ML20199G074
| ML20199G074 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/23/1998 |
| From: | Haag R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 9802040207 | |
| Download: ML20199G074 (59) | |
Text
{{#Wiki_filter:_ _ _ _ - - - - _ - . l January 23, 1998 i Virginia Electric and Power Company ATTN: Mr. J. P. O'Hanlon L Senior Vice President - Nuclear-Innsbrook Technical Center 5000 Dominion Boulevard
~G len Allen. VA 23060-
SUBJECT:
MEETING-
SUMMARY
- SURRY SELF ASSESSMENT - DOCKET NOS. 50-280 AND' 281
Dear Mr. O'Hanlon:
i L This letter refers to the meeting conducted at your request at the NRC Region -Il Office in- Atlanta. Georgia, on January 16' 1998. The purpose of the meeting was to provide Virginia Electric and Power Company an opportunity to discuss performance at your Surry facility It-is our opinion that this meeting was beneficial, in that, it provided us with an understanding of-your self assessment and corrective action-program results. In accordance with 10 CFR 2.790 of the NRC's "Rul_es of Practice." a copy of this letter and its encksures will be placed in the NRC Public Document- Room. Should:you have any questions concerning this letter, please let us know.
-Sincerely.
Orig signed by Robert C. Haag Robert C. Haag. Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos. 50-280. 50-281
-License Nos. DPR-32. DPR-37 1
(-
Enclosures:
- 1. List of Attendees
- 2. Surry Power Station Self Assessment - January 16. 1998
- 3. Safety Culture Memorandum
- 4. Supplemental Handout cc w/encls: See page 2 0FFICIAL COPY AAGOR7 9902040207 990123 llll-{lll:l'll,'lll{,lll PDR ADOCK 05000200 .....s .-
P PDR
- tbW
- j VEPC0 : 2-cc w/encls: # I J.'H.:McCarthy, Manager-
. Nuclear ~ Licensing and
-- Operations- Support. ?
Virginia Electric & Power Crmpany . ' 5000. Dominion Boulevard-
.c -Glen Allen,iVA: 23060 ~
David A. Christian, Manager- - Surry Power-Station-Virginia Electric & Power Company; 5570 Hog Island Road . Surry. VA 23883 W.-R. Matthews, Manager North Anna Power Station-
=P. 0 ' Box 402 Mineral, VA- 23117 Chairman-
-Surry County Board of Supervisors P. O. Box 130
-Dendron...VA .23839 Virginia State Corporation' Commission Division'of Energy Regulation.
P. O. Box 1197
-Richmond, VA. 23209
~ Michael W. Maupin Hunton and Williams:
Riverfront Plaza " East Tower. 951:E. Byrd Street Pichmond, VA 23219 State Health Commissioner
' Office of the Commissioner Virginia Department of Health P. 0. Box:2448--
Richmond,-VA 23218-
-Attorney General
-Supreme Court Building 900 East Main Street
-Richmond..VA 23219-
- . _ , .- ~ _ - __- _ - , . .. . -. . - . .
VEPC0 3 Distribution w/encls,: R. Aiello, RII P. Fi'ilion RII
-L. Garner, RII R. Gibbs, R!.I D.-Jones, RII W. Stansberry,- RII G. Edison, NRR PUBLIC jo NRC Resident Inspector i U.S. Nuclear Regulatory Comission l- Surry Nuclear Power Station 5850 Hog Island Road Surry, VA 23883 NRC-Resident Inspector U.S. Nuclear Regulatory Comission 1024 Haley Drive Mineral, VA 23117 GFFICE RII:DAP Ril:DW)
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"""c"?iS""
Introduction M. R. Kansler t Management Perspective D. A. Christia = and SALP Period Self-Assessment Self-Assessment and R. H. Blount Corrective Action Programs Closing Remarks M. R. Kansler 2 dnelO5ure 2
Introduction M. R. Kansler Vice-President Nuclear Operations b
Management Perspective D. A. Christian Station Manager y
Management Perspective
"""M7"""it,"""
Plant safety has been and continues to be our top priority. Our excellent safety performance is not by chance, but is the result of a systematic approach. l
- Decisions regar ding. plant operations and equipment operability are conservative.
- Safety systems are well maintained while optimizing their availability. ,
- Long-term equipmentproble.ns are being resolved.
- Excellent human performance is continually emphasized.
5
t Management Perspective
"""EC"""!L""
We will ensure our continued success through:
. Conservative decision making
. Strict adherence to the Nuclear Safety Policy
. High regardforpersonnel safety
. Rigorous self-assessments
. Timely and effective corrective actions
. Verbatim regulatory compliance
. Complacency avoidance
. Questioning attitude
. Open and candid communications 6
""""""?""it"""
Operating Performance The Surry team has been effective at maintaining and operating the units. The result - safe, reliable, superior operatingperformance. I Previous Current
- l
'SALP SALP (1f22/95 - 9/28/96) (9/29/96 - 3/21/98)
Automatic Trips 3 1 Forced Outage Rate % 2.8 2.0 Capacity Factor % (MDC Net) 86.7 88.2
- Through 12/31/97 7
__ Operating Performance """"!*""it," " We recognize that the industry's overallperformance is continually improving. Not to be satistled with the status quo, Surry is " raising the bar"in its quest ; forperformance excellence. 1997 Industry *- Surt,/ Average Average Automatic Trips 0.6 0.0 Forced Outage Rate % 10.7 2.6 Capacity Factor % (DERNet) 74.7 87.6
- Through 9/30/97 8
, Comparisori to industry SurryTrend: improving Percent "9 } Current (7/94 - 6/97) Surry Surry 100 - Unit 1 Unn2 85.0 87.1 90- ! ~~ 80-i Numberof Units M***" 83 6 E
> 87.0 70 - '
34 60 - t l# l 50 - 40 i , 4 91-93 92-94 93-95 9446 95-97 2000 Goals ; 24 - Industry Medan 3 Suny Unit 1 C Suny Unit 1 Goal {
. Industry Goal M Suny Unit 2 C Surry Urut 2 Goal I 20 -
tGood 104 Units
Background:
Tlus is the percentage of maxirruJm energy generation that the plant is capable of supplying to the grid krruted only by facers untNn the
.- control of plant management. Hgher nucumr generaton reduces the companfs overall generaten costs.
3l Initiathres: 10 - ;f
- Mamtei.ance Plan E.TF a.g Predctive and Preventatrve 9 /- 9 Maintenance and Use of Relatwhty Centered Maintenance 8 -
E (VPAP 0801) I
,
- Increased Management involvement in Dasty Work Plannmg Prowsees and Schedu Improvements 4 4
- Wovements b W and Msng Makes &
3 3 % Shoder Refuehng Outages 2 ' 1 f' * .nGaaLy Corrective Achon am improvernents 1 g , 1 1 ~ - 1
- Focusmg on Recumng Equipment O
g i ~ii
.U G , [
g 4- [ ., 3 g
- Focusmg on improving Human Peb.. -
- Reducson of Work Order Bacidog 0 10 20 30 40 50 60 70 80 90 100
- Servce water and Circulatmg water upgrades
- Maintenance Rule implementaten Percent Median: Midpoint of the dstribution. One-half of the units have values greater than the medan value while -> Good one-half have values that are lower. t 8a
d Surry ' Surry unn i Unit 2 38 Comparison to industry SurryTrend: Needs improvement 23 Long Term (1991-1997) L1 Current (7/94 - 6/97) l2000 Median 35-Goal 6.5 l < 3.0r*r . 30 - Numberof Uni:s 25-50 - 20 - l 15-10-4 0 91-93 92-94 93-95 94-96 95-97 2000
)
Goals [ o s , 30 - j j - Ind2stry Median 3 Surry Unit 1 C Surry Unit 1 Goat { e indu'ty Goal M Surry Und 2 O Suny Urut 2 Goal
. ; ,- 104 Units ,
y Good
, T. }l 20 - I Background
', h' This is the percentage of maximum energy generston that a i iI- plant is not capable of supplyng to the gnd because of unplanned l produccon losses (shutdowns, outage extensons. load j
i reduchons) Lower unplanned loss tactors should uttunately result
-j- 6 greater energy generaten and lower energy generabon costs.
t 10 - ; _[' 8 Intitatives: 1 [
- Instrtuted Predob Briefs for Known Load Reducsons
- Developed and Mantam a Forced Outage Cwa.- my Plan i' 5 4 includog Pre-approved Schedules and Vianned rk Orders.
3
- More Management and Erg.e..y involvement in Power 2
1
] 1 l- 1 1 1 1 1 Reducten for Increaseg Energy Outp**
- Rod Contel Card Repia ment anr* .estog O I' 'I I 'I I I
- Implemented Plan for Reducta s Human Performance Errors 0 10 20 30 40 50 60 70 80 90 100 . Feed Pump Motor Repe Percent
- Established a FIN Team to R spar, Diagnose Equipment Median: Midpoint of the dstribution. OneAaff of the units have values greater than t$e median value while 4- Good Problems
==
one-half have values that are lower. -- 8b l
Comparison to Industry SurryTrend: Steady Current (7/94
- 6/97) , 7 Long Term (1991-1997)
Hours Cnbcal per Unit 5-Suny Surry Unit 1 Und2 4-0.3 1.2 r 3-7 2-1.0 Numberof Units pp
~
70 - 67 ~ 60 - .
- d. 91-93 92-94 9345 94-96 95-97 2000 Goals
; [:. j j- q - Industry Medan E Suny Und 1 O Suny Unit 1 Goal e industry Goal B Sony Unit 2 O Suny Unit 2 Goal
- --J :
40 - p: p 104 Units 4%
- {-
Background:
This is the average scram rata per 7000 hours of reactor
.f 30 cntcaldy. Fewer automata:: scrams mean that we are reducmg 30 - -
the number of thermal hydraule transents and the number or cha8enges or times that we require aubmatic reactor protechon features to funcbon whrch increases the overalt salety of plant
~
- } ,p operanons.
20 - ;;
' . !- - kl1 Inttistives:
i'f a y' i
- Impeowed Opera
- PWm M ' ' W Mp Nd Margns to Se* points 10 - --
7
' ~:* y (PT Bnefing Sheet)
- Single Point Faihsre PM
'..*l* l -
e .~
- Focusng on improong Human Performance
- Rod Control Card Reptacerrvit and Testng 0 y i 0 1 2 3 4 5
- Feed Pump Motor Rep;acement Pp Scrams per 7,000 Hours Critical per Unit Median: Mdpoint of the distnbution. OneAaff of the units have values greater than the median value while 4- Good one4)att have values that are lower. a.
8c
l Comparison to Industry SurryTrend: Steady long Term (1991-1997) Current (7/94 - 6/97) t Unevadabarty/ N of Trains 0.030-Surry Surry Urvt 2 Unit 1 0.002 0.003 0.020-2000 Goal 0 020
~
Numberof Units 40 - 0.000 'I 91-93 92-94 93475 94-96 95-97 2000 32 Goals l 30 -
. Industry Goal E Surry Unst 1 O Surry Urwt 1 Goal N Surry Unit 2 O Surry Urut 2 Goaf 67 Units i yg 22__
Background-20 - This es the ratio of hours the high head Si mmpv.-,4s wure unavaslable to the hours the system was required to be avadable br sennce dnnded by the number of system trains. Alower
-nev a unavailabinty means that we have improved our plant 11 e margns by havng h high head SI system more e s 'it be required for RCS inventory and reactnnty control 10 - under accident condbons, inntatives:
- Developed CheckValve Marntenance Program
- Irvtiated Votes Testog of MOVs (VPAP 0805) 2
- Improved Scheduleg of Mantenance
- g.
- Reliabasty Centered Mamtenance Apple'd 0 I I I I I I I I
- Implemented DCP to Upgrade TCVs
.000 .C10 .020 .030 .040 .050 .060 .070 .080 .090 .100
- Strong Systern Wneenng involvement Component Unavadabdity/ Number of Trains
- Developed DCP to Remove Sunt Coce Systerr:
- Irnplemented DCP to Replace Deg Piping on CH 4--- Good Pump Servim Water Discharge Header 8d 1
SurryTrend: Improving Comparison to industry Current (7/94 - 6/97) Long Term (1991-1997) Component Unavadabaty! Number of Trains Suey Suey Urut 1 Urut 2 0 005 0 007 , , j 2000
. Goal 0 020 j i
0.010-Number of Units 30 0.000 4 91-93 9244 93-95 9446 95-97 2000 25 - geog __22 . Industry Goal 3 Surry Jnd 1 O Surry Unrt 1 Goal E Suny Und 2 O Surry Unit 2 Goal 67 Unds t g Y Backgrourut 15 - This is the rate of the hours the auxiliary FW
- -- - ,e,s mare unavalatie to the hours the system was requireu so be avadable for service dnnded by the number of system trains. A lower wngv.e J uryvadab&ty means that we have improved our overaB plant safety margns by havmp the auxiliary FW system 90 _ more avslable should it be required or core decay heat removal under acodent condtens.
7 Intilatives: 5 . New Govemor instaned and Overspeed Test Proadures 5-3 Rennsed a Fuff Flow Capabih Design Chanos implemented
- INPO Assist visst etedand Aecommendabons q- i Implemented 0
.000 .010 . . .050 . .070 . . .100 Approved Component Unavailability / Number of Trains
- Strong System and Mairnenance L .y involvement
- Thorough Root Cause Reviews withksu.ttant Procedural and 4- Good Equipment Upgrades Ongoing 8e
n Comparison to Industry SurryTrend: Steady Current (7/94 - 6/97) Long Term (1991-1997 ) Averrage Eme gency Generstor Unavelatmhty 0.060-Stanon 0.010 0.050-0.040-2000 0 030-0 . Number of Stations 0 020-0 - 91-93 9244 9345 94-96 95-97 2000 Goal 20
- Industry Goa! E Surry O Sorry Goef 17 69 Stah Good 15
Background:
This is the rr'in of the hours the e.e.p cp AC wngv.s.ts were uru!rvac4Jle to the hours the system was regtared to be 32 aJiable for service dwided by the number of system trams. A lower w,w,,7..t unavailabikty means that we have emproved 10 - our overaft plant safety margms by having the emergency AC power system more avslable should it be required to power safety related w % wits under accder.t condnons. Initiatives:
. Implemented EDG Ret Ailrly Program and Committee 3
(VPAP 0808) 1 1
- Immnted blegmW Acton Plan W EDG Upgrades
, ,- ~, - Completed Rehabdify Centered Mantenance Report for 0 g ; l 3 1 1 I E #4r ACSystem 000 010 020 030 '040 2 50 .060 .070 .000 C .100
- trnWM Ups 6 M G h a@m
- Insnated Degnostc Test Methods Average Emergency Generator Unavailabikty . stem and Maintenance Engmeenng involvement
+ Good . Fuel Pipe Replacement Aceve :.'e..h 4,ip e EMD Owners Group 8f l
Comparison to industry SurryTrend: Steady
. Current (7/96 - 6S7) U Long Term (1992-1997) 99.7 99.7 Percent 100-2000 %
Numberof Unrts 99 7 l 60 - 99' 58 _ 50 - -
<a
; gy ,
1992 1993 1994 1995 1996 1996 2000 40 - Gods E - Indsstry Median E C irry Unst 1 O Surry Unit 1 Goal
. Industry Goal 3 Suny Unrt 2 O Suny Urut 2 Goal 30 - 89 Uruts g : Ag 24 4'
Background:
n This is the ratio of desgn to actual gross heat rate. By V , .ga lowenng the actual gross heat rate we operate more 20 - , _ 7;j.7 + efficiently (less BTUs required for the same KW-HR of
- 5 :-- electricity) and raise the mdicator. An efficent plant will vi '
' ^
produce rnore electncal energy and result in more reliable v' " operations. 10-- qd f'~ ., inmativw
+ Cornpleted Feedveter Heater Replacement Program
- Cp 5 . iC
- Perbrmed Weekly Thermal Perbrmance Evalustrens f1 ,
*U For Companson With PEPSE Trave 6ng Water Screens b Mirumize Wederbox 0
1 1 IN lT5
+
-t Y$:
1 g ng Frequency
. Increased Attention to Performance Related i i 96 97 98 99 100 101 Mantenance items Ratio of Design to Actual Gross Heat Rate (Percent)
Median: MKipoint of the distribution. One-half of the units have values greater than the median valus wtule -l> Good one-half have values that are lower. _ l 8g
Comparison to industry SurryTrend: Steady i Current (3/97 - 6/97) Long Term (1984-1997) l Number of Fuel Defects 20- l
= l Suny Suny i Unrt2 Ur.it 1 15-7.0E46 1.7E-05 Fuel Defect 10-Reterence 5.0E44 Numberof Units 5-40 -
0 9- ,- T 4
'~
(1- I "-- 10 10A 11 12 13 14 2000 Goals 30 - 3 Suny Unit 1 O Surry Unrt 1 Goa! E Suny Unit 2 O Suny Urut 2 Goal 63 Uruts g
Background:
20 - Lower corrected 1-131 actnnty indicates fewer fuel defects. By operatirg with zero fuel defects or leaks, we menwnize the 16 radiaton in our reactor coolant system water and uthmately 14 throughout our plant. This reduces our potenbal for radiation
, , " t ,1;" . , exposure and resuf s in sa8er workmg ces and a less
/
^ j{ restrichve working sw,;.w...ent 0- Initiatives:
7 '
' I
- Effectue Foregi Material Exclusion Program (VPAP 1302)
T '
- Fuel Monitorrig Procedure Was Revised to Provide R
- Addrbonal Fuel Failure identificahon Guidehnes 1 2
- heduced Spent Fuel Pool Actnnty Levels
- Modrfied Fuel Assemtfy to improve Debns Fadure Resrstance 0 g i
- Irwolved Management m FME Amereress Trarning 1E-02 1E41 1E40 1E41
- Post Inadiaton Exam N 1E-07 IE-06 1E-05 1E44 1 E-03
- New Fuel has Zirio Cladding to Redire Conesion Conected 1-131 Activity (Merocuries/ Gram)
- Unit 1 Core Offload and in Mast Sapphg Starts 3/17/97
+- Good
- UT Will be l%.'.v.m.ed on Suspected Assembles; Reconstruction of Assembhes as Requwed us .
I 8h
l l Comparison to Industry SurryTrend: Steady Current (7/96 - 6/97) Long Term (1994 - 1997) Surry Suny Umt1 1.10 Und 2 1.11 [.0 -) 25 - Median IM 1.10 2.0 - Plumber j of Unrts , 97 1.0 Y : 1997 1994 1995 1996 1997 I' ON
~7) .
15 y{1 - Industry Median 3 Suny Unit 1 O Surry Urut 1 Goal
- Industry Goal E Suny Unit 2 O Suny Urut 2 Goal 22 unas 4 Good 10
Background:
Lower concentrations of ~r npunbes in our secondary systems k.a -. results in a lower Chemistry index. Lower impurdy concentratens
, _k o wit! reduce corrosion and degrada*aon of our steam generators 4 which wsil maxrnize their thermal performance and operating myyo. lifetirnes.
>. Initiatives:
- i<W Condenser Dissolved Oxygen Testing Capabady
. -, g:. d' 1
- Irvtiated Condenser Waterbox Coabng Protect 0
'l :
4 mwv]
*~
i i ;
- On tsne son Chromatography Utilized i e i 4 4 e i i i i
- Imph Condenser inica% Teseng 1.00 1.50 2.00 2.50 3.00 350 4.00 - Sw Tmps, hry Swam Tg few and index Value Repacked Numerous Secondary Valves Meolan: Mrdpoint of the distnbution. One-half of the units have values greater than the median value while 4- Good orms4unif have values that are lower. _
-e_
81
suny l sony Comparison to Industry SurryTrend:Im roving Currerit (7/94 - 6/97) Long Term (1951-1997) Y58 l 58 hGog Man-nem per Urw 800 . e47 HO
; _a 700-i Nwnber o8 Uruts 600- ; ; $5 -
J S00-w- 400-46 300-1' 91-93 92-94 93-95 94-96 95-97 2000 j -
- Indtes7 Meder E Surry M j- -- i -
. Industry Goni G Sony Goal yGood 30- , . i.
71 Uris % . 25 - ;. Lo=er coseceve endenan uposum rocamps preper merey' mere l _. anorean as tres ama and me eesua e, reduced Asdahor Prosewan i, -fl - w em nem em menort roosromeres wen resuaare me 20 - R ;-7. seeznons arus an overas teePrm- woripece Lo=er coerowe ressman er -moures asso vesue from ae=== paart source terms arus less
'i 16 ,
ce,sammanon uructi tued to cour savngs frer', w merk - . ;. 15 - :j and righer wort produceves 1
;_4 i- T w ordnavvos 10 - ,
a..
- ]; 'f 7
- Impsowed AndcdogicalWork P!srring Pmeerges
- CareewJ source Tenn Reducson Program
+- _
= Nwg 5 Vaar MAAA Plan (VPAP 2m 5- . ; . weegreed use d Cameras, Commurucuriore and Emposure Aeducten
- W. y. 1 y . m m,a m y
'W:[ ,
_l
- Simeon kwe#ver,ertincreased use of At. ARA Amareness Caw 0
- ~
7 -eAm ..er ew Eceansed Fabohon Program 0 100 200 300 400 500 toc
- W " d W h A*'" W N h per Umt
. m . w,,..or wak Cvder Ecoeurs Proud
. Coreresad Leak Reduemon Pvogram Median: Mdpant of the dstnbunon. Or.e-half of the uruts have values greater than the medan value while 4- Good one4:alf have values that are lower. _
8J
1 l i 1 i
- Comparison to Industry SurryTrend
- Improving l Current (7/94 - 6/97) 1.ongTerm (1991-1997) l l cut =c ueners per Umt i
Sony 4 -nv e00- . i tina i Urut 2 l 59 59 L g_ l w_ } h j 32 j 45 I
- +, e 300-i Number '
of Uruts 200-55 - 100 - l 0 45 - 91-93 92-94 93-95 94-96 95-97 2000 Goals 40 -
- Indss*ry W-dan 3 Suny ,
- Industry Goal O Suny Goal T 35 -
71 Uruts 30 - Backgrounct f.krww volume of low level sok! radcachwe masse vd result n 25 - a reduchon in the ermrenmental unpact of nuclear power and v cost savngs from redaced maienal and tool reph-ushment. I 20 g. radencew!r weste processeg. 6.w2 son,and bunal O' regreements.
'-~
15 - g,
- Contmued Aggressewe Leak Reduchon Program 10 - . Less Than 1% of RCA Contammated
- Or.sste Scrap Metafs Decon > 95% Effecewe 5- 4 * < 1 See Van of DAW Per Outage i 2 1 * -uA- .a. of EPRI iodiout Program 3
0 'I ' I - ' ' I i i 6 1 , i 0 100 200 30C 400 500 600 Cutze Meters per Urut Median: Mdpoet of the drstnbubon. One4unft of the uruts have values greater than the median value while 4- Good one-half have values that are lower. _ 8k
l i Comparison to industry SurryTrend: Improving l g Current (7/96 - 6/97) Long Term (1992-t997) i Numberper200.000 Men 44ours Worked poco 3Gdt 0~40 0.40 j 2_50-Number of Stateris 22-
- 45 _ u_L "
150-N gg_ 40 - 35 - 0 00 . , . ,- .
. - Y i 19lEF 1993 1994 1995 19a6 1997 20C0 30 - Gee's
- inest y M 6an 3 Suny 25 -
,) - * % Goal C Survy Goad hGood )'
< 70 Statmns Bachgrourut This is the number of aceder'ts resultmg in dsys away from 20 ,
work, restncred work or totaktes per 200.000 man hours
. 18 worked 1. lower industnal safety acoderit rate rwufts si a safer i erivronrnent in which we wM and lower costs tor admerustrahon and lost worker productrwaty as a restA of lost 15 - ame acodents 3
~
~ ._
sy Initiatives: 10 - b
- EmgAyee amoimnere
- Safety Waikdowns Wiri Fee @edt to Supervisen 4
1 :
- Weekly Safety Meetings in Groups With Hgh Emposure 4* 5
- IndustnalSate ry Oversatts Beefd 5- 1 . Safe. Alerts and Naar f.frss %
' Bnets on Gatefy
_p 2 1
- Base OSHA Cert 6crions forSupennsors
~
0 g g g
- Staten W<le Job Obsenrahons 0 1 2 3 4 5 Number per2C3.000 Mar *-Hours Worked Median: %dpcmt of the dstnbunon. One4:stf of the urwts have values gesawr than the rneden value wMe 4- Good one-half have values that are lower. _
81
M Per~iod svyyomsynox Accoursphisiuseists In addition to good operating performance, several significant mileetones and successes have been achieved during this SALPperiod. 1997 Unit 2 Refueling Outage -- safe, efficient, well controlled and lowest accumulated dose in ' Virginia Power history
. An INPO 1 rating was maintained "An environment that encourages conservative decision-making..."
... improvingplantperformance as indicated by frequent benchmarking and self-evaluation."
9
SALPPeriod svargyasuraav AccoursplisMrsts l
. Severe Accident Management Guidelines were 1 implemented . Service Water System Operational Performance close-out inspection was completed . Risk-basedISIpilotprogram was submitted . Successful Maintenance Rule recovery effort . Excellent hr: man and equipmentperformance resulted in a Surry Unit 1 continuous run of461 days 10
"Nantleesr Senfety farnt'
. INPO accreditation was renewed for Operations and Technical Staff trainingprograms c Successfui Licensed Operator initial and requalification trainingprograms 1 1
. Selected as NEI benchrsark for work management
. Employee Concerns Program was established
. Nuclear re-engineering was completed 11
,e ,
. a ,
_ h
, m .
s h *
&n ""*"T,""*TL" "
Focus Areas u
- Corrective action and self-assessmentprocesses
. Radiation exposure i
. Fuelreliability 1
. Humanperformance
. Integrated Configuration Management and \
Improved Technical Specifications projects \ i
. Agingplant equipment \
l
. Regulatoryprograms implementation
_ _ _ _ _ , _ _ _ _ _ _ - _ _ _ _ _ - - - - - - - - - - ~
- e b
a e u l h 4 4 k
Plant Operations
===~ Strengths
. Conservative decision-making
. Excellent command and control ofplant transient conditions
. Response to oft-normal operational events
. Licensed Operator initial and requalification programs
. Innovative safety conscious initiatives 14 W
Pknt Operations
==g- Strengths
- Operations Review Board
. Operator work-aroundprogram
. Operations Maintenance Advisor
. Operations support of outage planning and scheduling 15 h p,
- r -
g3 g ' '-
Plant Operations "Nuclerar .%sfety Firet" Focus Areas
. Self-checking -- recent lapses have occurred followingperiods ofexcellentperformance ,
ImprovementActions
- Operations coachingprogram
- Pre-job brief training
- Animated self-check l
- Quarterlyperformance assessment shift meeting
- Standards and administrativeprocedure reviewprogram
- On-shiftprocedure writers 16
Plant Operations
-s. +. ,8..,..,r.~-
Focus Areas
. Supervisory involvement in field activities ImprovementActions
- Enhance observationprocess (i.e., simpler form, l easier to review) 1 1
- Conduct observation training 1
17
- ~
I
, a a .
, _ Q ,
8 Maintenance
====- .
Strengths
. High availability ofsafety-related equipment . Optimization ofon-line maintenance risk l . Improvedplant reliability . Plant materiel condition . Strong work planning, scheduling, and execution . Significant reduction (45%) in corrective maintenance work orders . Long-term equipmentproblem resolution 18
Maintenance ===,=.- Strengthe
. Eliminated Unit 2 operator work-arounds . ALARA . Knowledgeable and committed staff . Good work practices . Trending of deviations and corrective actions for adverse trends . Maintenance Review Board "-
19
"Nurtene %sfety First" Focus Areas
. Procedure compliance '
1 ImprovementActions
- Frontline leadership training for supervisors (Phase H)
- Continuing reinforcement ofstandards and expectations
- Train and assign personnel to the procedure process to prioritizeprocedure changes
- Revised Maintenance Job Observation card to emphasize safety, procedural adherence, and comnrinications 20
Maintenance
- Nan leur %fety 1aret' Focus Areas
. Agingplant equipment ImprovementActions
- Continue toperform ejfective maintenance
. - Systematic review and assessment ofequipment l performance
- Increase use ofpredictive-maintenance program
- Ensure appropriate allocation ofresources to continue optimum equipmentperformance 21
Engineering
~===- Strengths . Engineering staffinvolvement in the resolution of equipmentproblems FAC, NDE, ISI and Design Controlprograms . Support ofplant reliability improvements . Support of the Unit 2 refueling outage 22
Engineering
"""" 2 = "it, - SMgM
. Maintenance Rule Program recovery I
. Experienced, technically qualified, and highly skilled staff
. Integrated Configuration Management Project
. Industry leader in spent fuel storage p
23
Engineering " Nuclear %fety Fir r" Focus Areas
. Sharpen our compliance focus andproactive approach to ensure regulatoryprogram excellence ImprovementActions 1
- Conduct additional licensing and design bases training
- Clarifyprogram coordinator expectations and responsibilities
- Continue benchmarking-
- Strengthen the System Manager's role in work planningprocesses
- Enhance the self-assessmentprogram \
- Improve the work management and prioritizationprocesses 24
*%elear %fety First' Focus Areas
. Unit 1 fuel reliability ImprovementActions
- Examination offuel assemblies to determine root cause failure mechanism
- Develop and implementpreventive actions based on fuel assembly examinations
- Identify and remove failed fuel assemblies during the next refueling outage
- Identify and remove the potential source of foreign material 25
Plant Support en- Strengths Radiologicalprotection
- Planningandperformance!
- Technologicalimp.ovements -
- Gas management during Unit 1 outage
. Emergencypreparedness -
- Extensive drillprogramifacihty training
- Challengingscenarios
. Security
- Training
- Accesslin-processingprogram _
- Testingandmaintenanceprogram
. Fireprotection
- Operationalperformance offire detection systems 26
o _ __ _ _ _ _ Plant Support
- Nuclear .%efety fire!"
Focus Areas
. AppendixRprogram implementation ImprovementActions l
- Heighten awareness ofAppendixRpmgram and related licensing and design bases
- Continue theprogrammatic review ofthe program
. Posting and labeling ofradioactive material ImprovementActions
- More frequent walkdowns ofradiological controlled and radiological material controlled areas
- Increased awareness thmugh the use oftraining mock-ups
- Use ofnew, more fade resistant labels n
Plant Support "Naarlenar Mefety Fer"t* Focus Areas
. Emergency response capability ImprovementActions
- Installed new software -
- Morepager training activations l
- Reinforced management's expectationcfor the emergency response organization
- Procedures were streamlined
- Streamlined back-up manual notificationprocess
. Reliability ofsecurity computer system _
ImprovementActions
- Replace existing cardreaders with swipe readers
- Replace alarm interface electronics
- Replace access control system with a PC-based system 28
Self-Assessment t R. H. Blount Assistant Station Manager Nuclear Safe y and Licensing
- =
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Self-Assessment Program
- Nuclear Oversight Board External
- Managementsarew Oversight Review Committee M Internal
- NuclearOversight Oversight Department 1 Management iSelf-Assessment
<
- IntegratedStation l
- Department
- ContinuousMonitoring 30 l
SelfAssessment Matrix
""""""""it""
Continuous Monitoring \ Preventive - - Corrective
. PerformanceIndicators; .4 Deviation Report, Work
- MorningReport Requests
- CriticalParameters .
CategoryHIRoot Cause
- Maintenance Rule
= = gygggggggy, Monitoring
. Plant Observations =
- Executive and .- , -
Management Tours -
- OperatorLogs '~
- Daily Plant : ._
Observations :
- Housekeeping Inspections 31 - _ _ _ _ _ _ _ _ _ - c
sv SelfAssessment Matrix
""W,"7"?!t,5 "
Department Self-Assessments Preventive Corrective '
. Department 1NPO . CategoryIIRoot Cause Performance Objectives- Evaluations-and Criteria PerformanceBased
. Program Self- DepartmentAssessments Assessments
. IDesign Change Packages
. SystemEngineering _ .
QuarterlyReport .
. TrainingObservations
. Departmental PerformanceIndicators (e.g., Open Work Orders) 32
Sel}LAssessment Matrix
" " C " ;Tn".?"
Integrated Station Preventive - Corrective StationPerformance - .21ntegrated TrendReport 1 AnnunciatorPanel
-.JbategoryIRoot Cause
. NuclearBusiness Plan :Roaluations .
GoalPerformance Report -
-lSignificant and
. Deviation TrendReport l PrecursorEvents
. : Issue-DrivenTeam
. RefuelingOutage . Assessments Assessment and Safety Evaluation . -
. Programmatic Team Assessments as l-_--
Surry Performance
~ Nuclear Safety Fint" Annunciator Panel Fourth Quarter 1997 L_,. .. q 3,r=- . I I- I _i Main Generation Reactor Trips QCS"Integrisy[ Fuel 'Re lity 7 p "E i Non-Fruipment Nuclear Sakty Iwfsnee Training Materials Security g t;ce,,;,g Adm. Services
( - - ( Self- lluman M*"'
.,.. I b'*'"*
Safety 5 C C4 s Culture Evz!uation Performance N Performance 8 t% ip . Perf. [ Complacency; n Corrective i Maintenance ; Engineering . LEGEND
~' ^' "
Condit n e Fourth Quarter Red - Significant Weakness White - Satisfactory
'" 7ellow -- - Improvement Needed Green E - Significant Strength com.
l 34 1 ._. . _ _ _ .
ym SelfAssessment Driven
" Nuclear Safety Firnt" OperationalImprovements
. Emergency service waterpump improvements
. Reactor coolantpump, replacement
. Radiation irsnitor upgrade--
. Source term reduction to: lower station exposure
,u Letdown line modifications :
? ,?
. Main feedwaterpump motor replacement
- 35 l
l -
SelfAssessmentDriven s-- -
*Nucieur Safety Fint' nalImprovements
. Flow assisted corrosion piping replacements . ,
. Reduction ofoperator: work;arounds ;
. Pressurizerpower operated) relief valve l modifications , ;
+ . .
. Process control system upgrades
?
}a
. Control room recorder improvements Vital bus modifications .
36 i
Closing Remarks M. R. Kansler Vice-President Nuclear Operations 37 E m .
Closing Remarks
""""C"""iS "
- Surry has excellent safetyperformance
. Plant safety systems are well maintained and are reliable 1
. Conservative decision-making is the norm \
. Our self-assessment capability is very good
. Equipmentproblems are being systematically and ejfectively corrected
. We are committed toperformance excellence 38
O Mamorandum U wn0MIA PoeWM mmmcanounA rowen TO: All Supervisors March 18,1997 FROM: David A. Christian Surry Power Station SAFETY CULTURE By now, many of you have seen the attached depiction cf the Safety Culture Model posted around the plant. I extracted this model from a document published by the International Atomic Energy Agency and inserted the "you are hero" circles so that the model can be used to emphasize the roles and responsibilities of individuals and supervisory / management personnel in maintaining plant safety. While 1 find the model self explanatory I am taking this opportunity to express to you in hard copy my expectations of you in implementing the Virginia Power Nuclear Safety Policy defined in ASNS 3000. You must understand the two fundamental principles of our Nuclear Safety Policy:
- 1. Every NBU employee has a profound respect for reactor care safety and takes this responsibility into account in their decisions and actions.
- 2. Every NBU employee works proactively to prevent events which compromise reactor safety.
In fulfilling the demands of the Nuclear Safety Policy, I expect you, as a supervisor to demonstrate the following behaviors: Establish expectation of performance that recognize safety as the overriding priority. Solicit feedback from station personnel to identify problems, impediments, and opportunities to improve. Reinforce individual behavrs that promptly and forthrightly identify problems. Verify work is performed in accordance with established plans, schedules, and procedures to , achieve clarity of diree , nquality of performance, and credibility of management. i Reinforce the principle tha' a safe, reliable plant results in economical plant operation. Reinforce the use of in-h use and industry experience to improve performance. Please revie, api.. J. ,nNhed Safety Culture Model and reflect on your personal role in achieving our objectives. You may want to detach and post the model as a constant reminder or otherwise keep ) handy as a quick reference, i
.l o _
I David A. Christian Station Manager Enclosure 3 m no w .nen I
. ~
Scafety Culture Model St&tement of* Safet'y Policy Managenient
@ ( ' Structures Rolicy Levgl _
. Commitment -
t Resources SelpRegulation s Definition of i Responsibilitles Definition jind Control of Safety Practices QualiMcations , Managers' and Training Commitment e Rewards.and Sanctions Audit, Review-and Comparison Questioning Attitude Individuals' Rigorous and
- Commitment Prudent Approach Commugicatioh hfety
- Culture umm
. g,
Safety Culture Model Statement qf Safety Policy - Management Mrdctures Policy Lev'el. Commitment Resources o M Definition of Self-Regulation
~
Rsdhonsibilitibs ,, , l Definition and ' Control BR$atety Practices
=
Qualifications , Managers' and Training Cbmmitment Rewards angi Sanctions 8 Audit, Review and Comparisdn Questioning Attitude individuals' Rigorous and
- Commitment - Prudent Approach Co[nmunication g .
Safety Culture a umou
OPERATIONS EVENTS . Annual Tagging Performance Inc ex Jan.1994 - Dec.1997 lll V. , _ i . 1994 TPI 0.095 1 Event per 1056 Tagging Opportunities . 1995 TPI 0.066 1 Event per 1516 Tagging Opportunities 1996 TPI 0.046 1 Event per 2182 Tagging Opportunities l 1997 TPI 0.011 1 Event per 8846 Tagging Opportunities 1993 1995 1996 1997 TPI (Tagging Perfbrmance Index) is the number of Tagging Errors divided by the number of Tagging Opportunities times 100% Erclosure 4 L_______ _ - -
OPERATIONS Cumulative Tagging Performance Inclex Jan.1996 - Dec.1997 HI
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Nul-962 Oct-96I mas 9@ /Abr 971 - iJul97j - Oct-971 l )f f p*,'. I y During the 24 month period graphed above, Operations personnel were presented with 69,052 opportunities to commit a tagging error. During this period,20 tagging errers occured. This represents a Tagaing Performance Index value of 0.029 %. TPI (Tagging Performance Index) is the number ofTagging Errors divided by the cumber ofTagging Opportunities times 100% l c2C 1 .. .
993( We**S '993 St "*d$~ Surry Pswer Stati n Dose Rate Trending Program Auxiliary Building All Areas 1993 through 1997 Quarterly Averages 4 i 3.5 3! , 4 2.5 : M R I ( H ! R t 1.54 i i l 1 0.5 - - - i 0; . . + +- + +. .+ + + ,. , , < . . . . , Actual Dose Rate Dose Rate Trend l l [ .
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