ML19332F097
| ML19332F097 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/30/1989 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Wilgus W FLORIDA POWER CORP. |
| References | |
| NUDOCS 8912130399 | |
| Download: ML19332F097 (83) | |
Text
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~ OFFICIAL f,
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k[A NOV 3 01989-oy Docket No. 50-302
- License No. OPR-72
~ Florida Power Corporation Mr. W. S. Wilgus _
'Vice President, Nuclear Operations ATTN: Manager, Nuclear Operations
. Licensing P, 0. Box 219?NA-21 Crystal River, FL 32629 Gentlemen:
o'
SUBJECT:
~ MANAGEMENT MEETING
SUMMARY
- CRYSTAL RIVER UNIT 3 This letter refers to the meeting which was held at the Crystal River facility at.our request on October 18', 1989. The purpose of this meeting was to discuss the various topics of current interest and take a plant tour.
'It 'i_s: our opinion that this meeting was beneficial and provided a better
-understanding of the issues and-status of current programs.
-I'n = accordance with~ Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures-will be'.placed in-the NRC Public Document Room'.
- Should you have any questions concerning this letter, please contact us.
1 Sincerely, Or% r1 Signed By, 1 i.. Aillhoan i
Stewart D. Ebneter i
Regional Administrator j
]
Enclosures:
1.
' List of Attendees j
2.
Meeting Agenda j
3.
Meeting Summary J
4.
Meeting Handouts cc w/encis:
(See page 2)
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- 8912130399.891130 PDR. ADOCK 05000302 P
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l Florida ! Power Corporation 2
N OV 3 0~1989'-
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I' cc w/encis:
L Gary. L. Boldt Vice' President, Nuclear Production Florida Power. Corporation i
P.-0. Box 219-SA-2C Crystal' River, FL-32629
[
P. F. McKee, Director Nuclear Plant Operations
~
Florida Power Corporation-
.P. O. Box 219-NA-2C.
l
~ Crystal River, FL 32629 R..C. Widell,. Director Nuclear ~ Site Support.
. Florida Power Corporation-
-P. 0, Box 219-NA-21 Crystal River, FL 32629.
- A.'H. Stephens reneral Counsel y
Florida Power Corporation MAC - A5D~
P. 0. Box.14042~
St, Petersburg,-FL 33733
' Attorney General.
' Department.of Legal Affairs.
l:
.The': Capi toi.
l
. Tallahassee,!FL 32304 J
Jacob Daniel Nash Office of Radiation Control i
4
< Department'of Health'and
- Rehabilitative Services 1317 Winewood Boulevard Tallahassee,'FL 32399-0700 LAdministrator Department:of' Environmental Regulation Power Plant Siting Section State of Florida
~2600 Blair Stone Road Tallahassee, FL 32301 7
-(cc w/encls cont'd - see page 3) h
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L Florida Power Corporation-3'-
NOV 8 01989 ri (cc w/encls cont'd) 1 state' Planning-and Development.
L
-C1'earinghouse c
Office of Planning and Budgeting
'~
Executive Office of the Governor
.The Capitol Building
,~ x Tallahassee, FL 32301.
' Chairman Board of County Commissioners Citrus County.
110 N. Apopka Avenue
-Iverness, FL 36250 Robert B. Borsum-.
Babcock and Wilcox Company Nuclear Power Generation Division
- 1700 Rockville Pike, Suite 525 Rockville, MC 20852-1631
. State of Florida
!bec w/encls:
-Document Control Desk NRC Resident Inspector U.S.-Nuclear Regulatory. Commission 15760 W. Power Line Street Crystal River, FL -32629-
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O ENCLOSURE 1 s
LIST OF ATTENDEES j
i NRC-I S. D. Ebneter,-Regional Administrator
- L. A. Reyes, Director,, Division of-Reactor Projects (DRP)
P. Holmes-Ray, Senior Resident Inspector, Crystal River.
S.;J. Vias, Project Engineer, Reactor Projects Branch 2, DRP W. Bradford, Resident Inspector, Crystal River
' E. W. Merschoff, Deputy-Director, Division of Reactor Safety (DRS) i P. - Fillion, Reactor _ Inspector, Plant Systems Section, DRS 1
G. C. Lainas, Assistant Director for Region II Reactors, NRR i
H..Berkow,= Director, Directorate'II-2, NRR l
H. Silver,' Project Manager, NRR
' FPC:'
B.= L. Griffin, Executive Vice President W -S. Wilgus, Vice President, Nuclear Operations
- G.~ L. Boldt,'Vice President,uNuclear Production
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P. F. McKee, Director, Nuclear Plant Operations E. E. Renfro,: Director, Material and Control
]
E.:C. Si:pson,1 Director, Nuclear Operations, Engineer and Projects-r G.;Westafer, Director, Quality Programs
-l R'l C. Widell, Director, Nuclear.0perations, Site Support J. Alberdi, Manager, Nuclear Plant Technical Support
~ K.-Baker, Manager, Nuclear Conf. Management J._ Cooper, Jr.,-Nuclear Technical Support Superintendent "j
B. J. Hickle, Manager, Nuclear Plant Operations G.'A. Longhouser', Nuclear Security Superintendent V.. R.'Roppel,_ Manager, Nuclear Plant Maintenance F. X. Sullivan, Manager,' Nuclear Plant Systems P.'Tanguay, Manager, N0E j
K.- Wilson, Manager, Nuclear Licensing su j
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MEETING AGENDA.
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LNRC/FPC MANAGEMENT MEETING-
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. CRYSTAL RIVER FACILITY:
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- CYRSTAL RIVER, FLOTIDA P
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OCTOBER 18, 1989 8:00 AM.
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Introductions
Introduction of Engineering: Topics-a
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- 1)D UpdateLon: Current Electrical Issues
- 2) ' ' Corifiguration Management x, ' '
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Engineering 1.0verview -
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.4)'2-Systems Engineering-
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LOpen Discussion:
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ClosingiRemarks; f
. Tour of=CR-3'-
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ENCLOSURE 3 MEETING
SUMMARY
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'On October 18, 1989,- a meeting was held between Florida Power Corporation and l
the NRC Region II Office at the Crystal River Facility, to discuss various topics of current interest and take a plant tour.
l i
The Vice President - Nuclear Production, Mr. G. L. Boldt, opened the meeting with a general overview of Crystal River Unit 3, and their appreciation of being-allowed to give a comprehensive presentation of the current efforts at the facility.
-Mr. S. D. Ebneter, the Regional Administrator, for NRC Region II, then stated that the NRC was there to obtain a clear status of their programs and' initiatives to enhance the safety and operability of the facility.
i The licensee then proceeded into specific presentations on topics of current
)
interest, beginning with an introduction of various engineering topics.
l Presentations were made in the areas of:
an update of current electrical issues; status of the Configuration Management Program; an overview of the
-engineering efforts; an introduction of the Systems Engineering Program; a presentation of the maintenance program; an overview of current practices and efforts of. the operations staff and plant operations; a status of the radiological controls and chemistry program; and an overview of the Technical Support Staff and their efforts in the ISI and Security areas.
l The formal presentations were then followed by open-discussions, and concluded with closing remarks by the senior management for Florida Power Corporation and
~
the - NRC.
It was noted by the NRC that this meeting was very comprehensive and thorough, which contributed to a greater understanding of the comprehensive programs and initiatives being undertaken by the licensee, to improve safety and long term reliability of the facility. The formal meeting was followed by plant tours conducted by licensee senior management.
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ENCLOSURE 4
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4-7 STATUS OF ELECTRICAL a
ISSUES.AT CR-3 t I h
STATION BATTERIES SECOND LEVEL UNDER VOLTAGE RELAYS (SLURS)
DC COMPONENT VOLTAGE ISSUES ALTERNATE OFFSITE POWER SOURCE EMERGENCY DIESEL GENERATORS ELECTRICAL CALCULATION ENHANCEMENT PROGRAM
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STATUS OF CR-3 BATTERIES l
THERE ARE FOUR ISSUES RELATED TO THE CR-3 BATTERIES O
E
' AGE OF EXISTING BATTERIES
. BATTERY PROFILE CALC UTILIZED INCORRECT COMPONENT LOADING TIME L
PROPOSED TSIP TECHNICAL SPECIFICATIONS FOR CR3 l
STATION BLACK 0UT (580) EVALUATION BATTERY. AGE CR3 BATTERIES ARE RELATIVELY NEAR THE END OF THEIR 20-YEAR DESIGN LIFE CR3 BATTERIES HAVE BEEN A GROWING MAINTENANCE CHALLENGE FPC INTENDS TO REPLACE ALL 232 BATTERY CELLS AT CR3 WITH THE VENDOR RECOMMENDED REPLACEMENTS DURING REFUEL 7 (SPRING 1990) 4 n
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BATTERY PROFILE CALCULATION WAS REVISED TO REFLECT THE CORRECT LOADING TIME FOR TSB-10 AND REBALANCING OF "B" BATTERY LOADS PROFILES TO WHICH BATTERIES WHERE PREVIOUSLY TESTED WERE FOUND TO BOUND THE REVISED BATTERY LOADING i
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-TSIP THE PROPOSED-TECH. SPEC. WILL REQUIRE FPC T0 COMPLY WITH THE REQUIREMENTS OF IEEE 450 AND-i 485 REGARDING THE SIZING, MAINTENANCE AND TESTING 0F BATTERIES ANY CHANGES REQUIRED WILL BE IMPLEMENTED AT CR3 DURING REFUEL 7 AND/OR PRIOR TO IMPLEMENTATION-0F THE NEW TECH. SPEC.
S80 CURRENT SB0 SUBMITTAL REQUIRES THAT DC CAPACITY-BE CONSERVED BY USING THE REMOTE SHUTDOWN PANEL TO MITIGATE THE EVENT RATHER THAN THE MCR.
FPC-HAS DECIDED THAT THIS APPROACH IS NOT ACCEPTABLE AND WILL INSTALL ADDITIONAL NON-1E L.
THIS WILL. PRECLUDE THE NEED TO USE THE RSP TO MITIGATE SB0 EVENTS DESIGN ACTIVITIES ARE PROCEEDING ON AN EXPEDITED BASIS 1
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H SECOND LEVEL UNDERVOLTAGE RELAYS (SLUR) l
- THE CALCULATION TO ESTABLISH THE PREVIOUS SETPOINT DID NOT CONSIDER THE V0LTAGE DROP BETWEEN THE MOTOR CONTROL' CENTER AN THE END DEVICE, THEREFORE IT WAS SET T00 LOW.
THE SETPOINT HAS BEEN RECALCULATED CONSIDERING THE VOLTAGE DROP FRON THE 4160V BUS DOWN TO THE END DEVICE.
THE SLUR RELAYS WERE REPLACED TO PROVIDE THE REQUIRED SETPOINT RANGE AND THE PROPER SETPOINT ESTABLISHED.
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i DC COMPONENT VOLTAGE ISSUES i
SAFETY RELATED 'DC COMPONENTS-COULD HAVE BEEN SUBJECTED TO VOLTAGES IN EXCESS OF MANUFACTURER STATED VOLTAGE RATING.
SAFETY RELATED COMPONENTS WERE IDENTIFIED AS i-L REQUIRING REPLACEMENT.
COMPONENTS FOR WHICH REPLACEMENTS WERE AVAILABLE HAVE BEEN REPLACED.
ALL COMPONENTS NOT REPLACED WERE REVIEWED FOR SAFETY SIGNIFICANCE /0PERABILITY AND A JC0 PREPARED.
REPLACEMENT COMPONENTS HAVE BEEN ORDERED AND WILL BE INSTALLED PRIOR TO OR DURING REFUEL 7.
l
ALTERNATE OFFSITE POWER SOURCE i
THE CR 1 & 2 STARTUP TRANSFORMER, WHICH IS CR3's i
ALTERNATE OFFSITE POWER SOURCE, DOES NOT HAVE SUFFICIENT CAPACITY TO HANDLE THE LOADS AT CR 1 &
~2 COINCIDENT WITH THE SIMULTANEOUS LOADING 0F BOTH l
l TRAINS OF CR3= EMERGENCY SAFEGUARDS BLOCK LOADS.
INSTALLING NEW ALTERNATE OFFSITE POWER SOURCE DEDICATED TO CR3 COMMITMENT TO COMPLETE BY MID-CYCLE OUTAGE I
1991 L
GOAL TO COMPLETE BY END OF REFUEL 7 CABLE SIZING IS COMPLETE AND CABLE IS BEING ORDERED CABLE ROUTING AND TRAY SIZES HAVE BEEN l
FINALIZED-TRANSFORMER PAD AND DUCT BANK DESIGNS ARE t
BEING DEVELOPED WILL USE EXISTING SPARE TRANSFORMER 1
i REFUEL 7
GOAL FOR COMPLETION APPEARS TO BE ACHIEVABLE
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EMERGENCY DIESEL GENERATORS THE-EXPECTED WORST CASE LOADING ON THE EDG's EXCEED THE 3300KW OR 30 MINUTE RATING 0F THE DIESEL CORRECTIVE ACTION IMPLEMENTED LOAD MANAGEMENT j
LOAD REDUCTION MODS INSTALLED HVAC DUCT MODS INSTALLED INSTALL TURB0-BLOWER SERIES CONFIGURATION EQUIPMENT ON-SITE DESIGN MOD PACKAGES ISSUED COLT TO PERFORM ENGINE WORK LARGER LUBE-0IL COOLERS ORDERED DESIGN MOD PACKAGES-ISSUED MONITORING SYSTEM TO BE INSTALLED EQUIPMENT HAS BEEN ORDERED SCHEDULE MAY NOT SUPPORT COMPLETION DURING REFUEL 7 MAY BE COMPLETED ON-LINE
- ~.. - ~
INSERVICE INSPECTION 1111) $NAPSH0T f
Strenaths; o
pride of ownership and single point accountability o
_ strengthening administrative and supervisory control-to 1
Superintendent level.
o o
minimize contractor reliance o
_ establish eight (8) "standalone" programs with Specialists accountability for implementation o
best OSTG in the business-o trends of statistical performance parameters o;
improved interface with Systems Engineering Challenaes o
effect required modifications and procedure revision. IAW.NRC '
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Generic Letter 89-04 validation of testing of new components added to program (check '
o valve program) l o
develop an "in house" Appendix "J" Leak Rate p
Training Program lJ Action Plan o
Cross Train "in house" expertise in all areas of ISI/IST-Address previous weaknesses in IST of check valves and correct o
deficiencies l-o UtilizeLthe EPRI Guidelines in ECT of OTSG's -18.2% in "A".
13.5% in "B" in RCP outage-L will accomplish 215 in each OTSG in RF-7 Utilize competitive Contractor bidding instead-of NSS Sole o
Source C. E. Development of Program Manuals Westinghouse to perform reactor vessel inspection PMA developing vibration analysis program L
o Utilize " State of the Art" tooling and processes Accomplish Rx Vessel Inspection with
" Rover" type submarine TV technology EPRI endorsed Hi-speed UT data recording and processing o
Continued involvement in Industry Organizations gather information to strengthen ISI Program
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ISI SECTION
~ RESPONSIBILITIES:
is Nondestructive Examination Progre Eddy Current Testing Program Repair'a Replacement Prograri
. t Pump and Valve Progrert 1.
Hydrostatic Testing Program r
Snubber Program Leak Rate Testing Progre Surveillance Capsule Program 1.
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MMES: 'No Amational Amses - III, OtBG
- Persarmal Qup13aent - 6 1tures arut csie4aalf peuple dedicated to ISI t
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Na Gun Rautional Area - III 3 Perunnnel QupUmset - 8 L ElW 2 (8) people duticated to III, i.e.,130% increase
. six (6) Of Prumart Qapliment of (S), are new to III agenhut.laun e
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i INSERVICE INSPECJ_L0li
'1.
NUCLEAR TECHNICAL SUPPORT SUPERINTENDENT FORERLY SPLIT 4
HIS TIE BETWEEN ISI SECTION AND OTSG INTEGRITY SECTION.
HE NOW DEVOTES 100% OF HIS TIE TO ISI MANAGEMENT ISSUES.-
RESULTS:-
INCREASED MANAGEENT AT1ENTION.
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ISI ORGANIZATION FORERLY CONSISTED OF 3 1/2 EMPLOYEES
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(1/2 IS SUPERINTENDENT);
HAS BEEN EXPANDED TO EIGHT I
(8) FULL-TIE EMPLOYEES.
RESULTS:
INCREASES. ATTENTION TO DETAILS.
3.
PROGRAM IS LESS CONTRACTOR DEPENDENT AND MORE SELF SUFFICIENT WITH PERMANENT FPC PERSONNEL.
RESULTS:
INCREASED CONTROLS AND DEVELOPENT OF IN-HOUSE EXPERTISE.
f4.
THE OVERALL ADMINISTRATIVE CONTROL PROCEDURE FOR IN-SERVICE INSPECTION, AI-701, WAS RE-WRITTEN AND STRENGTHENED TO L
INCLUDE NEW ORGANIZATION AND COMITENTS.
RESETS:
STREN6HTENS CONTROLS OF ISI ACTIVITIES.
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i;i 5.
EIGHT STAND-ALONE ISI RELATED PROGRAM DOCUMENTS HAVE BEEN DEVELOPED OR ARE UNDER DEVELOPMENT:
DEVELOPED:
NDE-L PUMP AND VALVE q
. REPAIR AND REPLACEMENT EDDY CURRENT TESTIN6 w
HYDROSTATIC TESTING
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SURVEILLANCE CAPSULE L
SNUBBER LEAK RATE TESTING RESULTS:
IMPROVED DEFINITION OF PROGRAM ACTIVITIES-AND RESPONSIBILITIES, 6.
ALL ISI COMITENTS ARE UNDER REVIEW AND ARE BEING UPD i
IN THE NUCLEAR OPERATIONS COMITENT SYSTEM -(NOCS).
RESULTS:
BETTER DEFINITION OF PROGRAM COMITENTS.
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NEW TEN-YEAR CYCLE STARTED AT COMPLETION OF REFUEL WITH NEW MANAGEE NT TEAM, REQUIREMENTS AND PROGRAMS.
RESULTS:
OPPORTUNITY TO LEARN FROM PAST MISTAKES AND START ANEW.
1 8..
THE FIRST TEN-YEAR PROGRAM WAS DEVELOPED AND CONTROL BY A
CONTRACTOR (BaW).
THE SECOND TEN-YEAR PROGRAM WAS DEVELOPED AND IS BEING CONTROLLED BY FPC.
r RESULTS:
L LESS DEPENDENCE ON CONTRACTORS.
MORE INTERNAL CONTROLS.
9.
DEVELOPING STATE-0F-THE-ART COMPUTER BASED INFORMATION L
SYSTEM-TO 'IMPLEENT ISI PROGRAMS.
2 RESULTS:
IMPROVED WORK PLANNING AND DEFINITION.
l
- 10. ' DUE-TO SECOND TEN-YEAR INTERVAL AND NEW CODE, ALL ISI RELATED SURVEILLANCE PROCEDURES ARE BEING REWRITTEN, l
- VERIFIED AND VALIDATED.
RESULTS:
IMPROVED PROCEDURES, IMPROVED RELIABILITY OF-SAFETY RELATED EQUIPENT AND IMPROVED OPERATOR
- INTERFACE.
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INSERVICE INSPECTION / TESTING SALP PRESENTATION Florida Power Corporation's Inservice Inspection and Inservice Testing Section is dedicated to the safe and efficient operation of Crystal River Unit #3. The ISI/IST Section emphasizes superior performance through comprehensive, well planned programs and enhances this culture through " pride of ownership" by the responsible specialist -
.for each program, o
l With the implementation of the second -10 year Inservice Inspection and Testing Program in 1987, a significant commitment was made by Florida Power Corporation to
[
improve the inservice surveillance programs by strengthening the administrative u
control; upgrading procedure adequacy, adherence, and supervisory review; and growth of "in-house" expertise in all areas relating to ISI/IST. This commitment remains paramount and significant progress has been achieved during the current SALP period.
J The Nuclear Technical Support Superintendent remains 100% dedicated to the management and administrative control of ISI/IST issues including supervisory review of all i
ISI/IST activities, management of organizational interfaces, and maintaining commitment status.
Each of the Inservice Programs (OVERHEAD 1) now have an associated Program Manual that describes the administrative controls and technical / code requirements for the program and, where applicable, define implementing documents and procedures. During this SALP period, five of these Program Manuals have been developed and implemented.
Specifically, the Snubber, Leak Rate Testing, Eddy Current Testing, Hydrostatic Testing, and Surveillance Capsule Programs have been implemented and join the 1
1
~
y existing NDE, Pump and Valve, and Repair and Replacement Programs to totally define the functional scope of the ISI/IST Section.
Each of these programs is the responsibility of an assigned Specialist and accountability for implementation, maintenance, and assurance of. code compliance is clearly defined.
Contractor t
involvement within these programs has been minimized and all programatic control rests exclusively with Florida Power Corporation Personnel. This dependence on "in-i house" personnel will ultimately *: sult in maximum benefit and continued performance p
improvement.
Specific accomplishments during this SALP Period are numerous, with some of the more noteworthy as-follows:
l.
Adoption of the " State of the Art" Reactor Vessel inspection techniques, u
l Subsequent examinations will be' accomplished utilizing EPRI endorsed tooling that provides high speed ultrasonic data recording and processing. Reactor Vessel visual inspections will be performed with submarine T.V. technology that will yield-reduced. personnel and equipment support requirements and provide significant ALARA-savings.
i 2.
(OVERHEAD 2)
Data from surveillances performed on pumps and valves have been entered into a computerized trending program that produces plots and statisNgal parameters useful in analysis of equipment performance.
This program exceeds the requirements of ASME SEction XI.
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3.
The Pump and Valve Program has been reviewed and modified in accordance with NRC Generic Letter 89 04. This update was accomplished within the original time constraints and schedules for required modifications and procedure revisions have been developed.
Of the Eleven (11) positions presented in the Generic Letter, the Pump and Valve Program was addressing the intent of four of these positions. One of these positions is BWR specific, therefore, this required incorporation of an additional six (6) positions into the -
program.
By virtue of these revisions to the Pump and Valve Program, previous concerns with weaknesses in the inservice testing of check valves j
have been addressed and deficiencies corrected, i
l 4
An aggressive Appendix'
'J" testing
- program, with conservative valve repair / replacement criteria has been maintained and Type "B" and 'C" t
measured leakage is currently at approximately 15% of allowable.
Additionally, engineering studies are in progress to upgrade instrumentation und for Integrated Leak Rate Testing so that more accurate and reliable test performance can be achieved.
l l
l 5.
The EPRI Steam Generator Inspection Guidelines have been endorsed.
In the areas of Eddy Current Testing, Florida Power Corporation has taken the pro-active position to utilize this tube inspection technique aggressively. In the SprJag 1989 Outage, Eddy Current Testing was performed on more tubes than any previous outage.
(18. 5 in 'A' and 13.5% in "8' steam generator.)
Planned inspections for Refuel VII will accomplish 215 in each Steam Generator.
Steam Generator cold leg nozzle dass are being procured for installation in future outages to support increased tube inspections.
i l
i The ISI/IST Section has maintained involvement in Industry Organizations such as the BW Owners Group and the Snubber Utility Users Group with the emphasis on gathering information from these interfaces to be used in further strengthening the Inservice Programs. Assessments in all functional and administrative facets of the Inservice 1
Program will be continued to identify opportunities for performance improvement.
We fees inat considerable progress has been made throughout the past SALP evaluation period in the IS!/IST Section.
The strong foundation anchored by dedicated.
responsible personnel coupled with well defined programs provides an excellent basis for continued support of Crystal River Unit f3's goal of safe, legal and efficient operation.
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Sys 10 Nees Description I.est Date Units Nean y,g o
RwP3A-01FF O!FFERENTIAL PRESSURE 09/04/1999 0
PS!
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DCP14-01FF DIFFERENTIAL PRESSURE 09/04/1999 36.9 PS!
36.75 702 1,
DHP!A-DIFF DIFFERENTIAL PRESSURE 09/04/1989 0
PS!
147.5 2.761 BSPiA-DIFF DIFFERENTIAL PRESSURE 09/04/1999 0
PS!
171 2
0
i NUCLEAR PLANT TECHNICAL SUPPORT FUNCTIONAL CHART 4
Nanager, Nuclear Plant Technical Support i
k i
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Reactor Results Shift Technical In Service Nuclear l-Engineering Engineering Advisors Inspection Security l
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1 REACTOR ENGINEFElliC j
L l
l STRENGTHS Recognized by INPO regarding our 1
)
" good practice" in Reactor and Fuel Integrity Performance Monitoring.
'l t
i, Active with other B&W plant involvement -
past chairman of the B&W Owners Group, Reactor Engineering subgroup.
CHALLENGES Improve fuel reliability A_CTION plan Continue to provide maneuvering recommendations on plant operations'and activities effecting fuel integrity.
Study procedures with Operations personnel to improve use.
i Implement complex or lengthy procedure calculations with validated, approved and controlled software.
Continue to perform periodically as a
" guest lecturer" during Operations and OTA requalification cycles.
. - =.
.t RESULTS ENGINEERING S.lRENGTHS Highly rated Secondary Side Performance Monitoring Program.
High praise from INPO.
Excellent Heat Balance computer modeling ability.
t i
CHALLENGES Increase scope of testing.
P t-P ACTION ?LAN Increase computerization of performance 1
monitoring.
Increase frequency of plant inspections.
Procure new performance equipment:
- Infrared Camera 1
- Flow Meter
- Condenser Tube Cleaning Techniques
{
c:
SHIFT TECHNICAL ADVISORS STRENGTHS SOTA personnel with strong and l
varied nuclear background (>10 years average).
Strong, INPO recognized NPRDS program.
CHALLENGES More Control Room support / visibility to the Operators / Operating Shift.
ACTION PLAN Hope to get SOTA " office"'in the Control Room area.
System Walkdowns Mode 5 & 6 coverage vs legal Tech. Spec.
requirements for Modes 1 - 4.
Attend SS (Shift Supervisors) Meeting w
m
-,w-,
l.
OPERATIONS SNAPSHOT Stranaths o
above average response to operating events o
adequate resources o
good quality operating procedures and EOPs o
good moral and professional attitude o
safety culture o-capable, experienced supervision.
Challances o Relatively inexperienced watchstanders o
too many operator errors l
l o
need for greater consistency between shifts Action Plan o
' Increase on-shift supervisor contact hours with watchstanders l
l established dedicated Daily Support Group established dedicated projects group l
analyzed and reallocated some of. the on-shift responsibilities eliminated Control Room distractions; i.e., unnecessary traffic, phone calls, nuisance alarms o
Improve effectiveness of on-shift training established Peer Evaluator program establish program for line management observations of on-shift activities 1
l l
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Operat1ons Superintendent sao
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peer Evaluator Ops Projects operating CPS Detly Support 4
(SAS)
(SM/Eng/Segerintendent)
Sh1fts (Full-tsee asstgnment)
(4)
(flo acttwo license J
-Shift proffency
=========*s
-Projects
-SPs i
4
-Licensed op. assessments
-Ops Engsneering
-PC reviews f
. rout $ne
-PC metatenance
-On-shtft training
. nonrouttne and dowelopment 7
-flon-18consed operator support
-senet$ng attendence
=========*s
-elodtfscat1on rev1ew
-setsc. authortratten STA a - - *s
,and system acceptance -
a revtows Steeletor evais
-cieerences 45pe study took entries
-Ouality Program /esRC/IssPO
-ops planning /
(
-trES evaluettons responses schedulang en-shift treintas
-Engineering (Design)
-Interface with i
Training Dept. interface interface i
Planningespertment Gand Practica tratalag i
i i
. ~
1 t
RADIATION PROTECTION SNAPSHOT Stranaths o
Stable experienced staff o
Contamination Control - areas and personnel o
Effective dose reduction program Challances. o Reduce administrative burden and improve record keeping o
Develop Model TLD QC Program o
Enhance effectiveness of personnel frisking o
Increase worker awareness in R. P.
Action Plan o Reduce administrative burden and imoreve record kaanina by:
completion of computerized access control program 1
(
l o
Enhance effectiveness of corsonnel friskino by:
1 use of whole body friskers improved GET In-plant check outs frisk before dress policy o
Incr==== worker awareness in R.P. by:
rad safety topic at each safety meeting Improved Radiological Safety and ALARA Committee HP/ Operator crosa-training program 1
Radiation Safety handbook l
Improved GET Use of prompts in plant i
-x
,....,m--.....e
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F CR-3
- TOTAL RADIATION EXPOSURE 700 LEGEND 645.51 ANNUAL l
x j-I l
600-I 89 BY QTR.
i 487.28 500 i
i 447.08 g 400-i 4
- a. 300-i 206.364
[
200-l 129.701 N N 70.o34 100' 63.9 0
85 86 87 88 89 Q1 Q2 Q3 Q4 (sept. data not even.w. in tim. for the n.p.et.)
(Annual figure revloed thru 8/31/89)
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9 i
CR-3 PERSONNEL CONTAMINATIONS
~
't i
INCIDENTS j
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25 1988 4
1989 20
~
15 10
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/
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4 s.
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JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC DATE TOTAL 1988 - 43 TOTAL 1989 - 59
... ~.. - _.. -.
1 i
i CHEMISTRY SNAPSHOT
-i Stranaths o
Consistent analytical results o
Excellent feedwater chemistry Challenaea o OTSG fouling i
o Accumulation of crud in primary systems l
o Technician attention to detall o
Chemical swings in closed loop systems Action Plan o Reduce fouling of OTSGs by:
t waterslap L
elevating pH of secondary systems Morpholine treatment of feedwater systems Condenser air inleakage reduction Remove crud from primary systems by chemical cleaning o
Improve technician attention to detail by:
o relocation of chemistry supervisor to laboratory reemphasis of management expectations and aggressive follow up to near misses o
Reduce chemical swings in closed cycle systems by:
optimizing sampling and chemical addition frequencies reducing system leakage Improved maintenance
I
'lUCLEAR SERVICES CLOSED CYCLE COOLING - HYDRAZINE (1987) 2
. O Hyde stia.
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NUCLEAR WASTE SNAPSHOT Stranaths o
Effective volume reduction program o
Excellent compliance posture Challennes o Implement new methods to reduce rad waste volumes further o
Improve plant cleanliness Action Plan o Improve volume reduction by:
eddy current of condenser tubes training personnel more effective waste processing Increased usage of nondisposable products o
Improve plant cleanliness Area Mothers dedicated decon crew improved maintenance
,. -. -..... ~...
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t CR-3 RADWASTE DATA-FT3 60,000 GENERATED SHIPPED 50,000 LEFTOVER i
s 30,000 20,000
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{
NRC VIOLATIONS 1985 TO 1989 VIOLATIONS L
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6.0 l
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2.0 0.0 1985 1986 1987 1988 1989 YEAR ONLY LEVEL IV VIOLATIONS WERE RECEIVED
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- MAINTENANCE 1
l Strengths o
Stable, experienced craft L
o Well established maintenance program r
o Strong predictive maintenance o
Strong self assessment effort Active participation in industry / owners groups l
L o
^
Job sponsor concept: single point of accountability L
o o
Concentration of maintenance support functions i
Experienced, multi skilled mechanical contractor o
o Senior maintenance management has SRO or equivalent l
training r
Challences o
Reduce security equipment problems Improve leadership at supervisor level o
o Improve shift turnovers Maintenance programs (RCM, PM-200, MOVATS, Tool l
o
' Control, Valves) t Improve maintenance equipment history and PM o
program management Improve maintenance / engineering interface o
Improve maintenance involvement in ALARA/
o Radiological Safety L
o Parts and Materials l:
Improved security maintenance capability
' Action Plan o
Expanded security, I&C workshop area Established improved security PMs o
Leadership Rotation of maintenance supervisors Engineers in first line and senior supervisor positions o
Shift turnover Participate in Operations turnover Keep written log and conduct formal turnovers
~~
o Maintenance programs o
Dedicated PM program manager Dedicated shop engineers and component engineers o
Maintenance manager chairs Radiological Safety and o
ALARA Committee Staging of materials in ready warehouse o
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MAINTENANCE u
PLANNING AND SCHEDULING y
L L.
p Strengths.
o
. Accurate and flexible scheduling capability o -
Highly experienced Ops planning staff in
.o Computerized PM and SP scheduling programs o.
Computerized on-line work request system (MACS).
4-(\\
Challenges
-o Training for planners y
o Additional outage planning expertise o
Improve Plan of the-Day o-Continue improving coordination with Operations o
Reduce length of refueling outage 4
l
- Action Plan o
Training Job task analysis complete l
Guidelines for work request package content issued:
o Outage planning expertise Contract planning engineers 3 Net'new positions o
Plan of the Day Includes schedules for all crafts Multi-day look ahead Direct link to computer scheduling (Artemis) o Coordination with Operations Operations planning supervisor' move to head up Operations daily work group o
Outage length Mechanical and Electrical /I&C supervisor and HP supervisor to outage group romparison to other plants j
Work. scope control Operations shutdown and startup sequence P
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FLORIDA POWER CORPORATION p
ELECTRICAL CALCULATION ENHANCEMENT PROGRAM OCTOBER 18, 1989
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PAGE 2 E.C.
ENHANCEMENT PROGRAM
-PROGRAM SCOPE WAS DEVELOPED AS A RESULT OF FPC CONTINUING TO FIND ERRORS IN:THE ORIGINAL ELECTRICAL CALCULATIONS w
PROGRAM ENHANCEMENT WILL INCLUDE THE FOLLOWING FIVE p.
AREAS:
AC DISTRIBUTION SYSTEM i
DC DISTRIBUTION SYSTEM l-V
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s LICENSING i
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-CR3 LICENSE DOCUMENT
(
NRC GENERIC LETTERS NRC BULLETINS w
a; NRC NOTICES
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.:q p4 PAGE 4
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STATE OF THE ART PC BASED SOFTWARE DATA. BASE DEVELOPMENT NAMEPLATES READ IN FIELD MANUFACTURERS RATING' CABLE LENGTH FROM CONSTRUCTION DOCUMENTATION
-r SHORT~ CIRCUIT CALCULATIONS 4160 VOLT BUSES DOWN TO AND INCLUDING THE 120 VOLT BREAKER-PANELS PERFORMED TO ANSI C37.10 i
VOLTAGE DROP. CALCULATIONS 4160 VOLT BUSES DOWN TO AND L
INCLUDING THE 120 VOLT CONTROL l.
CABINETS AND MOTOR: CONTROL CIRCUITS LOAD FLOW CALCULATIONS 4160 VOLT BUSES DOWN TO AND INCLUDING 120 VOLTS-BREAKER PANEL (PRIMARY SIDE OF TRANSFORMER) u
ci,
.PAGE 6 a
t P
'6 OTHER AC ACTIVITIES J
REVIEW'ALL POWER CABLES (CURRENT) a
- u i
- m PROPER RATINGS ON:
START-UP TRANSFORMER 1
NON-SEGREGATED BUS DUCT-g.
SWITCHGEAR R
. INVERTERS-
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SAFETY VS. NON-SAFETY-ALL SAFETY RELATED h
NON-SAFETY RELATED EQUIPMENT THAT. IMPACT SAFETY RELATED EQUIPMENT
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STATE OF THE ART PC BASED SOFTWARE l
- i DATA BASE NAMEPLATES READ IN THE-FIELD MANUFACTURERS RATINGS CABLE LENGTHS FROM CONSTRUCTION DOCUMENTATION L
SHORT CIRCUIT CALCULATIONS 1,
DOWNSTREAM 0F ALL PROTECTIVE DEVICES
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250 V0LT DC LEVEL L
125 VOLT DC LEVEL L
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VOLTAGE DROP CALCULATION
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~.53 FUSE PANELS MOTORS MOTOR CONTROL CIRCUITS L
L LOAD FLOW CALCULATION
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.a SAME AS VOLTAGE DROP 1
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OTHER DC AC11VITIES REVIEW ALL POWER CABLE (CURRENT RATING) j PROPER RATINGS ON:
BATTERIES E
CHARGERS O
u o
DC FUSE-PANELS.
BATTERY DISCHARGE PROFILE D
EACH OF BATTERY o
l LOSS OF AC AND NO DIESEL l-TWO HOURS SAFETY VS. NON-SAFETY ALL SAFETY RELATED EQUIPMENT u
l:
L NON-SAFETY RELATED EQUIPMENT THAT IMPACTS SAFETY RELATED EQUIPMENT r
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PAGE 10
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P COORDINATION 3
FLORIDA POWER RELAY DEPARTMENT
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230KV SUBSTATION START-UP TRANSFORMER 4160 VOLT AND 6900 VOLT LEVEL t'
b 480 VOLT SWITCHGEAR B
N BREAKERS AND' FUSES 480; VOLT-MOTOR CONTROL CENTERS 120-VOLT.AC i;
125 VOLT DC L
250' VOLT.DC l
ALL SAFETY RELATED EQUIPMENT NON-SAFETY RELATED EQUIPMENT THAT IMPACTS SAFETY RELATED EQUIPMENT L
.~ _ _
PAGE 11 i
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FIELD DATA a
REVIEW. PREVIOUS FIELD DATA ADDITIONAL-INSTRUMENTATION u
L VALIDATE / INCLUDE IN CALCULATIONS i
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FIDRIDA POWER CORPORATION' t-C CONFIGURATION MANAGEMENT PROGRAM
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c ENHANCED CONFIG RATION MANAGEMENT PROJECT APPROACH AT FPC o
FPC's CMP WAS DEVELOPED FOLIDWING LENGTHY REVIEW OF NUMEROUS' INDUSTRY DOCUMENTS AND DISCUSSIONS WITH OTHER' UTILITIES-INPO REPORT 87-006,. " REPORT ON CONFIGURATION MANAGEMENT IN THE NUCLEAR INDUSTRY" s
INPO RECOMMENDATIONS FOR A
DESIGN BASIS DOCUMENT IN THE NUCLEAR UTILITY INDUSTRY NUREG/CR-5145,
" FUNDAMENTAL ATTRIBUTES OF A L
PRACTICAL CONFIGURATION MANAGEMENT PROGRAM FOR L
NUCLEAR PLANT DESIGN CONTROL" p.
L NRC INSPECTION 87-22, OSTI INSPECTION AT CR-3
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FPC INSPECTION REPORT 87-41 l
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,5 o-CR-3 CONFIGURATION MANAGEMENT PLAN IS BROKEN DOWN
- 1 INTO SEVEN PROGRAMS AIMED AT ACHIEVING THE
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FOLLOWING:
ENHANCE THE EXISTING CR-3 DESIGN BASIS ENSURE THAT THE DOCUMENTED CR-3 DESIGN BASIS IS REFLECTED IN THE "AS-BUILT" CONDITION OF THE l
PLANT AND EXISTING CR-3 SOFTWARE (i.e.,
PROCEDURES)
DEVELOP AN EFFICIENT MECHANISM BY WHICH CR-3 PERSONNEL MAY QUICKLY AND CORRECTLY IDENTIFY L
-ALL PERTINENT DESIGN REQUIREMENTS / DOCUMENTS PRIOR TO DEVELOPING A
PLANT MODIFICATION (HARDWARE OR SOFTWARE)
L ENSURE THAT CR-3 PERSONNEL PROPERLY UNDERSTAND THE CONCEPTS OF THE PLAN, THAT END-USER INPUT i
l IS CONSIDERED DURING PROGRAM DEVELOPMENT, AND END-USER SUPPORT IS AVAILABLE AFTER EACH l
PROGRAM'S STARTUP.
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1 FPC PROGRAM NO.
I.
ANALYSIS BASIS DOCUMENT (ABD)
FIELD VALIDATION PROGRAM t
II.
ENHANCED DESIGN. BASIS DOCUMENT (EDBD) PROGRAM i
III. EDBD FIELD VALIDATION PROGRAM IV.
SAFETY LIST SYSTEM (SLS) PROGRAM i
V.
CONFIGURATION MANAGEMENT INFORMATION SYSTEM (CMIS)
PROGRAM VI.
CONFIGURATION CONTROL PROCESS EVALUATION / ENHANCE-I' MENT PROGRAM 1
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VII. CONFIGURATION MANAGEMENT IMPLEMENTATION PROGRAM 1
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ANALYSIS BASIS DOCUMENT (ABD) FIELD VALIDATION PROGRAM l
PURPOSEt VALIDATE THAT THE CR-3 PLANT ACTUALLY CONFORMS-TO THE FSAR CHAPTER 14 ASSUMPTIONS
- O o
IDENTIFY THE ANALYSIS INPUTS TO THE FSAR CHAPTER 14 TRANSIENTS.
o LOCATE DOCUMENTS THAT VERIFY THE CR-3 NUCLEAR PLANT CONFORMS TO THE ANALYSIS INPUTS.
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OP's TAP REPORTS ETC.
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IDENTIFY DISCREPANCIES BETWEEN THE ABD AND THE FSAR..
l=
STATUS:
THIS PROGRAM IS ESSENTIALLY COMPLETE.
THE.18 l
ABD's HAVE GONE THROUGH THE FIELD VALIDATION L
EFFORTS TO ENSURE THAT THE KEY ITEMS /ASSUMP-u h
TIONS IN THE ABD's ARE ACTUALLY REFLECTED IN 1
THE "AS-BUILT" PLANT HARDWARE AND SOFTWARE (i.e.,
SURVEILLANCE / OPERATING PROCEDURES,
~
ETC.).
ALL IDENTIFIED DISCREPANCIES TO BE RESOLVED AND VALIDATION PACKAGES COMPLETED BY
- END OF THIS YEAR.
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ENHANCED DESIGN BASIS DOCUMENT
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(EDBD) PROGRAM PURPOSE:
UPGRADE THE EXISTING DESIGN BASIS DOCUMENTS TO i
CLEARLY. IDENTIFY THE SYSTEM DESIGN BASIS FUNCTIONS, PARAMETERS, AND COMPONENTS.
ADDITIONALLY, DESIGN SOURCE DOCUMENTS WILL BE I4CATED AND REVIEWED.
PHASES I.
PILOT-(2 SYSTEMS)
II.
SYSTEMS REQUIRED FOR SAFE SHUTDOWN f;
(27 SYSTEMS) 1:
L
III. REMAINING SAFETY-RELATED SYSTEMS (8
1
-SYSTEMS) t:
STATUS:
THE 2 PILOT SYSTEMS ARE COMPLETE AND WERE l
ISSUED 7/31/89.
5 SYSTEMS OF PHASE II ARE CURRENTLY UNDER DEVELOPMENT AND SCHEDULED FOR COMPLETION BY JANUARY 1990.
IN ADDITION, THE 3 PRIMARY ELECTRICAL SYSTEM HAVE BEEN INITIATED WITH COMPLETION BY MARCH 1990.
THE REMAINING SYSTEMS WILL BE DEVELOPED IN GROUPS PER ATTACHED CHART.
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TYPICAL EDBD DEVELOPMENT PROCESS
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o DEVELDP. SYSTEM LOGIC TREE DIAGRAMS o
IDENTIFY, RETRIEVE, AND CATA!4G POTENTIAL EDBD INPUT SOURCES i~
o-REVIEW ' INPUT SOURCE DOCUMENTS i
o PREPARE DRAFT EDBD o
REVIEW DRAFT EDBD l.
o ISSUE FINAL EDBD 1
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PROBLEM IDENTIFICATION L
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S CRYSTAL RIVER UNIT 3 Page 16 of 49 DMANCED DESIGM 8A515 DOCUMENT ~
f DECAY HEAT REMOVAL t'. 0 : SYSTEM PARAMETERS PARAMETER REASON SOURCE
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1967 Edition.
The DH System was fabricated, erected,and
~ inspected to B31.7-69 (Class 1 from the 8 hotleg
~to DHV-41 and u
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Class 2 from l:
DHV-41 to the DH i-pumps).
'FSAR FSAR Section 6.1.2.4 Table 6-3 For a large break-
.A conservative 90% of DH System References 1, 2 LOCA, the minimum design flow (3000 gpm) was used in p
- analyzed injection' the LOCA analyses to ensure flow rate is 2700 sufficient core cooling for large L
gpm at..an RC
-break LOCA injection and System pressure of recirculation. This value allowed 94 psig, for pump degradation.
A-lower flow rate:could negatively impact core cooling and cause the plant L
to exceed 10CFR50.46 limits.
l
.T.S.
- Technical Specification 4.5.2 L
requires demonstration of a LPI System flow capability between L
2800-3100 gpm after any modification which could alter system flow characteristics.
FSAR FSAR Section 6.1.2.1.2 l.
For a small break Following a small break LOCA when Reference 1 LOCA, the DH the BWST-is exhausted, the DH System provides System may be used to boost l'
suction for the MU suction pressure to the HU pumps pumps from the (piggybackmode).
The DH flow rate would be the same as the MU sump.
flow rate and would be dependent on RC System pressure.
Piggyback mode continues until the RC System pressure decreases below the DH
CRYSTAL RIVER UNIT 3 Page 41 of 49 i;
l ENHANCED DESIGN BAS!$ DOCUMENT DECAY HEAT REMOVAL $YSTEM 3.0 COMPONENT PARAMETER $'
Component / Parameter Reason / Source Interface 1'
. isolation valve, gravity draining through the Unit 4C droplin6 to the sump to prevent boren-precipitation. This valve TheHVAC(XJ) i may be remotely closed by the System maintains DH
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operator when containment compartment isolation is required.
temperature within c
design limits.
L Reference 26 Key Parameter:
Heat Removal (Stu/hr)
E T.S.
Technical Specification 3.6.3.1 FSAR FSAR Tables 5-4 & 5-9, Section 1.4.53 DHV-42, DHV-43 are These valves are required to be Electrical Power:
i:
containment closed during the initial phase of DHV-42:
isolation valves.
. a LOCA to prevent loss of BWST 480V ES MCC 3Al inventory to the sump. Once the Unit 48-
'BWST is depleted, these valves are L
opened to allow DH pump suction DHV-43:
l-from the sump. These valves may be 480V ES MCC 381 remotely closed by the operator Unit 6A 7
when containment isolation is i
required.
TheHVAC(XJ)
System maintains DH.
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Reference 26 compartment L'
temperature within l
design limits.-
1 Key Parameter:
Heat Removal (Btu /hr)
T.S.
Technical Specification 3.6.3.1 L
FSAR FSAR Tables 5-4 & 5-9, Section 1.4.53
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DHV-69 DHV-70 These valves are sized to protect l-provide 10 psi the BWST for maximum pump out vacuum relief.
capacity.
Reference 37 l
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ELECTRICAL SYSTEMS EDBD'S
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. ORIGINAL SCHEDULE ACCELERATED FROM JULY 1991. AND MARCH 1992 TO-MARCH 1990 COMPLETION l.
o-EFFORT WILL INVOLVE 3 BASIC SYSTEMS I
AC POWER DC POWER-EMERGENCY DIESEL GENERATORS I
2
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s ELECTRICAL' SYSTEMS EDBDM o-AC POWER WILL INCLUDE DESIGN BASES RELATED TO' OFFSITE POWER SOURCE, IN-PLANT DISTRIBUTION SYSTEMS, -
BUS PROTECTION, BREAKER CONTROL, AND TRANSFERS EQUIPMENT EXPECTED TO BE ADDRESSED:
230KV SUBSTATION CR-3 STARTUP TRANSFORMER 4
CR-l&2 STARTUP TRANSFORMER l
4160V & 480V SWITCHGEAR 480V MOTOR CONTROL CENTERS I
1 I
AC DISTRIBUTION PANELS i
120V VITAL AC POWER AND CONTROL CABLE CABLE RACEWAY AND SEPARATION ELECTRICAL PENETRATION ASSEMBLIES
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ELECTRICAL SYSTEMS EDBD'S 2
o
- DC POWER WILL INCLUDE DESIGN BASES FOR BATTERIES AND DISTRIBUTION OF DC POWER.
EQUIPMENT EXPECTED TO BE ADDRESSED:
BATTERIES l BATTERY CHARGERS l
s DC GROUND DETECTION l'
l DC DISTRIBUTION PANELS 1
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ELECTRICAL SYSTEMS EDBD'S i li o
EMERGENCY DIEGEL GENERATOR EDBD WILL INCLUDE DESIGN BASES FOR THE DIESEL ENGINE AND ELECTRIC GENERATOR..
i EQUIPMENT EXPECTED TO BE ADDRESSED:
.g.,
FUEL OIL TRANSFER l
JACKET COOLANT 1
L l-AIR. COOLER l'
7 LUBE OIL l
1 l
COMPRESSED STARTING-AIR l
ENGINE EXHAUST l
GENERATOR CONTROLS GENERATOR LOADING GENERATOR PROTECTION
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PURPOSE:
VALIDATE THAT THE CR-3 PLANT ACTUALLY CONFORMS TO THE EDBD AND IT'S SOURCE DOCUMENTS.
l L.
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PROGRAM MODELED AFTER THE NRC "SSFI" TECHNIQUE.
e o-THE SYSTEMS ARE CAPABLE OF PERFORMING THE SAFETY FUNCTIONS l~
REQUIRED BY THEIR DESIGN BASES.
l o
TESTING IS ADEQUATE TO DEMONSTRATE THAT THE SYSTEMS WOULD PERFORM ALL'OF THE SAFETY FUNCTIONS REQUIRED.
l o
OPERATOR AND MAINTENANCE TECHNICIAN TRAINING IS ADEQUATE TO l.
ENSURE PROPER OPERATIONS AND MAINTENANCE OF THE SYSTEM.
o HUMAN FACTORS CONSIDERATIONS RELATING TO THE SELECTED SYSTEMS (e.g., ACCESSIBILITY AND LABELLING OF VALVES) AND THE SYSTEMS -
SUPPORTING PROCEDURES ARE ADEQUATE TO ENSURE PROPER SYSTEM L
OPERATION UNDER NORMAL AND ACCIDENT CONDITIONS.
L--
STATUS:
THE 2 COMPLETED EDBD's ARE CURRENTLY IN THE PROCESS. WITH COMPLETION EXPECTED BY THE END OF THE YEAR.
THE REMAINING EDBD's WILL BE FIELD VALIDATED FOLLOWING-l COMPLETION OF THE EDBD.
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s r-SAFETY LIST SYSTEM (SLS) PROGRAM PURPOSE:
DEVEI4P A MAINFRAME COMPUTER DATABASE PROGRAM THAT WILL PROVIDE COMPONENT / SYSTEM SAFETY CLASSIFICATION INFORMATION BASED ON COMPONENT / SYSTEM I.D.
(TAG NO.).
PHASES i
I.
DEVELOP SYSTEM SOFTWARE AND LOAD THE EXISTING MAROCO?Y SAFETY LIST DATA (9000 COMPONENTS).
II.
EXPAND THE SAFETY LIST SYSTEM DATABASE TO SPECIFY THE SAFETY CLASSIFICATIONS FOR ALL THE COMPONENTS IN THE APPROVED 37 SYSTEMS ESTABLISHED IN PROGRAM NO. 2 ( APPROXIMith LY 18,000 ADDITIONAL COMPONENTS).
STATUS:
PilASE I COMPLETE 2/1/89 PHASE II ESTIMATE COMPLETION 12/31/89
CONFIGURATION MANAGEMENT INFORMATION SYSTEM fCMIS) PROGRAM PURPOSE EXPAND THE MAINFRAME SLS COMPUTER DATABASE PROGRAM TO INCLUDE ADDITIONAL COMPONENT AND DESIGN BASIS INFORMATION.
o THE SLS PROGRAM WILL BECOME A MODULE OF THE OVERALL CMIS PROGRAM.
o DEVELOP THE SOFTWARE FOR THE FOLLOWING ADDITIONAL MODULES AND I.4AD DATA INTO THE PROGRAM.
COMPONENT DATA - THIS INCLUDES DATA FROM EXISTING LISTS SUCH AS VALVE, HANGER, EQUIPMENT, AND INSTRUMENT.
DOCUMENT CROSS REFERENCE INFORMATION THIS INCLUDES CROSS REFERENCING TAG NO. TO VARIOUS DOCUMENT 3 SUCH AS PROCEDURES, DRAWINGS, AND EBDB.
MODIFICATION CROSS REFERENCE - THIS INCLUDES A TAG NO.
I VS. MODIFICATION NO. CROSS REFERENCE.
STATUS THE CMIS FROGRAM BECAME OPERATIONAL ON MAINFRAME COMPUTER ON 9/23/89.
THE VALVE DATA AND HANGER DATA PORTION OF THE COMPONENT DATA MODULE ALSO BECAME OPERATIONAL ON 9/23/89.
THE EQUIPMENT DATA PORTION WILL BE OPERATIONAL BY 11/89 AND THE INSTRUMENT DATA PORTION IN THE IST QUARTER 1990.
THE REMAINING MODULES ARE SCHEDULED TO BE DEVEI4 PED IN 1990.
7 CONFIGURATION CONTROL PROCESS EVALUATION /ENMANCEMENT PROGRAM PURPOSE:
ENSURE ADMINISTRATIVE PROCEDURES ARE IN PLACE TO MAINTAIN THE CONFIGURATION MANAGEMENT SYSTEMS AND DOCUMENTS UP-TO-DATE.
FRASIS.
2 I.
ENSURE CONTROLS ARE IN PLACE TO MAINTAIN THE CMIS, SLS, EDBD's, ETC. AS EACH IS DEVELOPED.
II.
DEVEI4P A CONFIGURATION MANAGEMENT CONTROL PHILOSOPHY FOR CONFIGURATION DOCUMENTS.
IDENTIFY EACH OF THESE TYPES l
1 DOCUMENTS AND EVALUATE HOW THE DOCUMENT IS CONTROLLED. UPDATE THE CONTROLS AS REQUIRED.
l STATUS:
CONTROLS ARE IN PLACE FOR THE PHASE I PORTION, PHASE II IS AN ONGOING PROCESS WHEREAS CONTROLS ARE BEING IMPLEMENTED FOR DOCUMENTS IDENTIFIED AS REQUIRED.
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CONFIGURATION MANAGEMENT IMPLEMENTATION PROGRAM PURPOSE:
THIS PROGRAM IS INTENDED TO BE APPLIED TO ALL OF THE PROGRAMS IDENTIFIED WITHIN THE APPROVED CM PLAN.
THERE ARE THREE MAJOR GOALS THAT WILL BE ACHIEVED BY THIS EFFORT.
THESE GOALS ARE AS FOLLOWS:
GOAL NO. 1:
ENSURE THE CONCEPTS PRESENTED TO SENIOR MANAGEMENT IN THE FORM OF THE CM PLAN ARE DETAILED AND CARRIED OUT WITHIN THE ESTABLISHED SCHEDULE AND BUDGET.
GOAL NO. 2:
ENSURE CM AND USERS ARE IDENTIFIED AND CONSULTED TO ENSURE THEIR NEEDS AND REQUIREMENTS ARE CONSIDERED DURING THE DEVELOPMENT OF THE VARIOUS CM PRODUCTS.
GOAL NO. 3:
THE OVERALL PROJECT SHALL BE CONSTANTLY EVALUATED TO MAXIMIZE EFFICIENCY, THUS DECREASING PROJECT COST AND REDUCING PRODUCT DELIVERY TIME.
NEW CONCEPTS AND IDEAS WILL BE REVIEWED TO DETERMINE IF A SLIGHT INCREASE IN MARGINAL PRODUCT COST MAY RESULT IN ADDITIONAL PRODUCT BENEFITS.
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ASSURE ADMIN. CONTROLS ARE IN AS REQUIRED I
PLACE TO MAINTAIN AND THE DEVEI4 PED CM PRODUCTS l
INITIATE THE CONTROLS PROGRAM Complete PIIDT PROGRAM
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ISSUE PIIDT EDBD's Complete i
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CICSE-OUT ABD FIELD VALIDATION Complete PACKAGES i
COMPLETE THE SLS DATA BASE 12/31/89 EXPANSION (PHASE 2)
COMPLETE THE MS AND DH SYSTEM 12/31/89 L
FIELD VALIDATIONS (PIIDT)
COMPLETE THE DEVE14PMENT OF THE 12/31/89 CMIS SOFTWARE FOR THE ENGINEERING LISTS P
COMPLETE SECOND GROUP OF EDBD's 1/20/90 COMPLETE CMIS SOFTWARE 3/30/91 DEVELOPMENT AND DATA ENTRY COMPLETE LAST GROUP OF EDBD's 11/92 l
1' COMPLETE FIELD VALIDATION FOR 7/93 l
LAST GROUP OF EDBD's l
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