ML18152A169
| ML18152A169 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 09/13/1991 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9109260025 | |
| Download: ML18152A169 (32) | |
Text
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e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 September 13, 1991 Docket Nos. 50-338, 50-339 and 50-280, 50-281 LICENSEE:
Virginia Electric and Power Compa~y (VEPCO)
FACILITIES:
Surry Power Station, Units 1 and 2 (Surry 1 and 2)
North Anna Power Station, Units 1 and 2 (NA-1&2)
SUBJECT:
MEETING
SUMMARY
OF JUNE. 27, 1991 On June 27, 1991, representatives of the NRC and VEPCO met to discuss a variety of subjects as summarized below.
A list of attendees is provided in Enclosure 1.
VEPCO provided updated performance indicators for Surry 1 and 2 and NA-1&2 including net generation, reactor trips, industrial safety accident rate, actual/planned outage schedule and reliability data. These statistics are provided in Enclosure 2.
VEPCO indicated that imposition and collection of one-hundred percent recovery of 1991 NRC expenses by September 30, 1991 (as defined in the Omnibus Bud~et Reconciliation Act of 1990) would represent a significant impact.
In the case of VEPCO and its four nuclear reactors (Surry 1 and 2 and NA-1&2), the action will result in payment of NRC fees increasing from a budgeted $6,500,000 to an estimated $16,236,000 in 1991. This diversion of funds from previously planned plant improvements may impact completion dates for activities previously committed to the NRC.
VEPCO indicated that it is reassessing its.role as the lead plant (NA-1&2) for the Westinghouse Standard Technical Specifications.
VEPCO indicated that
$2,000,000 has already been spent on the program and the NRC draft Technical Specifications issued in January 1991 indicate that considerable additional effort will be required to find 11 common ground 11 between the NRC and industry.
Therefore, VEPCO will reach a decision by the end of calendar year 1991 whether
. to continue as the lead generic Westinghouse plant. Also, VEPCO inquired as to the status of NRC fees for lead plants in the NRC Technical Specification Improvement Program.
The NRC staff indicated that the staff is evaluating fees required for this matter at the present time.
VEPCO stated that the NA-1 steam generators (SGs) have undergone extensive SG tube plugging.
Results from the 1991 SG inspection have resulted in 13.6, 12.5 and 19.2 percent of total tubes plugged for SGs A, B, and C, respectively.
The final report, justifying full cycle operation for NA-1 without a mid-cycle SG inspection, will be submitted ~o the NRC by the end of July 1991.
VEPCO indicated new SGs for NA-1 would be on site in August 1992. Actual replacement of the NA-1 SGs would be determined after the next SG inspection. Replacement could occur as early as 1993 and as late at 1995.
9109260025 910913 PPDR ADOCK 05000280 PDR
\\
i I
September 13, 1991 Enhancing nuclear safety during plant shutdowns has become a basis of concern for VEPCO.
United States and foreign Probabilistic Risk Assessment {PRA) results indicate shutdown core melt frequency is a significant fraction of total core melt frequency. Also, for PWRs, mid-loop operation is a dominant contributor and uncertainties for shutdown conditions are much greater than for power operations.
VEPCO actions implemented during plant shutdowns include:
(1) Nuclear Safety Policy Statement, {2) monitoring of critical parameters, (3) consideration of shutdown risks in outage plan, (4) outage-specific safety evaluation, (5) training and increased awareness of shutdown risks, and (6) review of Technical Specifications and administrative control adequacy.
Monitoring of critical plant parameters during plant shutdowns would include a one-page management summary focused on critical parameters. Also, on a daily basis, the present condition and 2-day 11 Look Ahead 11 information would be provided for integrated management assessment (see Enclosure 3).
Finally, the NRC staff voiced concerns regarding the Surry IST Program and the number of relief requests submitted just prior to the requested relief.
VEPCO indicated that the IST Program was being reviewed for both Surry and NA and that VEPCO would be meeting with the staff in July 1991 to discuss the IST Program.
Enclosures:
- 1. Meeting Attendees
- 2. Statistics
- 3.
Enhancing Nuclear Safety cc w/enclosures:
See next page (Original Signed By)
Leon B. Engle, Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation DISTRIBUTION Docket File NRC & Local PDR PD22 Rdg TMurley/FMiraglia lJPartlow SVarga GLainas HBerkow LEngle BBuckley DMiller OGC ACRS (10)
MSinkule, RII JWeschelberger, 17621 EJordan, MNBB 3701 DDorman FTalbot MThadani FGi llespie llNorberg TSullivan
~~=---;-~---~----;-~~----~~ ___ ; ______________ ; _____________ _
NAME e
- L
- HBerkow DATE --~/ ()191 --------; CJ -,l~/91 -----; 'f 'J-::f 91 ------;--------------;--------------
FI C IAL RECORD COPY Document Name:
SURRY & NA MEETING
SUMMARY
/
North Anna Power Station, Units 1&2 Surry Power Station, Units 1&2 cc:
Mr. William C. Porter, Jr.
County Administrator Louisa County P.O. Box 160 Richmond, Virginia 23219 Michael W. Maupin, Esq.
Hunton and Williams P. 0. Box 1535 Richmond, Virginia 23212 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, Virginia 23209 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. J. P. O'Hanlon Vice President - Nuclear Services Virginia Electric and Power Co.
5000 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Patrick A. O'Hare Office of the Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U.S. Regulatory Commission Route 2, Box 78 Mineral, Virginia 23117 Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 e
Mr. W. L. Stewart Virginia Electric & Power Company C. M-. G. Buttery, M.D., M.P.H.
State Health Commissioner Office of the Commissioner Virginia Department of Health P. 0. Box 2448 Louisa, Virginia 23093 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. G. E. Kane, Manager North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 Mr. E. Wayne Harrell Vice President - Nuclear Operations Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Michael Kansler, Manager Surry Power Station Post Office Box 315 Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission Post Office Box 166, Route 1 Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Mr. Martin Bowling Manager - Nuclear Licensing Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060
e NRC H. Berkow B. Buckley D. Dorman F. Gillespie J. Norberg J. Partlow E. Rossi T. Sullivan F. Talbot M. Thadani ATTENDANCE LIST MEETING WITH VEPCO JUNE 27, 1991 ENCLOSURE 1 VEPCO M. Bowling H. Fonticea J. 0 1Hanlon
- 1. Net Generation (MWH)
Definition: Comparison of actual net generation to projected goal net generation with adjustments for scheduled outages.
Total Nuclear NorthAnna
.,\\lonth.
Jan 1,882,957, 1,882,957 1,767,089 m,@
m,@
779,280 1,105,288 l,105,288
.987,809 Feb 1,611,714 3,494,671 3,178,524 614,726 1,392,395 1,298,501 9'.XJ,988 2,102,276 1,880,023-Mar 2,135,293 5,629,964 5,094,288 1,119,318 2,511,713 2,226,456 1,015,975 3,118,251 2,867,832 Apr 1,873,896 7,503,860 6,746,955 1,314,964 3,s26,6n 3,338,749 558,932 3,6n,183 3,408,206 May 8,391,827 4,489,717 3,902,110 Jun 10,413,814 5,603,557 4,810,257 Jul 12,552,591 6,754,525 5,798,o66 Aug 14,691,368 7,905,493 6,785,875-Sep 16,761,152 9,019,333 7,741,819 n
Oct 18,902,803 10,171,848 8,730,955 r r C u C
20,972,587 11,285,688 9,686,899
- l Nov rr I'
Dec 23,111,364 12,436,656 10,674,708
- 1. Net Generation (MWH) 1991 Goal: Achieve Net Nuclear Generation of~ 23,111,364 MWII MillionsMWH 27 -,-~~~~~~~~~~~~~~~~~~~~~~~~*~~~.~~~~~-~~
24 23.11 21
' 18 15 12 9
6 3
0 May_
Jun Jul Aug Sep Oct Nov Dec Nc,rth A1111a Surry YTD<.c,al e
Jan Feb Apr May Jun Jul Aug Sep Oct Nov Dec
. Definition: Number of automatic unplanned reactor ttips which occur while the reactor is critical.
0 0
0 0
Total Nuclear 0
0 0
0 0
0 0
0 NorthAnna 0
0 0
0 0
0 0
0 TM Annual Goal is to havt ltss than 3 reactor trips ptr station.
0 0
0 0
e
- 5. Reactor Trips 1991 Goal: Minimize Reactor 'frips 10 $ 6 Automatic Reactor Trips 8-,-----------------------------------.
6 6
4 2
0 0
0 0
0 -+---.-----.---.---.-----,---.....-----r--,----,.---.-----,----y-Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec mlf:I North A1111a
~ Surry
~lonth.
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
- 10. Industrial Safety Accident Rate Definition:
The number of accidents for all Virginia Power personnel ptrmanently assigned to the station, that result in one or more days away from work or one or more days of restricted work (excluding the day of the accident) per 200,000 man-hours. This does oot include contractor personnel.
Note:
INPO Revised International Safety Accident Rate Formula 0
0 0
0 Safety Accident Rate - (Number of Ipst-Time + Restricted Time Accidents+ Fatalities) x 200,000 Hrs (Number of Station Man-Hours Worked)
NorthAnna Surry 0
0.35 0
0 0.35 0
0.35 0
0 0.35 0
0.35 1.10
.37 0.35 0
0.35 0
.28 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35 0.35
- 10. Industrial SafetJ' Acclde11t Rilte Nt1rll1 A1111u 19')1 Cioal: 11111,n,v,* Nude:ar sar1*1y l'&*rf'orm:m1*1* - Minlml:t.1* A1*1*ld1*n1s and Ila,*,* Nu l'alallll1*s Per ZOCJ.INKI Man-Hours 0.6 --,~-------------------------------------
0.5 0.4 0.35 0.3 0.2 0.1 0
0 0
0 o-1-----,.----,.----,.----..---.....---.,-----.----.------------.--
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Surry 1991 Goal: Im provr Nuclrar sare1y Pl."rformancr - M h1lmlze Accldenl8 and Havr No Falallllrr.
Per 2CH),000 Ma11-Houn1 0.6 ------------------------------------,
0.5 0.4 0.37 0.3 0.2 0.1 0
0 0 ----.....---,,-
Jan Feb Jun Jul Aug Sep Ocl Nov YTD<iroal 0.35 e
North Anna I Planned Actual NorthAnna2 Planned Actual Surry 1 Planned Actual Surry2 Planned Actual
- 12. Actual/Planned Outage Schedule Definition: The number of days each unit is not generating electricity for any reason.
1/lVJl 1/12./91 0
0 3129/91 3/30/91 3/12191 3/9/91 0
0 6/04/91 ro 56 0
0 67 14 0
14 7
Refueling Outage None Scheduled 14 Contingency Days.
Refueling Outage/ AMSAC
- 12. Actual/Planned Outage Schedule I')') I
/\\ r Mo Jun Jul Oct Nov ~
Nurth Anna I
!>6 Oays Nurth Anna 2 14 Days Surry I 67 Days 7 Days.
Surry 2 Actual
- Planned
- Cootln1&cm:y
Definition:
Plant Operations Radiological Controls Maintenance/Surveillahce Emergency Preparedness Security Engineering/f echnical Support
- 15. SALP Rating The SALP (Systematic Appraisal of Licensee Performance) ratings are given on a periodic basis by the NRC. They are an average of the ratings given for different Nuclear Plant Categories. They r.mge from 1 to 3 with 1 being the best.
NorthAnna 1
2 Improving 2
1 2
1 Safety ~ment/Quality Verification 1
AVERAGE l.86 1.43 Suny h11Ktio11al Hating Period 1
Rating Last Period
,,.,. Current Period Arca (05/01/88 thru 06/30/89 : (07/01/89 thru 03/31/90)
(04/01/90 thru 03/3i/91) :'. (-
Plant Operatiom Radiological Controls Maintenance/Surveillance Emergency Preparedness Security Engineering/f echnical Support Safety ~ment/Quality Verification AVERAGE 3 Improving 3 Improving 3
3 1
2 3 Improving 2.57 2
2 Improving 3 Improving 1
1 2
2 t.86 SALP Meeting Scheduled 6/17 /91
- 15. SALi' Rtlll11g Nm*IIJ Am,a l'J<J I (;oal: lmprcn't." North Anna SAi.i* Rating lo,: 1..\\0 and llan* No.\\ Rat in,;"
Rating 3.00 -,----------------------------------,
2.00 1.86 1.30 1.00 0.00-t--
10-31-91 Goal Surry 1991 (ioal: Improve.- Surry SAI.P Ratlnic to~ l.(..CI and llavt." No j Rating,.
Na1l1111 3.00 --,-----------------------------------,
2.57 1.60 03-31-91 Goal
- 19. Emergency.Di,esel Generator Reliability Deftoldom,A.
Start Demande
- all valid or lnadvenent stan demandl, lncludina all start-only demandl and all load-nln dernandll, whether by automatic or manual initiation.
IL 5lal1 Pailura
- all valid !Wt failures. Any f'alwe wkhln the emcrsencv diesd seneraor lflleln that pre¥e1U lhe diesel senerator from achieving specif led frequency (or apeeiO and vdtase ls dualflcd u a valid aan failure.
C.
load,.llua Dmulodl
- all valid load-Nn auempu lhal follow a 1Uccessful stan and mr:e one of the followlns cneria:
I.
A load-Nn ol any duralkln lhat resuli. from a real (aaual) automalk: or muwal signal (not a lell).
- 2.
A load-Nn tat wllh lhe lnlenlion to meet the plant'* load and duration lea speclfkationa.
- 5.
Other opendona (e.1. apecial tata) of the ernf.1J1ffiCY aena,ator In which II lo lnlended to run for at leut one hour at 50K ol desifln load.
IIMC.,,._
- Umucicealw ~
to aan or load-run are not COlllidered valid demandl or r.lurea when they can be specifically auributcd to any ol the following:
I.
Spwloua opmlJan d * ~
lhat would not preclude llfe dleael senerat<< operation cbinf1 an emerse,tc.y.
- 2.
Malfunalon ol equlprmn lhal la not operable durln(r the emeqency operat)on mode.
- 5.
Small wan.er or ol lealu lhal would not preclude ufe diesd senaator operatron durtna an emasency.
- 4.
Openlk'8 emn that would not pevaa the dlead aenentor from belna reatruted and brousht to loed witlun a few minutea (wilhout corn:ctlve maintenance).
Addlllon,illy, valJd ckmlnda er raawa c:annlll raull from tata run while the dlead pnera1or II declared Inoperable.
D.
load,........._
- all nlld run fallura durlna whkh the EDG &Ill to meet the above load-run demand aileria, followlns a auccaaful stan.
L
............, - lhe pobabDy lhla lhe unll EDG'a or l!mqency Power Sy.-em wW carry oul lb ldended funaJon.
ltellabby * (Number ol Sucx:aaful Swu per.... 100 Valid SUrt Demands) * (Number ol Suca:uful load-Runa per.... 100 Valid Loed-Run Demands)
\\l11111hh 11)(, *~*11L1111L..,uln-~,1111 lkliahilirY
\\\\11111 h
~
- ffl
- 1,.\\h111thh*
\\"11) * *
,rar,..
- ltum,
.\\l*mar
.kmal *** *
(in:ll Jan 1n 1n 0.990 0.990 0.950 15/15 15/15 0.980 0.980 0.975 Feb 4/4 4/4 0.990 0.990 0.950 5/5 5/5 0.980 0.980 0.975 Mar 5/5 5/5 0.990 0.990 0.950 6/6 6/6 0.980 0.980 0.975 Apr 919 919 0.990 0.990 0.950 14/14 11/11 0.980' 0.980 0.975 May 0.950 0.975-Jun 0.950 0.975 Jul 0.950 0.975 Aug 0.950 0.975 Sep 0.950 0.975 Oct 0.950 0.975 Nov 0.950 0.975 Dec 0.950 0.975
- 19. Emerge11CJ' Diesel Ge11erator RelfabllltJ' Nort/JAnna 1991 Goal: Acldeve t!.9so F.mergen,*y l>k!ld Generator Rellablllty HellahlUty 1.000
_990-_990-_990-_990-------------------------
.950
.950
.900
.850
.800 May Jun Jul Aug Sep Oct Nov Dec YTD Goal
.-G-oocl--.1 Surry 1991 Goal: Ac~~.975 Eme~c:y Dlnel Generator RellablUty llellabllky 1.000 ------------------------------------
.980
.980
.980
.980
.975
.950
.900
.850
.800 May Jun Jul Aug Sep Oct Nov Dec
-- YTD Goal
-1.-G-ood--,
Month Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
- 21. High Head Safety Injection System Unavailability Definition:
Safety system unavailability is the total number of hours that safety system trainc; are not operable due to failure, maintenance, testing, or other causes.
NorthAnna Surry
.2
.2 10 14.1 14.1 15 13.0 13.2 17 7.3 21.4 28 1.7 14.9 29 4.0 25.4 43 17.6 32.5 43 12.4 37.8 52 58 59 72 72 87 87 102 102 117 117 132 132 146 146 161 161
- 21. lligh Ilea~ SafelJ' hijection ~'J,stem U11availabilil)'
Nm*l h A 11na 19'}1 Cimal: l.lmll llw llmw:dlablt* llour" ol'lhc lligh lkad Safely lnjt*t*llou Sysll*m lo:* J(,J llnav:dlahlt* llour..
200 -,-------------------------------------,
150 100 50 0.2 0-t--.......
Jan
............. 32.5 13_2....... 14.9 May Jun Surry Jul Aug Sep Oct Nov Dec YTD <ioal 1991 Goal: 1.lmll lhc.- ll1111v11Uablc-llctul'tll oflhc Illich llcad Safety lnJcc:tlon SyNlem 10 S 1(,1 llnavaUllblC' lloun 200 150 100 50 0
May Jun Jul Aug Sep Oct Nov Dec Yl'I> <io11I 161 161 e
. Month**:.*
Jan Feb Mar Apr May JWl Jul Aug Sep Oct Nov Dec
- 26. Temporary Modifications Definition:
The total number of jumpers, lifted leads, and other temporary design modifications.
3
.3 I 2
! 3 NorthAnna
> 6 Month.4' amm*
3 6
2 5
1 3
0 3
- .Goai /.,..
- 1 -
10 11 10 10 4
10 5
10 2
10 10 10 10 10 10 10 10 Surry
- > 6'°Monlli'i:.
~.
\\ tu.*.. ***, : :. :*:
'*, *g*
- i:\\;;'; ;,'.. :£..
- i C a._*....'*:*.. :*. *.. : *."-.;* *: :-,'-.. '. *: ***,:.. "**:*/:~,:*:(~:'i'.
'.. J~:- }\\*::: :/~~ :.-f :,~--~~t'Ll) 3 13 10
- 6 2
10 2
7 10 2
4 10 10 10 10 10 e
10 10 10 10
- 26. Temporary, Modifications North AIIHU 1991 (ioal: Mlnlml:1.t* Monthly '1'..-mporary Modlflc:atlom, lo :s JO Modmcallons 20-,---------------------------------,
15 10 6
5 0
May Jun Jul Aug Under 6 Month*
Over 6 Month*
Surry 1991 Goal: Minimize Monthly Temporary Modlf1caitlon11 to S 10 Tnnponry Modifications Sep Ocl YTD Nov 10 20--..--------------------------------------
15 13 10 10 5
0 May Jun Jul Aug Sep Ocl Nov llndrr 6 Month*
Over 6 Month*
YTD
- 27. Non-Outagi. Corrective Maintenance Backlog - North Anna Ddlnltlon: Number of incomplete or completed, not closed work orders for Corrective Maintenance at the end of each month.
- 'tlonth Jan Feb Mar Apr May Jun Jul AUi Sep Oct Nov Dec Complctm, Not Closed - Maintenance work complcted, but work order package review and document dose-out not complete (both safety and non-safety related).
Safety Rclatal - The number of non-outage work orders with a QA category of SR or NSQ.
Total - Number of incomplete and completed, not d~ed, non-outage CM work orders at the end of each month (both safety and non-safety related).
- Aw::r* A&e - The average number of days since the outstanding, non-outage CM work orders were approved and completed.
Completed Not Closed Incomplete Total I
J I
(Includes Compicted
- \\011-Sakty Saktv Total
~on-Saf~ty Safety Total Hdated Hclatcd Relate~
Related
~ot Closed) 15 10 25 301 99 400 425 13 6
19
- 328 101 429 448 108 29 137 308 119 427 564 27 16 43 242 127 369 412 Average
- .: Age*
106 106 95 90 e
27~ No11-0utt1ge Correct i,,e Mt1h1le111111ce B,u:klog -North A:11u1 19')1 (im1I: (:cmtrol No11-lh11:11,;,* l111*ompl,*1t* Corn*c*th-,* '1:1i11h*11.111c*,* Hac*kloi.; tu~* ~00 Work Ord,*rs 600 --,-------------------------------------,
500 400 300 200 100 0 -
429 427 h1,*omplrtr Safc*ty Rl"lal~
M:ly Jun Jul Aug ln,*ompkll" Non-Safety Rdatc*d Sep 500 Oct Nov
-- YTDGoal Average Age of Co_rrectlve Mtaintenance Work Requests 19')1 Goal: C:onlrol Avrr~ Age' ofC:orrL"c:tlvr MalnlL"na1u*e Work OrdL"r.i lo S 90 Days Dap 150--..-------------------------------------,
125 106 100 75 50 25 0
106 M.ly Jun Jul Aug Sep Oct Nov Dec Yl'DGoal 90
- Month*
Jan II Feb II Mar II Apr May Jun Jul Aug Sep Oct Nov Dec
- 36. Procedure Upgrade Program Definition:
The total number of Technical procedures that have completed verification and validation. The total number of Administrative procedures that have been completed and approved Administrative Technical North Anna Technical Surry 13 5
II 55 50 II so so 18 10 II 149 100 133 100 22 15 295 150 201 150 24i 20 550 200 370 200 25 250 250 29 300 300 33 350 350 37 400 400 41 450 450 45 500 500 49 550 550 53 600 600 e
- 36.,J',-oc:edure UJJgr11de l'rogr,1111 Nt>rl/J A1111u l'J'JI Cimal: c;omplt*h-,* f..CMI h*l"l111in1l l*rm:t*dun* ll1,~:ad,*.,
.,; 81,.,.,.
l*r,a Cio:al: c:01111,h*h* ;, f..CMI 'h*l"11111,*:al l'rotl"dm*,* llp);rad,*,
(:omplc.-h-d Pron"'lurn c:ompl,*t,*d Pron-durn 700-,.-:
700 --,.-----
600
- J 600 500 400
=J,'~
295 300 200
~,~
100 100
- m.
0,-,~,-,-, ~I §lsl~I ~181 ~1¥1il
~ -, -,
U>
Z O
Cl 0
~
~
C YTDGoal I* Ciood I A1lml*lslra11,,e 1991 Goal: t:omplrtC' ~ ~j AdmillistratiwC' Proc.Tdu~ U~
Complc.-ced PrOCC'llu~
60--------
53 50 40 30 20 10 0 I§ Ea 1a Ea 1 *I* 1-1 clsl ml a.lg! >I ulii
~
0
~
0 U>
Z O
c, YTD Gual I* Goud I 3 -,
~I~
U)
/'/
u 0
~
z
¥ 0
600
~
~
ii 0
C)
YTD Gual I t Good I e
e
Virginia Power ENHANCING NUCLEAR SAFETY DURING PIANT SHUTDOWNS rr,
- z n r-0
(/)
C ;o rr, w
Shutdown And Low Power Evaluation Relevant Actions
- Bulletins Arid Generic Letters, Including:
IEB 80-:t.2, Decay Heat Removal System Operability GL 80-53, Decay Heat Removal Capability GL 88-17, Loss of Decay Heat Removal NRCB 89-03, Potential Loss Of Required Shutdown Margin During Refueling Operations
- Need Comprehensive Reevaluation Because Requirements Have Been Developed One By One. Some Recent Actions:
IN 91-22 On Four Recent Shutdown Events Letter To Utility CEO's From NRR Director Staff To Monitor Activities During Outage More Closely
Nuclear Safety Policy Statement Issued By Senior Vice President
- Emphasis Is On:
Protection Of The Core Preventing Plant Events
- Key Shutdown Risk Reduction Requirements Include:
Maximize The Availability Of Equipment Required By Technical Specifications Minimize Station Activities During Critical Evolutions Minimize Potential To Reduce Decay Heat Removal Or Shutdown Margin Ensure Management Cognizance Of Plant Conditions And Work Activities Promote Self Check Program
Monitoring of Critical Plant Parameters During Plant Shutdowns e
- One Page Management Summary Focused On Critical Parameters
- Present Condition And Two Day "Look Ahead" Information Provided For Integrated Management Assessment On A Daily Basis
- Incorporated Into Outage Planning
- e e
Date:05-17-1991 NORTH ANNA UNIT 1 MODE 5 AND 6 CRITICAL PARAMETERS FOR 05-.17-1991 EMERG:NCY DIESB..
GENERATORS SERVICE WATER PUMPS CCMPO'JENT COO..ING PUMPS REACTOR CCXl.ANT SYSTEM INVENTORY AHR PUMPS lma BORATIO'J FLCJN PATH RCS BORO'J CHARGING PUMPS Parameter _{A~ce1u agl t_Rangl}
RCS Inventory (10-120 in.):
Boration Row Paths Available (0-4):
16 in.
4 Drained for RCS piping work.
All paths available.
Charging Pumps Available (0-3):
AHR Pumps Q:>erabl e (0-2):
CC Pumps Q:>erabl e (0-2):
3 2095 ppm 2
2 Service Water Pumps Q:>erable (2-4):
4 E~ Q:>erable (0-2):
2 STAIUS_OF_CHANGES~
RCS I evel remains at centerline +16
'A' I
'B' I
'B' TO AFWP RHR COLD PUMP LOO BCST I.. ;..~,... I uw LBVBL TO HOT LBG HH.11 TO HOT LOO -
HHSI TO cow LOO Surry Unit 2 CSD & RSD Critical Parameters Is~~ I I -
HHSI cc PUMP
'B'
'D' HHSI cc PUMP PUMP MANUAL
'C'
'A' BMBR HHSI cc BORATB PUMP PUMP aLUGnW I UNIT2 X-TIB
'B' RWST FROM cc UNITI PUMP RCS LBVBL J(l()II P'ZR.
RBDUCIID TR:HSPOC INVENTORY?
3.10 IN EFFECT?
NO NO I
'B' I
'A' RSST ESWP
'C'
'B' RSST ESWP UNITI BACKFBED
'C' AV.AILABLB ESWP CTMT CLOSURBOR INTEGRITY RF.QUIRED?
NO
,~~,
'B'MCR CHll.J...HR PCV-2455C PCV-I SOURCB RANGH 2456 Nl-32 TOCH SPEC I SDM*
3.1.0 479PPM MBT Condition Acceptable,
~
Component(s) Degraded or 1 Power Supply Unavailable Component Inoperable, Condition Unacceptable
Methods
- Construct A Comparative Matrix Of Shutdown T.S. For Mode Or Condition Versus Major Nuclear Safety Functional Goals.
These Goals Have Been Defined Within The Context Of The NUMARC Critical Safety Functions:
Containment Integrity Reactivity Management RCS Integrity Fuel Handling Decay Heat Removal RCS Inventory I*
e
Methods
- Compare The Key Shutdown Activities With The Supporting Systems Required And The Availability Of The Systems Based On The Existing Minimum T. S. Requirements
- Identify The Conditions Where The Administrative Controls (Procedures) Or Technical Specification Changes Are Needed To Ensure The Availability Of The Necessary Equipment
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