ML20149K028
| ML20149K028 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/24/1997 |
| From: | Raghavan L NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| CAL-2-97-01, CAL-2-97-1, NUDOCS 9707290208 | |
| Download: ML20149K028 (43) | |
Text
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July 24,1997 LICENSEE: Florida Power Corporation FACILITY: Crystal River Unit 3
SUBJECT:
SUMMARY
OF MEETING ON JULY 22, 1997, REGARDING CRYSTAL RIVER 3 RESTART PROGRESS On July 22, 1997, representatives of the Florida Power Corporation, licensee for Crystal River Nuclear Plant, Unit 3 (CR3), met with members of the staff at the U.S. Nuclear Regulatory Commission (NRC) Headquarters in Rockville, Maryland. Enclosure 1 is a list of attendees. Enclosure 2 is a copy of the handout distributed at the meeting.
The licensee presented an overview of its progress toward readiness for restart, including issues specified in the Confirmatory Action Letter (CAL No. 2-97-001) dated March 4, 1997 and discussed the effectiveness of its corrective action measures. The licensee indicated that it has established clear plans, schedules and metrics for performance measurement to support its planned December 1997 restart. The staff requested the licensee to establish good communication with them regarding the licensee's schedule for its licensing submittals and target date for staff review and approval. 1 I
/S/
L. Raghavan, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosures:
- 1. Attendance List
- 2. Meeting Handout cc w/ enclosures: See next page DOCUMENT NAME: G:\ CRYSTAL \970722. SUM mm l To receive a copy of this document, indicate in the box: "C" - Copy without "
\
)x attachment / enclosure "E" - Copy with attachment / enclosure "N" - No copy /
DOCUMENT NAME: G:\ CRYSTAL /97022. SUM Ts seceive e sepy of this document, indicate in the boat "C" = Copy without ettschenent/ enclosure "E" = Copy with attachment / enclosure "N' = No copy OFFICE PDil 3/PM l PD!l 3/LA ,, lCl PDil 3/0 i l l A.) l NAME LRaghavan [L, BClayton Af W FHebdon IN DATE- 07/2g,/97 07/ A /97 ' 07/).V97 OH ICIAL RECORD COPY e
3-W) t"* ' H CHg m COPY 9707290208 970724 PDR ADOCK 05000302 P PDR
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SUMMARY
OF MEETING Ott JULY 22, 1997, REGARDING CRYSTAL RIVER 3 RESTART PROGRESS Distribution: a usan enoY w/ Enclosures 1 and 2 4
d geghet file
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PUBLIC
-L.-Raghavan Crystal.-River Reading OGC -.
ACRS .
t E-Mail w/ Enclosure 1 !
S. Collins /F. Miraglia (SJC1,FJM)
R. Zimmerman (RPZ) >
Be Boger (BAB2)
J. Zwolinski-(JAZ) ,
, _F. Hebdon (FJH) :
80 C1ayton (BAC2)
D.- Ross (SLM3)
J.~Jaudon (JPJ) . ;
i H. Cristensen (H0C) *
.N. Dudley (NFD) !
-S. Cahill (SJC2) !
J. Johnson (JRJ) j L. Reyes (LAR1)
C. Julian (CAJ)
K. Landis (KDL)
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y g UNITED STATES l
e a NUCLEAR REGULATORY COMMISSION D f- WASHINGTON, D.C. 20656 4 001 l l \
, ,,,,,# July 24, 1997 l
l LICENSEE: Florida Power Corporation
. FACILITY: Crystal River Unit 3
SUBJECT:
SUMMARY
OF MEETING ON JULY 22, 1997 REGARDING CRYSTAL RIVER 3 RESTART PROGRESS 2'
On July 22, 1997, representatives of the Florida Power Corporation, licensee for Crystal River Nuclear Plant, Unit 3 at the U.S. Nuclear Regulatory Commission (CR3),
(NRC) met with members Headquarters of the staff in Rockville, Maryland. !
Enclosure 1 is a list of attendees. Enclosure 2 is a copy of the {
handout distributed at the meeting.
J
, The licensee presented an overynw of its prog: ess toward readiness for l restart, including issues specified in the Confirmatory Action Letter I (CAL No. 2-97-001) dated March 4, 1997 and discussed the effectiveness of its l corrective action measures. The licensee indicated that it has established l clear plans, schedules and metrics for performance measurement to support its planned December 1997 restart. The staff requested the licensee to establish good enraunication with them regarding the licensee's schedule for its licensing submittals and target date for staff review and approval. .
1 k -
L. Raghavan, Project Manager Project Directorate II-3 i Division of Reactor Projects - I/II I Oi.' ice of Nuclear Reactor Regulation
- Docket No. 50-302
Enclosures:
- 1. Attendance List
. 2. Meeting Handout cc w/ enclosures: See next page
.6 4
. i 4
i Florida' Power Corporation CRYSTAL' RIVER UNIT N0. 3 GENERATING PLANT cc:
. Mr. R. Alexander Glenn ' Senior Resident Inspector j ' Corporate Counsel- .
Crystal River Unit 3 Florida Power Corporation. U.F. Nuclear Regulatory Tommission MAC-A5A .6745 N..Tallahasseo Road P.O. Box 14042 Crystal River, Fl.orida 34428 St. Petersburg, Florida 33733-4042 Mr. James S. Baumstark
+
Mr. Bruce J. Hickle, Director Director, Quality Programs-(SA2C)
- Nuclear' Plant Operations (NA2C) Florida Power Corporation Florida Power Corporation- Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708
- Crystal River, : F1orida -34428-6708 .
Regional Administrator, Region 11 q Mr. Robert B. Borsum U.S. Nuclear Regulatory Commission
). B&W Nuclear Technologies 61-Forsyth Street, SW., Suite 23T85 '
1700 Rockville Pike, Suite 525 Atlanta, GA 30303-3415 Rockville, Maryland 20852 '
Mr. John P. Cowan Mr. Bill Passetti Vice President - Nuclear Production
! Office of Radiation Control (NA2E) i Departmeat of Health and Florida Power Corporation {
Rehabilitative Services Crystal River Energy Complex i 1317 Winewood Blvd. 15760 W. Power Line Street Tallahassee, Florida 32399-0700 Crystal River, Florida 34428-6708 Attorney General . Mr. Roy A. Andarson !
Department of Legal Affairs Senior Vice President, j The Capitol Nuclear Operations Tallahassee, Florida 32304 Florida Power Corporation ATTN: Manager, Nuclear Licensing
[ Mr. Joe Myers, Director Crystal River Energy Complex (SA2A)
Division of Emergency Preparedness 15760 W. Power Line Street-
- Department of Community Affairs Crystal River, Florida 34428-6708 i 2740 Centerview Drive i Tallahassee, Florida 32399-2100 Mr. Kerry Landis l
, U.S. Nuclear Regulatory Commission Chairman 61 Forsyth Street,.SW., Suite 23T85 Board of County Commissioners Atlanta, GA- 30303-3415 ;
Citrus County ;
110 North Apopka Avenue i Ivernessi Florida 34450-4245- i
- Mr. Robert E. Grazio, Director Nuclear Regulatory Affairs (SA2A) n Florida Power Corporation
' Crystal' River Energy Complex i
, :15760 W. Power Line Street ;
34428-6708 j ^ ${rystalRiver,. Florida -
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. . - . . . . . . . - . = . . - --. --- .~ -.
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CRYSTAL RIVER 3 MEETING-JULY 22. 1997 ,
I HAmt Oraanization
- Sam Collins NRC-NRR '
- Roy Zimmerman NRC-NRR-Bruce Boger NRC-NRR Luis Reyes NRC-RII Caudle'Julian NRC-RII L. Raghavan. NRC-NRR K. Landis- NRC-RII
- Johns Jaudon 'NRC-RII ,
1 Fred Hebdon NRC-NRR .
.Chris Cristensen NRC-RII ,
lS. Cahill NRC-RII.
John J. Holden Florida Power Corp. .
Mark Van Sicklen : Florida Power Corp.
. D.--Kunsemiller Flo.ida Power Corp.
[ John Paul Cowan Florida Power. Corp.
1 Roy. Anderson Florida Power Corp.
Thomas. Taylor Florida Power Corp.
Chip Pardee Florida Power Corp.
Jim Baumstark Florida Power Corp. l
. Jim Terry Florida Power Corp.
Robert Grazio Florida Power Corp.
Bruce Hickle Florida Power Corp. ,
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Y4.-+.Q 1 FLORIDA POWER CORPORATION
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- - .u CRYSTAL RIVER - UNIT 3
.-4 l rre CR.3 i
9 FPC RESTART !
m M PROGRESS n July 22,1997 d
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, f.
i 7/22/97 1
AGENDA
' FPC C.R-3 .
I
- ..:
- Opening Remarks
, R. A. Anderson
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j :
.j* Restart Status i
... J.P.Cowan ;
f '.'
- Engineering Progress J. J. Holden i
- c ' .~
- MCAP Progress )
J. S. Baumstark l
'I
- Condition of CR 3 at Startup /
v Metrics to Measure Performance B. J. Hickle
{
f .
- TechnicalIssues J. J. Ifolden l
- Operations Focus / Update C. G. Pardee
- '
- Concluding Statements R. A. Anderson i l
l 7/22/97 '
2 l
l l
l
l .' .
l' 1
i Current Status EE?s j Steam Generator inspection i
l
- FWP-7 Diesel Generator Progress i
- Turbine Generator Rotor Removal
) *
"A" Diesel and "A" ECCS Work i
Preparation i
- l 7/22/97 i 3 i
CR - 3 Readiness Program j
4 Objectives
[Nf3 1. Frequent Open Communications
- 2. Resolution of Confirmatory Action Letter issues
- 3. Close Book on First 20 Years of Operation
! 4. Invest for the Next 20 years of Operation l 5. Integrate Startup Activities into Long Term i improvement Plan i
Do What is Hight For The Long Haul, a
Not Just What is Required For Startup i 7/22/97 i 4 5
. . ~ . . .- - . - . . _ . . - . _ - - . . _ . . . . . . _ . . . . . . . . - . - . .. ...-
t 4
s 1
Restart Schedule
- FPC ='"0"" =***** "'"t* = ?" 0" " ='*c"='*0- =*"0" ' ?"4 ^~ " =
1 CR-3 o..ign And uc.n.ing a..i. R. 6.. I j m #eview Desena resee m
- e,-g-. . ,w Piant Modifications l 2 e nn..., aran m 2 tesarg ' m j Regulatory Requirernents YEcw spac me Aoere .e m senC Assten Aushenaar
)
i Procedure. And Traibang l 'm eop<ap op y amma m
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Startup t g a
"**'"' 'jg
{ 7/22/97
.' 8 4
i Confirmatory Action Letter FPC CR~3 i 1. Design issues identified in FPC Letter of 10/28/96
- , 2. Extent of Condition Reviews
- - 3. Resolution of Safety and Licensing issues 2
, 4. MCAP 11 Progress
! S. Regional Administrator Concurrence for Mode 2
-7 l
7/22/97 6
l
O Crystal River Unit #3 Restart Milestones
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- i ~ ._i J e Prenm.e] j a em.a.e 1 J s em.cs.e ] ] a e ,a.e [ _ l e rmence.e l l a reas.a.e L J 1r ev t.co.e g j a eves.cs.e j 1
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flGTSG Eddy Current {.
Appendix 'R' Mod w3 m InstmR R.B. Penetretbn Mod ~ . . . . .T.es.t.m.g..
3 y -
DG/ EFWInteraction
.e........................................... :
System Lineups, Heatup And Testina
_- ' EFW Cavitating Venturi Mod C ' 7 : '
2 Startup/ Power CRITICAL 93 i N Tce t Design & Work Pkg.Preparatson w < *cvc_ FWP-7 Standby Generator Mod Escalation PATH i inM4M EX3(MFet%T?pMi& -- G R .Me '
EFP Defeat Switch Mod v _ HPl Cavitating Venturi Mod ;
"A" EGDG Work ['D' EGDG Work _
EFV-12 Valve Mod .
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l D.H. System Vent Mod
. "3" Side sASV.204 Med : *
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D.H. System Vent Mod "A*SMe EFIC Module Mod w e
RWP/SWP PTL Mod MOV-27 Auto Closura f yy y g- % R_B. ThermalReEef Valve Mod y- - . .-
EP-2 Flow indacation N oid Remote S/D isofation A :
G o - . . . . . . . . . .R.m.B.u.il.d.in.a.S.pr.ax.P.u.m.p (B.S.P.18.).N.P.S.H.
.......h LPt Pump Messson T,irr , = ,<ac C*as8*.
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7*
'e "jReview
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DeMgn, Bads Q~"c" n . Y' -
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^ :>(i.A NRC Restart Authorization
.7.D ***. . . .. ^ System Reediness Wathdowne " >
C*"*""*****'""** ~
NRC Reviews I
w.ek rai.n a
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .ECH T SPEC Changes /Approvat Integrated Verification 7
__ __ - _ _ _ _______ ____ ____ _________________ _ _ _ _ m __ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ - - _ _ . . _ . _ _ _ _
) *
?- Resolution of Confirmatory
~
Action Letter Design ssues l ,
FPC CR-3 From RC LeMer of 10 28 96 '
i Design issue Description NRC Briefings Nf!C Sasieneettal & Modencatloa
, Tects Staff Restart Fanni FolknHsp Briefted " fork Testlad Coasp_iese A. HPI Punsp Recirculation IJee Comeplete Complete None / TBD 25 % Oct New i B. HPt Systems Modifications
',~ ;'l Cosuplete Cossplete Comeplete 45 % Jul . Nov Nov
.-' O.1Pt Puasp Ma6sion Tlase Complete Cosnplete Complete
. -f 90 % Consplete Sep D. Reactor Butiding Spray Punny Complete Casuplete Ainsi/ TBD 90 % Aug Anag
-NPSH
.; E. Emeergency feedwater Splene Cotaplete Complete Comeplete / Jeal 21 75 % May - Aug Sep
- j'- ased Olesef Generator
- t. mad Inspact
...- . .. ; F. Emeerger:ty Diesel Generator Complete Complete Ceeplete /TBD 70 %
Jiel - Sep Sep g
1.sading
..;- G. Failure Modes and fftects Aug Aug Aug 30 / Aug 90 % Jul Sep
.. AnaJysts of 1. ass of DC Power
.- '. H. GI. 96 Containment Cossplete Comp!lete Complete PMranons 65 % Aug - Sep Sep -
c -
, . . f-7/22/97 '
8 '
f l
Design issues identified in l
FPC Letter of 10/28/96 i E'3
' < A.
H.Pl Pump Recirculation Line l }' - Directs Hecirculation to the Reactor
-l Building Sump i
- 4 Valves (Operated from the Control l
Room) Will be Installed I
l j 7/22/97 l
Design issues identified in FPC Letter of 10/28/96 l FPC
! B. IIPI S: stem Modifications i 3 (SB LvCA Improvement) l
- l
- HPl Cavitating Venturis j l
- Installed / Tested / Hemoved / l Spool Pieces Installed j
- HPI Crosstle Piping / Valves l
- Evaluating l 1 .
- MOV-27 Normal Make-Up Automatic l j 7/22,,, Isolation i
- *
- Installed and Tested ;
i i
i l
i-4 1
1 l
Design Issues identified in l
FPC Leuer of 10/28/96 O. LPI Pump Mission Time i
l - Manufacturer Performed Rigorous 20 Day i Test i
1 -Increased Mission Time to One Year at Low i Flow
! - Restart issue Closed by FPC
- )
i i l
7/22/sr
! l l
i f
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Design issues identified in j ;c . FPC Letter of 10/28/96
, D. Reactor Building Spray Pump ;
(BSP-1B) NPSH
- i
- BSP-1 A impeller Modified, Installed, and i Tested
. l l - BSP-1 B Impeller Modified and Installed
- Gained 3 Feet of Water NPSHa i
7/22/97 .
12 l
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1 4
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4
_ Design issues identified in j
, E. Emergency Feedwater System and Diesel Generator Load Impact l
i
, - Ecaergency Feedwater Cavitating Venturis j
- Installed and Tested I 1
- . - ASV-204 Steam Driven Emergency
?
Feedwater Pump Steam inlet Valve ,
- EFV-12 Emergency Feedwater Pumps I l
Discharge Crosstie Valve
- '**f *
- Installed l i I
j
~ -
Design issues Identified in FPC Letter of 10/28/96 i
MS l g4 F. Emergency Diesel Generator 7'
(EDG) Loading
- Upgraded Both EDG Engines l .
- - Currently Planning Radiator Changeout
-Improved kW Meter Accuracy t ..
i
- 7/22/97
! 14 i
I
i i
l Design Issues identified in l
j '
FPC Letter of 10/28/96 cE's
! -- G. Failure Modes and Effects Analysis j o (FMEA) of Loss of DC Power (SB LOCA / LOOP / DC Failure)
! . - 21 Systems impacted l .,
_ .,- - Analysis Complete - including Third Party Review j
- Currently Performing 120 v AC Load ra2/sr Study j 15 1
l Design issues identified in j - .
FPC Letter of 10/28/96 FPC H. Generic Letter 96 ! .
Containment Penetrations
-Thermal Helief Valves 1
- 39 Planned to be Installed This Outage
- Expansion Chambers
!
- All14 Installed I
ra2j.
l
, . l Extent of Condition i FPC i CR 3 p
Increase Margin ,
i
- Reduce Operator Burden w
j
= Defense-in-Depth 1 i
- i
! 7/22/97 17 i
Extent of Condition i FPC
' CR-3
- Reasonable Assurance That CH 3 Will Operate Within its Design and Licensing Bases j - . CR 3 Can Mitigate All Design Basis Accidents I !
j i l I
%fodifications System Configuration and Focused Readiness Document 3
Reglew Reglew Integration of Programs Program Project
- 7/22/97 _
18 1
4 i
r .
I i
Emergency Diesel l Generator Power Upgrade MS '
. \
- Part of a Three-Tiered Approach l l -EDG Power Upgrade l l
-EDG Load Reduction
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l
-EDG Margin Verification l
-i <
] 7/22/97 19 l
l I
- Emergency Diesel i
- Generator Power Upgrade FPC cR-3 Sept'96 July '97 i
Old ED_G Ratings New EDG Ratings j 30 Min 3500 kW 30 Min 3500 kW
{ . 200 Hr 3250 kW 200 Hr 3400 kW 2000 Hr 3000 kW 2000 Hr 3200 kW j Contin. 2850 kW Contin. 2850 kW l
l Auto Connect Load Auto Connect Load 3159 kW 3057 kW !
[ 7/22/97 20 i !
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MS l System Readiness Review 1
1 I
i 1
.i l 7/22/97 l 21 2
System Readiness Review l MS i .
Level 1 and Level 2 Systems i
j Represent Essentially 100% of l
the Systems impacting Core
! Damage Frequency l
7/22/97 l 22 l
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e i
) System Readiness Review l
Assessment Completion i !!S j
Level 1 Systems -
100%
Level 2 Systems -
100%
- Level 3 Systems -
100%
i 7/22/97 23
}
)
l System Readiness Review
! Attribute Evaluation 4
! FPC l Level 1 and Level 2 l Attribute Checks 16096 l
SAT Discrepancy Reportability j .
14573 1523
\
Work Controls
/\ Restart I
4 Process Issue 24 1302 221
. _ _ _ _ - - . ~ _.- - - - . .
4 e i
t Configuration Document i
integration Project 5
.
- Project input Information From
- - System Readiness Review, Precursor i Cards, Problem Reports, Docket Review, J Independent FSAR Review, Individual Reviews, Modifications, Analyses
,
- Consolidate Information into Specific Plant System Information Sets j
- Resolve Open items
!
- - l l
j Configuration Document l
.J Integration Project Status i FPC l
- Compiled All 49 System j Information Sets I l
- 1320 items in the Database
-320 items Resolved l -1000 Items Being Worked i
j 7/22/97 L- ---- - ------ - ----- ---- - - - -- - - --- _ _ - . - - -- _
l l
l MCAP 11 Update l FPC C"'3 i
Ahead of Plan:
i .
- 90 items Complete j - 58 Items Remain to be Completed Effectiveness Assessment Scheduled for l August j 7/22/97 27 i
s MCAP 11 Update EN's j
- Restart items Progressing j - 19 Restart items Complete j - 13 Restart items Remain to be Completed
- Due Dates for Two items Revised to August Due to Scope Expansion i4 i 7/22/97 28
. O
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1 FPC j CR3 J
l J
j Condition of CR-3 at Startup d
Metrics to Measure i Performance !
4 1
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, T!22/91 29 l
i i
l l
Condition of CR-3 lI at Startup FPC CR3 i Performance Indicators Goal at Startup l
Organizational Readiness j
- l
- Restart issue Closure 0 l
- MCAP ll Restart item Closure 0
) - Self-identined Precursors 60 % or Greater
! - Self-identined Violations 67 % or Greater i
- I
- System Readiness l
- Corrective Maintenance 200 0 pen horli ttequests i or Less
- Temporary Modincations 5 or Less l - Requests for Engineering Assistance 200 Open or Less j - Restart Modifications 0
- Systems Remaining to be 105 Systems Accepted l 7/22/97 30 Accepted by Operations i
l
s 1
i Condition of CR-3 l at Startup FPC l Perforniance Indicators Goal at Startup l
- Operations Readiness j - Control Board Deficiencies 10 or Less g - Operator Work Arounds 7 or Less j - Operating Procedures 25 Comments or Less l - Emergency Operating Procedures All EOPs issued i - Abnormal Procedures 15 Comments or Less
- Regulatory Readiness
! - Ucense Amendments and Tech Spec Submittals All Submittals Made j
- Other NRC Restart Submittals All Submittals Made
- Total 1997 Commitments Complete l
7/22/97 31 Condition of CR-3 i
i at Startup 1
4 FPC CR-3 pgg gg , g,gg 1
A
- Communications Readiness ;
l j
- Employee Surveys improving Results
- Community Leaders Meet Prior to Startup j
- State & Federal Officials / Staff Meet Prior to Startup j
- Opportunity to Tour Plant All Elected Officlafs and i
Staff invited to Tour 4I - Open Communication with Media Editorial Boards, interviews, and Plant Tours Conducted for Those who d
Routinely Cover CH-3 i
i q 7/22/97 32 i
i l
l
! Organizational Readiness
- Restart issue Closure FPC CR3 200 -
l 180-l g 160 - .'
i 3 140 - \
f 120 -
f 100 -
g 80 m Adddlons
\ N l
60 - Octosed N
! 40 -
~ ' ' ' \
-o workoff zs g j g _
-Actual \
O I . t .
, Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 7/22/fs7 j 33 i
i i
)
Organizational Readiness MCAP 11 Restart item Closure FPC C R.3 -Coat = 0 I
-o Workof.'
~~ ^ C 'U * '
! 20 -
i 2:
i e M
i 5-s g_
N O - : .
, Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
, 1997
! 7/22/97 34 i
i l
i J
- _ Organizational Readiness i
Self-Identified Precursors I
a FPC
~
100, C3 Actual (Rolling Average)
'*~ ""%'O'**'
U 90 - - Actual (Monthly) 4 4
g 80 -
o j l 70 -
1 y 60 - - . - - - -
4 %0 "
i j 30 - ;
i $ 20 -
! E 10 -
! E O l
l Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l l 1997 i 7/22/97 j 35 Organizational Readiness
, Self-Identified Violations FPC CR-3 C2 National (Average) l 100-
- 90 - ---Goat = $7% or Greater S g 80 - - Actual (Average) l b ; 70 - - - _ _ _ _ _ _ _ _
4 E $ 50 -
h 40 - _
, . . 30 -
u 0 s-=
l g $ 20 -
10 -
l
! O Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
~
1997 7/22/97 3
36 4
9 f
1 l Organizational Readiness Total Number of Open Precursors
=
j .
l FPC CR-3 2000 1800-I $ 1600 -
l $ 1400 -
j y 1200 -
$ 1000- s3s 8 800 - me PCs Opened I
S 600 C3PCs Closed 2
! 400- -PCs Total
-PCs Restart 200" -e- Action Plan
] .
j 0* ,
j Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 7/22/97 l 37 i
)
' System Readiness i
Corrective Maintenance
! FPC i
- f3 . 1000-
{ , j 900-4 8 800 -
60 ,
o 500-1 N '
mag incommg 1 o Clll3 Completed w 2ss
! 300 - -coat = 20o or Less
- workoff "8 i 200 - ; ;
y ~*** Actual 1 z 100- __,_,,,,,,,p;,,
O q
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 7/22/97 38 i
4 L
4
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System Readiness Temporary Modifications FPC
--*--Goal u 6 or Less Prior to Heat Up 10 - a workort
=* Actual p 9' i 8.uc7 -*-S.,
s!S6*
N a \
g j 5- - g -- -
~g4- % ;
N f 2 3- 2'
- ! 1 i o Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l 7/22/97 j 39 4
5
! mm4 -
System Readiness Requests for Engineering
~
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FPC Assistance (REAs) i 800 - --*-,(Goal rgHeat=Up 200 or Less
! 700 - ,
600 - \, _,_,_,
g, ,e,,3,n pi,n j I
- i g 500-400 -
\
A '
8 300- n "*
z 200 - g RgA, n,c.iv,4
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100 O REAs closed 1
0 , , , , ,
l Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 7/22/97 i 40 t
a 1
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System Readiness l
- Restart Modifications i FPC
~
60 - coal e O Prior to
- NSLUoH 50 - 3%
{ *E 4g . -*- Action Plan h f h 30 -
$$ 20 -
l2 10 -
Field Complete O . .
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997
! 7/22/97 41 i
i i System Readiness )
l Systems Remaining to be l Accepted by Operations i FPC CR 3 ,
I '
g f 100 -
l l ,
f k 80 - '\
- =2 60 - \
i g
, 8o E f gn . %
!.5 -+-coal = 0 Prior to Heat Up \
Z $ 20 - ~* '* *'" \
$ ~ Actual \
0 . . . . . . . - \ ;
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 7/22/97 1 42 l
l 4
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l l l i
Operations Headiness l l
=
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l FPC l
. CR 3 -coal = 1o or Less at stan up 1 25
- Actual i
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U0-8
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l j$,10 --
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$$ 5- ,
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1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec ;
l 1997 i 7/22/97 i
- 43 i
- l i
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Operations Readiness )
4 Operator Work Arounds I
! FPC CR 3 g.,, , y ,, t,,, prio, ,, g, ,, up 40 - .wyg ,,
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- g 1 ] . 30 -
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Og 1
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$ k 15 - % \
E3 10 - \
j g %
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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 7/22/97 1997
] 44 I I
l I
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, .3 ,w Operating Procedures .
., g h FPC i C R-3 1000 -
j . - -
m 900 -
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,8. y $ 800 -
jE 700 -
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l .- -
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\
l '. .- L g
21] A!? 200 - ~
100 -
.'?... 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 7/22/97
- 45 i
i i
Operations Readiness
- Emergency Operating Procedures l FPC l
, CR3 140- I
,, a y
g 120- g
.8 j 100 - \
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. .' Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997
, 7/22/97 46 i
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i l Operations Readiness Abnormal Procedures FPC 160 - _,
! '. p3 140 \
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j E 120 - \
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! .'.. Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l -
1997 1
7/22/97
! 41 7 i
I l . Regulatory Readiness l License Amendments and i-s# /.
Tech Spec Submittals j 1 FPC l l CR-3 j auss Aciditions
- /s 25 - _ o,,i , o ;
- ==o WorkoM I
- A- -- Actual 20 ]
h -e- Action Plan j 15 -
$O j 10 - \ '" 's 1
g 1
, s N= ,
B 5- i i '? , z 'N N l 0 " E " E .
- Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l f 7/22/97
, 48
v ..
l
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i mm Regulatory Readiness
> Other NRC ;
s '"4 Restart Submittals FPC l CR.3 m AOdctions l 33 C=3 Submitted l
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j 5- % .g%, j 0 . , -
Jan Feb Mar Apr May Jurt Jul Aug Sep Oct Nov Dec ;
l 7/22/07 80
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l
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! , Total 1997 Commitments l
- -x .
4 FPC i unum Received
' C=Ictosed 200 l j -
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= 140 N
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- 1. o 80 - N s I j 60 - N
! E 40 - s='
$ 20 -
i 0 . . . . . . . , N Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
$- 1997 l 7/22/97 j So 4
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4 Regulatory Readiness
.L Other NRC
- Restart Submittais FPC CR-3 25
"'" Ad8't'o".
l !=l35ubmitted
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\ N, -. Action Plan
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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 7/22/97 49 i
. -:r=
Regulatory Readiness yg ~ , Total 1997 Commitments l FPC
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! PC 3 Closed g180 ,_g,,,,,
o 160. / N .m,g o rr
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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 i 7/22/97 j
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- 2 Communications Plan l Organizational l
l -
/ Communications Effectiveness FPC ca.3 _ gpjg ,
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me informed fl I understand critica: 3 l
restart issues =
i 111. I understand safety ref,ulations and standards {
[
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. ma and how I fit into the
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! materials enhance my understanding of Cit-3 Issues o -
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1 l l 4 l Communications Readiness 5 NC3 1
- FPC Community Meeting, June 19, l i 1997 in Crystal River !
l
- FPC Community Meeting Scheduled i for the First Week in August at j inverness 4
4 l
- FPC Speaker at Meeting in Inglis /
l Yankeetown Being Arranged i 7/22/97
, 53 1
)
l Technical Issues I
! FPC j"l'
! .Y... .
Oprate I ;j
- Proposed Resolution to IN 92-18 (Appendix R) l (]
i
- Boron Precipitation I
- HPI Nozzle Non-Destructive Examination
- Unresolved issue A-46, Seismic
~
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! EES
- Improve Performance in
-Operations Ownership l -Plant Configuration Control 4 ,
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) 7/22/97 J 55 i
Operations Focus Areas i !!S
..5.. . .
Reduction in Watchstander Distractions
- -Move Non-Critical Functions Outside of Control Room i
. -Focus Operating Staff on 1
= Striving for Flawless Execution Proactively Identifying / Driving Issues 7/22/97 S6 l
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-Control Room Formality l
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l -Self Assessment Effectiveness i
j 7/22/97 57 Operations Focus Areas I !!S l .
-
- Staffing / Organization Structure l -Clarity of Roles and l Responsibilities
-Staffing Levels l
l l
7/22/97 89 i l
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Operations Readiness 2 For Restart
~
i L FPC CR-3 JUL AUG SEP OCT NOV DEC l l 1 I I I I i
' 1997 1998 OPERATING AND ABNORMAL PROCEDURE UPDATES A N
,, a EOP TRAINING (CLASS ROOM & SIMUIATOlt) m MODIFICATION TRAINING i p
PLANT BENCIIMARKING VISITS 2
m m n
SECO,NDARY PLANT OPERATOl{ CLASS (8) 2 MODIFIED SilllT SCIIEDUI.E m i
N .
OPERATOR WATCJSTANylNG ASSESSMENT i
, INSTANT SRO CLASS 07/98
- r Ol'ERATOR ANh]AL ltEQUA{FICATION EXAMS r "
l .
OPERATIONS INTEC D SELF- ASSESSMENT
' - i STARTUP TRAINING-CLASS ROOM l
+
[. 'o STARTUP TRAINING 2 w
-SIMULATOR ,
m r 7/22/97 I' 59 I
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- j.
NRC RESTART L[ CENSING SUBMITTAId ,
l Restart License Amendments l l
Submittal Luut Ra.ts i
- 2. Decay Heat - Flow Instrument Removal Complete l 6/26/97 )
- 3. Appendix R Thermo-Lag Resolution Schedule (letter to address exemption request) 7/25/97 (N) 1
- 4. Appendix R 10/8/97 (N)
- a. (III.O - Reactor Coolant Pump Oil Cooling) Potential Exemption withdrawal or ;
revision - When "A" pump is in compliance
- b. Exemption Request for Lube Oil Fill Line (N)
- 5. Low Temperature - Over Pressurization (LTOPs) - Code Case N-514 exemption Complete 4/7/97
- b. 30 EFPY License Amendment (not needed until cycle 12)
(N)
- 7. Letdown Rupture Line (Potential USQ) 9/15/97 (R)
- 8. Integrated Leak Rate Test, App. J Option B Complete 1 2/1/97
- 9. Integrated Leak Rate Test, App. J Option B, Rev.1 Complete 5/1/97
- 10. App. J. Option B .Additionalinformation (LLRT Results) 8/4/97 (N)
- 11. System Readiness Reviews (potential License Amendment) Resolved
- 12. License Condition Amendment (if needed) Resolved Items 13-24. Potential USOs Submittals-
- 13. Emergency Diesel Generator Protective Trips during Engineered Safety 8/25/97 (R)
Actuation and Loss of Offsite Power
- 14. HPI analysis (without cavitating venturis) Complete 6/14/97
- 15. HPI Pump Recirculation Resolved
- 16. High Pressure Injection Nozzle Cycles (Contained in the FSAR R.23 7/3/97 Resolved letter and not a USQ)
- 17. Air Handling Filter-1/2 Testing Requirements 7/30'97 (R)
- 18. Makeup Supply Valve (MUV-27)- Add automatic closure upon receipt of Complete
- 1500 signal 6/14/97
- 19. EDG Fan Upgrade 8/25/9"' (N) 1 w . - - - - - - - _ - - - - - - _ . - . _ - - - - - - - _ .
fo .. - u 9-NRC RESTART LICENSING SUBMITTALS
- 20. ' Atmospheric Dump Valve (ADV) design capacity . 8/25/97 (N)
. 21. Operator Actions for EOPs and APs 9/30/97 (R)
' 22. Remote Shutdown Panel Added Components 8/25/97 (N)
- 23. RW Cyclone Separator Fouling Resolved
- 24. MUV-31 Control Logic Reso'Ived j 1
I
- 25. Once Through Steam Generator (OTSG) License Amendment 211, Rev.1 Complete 3/27/97-
- a. OTSO, License Amendment 211, Resubmit Sholly Notice Complete !
5/1/97 (N) !
- b. OTSG Response to Additional Information Request from NRC (add language 8/18/97 (N) I to address plugging criteria for identified IGA growth)
- 26. Post-Accident Monitoring (PAM) Table Revision , TSCRN 209, Reg. Guide 1.97 7/25/97 :
Issue (EDG kW Meters)
- 27. ECCS Mode 4 Tech Spec Change 9/1/97 (N)
- 28. Control Complex Habitability Envelope Surveillance Tech Spec (submitprior to 11/24/97 Restart)
- 29. 500 kV Backfeed Tech Spec Change (not needed before restart) Resolved j (N)
Licensing Restart Submittal (Non-License Amendments) t
- 1. Boron Precipitation Letter (May result in a license amendment) 9/2/97
- 2. Appendix RIssues:
- a. Independent Assessment Summary Complete 7/3/97
- b. Appendix R - Revise response to address 72 hr. cold shutdown (NRC RAI 7/7/97) 9/1/97 (N)
, c. Appendix R - Thermo-Lag ampacity (NRC RAI) Complete 7/3/97 (N)
- d. Appendix R - NRC Information Notice 92-18 (Hot Shorts) 8/8/97 (N) 4
- e. Appendix R - Submit description ofissues related to Restart Issue D-11 to 9/25/97 (N) support NRC plans for close out (NRC 7/7/97 RAI)
- 3. System Readiness Review - Summary Report 11/5/97 t
- 4. Generic Letter 96 Summary Report 8/22/97 (R) 2
j .. - e
' ' ' '^ '
N}LC RESTART LICENSING SUBMITTALS 5 '. FSAR Revision 23 - USQ Review ' Complete 7/3/97
. 6. Generic Letter 96 S"mmary Report il/15/97(R)
- 7. Tendon Surveillance Report (If needed)' 9/15/97
- 8. ' Maintenance Rule Structural Baseline - Walkdown Summary Report 9/30/97 (R)
- 9. In'tegrated Safety Assessment of Current Outage Modifications - Summary Report 10/27/97 fl0. FSAR Rev. 24 submittal 12/4/97
- 11. Restart Request Letter 12/1/97
- 12. RCS Attached Piping - Respond to NRC 4/7/97 Letter Complete 6/17/97
- 13. Loss of DC Power, Failure Modes Effect Analysis - Summary Report 8/30/97 (R)
- 14. FSAR Rev. 24/25 Upgrade Program Description Complete 7/17/97 (N)
- 15. 50.54(f) Letter to address discrepancies (If needed) 8/19/97 (N)
- 16. Review ofImplementation of License Conditions Complete 5/20/97
ll 7
- a. Letter to confirm calculations (EDO Loading, Block Valve Cycling) 9/15/97 (N) i
- - i
- 18. Licensing Basis for Dynamic Loads:
- a. Initial Response (pipe whip) to NRC 4/10/97 letter Complete 6/5/97 (N)
- b. Supplemental Response (re Jet impingement)to NRC 4/10/97 Letter 9/26/97 (N)
Complete
- 19. Low Pressure Injection - Mission Time 5/15/97 Complete
- 20. Appendix R - Atmospheric Dump Valve 30 day Response 4/30/97 Complete
- 21. Sys:em Readiness Review Plan 3/27/97 3
Qo . , .
3 NRC RESTART LICENSING SUBMITTALS Complete
. 23. GL 96-06, Letter regarding Service Water fittings 4/30/97
- 24. ASME se; ion XI - Code Case Relief Request - N509 Complete .;
3/24/97
- 25. MCAP II, Rev. 2 Complete ,
4/25/97
- 26. ITS Bases Submittal Complete 4/18/97 .
k
- 27. Letter on Pressure Locking re. EFV-12,32,33 (Supports SERfor GL 95-07) 8/l1/97 (N)
- 29. Temporary Waiver of Compliance for CCHE Modifications (FSAR Requirements) ' 9/2/97 (N)
(N) New (R) Revised I submittal. doc.7-14 4
1 J
1
] _
4
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