWATER LINE ~' f / VALVE 7 ""
g
. 6"OYPASS i g
. FEE 0 WATER LINE l GRADE PIPING
,, ((:/, f f FORGING r ov
%g;g.N
' 831.1 g ,J, PIPING SYPASS 4" FEE 0 WATER F> I CONTROL VALVE l / 6' ' r@4 '
(uy.tka '
, 1s" 8"
\ MAIN 18" FEE 0 WATER CONTROL VALVE 4 >
4e
.~.---m-y_,-- ,,..--.,m .x_.__m. - - _ _ - - - _ - - - - - _ - - , - . , . - _ . - - - -
. . . . . = .
FEEDWATER ISOLATION u
~
SSG HI HI LEVEL (2/4 ON 1 SG)
SSI SIGNAL eREACTOR TRIP AND LO T-AVE go
'T ACTIONS GSG HI HI LEVEL ALSO TRIPS BOTH MAIN FEED PUMPS G CLOSES MFRV'S
{ NL f) 9 '
- e CLOSES BFRV'S fg3-1 hS h
i
!. 8" Agp AJs>
. O CLOSE'S MFIV'S FAr OCLOSES BFIV'S S y *" h AT / '
l l
t
. . I r
1 RPS ACTUATIONS EVENT DATE
. REACTOR TRIP ON POSITIVE RATE 3/19/87 4
REACTOR TRIP ON STEAM GENERATOR LO-LO LEVEL 3/20/87
~
REACTOR TRIP ON STEAM GENERATOR LO-LO LEVEL 3/21/87
- REACTOR TRIP ON STEAM GENERATOR LO-LO LEVEL 3/23/87 REACTOR TRIP ON STEAM GENERATOR LO-LO LEVEL 3/24/87
}
[ REACTOR TRIP ON STEAM GENERATOR LO-LO LEVEL 3/27/87 l REACTOR TRIP ON STEAM GENERATOR LO-LO LEVEL 4/05/87 REACTOR TRIP ON STEAM GENERATOR LO-LO LEVEL 4/10/87 REACTOR TRIP ON STEAM GENERATOR LO-LO LEVEL 4/11/87 i
s j
...c__u = -
ESF ACTUATIONS u
EVENT DATE AFW ACTUATION DUE TO MFP TRIP & PERSONNEL 2/25/87 ERROR-FEEDWATER ISOLATION FROM SG HI-HI LEVEL /
AFW MANUAL CONTROL & PERSONNEL ERROR 3/01/87 FEEDWATER ISOLATION FROM SG HI-HI LEVEL /
AFW MANUAL CONTROL & PERSONNEL ERROR 3/06/87
~
FEEDWATER ISOLATION, AFY ACTUATION ON SG HI-HI LEVEL 3/23/87 FEEDWATER ISOLATION, AFY ACTUATION ON SG HI-HI LEVEL 3/25/87
}
FEEDWATER ISOLATION, AFY ACTUATION ON SG HI-HI
{ LEVEL 3/26/87
- FEEDWATER ISOLATION, ON HI-HI SG WATER LEVELS 4 /13/ 8 7 l
l l
l
~
AFW ACTUATION t M MOTOR DRIVEN' PUMPS GSG LO LO LEVEL (2/4 ON 1 SG)
STRIP OF BOTH MAIN FEED PUMPS OSI SIGNAL SBLACK0UT SIGNAL
{ '
, # MANUAL TURBINE DRIVEN UMPS
] GSG LO LO LEVEL (2/4 ON 2 SG'S)
S BLACK 0UT SIGNAL O M ANUAL 1 -
ACTIONS OSTARTS AFW PUMPS SOPENS DISCHARGE VALVES TO SG'S SCLOSES SG BLOWDOWN VALVES
- . . . a.. - ,--- - . . - - , --- - - . r --
-^
l STEAM GENERATOR TRIPS t pm j tja # 41d
~
eGENERIC PROBLEMS EXPECTED COMPONENTS TO RESPOND i
p PER THE PLS L AUTOMATIC CONTROLS HAVE MORE y FINITE CONTROL i 1% ACCURACY VS 20% ACCURACY IN MANUAL
- , ade~ STEAM DUMP TUNING BYPASS REG VALVE TUNING l
[ # GENERIC LESSONS LEARNED p- TUNING OF REG VALVES FIRST LEADS TO SUCCESSFUL TESTING f*
r.
l.--. _
i l
SUMMARY
& CONCLUSIONS t
425 TOTAL EVENTS
- 90NLY 4 DUE DIRECTLY TO PERSONNEL ERROR 2 h}sk , 9 cp& -
L 90NLY 1 OCCURRENCE OF ESF COMPONENTS NOT RESPONDING PER DESIGN _UPON ACTUATION SIGNAL c & /NR%N=W && 1 'P*>'
L-SSEVERAL LESSONS LEARNED FOR SG LEVEL
- CONTROL
~
ADDITIONAL OPERATOR FOR MANUAL CONTROL 3
MORE ATTENTION TO TUNING CONTROL CIRCUITS FOR FRV'S AND STEAM DUMP VALVES IMPROVED PROCEDURE FOR SWAPOVER FROM BFRV'S TO MFRV'S 1 -
QUESTION VENDOR RECOMMENDED SETTINGS FOR
[1 CONTROL CIRCUITRY
~
IMPROVE SIMULATOR MODELING REMOVED FLUX SIGNAL TO BFRV CONTROL CIRCUIT TRIP SETPOINTS TOO CONSERVATIVE -
-t 4 p w 17 s% a A 4 se ."g, r% x= v %
5 PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM
- " PERMS" L
e MICROPROCESSOR - BASED DIGITAL RADIATION MONITORING SYSTEM
_ e SYSTEM CONSISTS OF THE FOLLOWING MONITORS:
- EFFLUENT MONITORS: 15
~
- PROCESS MONITORS: 27
[ - AREA RADIATION MONITORS: 13 3 - POST ACCIDENT MONITORS: 12 e READOUT OPTIONS:
- LOCAL DATA PROCESSING MODULE j - SAFETY-RELATED DISPLAY CONSOLE (SAFETY MONITORS)
- COMMUNICATIONS CONSOLE (CONTROL ROOM)
- MINI-COMPUTER TERMINALS IN CHEMISTRY, HEALTH PHYSICS LABS l
l l
l l
n --
n m n m m .m m r- -- -
TO - DATE PERMS ACTUATIONS <
EVENT CAUSE DATE
- 1. CONTAINMENT ISOLATION FROM RE-0006 DEFECTIVE UTILITY BOARD 02/13/87
- 2. CONTAINMENT ISOLATION FROM RE-0006 DEFECTIVE UTILITY BOARD 02/17/87
- 3. CONTROL ROOM ISOLATION FROM RE-12116 APPARENT LOSS OF POWER 02/23/87 TO DPM ;
- 4. CONTROL ROOM ISOLATION FROM RE-12116 APPARENT LOSS OF POWER 02/27/87 TO DPM f
- 5. CONTAINMENT ISOLATION FROM RE-0006 LOSS OF POWER 03/04/87
- 6. CONTROL ROOM ISOLATION FROM RE-12116 APPARENG LOSS OF POWER 03/26/87
- 7. CONTROL ROOM ISOLATION FROM RE-12116 SUSPECTED LOSS OF POWER 04/06/87 INTERNAL TO DPM
- 8. FHB ISOLATION FROM RE-2532B EXCEEDED HIGH RADIATION 04/15/87 SETFOINT 9 CONTROL ROOM ISOLATION FROM RE-12116 ACTUATION SIGNAL NOT 04/21/87 l BLOCKED DURING TESTING ,
- 10. CONTROL ROOM ISOLATION FROM RE-12116 CONFIRMED LOSS OF POWER 04/22/87 INTERNAL TO DPM ;
pf, i Q w & Or
. - l l
I L-RESTRAINTS TO SYSTEM RELIABILITY L.
- LATE TURNOVERS CAUSED A LATE PREOP TEST START.
NO SYSTEM BURN-IN TIME.
I
- THIS IS THE FIRST OPERATIONAL SYSTEM DELIVERED f BY THE VENDOR; NO EXPERIENCE BASE FROM WHICH TO START.
R
- LIMITED SPARE PARTS AVAILABILITY; LONG LEAD TIMES.
b e MI CABLE ELECTRICAL CONNECTIONS EXTREMELY SEN-
, SITIVE TO CONTAMINATION.
l1 l.
i i
I l
l l .
t
n m m m m m.P n . r i
PERMS ACTUATIONS l CONTAINMENT ISOLATION PHASE "A" i
MONITER DESCRIPTION SETPOINT RE-0005 CONTAINMENT "A" TRAIN HI-RAD MONITER RE-0006 10 0 hr CONTAINMENT "B" TRAIN HI-RAD MONITER 10 0 hr j CONTAINMENT VENTILATION ISOLATION i RE-0002 CONTAINMENT "A" TRAIN AREA MONITER RE-0003 CONTAINMENT "B" TRAIN AREA MONITER 15 m hr a 100mr/hr b RE-2565 CONTAINMENT PURGE MONITER 15 m hr a 130mr/hr b
! SE-7 uci cc 1.3E-7 uci B),
1.06E-5 uci (c)
A. REFUELING SETPOINT ,-
B. POWER OPERATION SETPOINT CONTROL ROOM VENTILATION EMERGENCY MODE ACTUATION RE-12116 CONTROL ROOM INTAKE RADIOGAS MONITER 3x BACEGROUND RE-12117 CONTROL ROOM INTAKE RADIOGAS MONITER 3x BACKGROUND FUEL HANDLING BUILDING POST-ACCIDENT VENTILATION SYS. ACTUATION RE-2532 A&B FHB EXHAUST DUCT MONITERS 4.29E-7 uci/cc RE -2533 A&B FHB EXHAUST DUCT MONITERS
- - - - - - - - - - . p g _, y S n .m m n . . r -
CUMULATIVE TOTAL OF ALL EVENT REPORTS LIWERICK 1 CE 220 - BYRON 1 WX CALLOWAY 1 WX WOLF CREEK WX 200 - R1VER BEND GE LoSALLE 2 GE WPPSS 2 GE EVENTS 160 -
WONTH 12 WATERFORD 3 CE PALO VERDE 1 & 2 CE 140 - TUIAL 38 CATAWBA 1 WX p V0GTLE 1 WX r FERMI 2 GE 120 - SHOREHAM GE x
( 100 -
t 80 -
- ST. LUCIE 2 CE 60 - McGulRE 2 WX D1ABLO 2 WX WILLSTONF_11 WX 40 - .DIABLO 1 WX SUSOUEHANNA 2 GE 20 -
l
- O i i i i i i i i i i i i i i i
0 2 4 6 8 10' 12 14 16 18 20 22 24 26 28 30 32 WONTHS SINCE OPERATING LICENSE ISSUED CTDAER STATUS DATE 4-22-87
__ _ m
-~~
n s. . _ n 7 n6 .
~
n F
~ ~*
l AEOD DATA I
13 0 - -
120 - - - BYRON 1 11 0 - /
/ CALLAWAY 100 - ,/ -- -
/
- ad 4 - -
90 - "
,/ ,, -
- cATAwsA
~
, p 80 - / /
9 ~~~
f / = = = ~ - " -
W -
B 70 - ,4' - ..,
w ,, / ..............
5 60 - -
, 's f
/././.
e E
z 50 -
i if, /
if , f
/./.
,,. p ....-
/
mEnscE
/ #
/ -
/
40 - // s
/ </f ,
/
' McCUIRE 2 30 - '//
/
/,, -
y
/ -
20 -
,,/, /
/
wotr CREEK 10 - / __. -
- ~~ MLE 1 0
i i i i 25 50 75 100 0
PERCENT POWER AEODDATA 1
l
._ 2 _ ;_ - - -
i
, NUCLEAR OPERATIONS DEPARTMENT
. PLANT AND NUCLEAR EXPERIENCE L l EXPERIENCE (YRS) AVG EXPERIENCE (YRS)
ENGINEERING
- ENGINEERING 772 11.95 NUCLEAR 622 9.2
' ~
CHEMISTRY TECHNICAL 233 9.0 NUCLEAR 96 3.8 HEALTH PHYSICS
- TECHNICAL 265 8.8 NUCLEAR 187 6.3
[ MAINTENANCE CRAFT 1598 9.2 NUCLEAR 556 5.3 QUALITY CONTROL INSPECTION 155 6.6 NUCLEAR 141 7.35
~
i NSAC POWER PLANT 165 12.4 l,. NUCLEAR 146 10.2 I
TRAINING TECHNICAL 227 10.3 NUCLEAR 204 8.6
~
OPERATIONS l POWER PLANT 466 7.1 NUCLEAR 466 7.1 i
e f.. .
)
i l
\
-NUCLE AR OPERATIONS DEPARTMENT
' DEGREES / AWARDS DEPARTMENT GRADUATE 4 YR 2 YR PE/EIT OPERATIONS 4 43 3 3 l'
ENGINEERING 15 89 5 6
~
CHEMISTRY 3 16 4 T HEALTH PHYSICS 8 16 6
~
MAINTENANCE 1 11 57
, QUALITY CONTROL 1 3 5 6 NDT LYL III l
2 3 AWS/CTI
~
NSAC 11 2 1 TRAINING 4 11 3 4
5
,. 7 .
6 L-
,. OPERATIONS DEPARTMENT QUALIFICATION HIGHLIGHTS
- OPERATIONS MANAGEMENT (4)
. 3 PREVIOUSLY LICENSED AT SIMILAR PWR 4 HOLD B.S/M.S. DEGREES IN ENG. OR RELATED SCIENCE
- OPERATIONS SUPERVISORS / SHIFT SUPERVISORS (32) 10 PREVIOUSLY LICENSED AT SIMILAR PWR
, 4 PREVIOUSLY LICENSED AT BWR l 21 HOLD B.S. DEGREE IN ENG. OR RELATED SCIENCE 7
~
7 2 STA EXPERIENCE AT SIMILAR PWR
.- 11 HOLD B.S. DEGREE IN ENG. OR RELATED SCIENCE I
- REACTOR OPERATOR (41) 1 PREVIOUSLY LICENSED AT BWR
~
41 > 6 WKS. HOT PARTICIPATION EXPERIENCE i'
f I
t a
es e < 4 w , w m' O h ,
O BACKGROUND AND EXPERIENCE GSRO TOTAL OF 27 22 WITH BS ENGINEERING 4 WITH OTHER TECHNICAL j
}
9 PREVIOUS LICENSED Le GRO 1
TOTAL OF 15 7 WITH BS DEGREE
- 4 OTHERS WITH AT LEAST TWO YEARS COLLEGE GCURRENTLY HAVE 4 YEAR COLLEGE DEGREE PROGRAM ON SITE PDA3
LICENSE EXAM RESULTS GROUP I PASS TOTAL %
i RO 2 10 SRO 11 19 TOTAL 13 29 45
[. GROUP II
~
PASS TOTAL %
, R0 13 14 1 SR0 16 18 IC 1 1 TOTAL 30 33 91
$ GROUP III 1
TOTAL
. R0 SRO 8 11
, TOTAL 19 I CURRENT LICENSES R0 15
, SR0 27 TOTAL 42 f
i LER I
A
5 1 TRAINING ENHANCEMENTS
- STARTUP TEST PROCEDURE TRIAL RUNS I7 # SIMULATOR FIDELITY STARTUP TESTS RESULTS OPERATOR EXPERIENCE
[
- 0PERATOR AWARENESS i i " WHOOPS" PROGRAM i
1:
- CONTINUING TRAINING i SIMULATOR OPERATION SPECIAL TOPICS SOER'S f
l r
l TE
.ws- .
.. --..-._--.-_ _._-. . , . . . . - , . _ , . . . _ _ . , __..,___._,_-...--..c -
~
I ACCREDITATION STATUS
{.
HEALTH PHYSICS JAN 31,1987
.. CHEMISTRY 1 REACTOR OPERATOR JUL 31,1987
_ SENIOR OPERATOR
_ NONLICENSED OPERATOR SHIFT TECHNICAL ADVISOR
[ ELECTRICAL MAINT JAN 31,1988 l ,
MECHANICAL MAINT j INSTRUMENT AND CONTROL l .. TECHNICAL STAFF l -
l l'
ACCSTAT
{
F i
+
i MAXAGEMENT PHILOSOPHY .
SHIGHLY QUALIFIED PERSONNEL EARLY STAFFING & TRAINING MANY DEGREES &/OR PRIOR EXPERIENCE RETAIN STARTUP EXPERIENCE
, SMART PEOPLE, SMART MANAGEMENT 9OPEN COMMUNICATION STYLE
} .
ORECOGNITION OF PROBLEMS AND QUICK HIGH QUALITY
- [ RESOLUTION F 9 ACCEPTANCE OF RESPONSIBILITY AND REGULATORY CANDOR
{
l 9 QUALITY INITIATIVES AND EXCELLENCE
- READINESS REVIEW
]
- QUALITY CONCERNS r
9 CONTINUING OPPORTUNITIES
- SECURITY ENHANCEMENTS
.
- ATTENTION TO DETAIL l'
f i MANPHIL k
P
[
, _2-k
. As' of April 28, the utility stated that it had received 15 ESF actuations separate from a reactor. trip.* The most prevalent types'of-ESF actuations are
- main feedwater isolation and control room isolation.' Each control room
-isolation'has been' caused by failure high.of a~ control. room inlet radiation monitor. The utility has had limited success in resolving the continuing-recurrence of actuation of the radiation monitor. ,
Prior to the meeting, the resident inspectors had informed the licensee that it should report control room isolations caused by actuation of a chlorine detector. 'At the meeting,-the staff emphasized its position that isolation of the control room irrespective of the initiating event is considered an ESF actuation and should be reported as such. The. licensee agreed to abide by the staff's position.
In closing,- the staff consended the licensee for a' thorough, well-prepared ,
presentation. While ~ interface with vendors and other utilities possibly should have occurred sooner on some recurring events, the staff concluded that the licensee appeared to be taking adequate corrective actions to address problems experienced during the Vogtle Unit 1 startup program.
\sh Melanie A. Miller, Project Manager Project Directorate II-3 Division of Reactor Projects I/II
Enclosures:
As stated-cc: -See next page
--This numoer differs from the NRC number in that the staff also includes a fuel handling building isolation and 3 control. room isolations initiated by a-chlorine detector as ESF actuations.
1
~
l lI l /
n3 PDp%]r ad P-I/II PDI -I/II 1 BJY @bld
/tL/87 05/ ,
u
w- __ :ra MEETING
SUMMARY
DISTRIBUTION Docket File NRC Participants NRC PDR B.J. Youngblood L PDR M. Miller NSIC A. Gibson PRC System V. Smwnlee PD#II-3 Rdg L. Crocker _
M. Duncan J. Mauck OGC-Bethesda R. Dennig ACRS (10) J. Rogge P. Gwynn R. Schepens C. Burger bec: Licensee & Service List
\