ML20137L102
| ML20137L102 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/17/1986 |
| From: | Siegel B Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8601240376 | |
| Download: ML20137L102 (69) | |
Text
,
- JAN 171986 Docket No. 50-461. s APPLICANT: Illinois Power Company FACILITY: Clinton Pcwer Station
SUBJECT:
SUMMARY
OF MEETING WITH ILLIN0IS POWER COMPANY RELATED TO CLINTON'S READINESS TO LOAD FUEL A meeting between representatives of the Illinois Power Certpany (IP) and the NRC staff (NRR and Region III),was held on January 13, 1986, at the llRC Office in Bethesda, Maryland. The purpose of the meeting was the following:
IP to apprise the staff of Clinton's readiness to load fuel; IP to define the approach to complete all remaining tasks; IP to discuss the status of major licensing tasks remaining; and IP to identify fuel load deferral items and justification for each. contains a copy of the list of meeting attendees and Enclosure 2 contains a copy of the meeting handouts.
During the me'eting a concern was expressed by Region III over the number of system test deferral items beyond fuel load that were being requested by IP.
This practice has the potential for diverting manager:ent attention away from the day-to-day problems that develop during plant startups. IP is planning to submit a letter no later than the end of January that provides the justi-fication for these deferrals. The NRR staff will assess the safety significance and Region III will assess the operational significance of these preposed deferrals, s
ownn:" n -! Ly Byron Siegel, Project fianager BWR Project Directorate No. 4 Division of BWR Licensing
Enclosures:
As stated DISTRIBUTION Docket File cc: See next page NRC PDR Local PDR FD#4 Reading JPartlow gRo1240376 e60117 WBUtler o ADOCK 05000461 Bsjegel N Goddard, OELD
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's ,o JAN 17 E5 Docket No. 50-461 APPLICANT: Illinois Power Company FACILITY: Clinton Power Station
SUBJECT:
SUMMARY
OF MEETING UITH ILLIN0IS POWER COMPANY RELATED TO CLINTON'S READINESS TO LOAD FUEL A meeting between representatives of the Illinois Power Company (IP) and the NRC staff (NRR and Region III) was held on Jcnuary 13, 1986, at the NRC Office in Bethesda, Maryland. The purpose of the meeting was the following:
IP to apprise the staff of Clinton's readiness to load feel; IP to define the approach to complete all remaining tasks; IP to discuss the status of major licensing tasks remaining; and IP to identify fuel load deferral items and justification for each.
Enclosure 1 contains a copy of the list of meeting attendees and Enclosure 2 contains a copy of the meeting handouts.
During the meeting a concern was expressed by Region III over the number of system test tieferral items beyond fuel load that were being requested by IP.
This practice has the potential for diverting management attention away from the day-to-day problems that develop during plant startups. IP is planning to submit a letter no later than the end of January that provides the justi-fication for these deferrals. The NRR staff will assess the safety significance and Region III will assess the operational significance of these proposed deferrals. -
./- O : .,' u(G ,i - u ByronSiehel,ProjectManager BWR Project Directorate No. 4 Division of BWR Licensing
Enclosures:
As stated cc: See next page
ce :. .
Mr. Frank A. Spangenberg Clinton Power Station Illinois Power Company Unit 1 cc:
i Hark Jason Jean Foy, Esquire Assistant Attorney General 511 W. Nevada Public Utilities Divisicn Urbana, Illinois 61801 Office of the Attorney General State of Illinois Center Richard B. Hubbard i 100 West Randolph Street - 12th Floor Vice President l Chicago, Illinois 60601 Technical Asscciates 1723 Hanilton Avenue - Suite K Mr. D. P. Hall San Jose, California 95125 Vice President Clinton Power Station P. O. Box 678 Clinton, Illinois, 61727
! Mr. D. C. Shelton Manager-Nuclear Station Engineering Dpt.
Clinton Power Station
- P. O. Box 678 9
Clinton, Illinois 61727 Sheldon Zabel, Esquire
! Schiff, Hardin & Waite 7200 Sears Tower 233 Wacke. Drive
, Chicago, Illinois 60606 ,
i Resident Inspector V. S. Nuclear Regulatory Commission l
RR 3, Box 229 A Clinton, Illinois 61727 Mr. R. C. Heider Project Manager Sargent & Lundy Engineers i 55 East Monroe Street l Chicago, Illinois 60603 L
f Mr. L. Larson I Project flanager General Electric Company 175 Curtner Avenue, N/C 395 San Jose, California 95125 Regional Administrator, Region III 799 Roosevelt Road i Glen Ellyn, Illinois 60137
't -
I cv . .-
Mr. Frank A. Spangenberg Clinton Power Station Illinois Power Company Unit 1 cc:
Mark Jason Jean Foy, Esquire Assistant Attorney General 511.W. Nevada Public Utilities Division Urbana, Illinois 61801 Office of the Attorney General State of Illinois Center Richard B. Hubbard 100 West Randciph Street - 12th Floor Vice President Chicago, Illinois 60601 Technical Associates 1723 Hanilton Avenue - Suite K Mr. D. P. Hall San Jose, California 95125 Vice President Clinton Power Station P. O. Box 678 Clinton, Illinois, 61727 Mr. D. C. Shelton Manager-Nuclear Station Engineering Opt.
Clinton Power Station P. O. Box 678 Clinton, Illinois 61727 Sheldon Zabel, Esquire Schiff, Hardin & Waite 7200 Sears Tower 233 Wacker Drive Chicago, Illinois 60606 ,
Resident Inspector U. S. Nuclear Regulatory Commission RR 3, Box 229 A Clinton, Illinois 61727 Mr. R. C. Heider --
Project Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Mr. L. Larson Project Manager General Electric Company 175 Curtner Avenue, N/C 395 San Jose, California 95125 Regional Administrator, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
. -. . - _ - . . . = _ . ..
l Enclosure 1 HEETING ATTENDEE'S FOR l
CLINTON POWER STATION'S READINESS FOR FUEL LOAD MEETING JANUARY 13, 1986 Name Organization / Title J. W. Wilson Ill. Power, Plant Manager F. A. Spangenberg Ill. Power, Manager, Licensing & Safety W. Connell Ill. Power, Manager, QA T. L. Riley Ill. Power, Licensing Project Engineer i
P. J. Telthorst IPC, Licensing Engineer B. L. Siegel NRC/ Licensing Project Manager PD#4 R. F. Warnick NRC-RIII, Chief, Reactor Projects Branch 1 T. P. Gwynn US NRC Region III/ Chief, Projects Section 18 F. J. Jablonski US NRC Region IV/ Project Inspector K. M. Campe NRC/ DBL /PSB Paul Boehnert NRC/ACRS Staff Wayne Hodges NRC/ DBL /RSB M. Srinivasan NRC/ DBL /EICSB G. Lainas NRC/ DBL W. R. Butler NRC/ DBL S. C. Black ' NRR/PPAS D. B. Vassallo NRR/ DBL /F0B .
, G. L. Edgar N&H/IP R.K.(Dick)Phares Illinois Power Technical R. W. Houston NRC/ DBL 1
e 1
i 1
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CHAIRMAN AND PRESIDENT EXECUTIVE I__ VICE PRESIDENT I
I l VICE g PRESIDENT -
l MANAGER l NUCLEAR PROGRAM
, COORDINATION . .
I I
DIRECTOR DIRECTOR g
NUCLEAR HUCLEAR I PROGRAM PROJECTS l ASSESSMENT
- GROUP 1
1 1
MANAGER MANAGER DIRECTOR MANAGER MANAGER MANAGER MANAGER MANAGER OUTAGE CLINTON NUCLEAR QUALITY LICENSING NUCLEAR NUCLEAR START-UP MANAGEMENT POWER TRAINING ASSURANCE AND STATION PLANNING
.] STATION SAFETY ENGINEERING AND SUPPORT O PE R ATIONS STAFF STAFF STAFF STAFF STAFF STAFF STAFF 2
o o
- E
.- -s (D
f9
MEETING OBJECTIVES O APPRISE NRC STAFF OF CPS READINESS TO LOAD FUEL o DEFINE APPROACH TO COMPLETE ALL REMAINING TASXS REQUIRED FOR FUEL LOAD & LATER MILESTONES O DISCOSS STATUS OF MAJOR LICENSING TASXS REMAINING O DEFINE FUEL LOAD DEFERRAL ITEMS & JUSTIFICATION FOR EACH O OBTAIN NRC STAFF SUPPORT FOR IP PROGRAMMATIC APPROACH 9 M9*
O
O .
MEETING AGENDA 0 CPS " READINESS TO LOAD FUEL" LETTER O SER AND I&E E ISSUES STATUS O FSAR CERTIFICATION O SITE W!DE STATUSING SYSTEM l
0 CONSTRUCTION AND TESTING STATUS 8 SPECIFIC AREAS OF REGULATORY INTEREST O
e POWER ASCENSION PROGRAM ACCELERATION'(PAPA) i
-. __ - . = _ --- ...
e I
i
" READINESS TO LOAD FUEL" LETTER 1
O INITIAL SUBMITTAL - DECEMBER 9,1985 O IDENTIFIES CURRENT STATUS OF DESIGN CONSTRUCTION, PRE-OPERATIONAL TESTING AND LICENSING ACTIVITIES O REQUIRED TO SUPPORT NRC ISSUANCE OF FUEL LOAD / LOW
~
' POWER OPERATING LICENSE 0 SUCCESSIVE MONTHLY REVISIONS UP TO FUEL LOAD o ALLOWS EFFICIENT ALLOCATION OF BOTH IP & NRC STAFF RESOURCES TO SUPPORT FUEL LOAD OF CPS l
SER/FSAR ISSUES (" CLIP" REPORT) i 0 CLOSURE OF LICENSING ISSUES PROGRAM (" CLIP" REPORT)
I O TRACKING SYSTEM FOR RESOLUTION OF LICENSING ISSUES
- O IN CONJUNCTION WITH NRC INPUTS, UPDATED ON WEEKLY BASIS ,
O INCLUDES ALL SER " OUTSTANDING", " CONFIRMATORY",
& " LICENSE CONDITIONS" O ALSO INCLUDES ALL TMI ISSUES, & OTHER MAJOR ISSUES WHICH REQUIRE RESOLUTION (E.G., DESIGN & FS AR CH ANGES)
O lDENTIFIES BOTH IP AND NRC STAFF ACTIONS REQUIRED
- # IP RESPONSIVE TO NRC SAFETY CONCERNS - RESOLVE i IN TIMELY MANNER
- i i
.j *
.L .e CURRENT "CL1P" ISSUES STATUS i
4 i
G ALL SER ISSUES HAVE NOW SEEN IDENTIFIED AS "UNDER NRC STAFF REVIEW" i
0 CURRENT " CLIP" STATUS (AS OF JANUARY 7,1986)
O TOTAL ISSUES REMAINING OPEN = 38 9 ISSUES REQUIRING NRC ACTION = 25 (NRC CLOSURE REQUIRED)
- ISSUES REQUIRING IP ACTION = 13 (FOLLOWUP ACTION)
I J
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i t .
MAJOR SER ISSUES REMAINING FOR CLOSURE 3 SER " OUTSTANDING" ISSUES O ONLY SIX (6) REMAIN
- REQUIRE HRC ACTION TO CLOSE (4)
- 1. +5 - POSTULATED P! PING FAILURES
- 2. +9 - POOL DYNAMICS LOADS
- 3. +13 - REMOTE SHUTDOWN SYSTEM
- 4. *15- CONTROL SYSTEMS FAILURES
- REQUIRE IP FOLLOWUP ACTION TO RESOLVE (?)
- 1. +7 - ENVIRONMENTAL, SEISMIC QUALIFICATION AND PUMP &
VALVE OPERABILITY
- 2. +18 - EMERGENCY PLANNING O SER "CONFIRMATOR " ISSUES' O ONLY FOUR (4) REMAIN
- REQUIRE NRC ACTION TO CLOSE (3)
- 1. +24 - ATWS RECIRCULATION PUMP TRIP
- 2. +68 - PRESERVICE AND INSERVICE TESTING
- 3. *71 - HUMPHREY CONTAINMENT ISSUES
- REQUIRE IP FOLLOWUP ACTION TO RESOLVE (1)
- 1. +1 - METEOROLOGICAL MEASUREMENTS PROGRAM
laE ]?)TERFACE - CORRECT]VE ACT]O?]
TRACX1?)G (" CAT") SYSTEN O " CAT" PROGRAM FOR TRACKING STATUS AND CLOSURE OF ALL laE OPEN ITEMS O OPEN ITEMS HAVE BEEM CATEGORIZED AND PRIORITIZED TO SUPPORT REQUIRED CLOSURES BY FUEL LOAD O OVERALL STATUS AS OF JANUARY 7,1986 NRC 50.55(e) Part 21 Inspect. Items PENDING N,RC ACTION FOR CLO5URE 17 13 102 REQUIRE IP ACTION FOR CLOSURE 11 15 185 TOTAL OPEN ITEMS 28 28 287 O ACTIONS ARE SCHEDULED ON A DAILY ACTIVITY LIST I
l&E BULLET]NS, NOTICES, C]RCULARS
& GENERIC LETTERS S UTILIZES " CAT" SYSTEM TO TRACX ACTIONS REQUIRED TO CLOSE I
O ACTIONS ARE SCHEDULED ON A DAILY ACTIVITY LIST O CURRENT STATUS - AS OF JANUARY 6,1986 0 l&E BULLETINS AND CIRCULARS TOTAL
- OPEN = 19 IP ACTION REQUIRED =11 NRC CLOSURE PACKAGE REVIEW REQUIRED = 8_
O I&E NOTICES (NOT ALT. REQUIRE CLOSURE PRIOR TO FUEL LOAD) -
l TOTAL + OPEN = 62 l 9 GENERIC LETTERS TOTAL + OPEN = 4_
l
.8 e 4
1 l
TM1 ACTIVITIES AND ISSUE RESOLUilON STATUS 0 NUREG-0737 ISSUES ARE RESOLVED AND ESSENTIALLY COMPLETED 1 0 NUREG-0737, SUPPLEMENT #1 ISSUES ARE RESOLVED 0 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) l
~
- DESIGN ISSUES RESOLVED, DYNAMIC SIMULATION TEST DEMONSTRATED EFFECTlVENESS
- STARTUP SYSTEM TESTING IN PROGRESS, FINAL VaV REPORT WILL BE ISSUED PRIOR TO FUEL LOAD (IP INTERNAL REPORT)
G DETAILED CONTROL ROOM DESIGN REVIEW (DCRDR)
)
- PROGRAM COMPLETED AND
SUMMARY
, REPORT SUBMITTED TO NRC
-NRC AUDIT IN OCTOBER 1985 WAS SU'CCESSFUL, OPEN ITEMS WILL NOT IMPACT FUEL LOAD
- SUPPLEMENT TO
SUMMARY
REPORT WILL BE SUBMITTED TO STAFF 6 MONTHS AFTER FUEL LOAD, ADDRESSING AUDIT
'OPENITEMS 9 R.G.1.97, POST ACCIDENT MONITORING EQUIPMENT
- ALL NRC TECHNICAL ISSUES RESOLVED
- FIELD INSTALLATION OVER 99% COMPLETE, WILL BE DONE BY FUEL LOAD
- lNSTRUMENTS AND CONTROLS LABELLED IN CONTROL ROOM
! - REACTOR VESSEL " FUEL ZONE" WATER LEVEL AND NEUTRON MONITORING SYSTEM WILL BE UPGRADED DURING 1st REFUEL
-=
_--e--- --e-e.. ,+- g_ . -,__ _ . - , .-wv- - -- - . - - - - ,--y_ , _g-,.-,,*.,,--,-,,s-y-,, ,--,, .--w, ---, -- . , , -.-, --
TN11 ACTIVITIES AND ISSUE RESOLUTION STATUS (continued)
NUREG-0737, SUPPLE 11ENT #1 ISSUES ARE RESOLVED (continued)
UPGRADING OF EMERGENCY OPERATING PROCEDURES (EOPs) .
- ALL REQUIRED EOPs UPGRADED TO SYMPTOMATIC-BASED
- 1. LEVEL CONTROL EOP
- 2. CONTAINMENT CCNTROL EOP -
(INCLUDES NRC APPROVED POST-ACCIDENT VENTING)
- 3. COOLDOWN EOP
- 4. REACTIVITY CONTROL EOP
- 5. SECONDARY CONTAINMENT / RADIOACTIVITY RELEASE
. CONTROL EOP -
- EOP FOR HYDROGEN CONTROL UNDER DEVELOPMENT, GENERIC PROCEDURE SUSMITTED BY HYDROGEN CONTROL OWNER'S GROUP EMERGENCY RESPONSE FACILITIES (ERFs)
- ALL ERFs ESSENTIALLY COMPLETE AND OPERATIONAL
- SUCCESSFUL DECEMBER 4,1985, EMERGENCY EXERCISE O 9 0
a ..
3 A1AJOR LICENSING ISSUE TASXS REA1AINING O SER ISSUES " CLIP" REPORT
^
0 HYDROGEN MANAGEMENT (SER LICENSE CONDITION +5)
- NRC STAFF MUST APPROVE OF CPS PRELIMINARY ANALYSIS
- PURSUANT TO 10CFR50.44 PRIOR TO 5% PO'NER AUTHORIZATION
@ PUMP & VALVE OPERABILITY REVIE'NS (PVOR) l 1 - AUGUST & NOVEMBER 1985 NRC AUDITS CONDUCTED ,
- ALL AUDIT OPEN ITEMS ADDRESSED WITH T'NO EXCEPTIONS
- 1. SYSTEM WALKDOWNS 'OF S AFETY RELATED PUMPS & : l
! VALVES
- 2. V ALVE " TEST VS. AN ALYSIS"
- IP COMPLETION LETTER TO NRC DUE JANUARY 31,1986 i G EQUIPMENT SEISMIC & ENVIRONMENTAL QUAllFIC ATION
- JULY AND AUGUST 1985 NRC AUDITS CONDUCTED ,
! - FSAR TABLE REVISIONS DUE IN AMENDMENT +36
! - EQ PACKAGES COMPLETE IN JANUARY 1986 l - 4 SORT PKGS. REMAIN - COMPLETE IN FEBRUARY 1986
- 4 AUDIT OPEN ITEMS REMAIN - COMPLETE IN FEBRUARY 1986 9 FIRE PROTECTION ISSUES .
I - SEPTEMBER 1985 NRC PRE-AUDIT REVIEW CONDUCTED
- ONE OF CPS " CRITICAL PATH" SYSTEMS i - NRC REVIEW OF CPS DEVIATIONS IN FIRE PROTECTION ;
EVALUATION PREPORT & SAFE SHUTDOWN ANALYSIS NEEDED i
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l l - - - _.- -- -- - - -
)
i FSAR CERT 1FICATION PROGRAM
\
O IP INITIATED PROGRAM TO ASSURE FSAR CONSISTENT WITH CPS DESIGN O VARIOUS REVIEWS PERFORMED BY IP, ARCHITECT EMGINEER (S&L), a NSSS VENDOR (GE) ,
O PORTION OF FSAR CHANGES RESULTING FROM THIS i PROGRAM WERE SUBMITTED IN AMENDMENT +35 I
O REMAINDER OF FSAR CHANGES RESULTING FROM THIS .
PROGRAM WILL BE INCLUDED IN AMENDMENT +36 '
1 4
e g .
SITE WJDE STATUS 1MG SYSTEN ("TH]NGS")
2 HIGH LEVEL, CONTINUOUS MANAGEMENT INVOLVEMENT 3 ACCESSES EXISTING DATA BASES AND CONSOLIDATES INFORMATION INTO MANAGEMENT
SUMMARY
REPORT o TRACKS WEEKLY TRE'NDS kND l TOTAL COUNT OF ALL " THINGS" REMAINING ON PROJECT G INDIVIDUAL COUNTS FOR EACH SOURCE DATA BASE PROVIDED O DETAILED PRINTOUTS, BY DEPARTMENT, .0F OPEN " THINGS"
- IDENTIFIES SYSTEM, MILESTONE AND DUE DATE p
4 6
6
WEEXLY ACTIVITY MEETINGS TO TRACX PLANT COMPLET]ON O EVERY MONDAY " PLAN OF THE WEEK" MEETING G COORDINATE & SCHEDULE ALL ACTIVITIES FOR COMING TWO WEEKS 3 CHAIRED BY J. S. PERRY (MANAGER OF NUCLEAR PROGRAMS) 0 EVERY THURSDAY - SYSTEMS READIMESS AND LICENSING MEETING G COORDINATE & SCHEDULE ACTIVITIES FOR SYSTEMS UNDER PLANT STAFF CONTROL - DECLARE SYSTEMS FULLY OPERABLE O COORDINATE & SCHEDULE ACTIVITIES FOR LICENSING TASKS REMAINI,NG FOR CLOSURE O CHAIRED BY J. G. COOK (ASSISTANT PLANT MANAGER)
O EVERY FRIDAY - STAT STARTUP " PHASE 11" SYSTEM RELEASE MEETING e COORDINATE & SCHEDULE ACTIVITIES FOR SYSTEMS UNDER STARTUP TESTING CONTROL e CHAIRED BY J. H. GREENE (CPS STARTUP MANAGER)
O ALL WEEKLY MEETINGS ARE FULLY SUPPORTED BY THE ATTENDANCE OF SITE MANAGERS 6
PROJECT CONTROL CENTER ,
O IMPLEMENTED ON JANUARY 8,1988 O LOCATION: PLANT STAFF - SERVICE BUILDING O FUNCTIONS O PLAN, SCHEDULE, AND TRACK DAILY PLANT ACTIVITIES O SUPPORT COMPLETION OF WORX RELATED TO FUEL LOAD l 0 RES LVE CONSTRUCTION, TESTING, ENGINEERING, LICENSING, l ~
RLANNING PROBLEMS AS THEY ARISE l
O INTEGH TE ALL WORK INTO PRIORITIZED PLAN O STRUChURE 1
e MANAGER - J. S. PERRY .
ASSISTANT MANAGER - H. R. LANE (STA'ND-IN RELIEF MANAGERS DURING EECOND SHIFTS)
PERSONNEL REPRESENTATIVE FROM EACH SITE ORGANIZATION
- ENGINEERING - CONSTRUCTION !
- LICENSING & S AFETY - STARTUP
- PLANT OPERATIONS - MAINTENANCE
- PURCHASING - -
0 2 SHIFTS EACH DAY, SIX DAYS PER WEEK 6 5 98 6 9-
l !
1 i l
- APPROACH TO SYSTEhlS REQUIRED FOR FUEL LOAD l 1
i 0 CURRENT NRC CONSTRUCTION / TEST DEFERRAL REVIEW l j CRITERIA O IF THE DEFERRED ITEM MEETS ONE OR MORE OF THE l
! FOLLOWING CRITERIA, THEN AN EXEMPTION IS NOT REQUIRED l l I
- 1. EQUIPMENT IS NOT REQUIRED BY REGULATIONS i ;
i
- 2. EXISTING PLANT DESIGN a CONSTRUCTION MEETS I THE REGULA'TIONS ,
- 3. COMPENSATORY MEASURES HAVE BEEN PROVIDED WHICH MEET REGULATIONS UNTIL CONSTRUCTION ITEM lS COMPLETE l
- 4. GDC OR OTHER REGULATION DOES NOT REQUIRE TESTING TO BE COMPLETED .
! O IP SYSTEM STATUS REPORT PREPARED i
- i j e IDENTIFIES REQUIRED SYSTEMS FOR FUEL LOAD !
l !
O ESTABLISHES REQUIRED MILESTONE COMPLETION FOR l I LATER SYSTEMS i l i i I
! o 9 IDENTIFIES CURRENT COMPLETION STATUS AND ASSOCIATED j l STARTUP TEST DEFERRALS IF APPLICABLE l 1 !
j S REQUIREMENTS FOR FUEL LOAD CONSISTENT WITH NRC l
! CRITERIA & BASED ON TECHNICAL SPECIFICATION NEEDS j BY PLANT MODE j i
)
j l
^
i l
t TEST PROGRAhl STATUS - THROUGH JANUARY 6,1988 0 CHECKOUT AND INITIAL OPERATION TESTS COMPLETED .95.5%
0 ACCEPTANCE & PRE-OPERATIONAL TESTS COMPLETED 68.6%
(83 out of 158 complete)
O TEST PROCEDURES
- ACCEPTANCE TESTS '
ONLY 3 TOTAL REMAIN ,
O PRE-OPERATIONAL TESTS O S'T A R T U P T E S T S ONLY 5 REMAIN
- O ALL PROCEDURES REMAINING WILL DE APPROVED IN JANUARY 1986 i 8 L
l
_ __ _. .._.- _ _ _ _ ..__.. - _ _ _ _ . _ . _ . _ . _ _ ~ - _ - _ _ .
l CONSTRUCTION AND TESTING STATUS '
3 CONSTRUCTIO?! IS "SUBSTA?lTIALLY COMPLETE" 3 ALL PLANT SYSTEMS TURNED OVER FROM CONSTRUCTION
- TO STARTUP ORGANIZATION FOR TESTING l
l 0 OVER 99% COMPLETE BASED ON COMMODITIES O CURRENT SYSTEM STATUS (AS OF JAN. 3,1988) &
l PROJECTED FUEL LOAD COMPLETION STATUS SYSTEMS REMAINING CURRENTLY FUEL LOAD ;
- IN STARTUP TESTING 60 20
- FUNCTibNAL (UNDER 59 32 i PLANT. STAFF CONTROL) .
- DEMONSTRATED FULLY -
l OPERABLE 14 81 :
t i .
TOTAL
- OF SYSTEMS 133 133 l O LIST OF SYSTEMS DEFERRED FOR TESTING AND OPERASILITY j COMPLETION PROVIDED AS A HANDOUT !
1 l 9 20 SYSTEMS IN STARTUP TESTING AT FUEL LOAD [
! - COMPLETE PRIOR TO INITIAL CRITICALITY = 4 j - COMPLETE PRIOR TO HEATUP = 7 )
i ,
j - COMPLETE PRIOR TO 5% POWER = 5 !
! - COMPLE~E PRIOR TO COMMERCIAL OPERATIONS = 4 l i
]
^
~
} [
T
STARTUP TESTING DEFERRAL ITEMS 0 VARIOUS STARTUP TEST PROGRAM DEFERRALS -
ACCEPT ANCE, PRE-OP., a ST ARTUP PH ASE TESTING O TOTAL # SYSTEMS AFFECTED = 34 O SYSTEMS REQUIRED FOR FUEL LOAD = 14 O SYSTEMS NOT REOUIRED FOR FUEL LOAD = 20 o SYSTEMS REQUIRED FOR FUEL LOAD (14)
O4 ARE PARTIAL PRE-OP TEST DEFERRALS
- COMMUNICATIONS (SOUND POWERED PHONES) - 5% POWER
- PROCESS COMPUTER (NSSS/ BOP PERFORMANCE CALCULATIONS)
- lNITIAL CRITIC ALITY
- FUEL POOL COOLING AND CLEANUP (POOL LEVEL CONTROL)
- 5% POWER
- LEAK DETECTION SYSTEM (TEMPERATURE SENSORS)
- INITIAL CRITIC ALITY
i
! STARTUP TEST DEFERRAL ITEh1S (continued) -
i
! O SYSTEMS REQUIRED FOR FUEL LOAD (14)
I j 3 10 ARE RELATED TO VENTILATION SYSTEM TESTS
! - FINAL Ala BALAtlCING (3 SYSTEMS) - (1) INITIAL CRITICALITY , l l AND ('7) 5% POWER !
3 - IN-PLACE FILTER TESTING (4 SYSTEMS) - (2) INITIAL '
CRITICALITY AND (2) 5% POWER
- j - PRE-OP TESTING (4 SYSTEMS) - (1) INITIAL CRITIC ALITY !
I AND (3) 5% POWER t
i j - PRESSURE BOUNDARY TESTING (2 SYSTEMS) - BOTH 5% POWER ,
4
- FIRE DAMPERS TESTS (2 SYSTEMS) - BOTH 5% POWER !
l . .
O SYSTEMS NOT REQUIRED FOR FUEL LOAD (20) {
f i
! e 5 ARE NOT REQUIRED UNDER FSAR CHAPTER +14 PROGRAM l t
I i
(
- CATHODIC PROTECTION (COMMERCIAL OPS.)
i
- CHILLED WATER (INITIAL CRITICALITY) , ;
i !
j - RESPIRATOR AIR (INITIAL CRITICALITY) .
i
- ELECTRICAL WELDING (COMMERCIAL OPS.) !
I - STATION HEATINO (COMMERCIAL OPS.) I 1
f i !
i .
STARTUP TEST DEFERRAL ITEMS (continued) o SYSTEMS MOT REQUIRED FOR FUEL LOAD (20) o 8 ARE EITHER FULL OR PARTI AL PRE-OP TEST DEFERRALS
- CONTAINMENT NONITORING (INITIAL CRITICALITY)
- MSIV LEAXAGE CONTROL (INITIAL CRITICALITY)
- COM3USTIBLE GAS CONTROL (HEATUP)
- SOLIO RADWA'NSTE PROCESSING (HEATUP)
- STEAM DYPASS (5% POWEH)
- REACTOR CORE ISOLATIO?l COOLING (5% POWER)
- HYDROGEN IGNITER SYSTEM (5% POWER) -
, - TRANSVERSING INCORE PRODE (5%' POWER)
O 7 HELATED TO VENTILATION / FILTER SYSTEM TESTING
- FINAL AIR BALANCE (O SYSTEMS) - ALL 5% POWER
- IN-PLACE FILTER TESTS (3 SYSTEMS) - ALL 5% POWER
- PRE-OP TESTP (2 SYSTEMS) - DOTH S% POWER O
- i l PERSONNEL A?lD STAFFl?lG STATUS I
O CURRENT STAFFING i
O PLANT STAFF : 27 LICEMSES .
4
- 18 SRos .
- l .
9 Ros '
i j O PROJECTED FOR FUEL LOAD r,
G PLANT STAFF : 41 LICENSES :
i - 26 SHOs !
4 ;
- 15 Ros
- i l 0 SHIFT STAFFING (OPER ATIONS) , l 4 5 SHIFT CAPABILITY -
- I
- ,. l
- # NORMAL SHIFT COMPOSITION l l * - 1 SHIFT SUPERVISOR (SRO) .
l 1
l
- 2 ASSISTANT SHIFT SUPERVISORS (SRos) 1 i
! - 2 CONTROL ROOM OPERATORS (ROs) l f - 1 SHIFT TECHNICAL ADVISOR l .
i j O SUPERVISORY OPERATING PLANT EXPERIENCE ,
I
- (SOPE) PROGRAM '
j .. .
1 4 FULFILLS GENERIC LETTER 84-16 REOUlREMENTS O HOT OPERATING EXPERIENCE REQUIREMENTS ARE MET O EXPECT CPS TO HAVE LICENSE CONDITION I
i 1 n-mw-~~--
CPS CRITICAL PATH ANAL'/ SIS l
1 O MONTHLY A1ANAGEh1ENT SUMh1 ARIES PROVIDED O CONTROLLING RESTRAINT IS CHECXOUT & INITIAL OPERATIO?!
. TESTING.ON THE HYDRAULIC CONTROL UNITS FOR CONTROL .
ROD DRIVE SYSTEM O CRITICAL ACTIVITIES (BY SYSTEM) ARE AS FOLLOWS:
O CONTROL ROD DRIVE SYSTEM O FUEL HANDLING EQUIPMENT
- PRE-OP PROCEDURE VERIFIC ATION
- CHECXOUT & INITIAL OPERATION TESTING O FIRE PROTECTION SYSTEMS
- PRE-OP TES
T. PROCEDURE
ISSUANCE - -
- VARIOUS EQUIP. INSTALLATION WORK O NEUTRON MONITORING ' SYSTEM
- COMPLETE CHECXOUT & INITIAL OPERATION TESTING
- PRE-OP PROCEDURE VERIFICATION J
O HEPA HVAC - CONTROL ROOM, STANDBY GAS TREATMENT,
& DRYWELL PURGE VENTILATION ,
- lMPLEMENT VARIOUS MODIFIC ATlONS
- COMPLETE CHECXOUT & INITIAL OPERATION TESTING
\
.. .. j CPS NAJOR N]LESTONES COMPLETE Pa REMAIN]NG o MAJOR MILESTONES COMPLETED O REACTOR INTEGRATED FLUSH 12/13/84 O REACTOR-COLD HYDRO PRESSURE TEST 1/17/85 0 RPV HOT OPERATION 7/3/85 O FUEL RECEIPT 8/19/85 O EMERGENCY PREPAREDNESS EXERCISE 12/4/8S O INTEGRATED LEAK RATE TEST 1/1/86 O MAJOR MILESTONES REMAINING TO FUEL LOAD O INTEGRATED ECCS/ LOSS OF OFFSITE POWER TEST 2/86 O FUEL LOAD LATE 2/86 - LATE 3/86 h
- = .
QUALITY ASSURANCE REVIEWS AND ISSUES O INDEPENDENT DESIGN REVIEW (IDR) 4 G BECHTEL IDR REPORT ISSUED IN JANUARY 1985 0 CONCLUDED CPS DESIGN IS ADEQUATE & MEETS APPLICABLE NRC RULES AND REGULATIONS O SEVERAL " OBSERVATION REPORTS" REVIEWED BY STAFF IN SSER +5
. O SEPARATE BECHTEL REPORT ISSUED ON HIGHnAEDIUM ENERGY .
LINE BREAK ANALYSIS - ALSO CONCLUDES DESIGN ADEQUATE O NO IDR ISSUES EXPECTED TO IMPACT FUEL LOAD
@ NRC CONSTRUCTION APPRAISAL TEAM (CAT) l
@ CONDUCTED IN MAY - JUNE 1985 l
9 CONCLUDED CPS CONSTRUCTION HARDWARE & DOCUMENTATION l
, GENERALLY ADEQUATE .
l l 9 INDICATED IPI OVERINSPECTION PROGRAM ADDED EFFECTIVE MEASURE OF QUALITY OF PLANT O SIX NOTICES OF VIOLATION WERE ISSUED -IP HAS RESPONDED TO ALL IN LETTERS TO STAFF '
O NO CAT ISSUES EXPECTED TO IMPACT FUEL LOAD e We e
- - - , -, _ -. .-- - - - - - - .- . . ~ , , .
QUAllTY ASSURANCE REVIEWS AMD 3SSUES (continued) o OVERINSPECTIO?) AND RECORD VERIFICATION PROGRAAIS O
IMPLEMENTED IN RESPONSE TO 1981-1982 STOP WORK ORDERS O IP SUSMITTED REQUEST TO TERMINATE RECORDS VERIFICATION PROGRAM IN NOVEMBER 1935 BASED ON RESULTS THAT ESTASLISHED HIGH CONFIDENCE IN QUALITY OF CONSTRUCTION RECORDS O OVERINSPECTION PROGRAM ELE.'.lENTS COMPLETED (NRC APPROVED)
- PIPING & MECHANICAL SUPPORTS
- ELECTRICAL HANGERS l - HVAC DUCT & DUCT SUPPORTS *
- CABLE TRAY, CONDUlT, CABLE, & CABLE TERMINATION
+
0 ALLEGATIONS O THREE SYSTEMS IN USE
- SAFETEAM"
- QUALITY " HOT LINE"
- - QUALITY CONCERN PROGRAM O 51 ALLEGATIONS REFERRED TO IP (AS OF JANUARY 6,1986)
-
- iP ACTIONS COMPLETED = 5j
+ AWAITING NRC REVIEW = 48
- + CLOSED BY NRC STAFF : J O NO ALLEGATIONS EXPECTED TO IMPACT FUEL LOAD l . - - _ .-
ENIERGEBICY PLABl?llF]G A?]D PREPARED?lESS ISSUES O ON-SITE PLANNING ISSUES WERE RESOLVED IN SSER 94 3 FEMA HAS APPROVED CPS EhlERGENCY PLANNING ZONE O CPS ANNEX TO ILLINOIS STATE RADIOLOGICAL ENERGENCY PLAN HAS BEEN PREPARED AND SUSMITTED TO FEMA a NRC FOR REVIEW G NRR/ Rill EMERGENCY PREPAREDNESS IMPLENENTATION AUDIT CONDUCTED NOVEMBER 12-21,1985 0 57 OPEN ITEMS BEING TRACKED FOR RESOLUTION -
ALL IP ACTIONS WILL BE COMPLETED IN FEBRUARY 1988 o CPS FULL- SCALE INTEGRATED EMERGENCY EXERCISE
~
HELD ON DECEMBER 4,1985
, O EXERCISE SUCCESSFULLY PASSED O OPEN ITEMS TRACKING FOR CLOSURE IN ABOVE 57 o EMERGENCY RESPONSE FACILITIES APPRAISAL AUDIT (FOR NUREG- 0737) TO BE PERFORMED PRIOR TO 5% POWER t
~
REQUESTS FOR EXEMPTIONS FROM 10'CFR50 REQUIREMENTS O TWO REQUESTS L1ADE IM IP LETTER DATED DECEh1BER 9,1935 0 BOTH RELATE TO 10CFR 50, APPENDIX J MAIN STEAhl ISOLATION VALVES (MSlVs) LEAXAGE TESTING O PARAGRAPH lil.C.3 - REQUIRES TH AT MEASURED LEAXAGE BE INCLUDED IN COMBINED LEAX RATE FOR LOCAL LEAX RATE TESTS O CPS SSER +2 - APPROVES CPS EXEMPTION O MSIV LEAXAGE HARDPIPED TO STANDBY GAS TREATMENT SYSTEM O RADIOLOGICAL ANALYSIS IN FSAR CHPT. + 15 INCLUDES THIS SOURCE TERM - RESULTS ACCEPTABLE O MSIVs PERIODICALLY LEAK RATE TESTED BY TECH. SPECS.
TO ENSUR,E ANALYSIS RESULTS REMAIN ACCEPTABLE O CONTAINMENT AIR LOCK LEAXAGE TESTING O PARAGRAPH lli.D.2(b)(ii) - REQUIRES TESTING AFTER AIR LOCXS OPEN DURING PERIODS WHEN CONTAINMENT INTEGRITY IS NOT REQUIRED BY TECH. SPECS.
l @ WOULD PLACE UNDUE RESTRICTION ON ACCESS DURING PLANT OPERATIONAL MODE +4 - NEEDED TO ENSURE SURVEILLANCE REQUIREMENTS COMPLETED 0 WOULD CAUSE UNDUE HARDSHIP - TESTING REQUIRES INSTALLATION OF "STRONGBACKS" (STRUCTURAL BRACING )
ON INNER DOOR O ALTERNAllVE TESTING OF SEALS OF INNER a OUTER DOORS AFTER SUCH TIMES BY PRESSURIZlNG AREA BETWEEN SEALS 4
- , - ,-- ,a-,, , , , - - . . . , , - , - . - - , , - - - - -
. POWER ASCENSION PROGRAhl '
4 ACCELERATION (PAPA)
O PRESENTATION GIVEN TO NRR & Bill REPRESENTATIVES ON DECEMBER 16,1985 i
0 SIMPLIFY & REDUCE STARTUP PHASE TESTING O FOUR BASIC CATEGORIES
- 1. REPLACE STARTUP TEST WITH TECHNICAL SPECIFICATION SURVEILLANCE THAT IS DONE ,
- 2. DELETION OF NON-ESSENTIAL EQUIPMENT TESTING
- 3. TEST SIMPLIFICATION - TIME SAVING METHODS
- 4. REPLACEMENT OF TEST!NG WITH DATA FROM OTHER TESTS O NET BENEFIT " DAYS SAVED" ON STARTUP PROGRAM O REQUIREMENTS OF REG. GUIDE 1.68 ARE STILL FULLY MET l -
l O NRC REVIEW WILL BE PERFORMED VIA SSER ROUTE S IP HAS IDENTIFIED TEST PACKAGE REVIEW PRIORITIES O ALL CPS SUBMITTALS DUE JAN. 24,1986
SUSElARY AND CONCLUSIONS O iP MANAGESlENT ATTENTION TO FUEL LOAD AND SUBSEQUENT MILESTONES IS AGGRESSIVE AND ENCOMPASSES ALL " THINGS" O SER ISSUES (" CLIP") REMAINING ARE FEW AND MANAGEAELE O APPROACH TO SYSTEMS REQUIRED FOR FUEL LOAD CONSISTENT WITH REGULATORY REVIE'N CRITERIA AND PL' ANT TECH. SPEC.NEEDS O SYSTEM DEFERRALS ARE PRIMARlLY RELATED TO PRE-OP TESTING O FUEL LOAD PROJECTED FOR 2/86 - 3/86
.M*.
.o , ,
U- 600405 L30 86(ci-10)-t 1A.120
/LLINDIS POWER COA 1PANY cow. rc..e swa wo e:x ca :uco, *wt.os m:7 Docket Nc. 5C 661 Jarcary 10, 1996
'. N . harold R. Denton, Directer Office of Euclear Reactor Regulation United States Uuclear Regulatory Cormission Washington, DC 20555
Subject:
Clinton Power Statier Readiness to Load Fuel
Dear Mr. Denton:
Illinois Pouer Company (IP) is submitting this letter to provide you with a current status of the design, censtruction, and pre-operational testing of the Clinton Power Station (CPS) in accordance with the CPS Final Safety Analysis Report (FSAR) and NRC regulations. IP anticipates that fuel loading will occur between late February and late March 1956. This letter describes the current status as revised frem the status in our December 9, 1985, letter on this subject. The status of each major activity needed to support fuel load is de. scribed below.
A. Construction ' -
As of December 31, 1985, construction of CPS is estimated to be over 997. complete based on commodities.
All systems have been turned over from' construction to Illinois Power for testing. Eased on the substantial construction completion of CPS, the percent ccmplete figure will no longer be referenced in subsequent revisions to this letter. As of this date, all proj ect milestones scheduled through December, 1985, have been achieved. The Integrated Leak Rate Test was completed on January 2, 1986. The only major project milestone remaining prior to fuel load is the Intecrated Emergency Core Cooling System / Loss of Offsite Power Test, scheduled for February, 1986.
B. Precueratienr1 Testinz IP project management has identified those systems which will be reauired to succort fuel load. The sustem recuirements for fuel' load are consistent with current NpC review criteria and support the conditions of oceration defined bv the CPS Technical Scecificatiens. Curreb.t clanning and scheduline does project that some system test deferrals beyond fuel load will be recuired. A tentative list of these system test deferral items is provided in Attachment 1
& 2. The ne::: revision to this letter will provide detailed justifications for each deferral item.
U-600405 L30 - 86 ( 01- 10 )-t 1A.120 C. Persennel The NRC Staff's Sucplemental Safety Evaluation Recort '
(draft SSEF. f5), Sectict 13.1.1, fcund the organization fer management and technical suppcrt of the CPS staff during operation to be acceptable. The organizatien, staff levels, cualifications, and e:<perience of the CPS niant staff were likewise found to be acceptable in Section 13.1.2 of draft SSER 45. Any future organizational changes thct might materially affect these findings will be submitted to the Staff in a timely manner.
Draft SSER #5, Section 13.1.2.1(3) found that prospective Clinten Senior Reactor Operators (SR0s) uho complete IP's Supervisory Operating Plant Experience (SOPE) program will also satisfy the requirements of Generic Letter 84-16, and stated that the Staff uill conditicn the license to recuire SRCs on shift to meet Generic Letter 84-16 guidelines for het operating experience. As of January 7, 1986, there are 36 personnel licensed at CPS (27 SRos and 9 Ros). The current number of licensed SR0s and R0s is sufficient to support the shift complement levels set forth in the CPS Technical Specifications.
D. Nuclear Reactor Reculation (NRR) Licensina Issues IP has maintained active communications with NRR to, assure expeditious and satisfactory resolution of open licensing issues. As indicated in the NRC Staff's September 3, 1985, briefing to the NRC Commissioners, the NRC Staff does not expect any FSAR issues to impact fuel load. The major issues requiring continued management attention to assure timely closure are as followe:
(1) Hvdrocen Manacement (SER License Condition #5)
Pursuant to 10CFR50.44, IP has submitted a preliminary hydrogen analysis to the Staff. It is understood that Staff approval of this~ analysis is not required for fuel load, but must be received prior to authorication to exceed 5% pover. IP met with the Staff on November 6, 1985, to present an overview of the CPS preliminary hydrogen analysis.
As a result of this meeting the Staff acreed to address this issue in SSER #6 (prior to fuel l load).
i t
U-600405 L3 0 - 86 ( 01- 10 )-1.
lA.120 (2) Mark III Containment Issues (SER Outstanding Licensing Issue #9 and Confirmatory Licensing Issue #71)
This ite.m includes Suppression Feel hydrodynamic leads during a Loss of Ccolant Accident (LOCA) and during Safety Relief Valve (SRV) discharges, as well as Humphrey-related issues. Currently, IP anticipates ERC Staff c1csure of that portion related to SRV hydrodynamic loads in Supplement
- 5 to the Clinton SER. IP anticipates that the remaining issues will be resolved in SSER .6 1 to be issued prior to fuel load.
(3) Pump and Valve Operebility Review [PVCR]
(Portion of SER Outstanding Licensirg Issue # 7)
IP has developed plans and actions to close open items resulting from an NRC audit performed during Movenber 19-21, 1985. IP cormits to resolve all open items in a manner acceptable to the Staff prior to issuance of the Operating License (OL).
Only 2 items remain open: (1) a system walkdown on safety-related active pumps and valves and (2) an NRC concern using analysis versus test results
- for valves. ,
(4) Equipment Seismic and Environme'ntal Qpalification (SER Outstanding Licensing Issue #7)
Items related to electrical equipment environmental qualification are expected to be resolved in SSER #5. IP does not anticipate the need for any exemptions to 10CFR50.49. The CPS mechanical equipment environmental qualification progrca is still under review by the Staff. Open items from recent NRC Staff audits (July and August 1985) of these programs are being addressed and the remaining FSAR revisione will be submitted in FSAR Amendrent #36. Illinois Power vill have ccepleted its respense to all audit concerns by the end of February 1986. NRC Staff closure of these issues in SSER #6 is anticipated.
(5) Inservice Inspection (ISI) Program (SER Licensing Condition #12)
The final ISI Prograr is required to be submitted uitbin six cenths after fuel lead.
Illinois Pcwer enticipates that requirements related to the ISI Program will become a License Ccndition in the OL.
l 1
U- 600405 i L3 0 - 86 ( 01- 10)-L 1A.120 (6) Enfezuards and Security It is anticipated that these issues will be i
resolved in SSER 45. An NRC confirmaterv implementation audit is expected following security lock-down, which is scheduled for
! late Januarv 1986. Illincis Power dces not exoect ~
any impact 'f rem the resolution of these remaining items on issuance of the OL.
(7) Fire Protection IP's Safe Shutdown Analysis (SSA) and Fire Protection Evaluation Report (FPER) have been completed and submitted to the NRC Staff for review and closure of remaining licensing issues on this item. Responses to seven specific icsues noted by NRR have been subnitted by IP and are currentiv under Staff review. IP action to resolve "o pen items identified during the Septenber NRC pre-audit will be ccepleted in February 1986.
All essential hardware installation is expected to be completed prior to fuel load. A final NRC 1 audit is expected after completion of fire protection systems.
(8) Technical Specifications .
7 -
- All CPS Tec'hnical Specifications have
! received substantial internal review and the 3 applicable Grand Gulf Nuclear Station experience has been incorp' orated at CPS.
. The NRC Staff issued the Proof and Review" copy of the CPS Technical Specifications in a September 4, 1985, letter to IP. Technical Specification conformance reviews will be completed and all necessary certifications will be provided to the Staff by the end of February, 1936.
(0) Implementation of TMI Requirements (NUREG-0737) -
1 IP has participated in the Boiling Water Reactor Owner's Group (BWROG) in connection with TMI issues. Currently, nearly all TMI Action Plan Items have been technically resolved with the Staff. Also, most hardwar'e modifications required of NUREG-0737 have been installed or will be I installed prior to fuel loading at CPS. The
, remaininc actions are scheduled for imolementation ~
! as folloss:
i
$ - - - - -_.,,,.-___ _ ,,_, w. ,.. . , _ , , , , ..,,,, . _ , , _ _ , , , . , _ , _ , - ,_ , , . , __ ,__ _ , _ _ _ _ _ _ _ _ _ _ _ , _ _
U- 600405 L30 86(ol-10)-t 1A.120
- 1. NUREG-0737, Supplement #1 " Requirements for Energency Response Cacability". See NRR Item (10) for discussion of this program (various actiens remain for ccepletion after fuel Iced);
- 2. I.G.1 " Training During Low Power Testint" -
the program will be performed after fuel load;
- 3. II.F.1 " Additional Post-Accident Instrumentation" - specific variances to these requirements have been requested in IP letters dated December 3 and 26, 1985.
- 4. III.D.l.1 " Primary C.colant Outside Containment" (leakage control program) - the program will be performed after fuel load.
(10) NUREG-0737, Supplement #1 " Requirements for Emercency Resconse Cacabilitv" These requirements were finalized by the Staff in Generic Letter 82-22. IP's response was submitted to the Staff in an Aoril 1983 letter which
^
provided the CPS Emergency Response Capability Implementation Program (ERCIP) Plan. ,
Implementation of these NRC requirements at CPS is '
nearing completien as follows: ,
(a) Safety Parameter Disolav System (SPDS)
The SPDS Dvnamic Simulation Test was conducted in August 1985, and a detailed results and analysis report was submitted in September. Based upon this report, the Staff has indicated that this issue will be closed in SSER #5. Results of additional testing of the analog optical isolators were also submitted in September 1985. Startup testing of the SPDS is scheduled for completien in Februarv 1986 and the IP Verification and Validation program shculd be completed by late February. Therefore, the SPDS will be operable prior to fuel load, based on current planning and scheduling activities.
(b) Detailed Centrol Rocn Desien Revieu (DCRDR)
The DCRDR was performed by IP personnel assisted by human factors consultants from Tcrrey Pines Technology. Inc. This review is ccmolete and an IF DCRDR Surmarv Re: ort has been reviewed bv the NRC Staff.' The Staff also ccmpleted 'ar. audit of the DCRDR program and results on Eovember 1, les5, I U-600405 L30 86(01-10)<-L 1A.120
- Category A Human Engineering Discrepancies (HEDs) will be implemented prior to fuel load. Catecorv 3 HEDs shall be imolenented within 180 'dcy's after fuel load. Category C REDS shall be completed before startup folicwing the first refueling outage. As a result or the NRC audit, several open items were identified by the Staff which require 4
further reviews by IP to resolve. A suppleuent to the DCRDR Sumscry Report shall
- be s'ubmitted to the Staff within six (6) months after fuel load. This Supplement will l '
address the NRC audit open itens and the Control Room environmental survey.
The Staff has indicated this issue will be resolved in SSER #5 and a License Condition will be imposed relative to the open audit i items.
1 (c) Emergency Resoonse Facilities (ERFs)
All ERFs were ccmoleted and operational, with complete, in suppcrt of personneltraining85,IntegratedEmergency the December 4, 1.
Exercise. The ERFs' appraisal will be i performed by the Staff after fuel load. A date for performing this appraisal has been o . scheduled for May 15, 1986.
(d) Upgrading Emergency Operating Procedures (EOPs) 4 This item relates to Confirmatory Licensing Issue #41, which has been reviewed and closed by the Staff in draft SSER #5. All required j EOPs have been upgraded to symptomatic-based procedures. Emergency Procedure Guidelines (EPGs) for hydrogen control (under development by the Hydrogen Control Owner's i
Group in which IP participates) and scme Staft, generic concerns associated with
- post-accident containment venting for decay i
heat removal will be imolemented after fuel
^
. load. (This is considered. acceptable since
- the generic issues related to these items are still under industry-wide resolution.)
' Specifically, in an IP letter dated November 4, 1985, IP committed to provide an operating instruction for hydrogen control prior to exceeding 5% power (pending final NRC approval of the generic hydrogen control EPG).
l i
l 2 . ,
U-600405 L3 0 - 86 ( 01- 10 )-L 1A.120 (e) Pcst-Accident Mcnitoring Inctrumentaticn Recuirements of Regulatory Guide (RG)l.97, Rev. 3 IP has satisfactorily resclved (draft SSER J5) all Staff technical concerns relative to R.G. 1.97. In a letter, dated December 3, 1985, IP requested a variance to the R.G.
1.97 recuirements related to sample line loss correction factors. This matter'is currently under NRC Staff review. Ecuionent
^
inctallation and field verification is scheduled for completion in early February 1986. As of January 3, 1986, equipment installation and verification is over 99.5%
complete. Equipment upgrading for the Reactor Vessel Fuel Zone water level instruments and the Neutren Monitoring System will be ccmoleted prior to restart following the first refueling outage.
(11) Financial Protection The NRC requires proof of financial protection in terms of $160,000,000 of insurance to be complete prior to CPS fuel load. An amendment to the Special Nuclear Materials (SNM) Indemnity Agreement (between NRC and Illinois, Power, ,
Soyland, and Western Illinois Power Cooperative) will be executed in connection with the OL. This indemnity agreement shall be signed by the CPS owners shortly after receipt of the OL. The CPS owners shall have and maintain financial protection of the type and amounts required by the Commission in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
E. Emernency Planning And Precaredness On-site Emergency Plan i: sues were resolved by the Staff in SSER #4. With respect to off-site issues, several important milestones have been reached. The Federal Emergency Management Agency (FEMA) has approved the CPS Emergency Planning Zone (EPZ). The State of Illinois Radiological Emergency Plan and CPS Annex have been prepared and submitted to FEMA and to the MRC Staff. Illinois Power has completed the FEMA-43 Report reFarding the Alert & Notification System (ANS). The NRR/RIII Emergency Preparedness Implementation Appraisal (EPIA) was performed during November 12-21, 19E5. IP resocnses to all coen items from this appraisal will be submitted by Februarv, 1986.
r f
U +00405 L30-86(01-10)-L lA.120 IP anticipates that the NRC Staff will require a License Condition to ecmolete the Emergency Response Facilities Appraisal, required by NUREG-0757, Supplement #1, after fuel load (see E.(10)(c) above).
IP does not anticipate resolution of the remaining audit open items will impact fuel load.
F. Atemic Saferv Licensing Ecard (ASLB) Proceedines On January 28, 1985, the parties to the CPS ASLB proceedings entered into a Joint Stipulation that reauested and led to dismissal of the preceedings. As incicated in the Stipulation, certain issues relating to Centention III remained for NRC Staff review and resolution. At present, the Staff has documented its review and resolution of CPS Regulatory Guide (R.G.)
1.97 compliance (draft SSER #5 Section, Section 7.5.3),
and the CPS Reactor Vessel Water Level Measurement System and plant improvements therein (SSER #4, Section 4.4.2). The Staff intencs to document its review and resolution of equipment identification under R.G. 1.97, SPDS color coding, color consistency between SPDS and Area Radiation and Process Radiation Monitoring (ARM /PRM) displays, and inclusion of ARM /PRM parameter (s) on the SPDS display in SSER #5. The Staff intends to document its review and resolution of test results for isolators installed to isolate computer signals from safety-related signals in SSER 06.
G. Exemotions The FSAR documents CPS conformance to the NRC rules and regulaticns set forth in 10CFR50 including Appendix A (General Design Criteria). At present, the only request for exemption from NRC rules and regulations pertains to Appendix J leak testing requirements submitted by IP in a letter dated December 9, 1985.
These exemptions relate to the Main Steam Isolation Valves and the Containment Air Lock.
l H. Desien and Construction Assurance Reviews CPS has undergone a series of reviews beyond the normal Quality Assurance Program to assure that CPS design and construction conforms to applicable requirements. The current status of each of the major reviews is as follows:
(1) Indenendent Desien Revieu (IDR) l To provide additional assurance of the design adequacy of CPS design, IP contracted with 3echtel Power Corporation to perform an IDR.
This review was ccmoleted with the issuanci of the 3echtel IDR Report in January 1985.
U-600405 L30-86(01-10)-L 1A.120 Bechtel concluded frcm this independent assessment that the CPS desien basis is
~
generally adequate and meets the applicable NRC rules and regulations. Several
" observation reports" were issued following IDR completion. Most of the required actionc from these cbservation reports are currently resolved with the Staff as identified in draft SSFP #5. All items currently remaining open will be resolved with the Staff. Bechtel has issued a separate report en the high energy /
moderate energy line break analyses, which concludes that the design of CPS is adecucce for these considerations. This supplemental report was submitted to the NRC via IP Letter U-600266, dated September 30, 1985. The NBC Staff's September 3, 19P5, briefine tc the Commissioners indicated that ncne of the IDR issues are expected to impact CPS fuel loading.
(2) NRC Construction Anoraisal Team (CAT) Review The NRC CAT team appraised CPS construction The activities on May 20-31 and June 10-21, 1985.
CAT concluded that hardware and documentation for CPS construction activities were generally in o accordance with NRC requirements and Illinois
, Power program commitments. In addition, the Team
, indicated that the IP Overinspection Program has provided an effective added measure of the quality of plant construction. In the CAT Report provided 1 in the Staff's letter dated August 15, 1985, deficiencies requiring additional Illinois Power management attention were identified.
Subsequently, Region III issued, by letter dated August 30, 1985, six Notices of Violation. IP is continuing to implement corrective actions for these items, as identified in its response to Region III's August 30, 1985, letter (IP Letter U-600282, dated October 1, 1985). As indicated in the Staff's September 3, 1985, briefing to the Commissioners, none of these items are expected to impact fuel load.
(3) Overinscection and Record Verification Procrams In response to the 1981-1982 Secp Work Acticns, IP implemented an Overinspecticn Program to provide additional assurance of CPS construction quality and a Record Verification Program te orovide additional assurance of CPS ionstru"cticn cuality records. SRC Regicn III's letter da'ted July 2, 1985, concurred with IP's request to terminate the Overinspection (OI) Program for
_9
U-600405 L30- 96(01-10)-t lA.120 piping and mechanical supports, finding that NRC insoections and independent reviews give reascnable assurance that CPS piping and suppcrts will perform satisfactorily in service. HRC Region III'c letter dated Septenber 13, 1985, concurred with IP's proposal to suspend, at its cwn risk, the OI program for electrical hangers, F.VAC duct and duct supports, cable tray, cenduit, cable, and cable termination, bcsed upon favorable results of the IP Overinspection Program and NRC inspections to date. On October 14, 1985 (IP Letter U-t00295), IP submitted additional information in four categories specified in NEC Region III's letter as necessary to support NRC concurrence in termination of the 01 Program for those commodities. IP intends to conclude the Overinspection Progret for radwaste (Aug D), fire protection, structural steel, mechanical /
electrical equipment, instrumentation, and instrument piping and to make the results
- available for NRC review prior to fuel load. On November 15, 1985, IP submitted a request to terminate review for the majority of record categories within the scope of the Record Verification Program based upon results to date that have established high confidence in the
, quality,of CPS construction records.
I. NRC I&E Items IP maintains formal systems for tracking and resolution of all NRC I&E inspection items, 10CFR50.55(e) items,
. and 10CFR Part 21 items. As of January 7, 1966, the status of these items is summarized as follows:
, NRC 50.55(e) Part 21 Inspecticn Pending NRC Action for Closure 17 19 102 Require IP Action for Closure 11 14 185 Total open Items 28 33 287
, IP has undertaken an intensive review to establish l schedules, acticn plans, and priorities fcr achievinc closure cf all itemc necessary to support ' fuel load. IP personnel have met with Mr.'T. P. Gwvnn, the C?5 NRC Resident Insoector, to establish initial priorities for closure of these 1:emr.
U-600405 L3 0 - 86 ( 01- 10)-L 1A.120 IP actions will be prioritized for coupletion of all items necessary for fuel load in sufficient tire to support t timely NRC review.
J. A11ccaticns IP maintains three formal systems on site to acdress ceployee concerns. None of these systers cre licensing recuirements and IP does not rely upon or take credit for these systems in seeking the CPS operating license. I? will review all safety-related concerns and will take actions to assure that any concerns that are still oper at the time of fec1' load will not challenge the safe operation of the Clinten Power Station. NRC Regicn III has referred fifty-one allegations to IP for investigation. Of these, IP has completed investigations on all fiftv-one, three have been closed by the NRC and ferty-aight await NRC revieu and/or closure.
If you have any ouestions or comments concerning the above information please centact me or Frank Spangenberg of my staff.
We will be prepared to discuss the above itens with you at your convenience.
Sincero- -
yours,
,/
(
Ch i /0 D .I Vice President TLR/kcf Attachments cc: Director, Office of Inspection and Enforcecent, USNRC R. M. Bernaro, Director BWR COL Dr. W. R. Butler, BWR Project Directorate f4 B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Begional Administrater, Regien III, USNRC Illinois Department of Nuclear Safety
Attachment No. I to U- 600405
~
PUEL LOAD - NUMBER IF STARTUP TESTING - 20 SYSTZ>iS System Projected Lesiencter Pescriution Ccenletier Milestene l
CM Containment Meritoring Initial Criticality EH Stear Bypass heacup (HU)
EW Electrical Welding Comm. Ops.
HG Cent. Combustible Gas Heatup HI Hydrogen Ignition System 5% Power HT Heat Tracing 5% Pcwer IS MSIV Leakage Control Initial Criticality OG Offgas RPV Headset (EU)
RA Respirator Air Initial Criticality RI P.CIC System Heatup SH Station Heating Ccmm. Ops.
ST Sewage Treatment Cott. Ops.
TD TG Misc. Vents 6 Drains 5% Pouer TP Transversing In-Core Probe 5% Power VA Aux. Bldg. HVAC 5% Pcwer VG Offgas HVAC RPV Headset (HU)
VP Drywell Cooling Heatup UA Warehouse Auxiliaries Comm. Oos.
FC Chilled Water Initial' Criticality WX Solid Radwaste Processing Heatup
$* 4 e
t
\
Attachment No. 2 to U-600405 FUEL LOAD - MUMBER FUNCTICNAL - 32 SYSTZMS (Not Lemonstrated Fully Operable)
Systen Projected Desiccater Descrirtion Ccm:1.etion Milestone AB ECA3 Comm. Ops AS Auxiliary Steam Heatup CA Condenser Vacuum Heatuu CS Feedwater Centrol 5% Peker CW Circulating Water Heatup DA Digital Accuisition 5% Power DL Laundry Equipment Ccmm. Ops.
DV Feeduater Heaters Heatup ES Extraction Steam 5% Power GC Gen. Stator Cccling ST. Pcwer
- GD Cathodic Protecticn 5% Pcwer GS Turbine Gland Seal 5% Power HD FW Heater Drains Heacup HY Hydrogen Cooling 5% Power LM Loose Parts Monit. 57. Power LV Low Voltage Aux. Power 5% Power MP Main Power 5% Powe-OT Turbine 011 Transfer 5% Power 1
RN Recirculation Control Heatup SE Spare Breakers . Comm. Ops.
SO Gen. H Seal Oil , 5% Power ~
. SW Screendash. , Heanup TE Varicus Bldg. Drains Heatup TF Various Eldg. Drains Heatup TG TG Aux, & Misc. Devic'es 5% Power TS Turbine Supervisory 5% Power VH Screenhouse & MWPH HVAC 5% Power VJ Machine Shop HVAC 5% Pcwer VS Service Eldg. HVAC Comm. Ops.
VV EOF Bldg. HVAC 5% Power WD MWPH Potable Water Comm. Ops.
1
i C,oMSTRLlCTI Okt WOR.K
', OVER 997o COMPLETE
'SASED 00 COMMop/ TIES.
51bTEM TURNOVER V TO START 4P a c.MECKouT y I/J T/AL STARTvP oesnAT,ox; c<ero>
TEST 1/JG ACCEFTAtJOE (.ATPh PRE-OFERATionAL (PTP)
AUp 5f'Ec/4L TEST /MG system (XTP).
FuMcTiOAJAL m
' SYSTEM PHASE E RELEA65
't
' TECMNICA L spec. N PLAdr $URJEILLANC66.
TLAur STAFF <
PREVEAITATIVE M/473, 4 SYSTEM LINEUPS NOW < COMPLETE PupcMLtsT REMAIN /N6 ITEM S.
v -
SYSTEM 'PECLAREP FutLY &ET>ABLE I
e J
o
. - - - - - - - - - - - - .w - __ _ _ _ - _ . _ _ _,_ . - _ _ _ __
CPS SYSTEM STA111S REPORT DATE: .f am.ary 3, lh RE(Af1RFh FOR FUEL LOAD PACE: 1 SYS'IMt BASIS FOR ltASE II SYSTFN S/tl TEST REl.EASFD OPERABILITY DEF13RAI. CatutFJrib DESIGr:ATOR REf?!!!!!EENT (IsESCR II' TION) (YES/NO) (YES/NG) (YES/r;O)
IFROJT. DATE] IPRO.17. DATEl IPRO.IT. DATEI j i
AC/t'41 Required by Tech. Specs. YES YES N0 fleeded to Make W eer for .
Otmdensate Polisher.4 I (Acid PandilDr.) [
i ADS Required prior to lleatup by NRC YES NO fn None.
! (Aut<matic regulation (CDC #35). 11/17/86} ,
i Depressurizattim /
System) 4 AE Required by Tech. Specs. YES h0 fK1 Two ind. pendent simrces of l
(Erwrgency [1/24/86] Aux. Power Required.
o P -se rve Auxiliary Transformer)
Ah Recuired by Tech. Specs. YES YES !!O Provides Essential Operator (Anneme la tar) Info. [
AP Required by Tech. Specs. YES NO t:0 Required to Provide Offsite (Auxi1iary [1/31/861 Power.
Pise r)
All creponents required prior NO NO NO Monitors locally interloclied AR/PH ,
l (Anca/ Process to initial criticality by NRC [2/26/86) [3/17/86] with cont rol eqtaipment and Radiation regulation (CDC #64). 4. l a rms .
Monitors)
AX Required 1.y Terh. Specs. YES N0 f30 Component of AP. Entire (4.16K VAC) [1/31/861 Capability Requined.
AY Required by Tech. Specs. YES NO NO Comp <mert of AP. Futire (6.9K VAC) (1/31/tsbl Capa.bility Required.
e t
l
_ _ _ _ _ . _ _ __ __ _ _ _ _ __ ._. _ _ _ _ ___ _ _ . . _ _ __ _. _ ~_
o CPS SYSTDI STAT 1!S REPORT DATE: .lanuarv 3, 1986 RFgilRED FOR MIEL 11)AD PA('E :2 -
i SYSTDt BASIS R
- PilASE II SYSTEM S/lf TEST l'LSICNATOR RFtK!IRtWENT RELEASED OPERABII.ITY DEFERRAL Cr e EffrS (14St3tlPTION) (YES/NO) (YES/NO) (YES/f;0)
IPR (UT DATEl (PRO.lT. DATEI (PRtifT. DATEl A7 Required by Tech. Specs. YES NO !;n Provides Control Power.
(i.ro VAC) (1/06/86)
CH Required by Tech. Specs. YES YES to Pinnps not required. CD purr.ps i (Condensate used to fill vessel. Ar.y I40 ster) ore of three fl w paths required.
CC Required by Tech. Specs. YFS YES NO Required to Rcrove Equipinent (Component Ilea t . System Nestly Ready.
] ,
Cooling Wter) .
CD Required by Tech. Specs. YES ho f;0 Need Any One Pump and F1 w (Condensate) (1/04/86) Path. System Hearly Ready.
C1. Required by Tech. Specs. YES YES N/A Req. to Eliminate lifological (Chlorination) Contamination in Fluid Syctems.
CO Required by Tech. Specs. NO NO NO Req. to Protect Diesel (Carbon [2/15/86] [2/21/861 Cenerators. Pa r t o f "Fl"'
bloxide) System.
i CP Required by* lech. Specs. YES NO NO At least one Polisher f.
(Corutensate [1/17/86] Regenerator Req. to provide Polin.hing) clean water to Reactor.
l CQ Required by Tech. Specs. NO NO YES Fanergency Cmms. Needed -
(Conaunicattuns) [3/21/86] [3/27/86) ITnitial Crit.] Caltronics, Radios, Fuel Pridge. All components prior t to initial criticality.
! i 1 . i i
1 i
~
CPS SYSTTH STATUS REPCW DA1E: 2.muary 3,19tt6 I:1XtilRED FOR WFL IAAD PACEt 1 SYS1Di BASIS H1R PilASE II SYSTDI S/11 TEST ICSIGNA1 W P.FQtliRDtFNT 1:ELEASED OPERABILITY LElERRAL Cd NFNTS (DEScwitneO (YES/tiO) (YES/NO) (YES/NO)
IPldUT. DATEl itinTT. DATE] IPRO.IT. DATE]
CX IP crnmitment to SPDS completicn to to YES t!eed portion:s f or SPDS (19ts Computer) prior to FL. Cupplete all (3/12/86] [3/26/66] IInit. Crit.) signals and displ,eys prior:
components prior to initial AT-004 to FL. Ren,ainder is NSbS/!OP criticality. AT-OO6 Calculations. f4SSS Performance Cales.
ATP-CX-02 Scheduled before F1.. STP-13A-0, Process Cmputer, scheduled 2 days after FL. Also, Process Craputer, $1T-13A-Il needed for heatup.
CY Required by Tech. Specs. YES 10 FC Need Path (and Tcol.) to RW (Cycled Completion of all components prior (12/26/851 Seals & Condens. system.
Condensatc1 to !!catup.
CZ See "CX". NO NO NO See Cmment s on "CX" Above.
(ICS Cieputer) (3/12/86) (3/18/86)
DC Required by Tech. Specs. PO to 10 Provides Instr. & Control (ItC Parer (3/05/86) [3/18/86) Power.
Distribution)
IC/DO Required by Tech. Spees. In NO IM All Threc !!equired, micset 12/18/861 12/26/661 Cenerators)
Tel Required for systems operation. YES YES f0 Need t4Til & SX Room Drains (Sc reentame & Dierel Fire Punip Drains,
& FLT11 Drains) t t
4 CPS SYSTEH STAT 1rs REPORT DATE: t<nuary 3, 196"a
) RErA11kED FOX FitEL IDAD PACE: 1 .
SYSTut EASIS Fldt M1ASE 11 SYS1Til S/tl TEST
- IWSIcuTor RuffIRI2 TENT R!' LEASED OPERJBILITY DEFERRAL 01MtillTS j (bFSCRllilON) (YES/NO) (YES/NO) (YES/NO) d lPROLIT. DATEI IPROJT. DATEI IPRO.lT. DATEI i tieed tiet. Towcr (Incl . %sa, IH Required by Tech. Specs. PU to tU j (Envi r.ms [1/17/861 (1/29/861 w/ Control Roen) & Seismic j
tkmi toring) Honitoring.
I iC Required to run integrated YES NO YES Final testing to be dime j
(FucI Pool tests. 11/07/861 15t Powerl after relocattro of fuel.
I CooIing & PT-014 Cleanup) nt Required by Tech. Specs. NO to to None.
(Fuel ILenitting) 13/21/86] 14/02/861 J
, FP/tR Brquired by Tech. Specs. and NRC !O FO ho Based on Reg'd Arc.m L (l'i re regulation (IP ccomitment to (3/21/86] [4/26/861 Licensing Cormitments.
Protectfon) 10CFR50, App. R).
tv Required by Ta h. Specs. Canplete !D f4 NO tieed path to inject water (Feedw.s t e r) all cooponents prior to licatup. 12/25/861 (3/06/861 to vessel. Ptsaps not req'd.
since "CD" used f or 17..
4 l !!C Complete all requirements prior NO NO 20 (for Ch. 14) Only Containment Polar
(!!.iist s, Cranes to use of caeponents. (TBD] (1/21/861 N/A (nf r.c.) Crane required for fteel i Inad.
Elevators)
ILP Required by Tech. Specs, and YES 10 FC Part of LCCS 1:equireets.
(1115. 1 Pressure regulation (CDC #35). 11/30/86)
IA/SA Required ley Tech. Specs. !D - NO !D None.
l (Inst / Service [2/28/861 (3/10/861 1 Air) e i
-0 I
CPS SYS1tM STATi!S RFPORT DATE: .lanetary 1, 1486
- ' kF(ttIRED Rik FilEL tdAD PACE: 1
. i
- t SYSTDI EASIS FOR PilASE 11 _ SiSTEM S/U TEST otsic' ATOM RFUllRDIEPG . K LEASED [ $ OPERABIL11Y tt FIIR AL QWta tni k IDEF/21 Prion) ys .
s.' OTS/t:0) (YES/NO) , (YES/flo)
=
lPROJT. DATE IPROJT. D!rEl (PRRIT. DATEI
- , ~
IP Required I.y Tecl;. Specs. 70 to tu All Did stons. All P.wer.; *
(Ins:rueent {2/14/86] {3/02/861 ,,
s P.we r) , ,
to i ID C6mpaetjfc of all c mpenents 10 NO YES Portion (e.g. St.utdown ,
(frak IRtection) requirW 7r 4r to Initial [3/13/86) (4/10/861 linit. Crit.] Cooling Isolation). NRC Criticality per NRC re;;ula'; ion. -
IT-010 extaption rer;utred (CDC #30
~'
l 4.nd 454). Test f ng ext-sption v vill not li.'volve isolation.
1.1. Cmpletion of all componeets for to 770 fu All Emerr.cncy I.ighr the,,
(I.t cht ing) Comercial Operations. I3/12/S61 l3/20/86) IJ.-1, 2, 3 t hase 11 re:t eases
- complete.
LP Reig:f red per Tech. St +cs. and YES 70, No ,
Part of ECCS Rignirewnt.
(Low P escure NRC regulations (CDC #35). [1/22/86]
Core Spray) -
PC Required per Tech. Specs. YES ,
M NO Needed to provide water to t
(Hakeup [12/30/85) C'! as Required, Cendensate) t2 Caplete all requirment prior YES (TBD) N/A tiltimate heat sink required.
(Hiscellaneous to use of components. ;
Equigaent)
MI Required by Tech. Specs. and NRC YES YES ?!/A Tesr!:rg and oper bflity recluirements ull! !>e fislillied in approprinte (Miscellancoins regulation, Int e rlock:.) cafety-related syst ems.
MS Required by Tech. Specs. PD to NO Pnrtion required to ensure (H. sin Steam)
[3/13/86) [4/17/86) int,oord stops are closed to prevent draining of the vessel. ;
o .
CPS SYSTlH STATitS PITORT DATE: .fanu:3rv 3, 198t.
RE0l!TRED FOR WEl. IDAD PACE: 6 SYSTFJi BASIS tt)R P11ASE 11 SYSTDi S/U T13T DESIGNATOR RE(AfIREMEiff I!El.EASFD OltRAP,1LITY DEFERR AI. (U7ILtTTS (DFSCRIPTION) (YES/NO) ()ES/NO) (yrs /NO)
(PInfl. DATEI lit.0JT. DA1T) { PRO.IT. DATEI n!t Rettuired by Tech. Specs and tiO NO t;O Inclu.tes all RPS (fluc lea r NkC renulation. 11/31/86] 13/10/86] i n e. t ru:nen t s .
lioll e r )
NR Required by Tech. Specs, aied teRC NO NO to Meed SRMs, lits, APl:fis (Neutron regulations (CIC d20-29). [3/06/86] [4/02/86]
Ik.n t t or ing) r:S Required by Tech. Specs. and NRC to N0 IM Partial - Secondary Contain-(Nucle ar Steam regulation (C11C #55). Complete [1/17/86] l1/22/861 ment wntilation isolation; Supply Shutoff) all components prior to initial Poss itely more. t;KC criticality. exemption reqnf red on Primary containment.
IC Re utred by Tech. Specs. and NRC YES [TEDI tJ /A Need entire Cr.nt r ol Rooni.
(PCCC) re ilat ions (GIC #19).
PS Required IP Coc.mitment to NRC. to !JO 1:0 Rcquired by WREC-0737 per (Process [3/16/861 13/24/861 NRC. NRC cremption needed Sampling) for test deterral.
i:C Require <!ly Tech. Specs, and NRC t;0 tiO NO Control Rod Interlocks (Rod Control & regulations (CIC 420-29). [2/23/861 , [3/09/861 needed for reac t tvity Informatlon) c oi.t rol .
Im See anCa. to NO tlo See anCa.
(Control tod (3/16/861 l4 /04 /86]
Drive)
RE Required by Tech. Specs. YES NO t:0 Needed to control possible (Con t . , Anx . , & II /14/861 cont aminated wter spills.
Fuel Bldg.
Equip. Drains)
- . _ . . _ . _ _ ., . . . . . , _ _ . _ , - - . - ~ _ _ _ . _.- _ - - _ _ _ _ _ . . - m . - _.
CPS SYSTEM STATUS REPORT DATE: Jr.nua ry 3, l'>R6 RE0lllRED FOR FUEL LOAD PACEt 7 s
SYSTDi ILASIS FOR PHASE II SYSTEM S/11 TEST DES 1CNATOR REQUIREMENT RELEASED OPERABILITY DEFERRAL (Y M WI,rtS I
(DESCRIPT100) (YES/NO) (YES/NO) (YES/NO)
Il'ROJT. DLTEI lPROLIT. DA1EI lPROJT. DATEI itF Hequired by Tech. Specs. YES NO NO Heeded to control pot.sible. ,
(Ci.nt., Aux.,t. 11/15/86) contaminated water spills.'
fuel 111dg. Floor j '
" D ra i ns) -
Q 1 R!t Required by Tech. Specs. and NRC NO NO fl0 Part of ECCS ar.d Shutdown (Residual regulations (CDC # 34 and 15). [1/21/86] [2/02/861 Cck> ling, llent Remo0al)
RP Required by Teth. Specs, aqd NRC NO N0 l'O Provides interlocks & Info.
l (Reactor regulatten (CDC #20-29). [2/27/861 [4/04/86] to Control Room Operator.
Protectiei) ,
i i RR Required by Tech. Specs. Cwplete NO N0 fl0 Needed to circulate water in (Reactor all components prior to Hentup. [1/24/86] [1/28/R61 reactor (piping only).
Recirculation) 4 RS Required to support testing NO NO NO Needeel to support testing j (Rer.ote Shutdown) and per NRC regulation. [2/27/86) [3/13/86] required for Fool leart.
I (CDC #19).
a RT Required by Tech. Specs. NO NO N0 To maintain clean water in (Reactor Wter [2/24/861 [3/11/861 reactor.
Cleanup)
SC Required by Tech. Specs, and NRC YES NO NO To provide emergency source
,~
(Standby Liquid regulations (CDC #27). [1/17/86) of Negative I:e,.ctivity.
1 Cout rol)
SF Required by Tech. S i,ecs. YES NO NO Maintains clean ECCS water (Suppression Pool [1/21/86] source.
! Cleanup)
I i
1
~ _
CPS SYSTEM STAWS PEPf'] DATE: _ Jant ary 3, 1986 '
REQUIRED FOR FUEL IT .D PACE: 8 SYSTH1 BASIS FOR PliASE 11 SYSTEM S/lf TEST Df'. SIC?tA10R 1:EQllikDiENT REI. EASED OPERA 1111.lTY DEFERRAL OM &:NTS (DESCR il' TION) t'YES/NO) (YES/NO) (YES/NO)
(PROJT DATEl (PROJT. DATEl IPR'UT. DATEl SH Required by Tech. Specs. Complet e YES YES NO Need to ensure all valves (Supprer.nfon Pool prior to lleatup to fulfill FSAR closed. Don't need logic Hakeup) Ch.15 post accident vent coverage circuits, requirements.
SP Required by Tech. Specs. NO NO h0 Required to ensure RPS (HSPS Self Test) [3/03/861 [3/10/861 Functions.
SR Required by E-Plan and NRC YES NO N/A Needed for Oftsite Dose (Spectral regulat.fon (10CFR50.47 and [1/22/86] Cales, & Dostmetry Records.
Analysis & InCFR20).
kccords)
SS Pequired by NRC regulation YES NO NO None.
(Security) (10CFR73). [1/18/86]
J
- SV Required prim to lleatup per YES NO No Vessel will nnt 1,e heated or l (System 1
- elief regulations. See " ADS" also. [1/17/861 pressurized during FL.
Valve Hmit.)
SX Required by Tech. Specs. No to NO l'rovides cooling for DCs.
[3/06/861 (Shutdown [TBD)
Service Water) i SY Required by Tech. Specs, ard NRC YES YES N/A Provides one of two required (Swit cliyard) regulat!< ns (CDC #17) . ,
sources of Offsite Power.
TT Required by Tech. Specs. tc to NO N/A Needed to support t esting.
(Transient support testing. [1/24/86] l3/04/86]
i Test Syst em)
TW Required by Tech. Specs. YES YES N/A Needed to make makeup water.
(l' altered Wat er)
_ . - _ _ . _ _ _ _ m. _ .. . _ - ..___m. ~~. . . _ _ .- .. . s_ ._ _ _ . _ . . _ . _ _ _. _ .,_ _ _. .
CPS SYSTfM STATIfS RE10RT DATE: .Innuary 3,19tl6 ,
! REOUlkED FOR FUEL. LOAD PACE: 9 l
SYSTDI BASIS FOR Pl!ASE 11 SYSTEM S/t! TEST 11ESIGNATOR REQUIRDIENf RELEASED OPERAHILITY liEFERRAL COHENTS (DESCRIPTION) (YES/NO) (YES/NO) (YES/h0)
-(PROJT. DATE] IPROJT. DATEl (PRO.1T. DATE ,,
}
VC . Required by NRC regulation NO No YES- One train requised. In-Place
- (Control (CDC #19). Complete rema
- .ning [3/23/86) [4/04/86 (Init. Crit.) Ifiter te$t L final balance i R.wnnIIVAC) train prior to Initial Cr:;ticality. PT-017. AT-002 not required.
VD Required to support DC function. NO NO YES In-Place filter test & final !
(tr. Rocun Complete final testing pr:;or to (2/18/86] (2/24/86) IS% Powerl balance not reipiired for FL.
IIVAC) 5% power. PT-017, VF Required to support area negative NO NO YES Nceded for Secondary Cont.
(Fuel Bldg. pressure requirements. Complete 11/15/861 11/23/861 15% Powerl Negative Pressure. In-Place j
] IIVAC) final testing prior to 5% power. PT-017, 007, 009 filter rest & final balance j not required for FL. I;eed VC functional if no VF.
f VG " Required to support area negative NO NO YES Needed for Secondary Cont.
(Standby pressure requirements. C.mplete [2/15/86) [2/28/86] linit. Crit.) Negative Pressure In-Place j Cas Treatment) final testing prior to initial 17-017, XT-002 Filter Test 6 Final Balance criticality, not required for FL. No l
I radioactivity prior to Initial Criticalit y.
i VL Requird to support onsite NO NO NO Needed for Onsite Analyses.
} (Chem Lab analyses. Complete final [2/26/861 [3/04/86] In-Place Filter Test & Final ,
IIVAC) testing prior to Initial lialance not required.
l Criticality.
j VQ Full system operability hO NO YES Needed to establish j requirc< prior to lleatup (1/24 /86) (TBD] [Ileatup) Secondary containment (Dr>well j Purge) to burp pre nure from drydell. XT-002, PT-005 (Close Valves). Operation not acquired.
i .
l VR Full system operability required NO No YES Needed to establish
- (Cootainment prior to Initial Criticality. [l/24/861 [1/23/86) (Init. Crit.] Secondary Containment.
I Bldg. IIVAC) PT-017, 004 (Close Valves). System
' Operation not required, l
CPS SYSTut STATilS REPORT DATE: January 1, 1986 l'F(X)lRED FOR 11JEL IDAD PACE: 10 SYSilli 3 ASIS FOR PilASE II SYSTEM S/U TF.ST DESl(.NATOR E20lllkt. MENT RELEASED GPERABILITY DEFERRAL C041FNTS (DESCRIPT10rn (YES/NO) (YES/NO) (YES /NO)
(PROJT. DAMI IPROJT. DATE] [PROJT. DATE)
Vr Complete remainder of system NO to YES Common Stack required. ,
(Turbine Bldg. prior to lleatup. 13/23/86] [Tl;DI lifeatupl llVAC) I'T-017 W Required for habitability. YES YES YES Needed for habitaleility (Radwaste Complete final system testing (5% Powerl during spill cleanup.
Itidg.1;VAC) prior to 5't, Power to support PT-017, XT-002 Inplace filter test & final Startup. balance not required.
VX Required to operate AP NO NO YES Required to Support Aux.
(Suitchgear componertts . [2/26/86) (3/03/86] lS%.Pouerl Power (AP).
Ileat Rernoval) PT-017, 003 VY Required to support ECCS *2ech. NO NO YES Fssential for FCCS (ECCS Equip. Specs, cperability. [2/17/86) (2/24/861 (St Powerl operation.
Cooling) PT-017, 002 UE Required by Tech. Specs. YES NO NO Required to process 1.
(Equip. Drain [1/24/86] contain traste water.
RW Reproc. &
Disposal)
WF Required to support radiological YES YES NO Required to process 6 (Floor Drain controls, cont ain waste bit er.
RW Reproc.
6 Disposal)
x.
CPS SYSTlH stall!S REPORT DATE: January 3, 1986 REQUll!ED FOR FUE!.I.0AD PACE: 11 SYSTDI 3 ASIS FOR PilASE 17 SYSTEM S/U TEST I)ESIGNATL >R I2QUIRDII:NT RET. EASED OPERA 1111.ITY DEFERRAL. CINiEPTI'S (DESCRIITION) (YES/NO) (YES/NO) (YES/t!O)
(PRfuT. DATEl IPROJT. DATEl IPRO.IT. DATE) 1A1 Required by Tech. Specs. YES YES t:0 Makeup demineralizer Otakeup required to ensure clean Demineralizer) watcr.
US Itequired by Tech. Specs. YES NO NO Provides rau teater for HWPil (Plant [1/12/861 & CC and provides backup Service Water) for SX.
VI Required by Tech. Specs. YES YES NO Cools bearings on conciensate (Turb. Bldg. pumps & provides water to Closed Cooling CRDs.
Uater)
UY Required to support radiological YFS lTBD) No To contain ct,ntaminated (i.aund ry controls, water during cleanup.
Equip. & Floor Drains, RW Reproc. &
Disposal)
UZ Requirc4 to support radiological YES YES NO To contain contuainated (Chemical, RW controln water during cleanup.
Reproc. &
Disposal)
^
CPS SYSTDi STARIS REPORT DATE: January 75, 1986 Ntfr REQtilRED FOR FUEL IAAD PACE: 1 SYSTEM FASIS FOR PilASE II SYSTDt S/tl1EST RELEASED g OPERABILITY DEFERRAL C(MILT.TS lYr.S1CtJATOR REQll!REMEffr (YES /NO) (YES/NO) (YES /t!O)
(DESCRIPT10ti)
- IPRO.!T. DATE] [PROJT. DATEl IPROJT. DATEl (TBEl t3 /A Provides only constrta rion Ah Required prior to Connercial YES related or administrative (SCAI.) Opera t toirs.
support loaIs.
NO tX) No Saf'ety-Related Function.
AS Required prior to llcatup to YES perform function. l'IBD] Provides Steam t o Radwaste (Auxiliary Evaporators, Turtelne Clanet Steam)
- cal and n.oisture separators / reheaters.
Required prior to Ileatup. YES NO t:0 tio steam generated during CA ITBD] open vessel testing.
(Cendenser Vacuum)
YES C!l not Req. unless CM Required prior to Initial tIO NO (Containment Criticality by regulatf or.s. [TBD] [TEDI (Initial Crit.] frrediated fuel. N!!C Honitoring) PT-013 exemption required for post-accident mealtoring equipment (CDC 213).
Required prior to St power to YES ITBD) fl0 No regular fitas of water CS perform function, into vecsel will occur (Feedvater during FL. STP-23A-li during Control) llea tup.
Required prior to IIeatup. YES ITBD] t'0 Coolicy s nter f or condenser.
011 (Circulating IJater)
Required prior to 5% power for YES [TBD] ti/A Provides for autfeiatic 11w DA and level monitoring in (Digital Data monitoring.
various radwaste systema.
Acquisition)
. -. - - - - -~
CPS SYSTDI STATUS RFPORT DATE: January 3, 18)P.6 PICT REOllIRED R)R FUEL IDAD PACE: 1 SYSTDI BASIS FOR PitASE II SYSTEM S/li TEST Dt.S it24 ATOR RE0lllREMENT RELEASED OPERABILITY DEFERRAL Cf&l flTS (DESCRIPTION) (YES/flO) (YES/NO) (iLS/NO)
IPROJT. DATE] IPROJT. DATEl lPROJT. DA1El l UL Required prior to Commercial YES ITBD] N/A Accuniulate contaminated (Laundry Operation. clottning until system is Equipment) ope rable .
DV Required prior to lleatup to YES ITBD1 No lleated water to versei not (nl llea ters) perform function. needed for fuet load.
Eli Required prior to lleatup to t10 .* NO YES Ilydraulic control f or steam (Steam Ilypass) perform function. (TBD] iTED] 15% Powerl liypass and Turbine Control AT-002 Valves.
l ES Required prior to 5% power to YES ITBDI 70 X*IP-TO-SO-02 perforud prior (Extraction perform function. to Initial synchroni::stion i Steam) during Tcut Coiwittion #1 l
Ett Required for Commercial NO NO ti/A System provides varfous (Electrical Operationc. (ThD) [TBD) CT-001 elect rical outlets for W1 ding) tuaintenance. Tempora ry cabling can be used, i
CC Requirett prior to 5% power to YES [TBD] N /A Generator not operated (Gen. Stator perform function. during IL Needed in Test Cooling) Condition #1 prior to initial turbine roll.
CD Required prior to 5% power to YES (TBD) tt/A Ancillar) system to "AP".
(Cat tied ic perf orm funct ion. XT-001 Provides protection to the Protection) distril,ution grid, lleeded prior to initial synclironizat ion in Test Condition 81
CPS SYSTEM GTAT11S REPORT DATE: .innu.is y 3, 1 *> 86 NtTf Rht!!! RED FOR FIIEl. LOAD PACE: 1 SYSTEt! BASIS FOR PilASE 11 SYSTElf S/tl TEST DESIGNATOR REf311RDIENT REl. EASED OPERABIL1'IY DMT13AL COMMFtTIS (DESCRIPTION) m (YES/NO) (YES/NO) (YES/NO) ll'ROJT. DATE] (PROJT. DATE] [ PRO.lT. DATE]
CS Required prior to 5% Power to YES (TBDI NO CS prevents radioactive (Turbine pertorm function per NRC release from Main Steam Cland Seal) regulaJion ,(CIX: #60) . components into Turbine Ill og. NRC exemption required.
IID Required prior to 11eatup to YES , [TBD] NO Collection of condensate not (RJ lleater perform function, need for FL (no steam).
Drains)
!!G Required prior to lleatup ger NO NO YES No release or 1.uildup of (Cont . Csunb. NRC regulation. ITBD] ITBD1 [lfeatupl hydrogen will occtar during Cons Control) PT-021 fuel load. NRC exemption required (CIC #41),
til Required prior to 5% power per NO NO YES System handles beyond design (llydrogen NRC regulation (10CFR50.44). [TBD] [TBD) [5% P werl basis accident hydroren Ignition) I'T-015 releases.
IIT Required for systems operability. NO NO N/A Testing and c.perability (lleat Trace) (3/15/861 [TBD1 requirements will 1,e fulfilled in appropriate sa fety-related systems.
IlY Required prior to 5% power for YES [TBD] N/A Cencrator will not be (llydrogen Cooling) support function. operated during Ft..
IS Required prior to initial NO NO YES No steam generated during
(!!S!V Leakage Criticality per NRC regulation [TBD] [TBD] linit. Crit.] Ft. . Main Steam II.es Control) (CDC #60). PT-016 closed. NRC exemption required (CDC J60).
CPS SYS1TN STAT 1!S kEPORT 11 ATE: .lanuary 3, l'44 N(TT REG 11 RED FOR Fl!EL IDAD pW: i SYSTDI LASIS FOR PitASE II SYSTDt S/tl TEST DESIONATt* REQlflRatENT RELEASED OPERAtlLITY DEF11RAL CIVIf1Ft3 (DESGIPTION) (M3/NO) (YES/NO) (YES/NO)
IPRO_IT. DATE] IPRMT. DATEl IPRitiT. DATE]
111 Required prior to 5*t. power YES ITBDI tR) No significant u. iter ,
IL.cre Parts for testing. velocity in vessel, rectre.
Honitoring) or feedwater lines during FL.
e IN Complete all requirements prior YES [TBD) N/A Testing an.1 operability (law Voltage to use. requirements will be Aux. Power) f ulfille.1 in appropriate
. s.stety-related systemn.
ttP Required prior to St power to YES NO N/A Needest to suppor t initful Ot. sin Power) support testing. [TED) AT-003 Synchronization during Test Condition #1, CG Required prior to RV head set NO NO YES RIS got sa.ne . Ste.m jet air (oftgas) before heatup. (TEDI ITBD) IPrior to RV electors will not by in head set l'efore operation during FI.. N.
Ileatup! radioactivity.
PT-11, XT-004 OT Required prior to 5% power YES [TBD] N/A San.e as "TO".
(Turbine Oil (initial synchronization)
Transier)
RA Required prior to Initial NO NO YES SCBAs availatile if needed.
(Respirator Criticality for system fraction ITED) ITEDI ITnitial Crit.] tio Airborn.: Contamination Air) and N"C regulation (CDC #19). XT-002, AT-007 during FI.. NRC excuption req'd.
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