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0-f PS G PubhcSeMce Electric and Gas Company 80 Park Plaza, Newark, NJ 07101/ 201430 7000 MAILING ADDRESS / P.O. Box 570. Newark, NJ 07101 Aug us t 8, 19 83 Mr. R.
A. Hartfield Chief, Management Information Branch of fice of Resource Management United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Hartfield:
HOPE CREEK GENERATING STATION UNIT NO. 1 DOCKET NO. 50-354 LICENSE NO. CPPR-120 CONSTRUCTION STATUS REPORT AS OF JUNE 30, 1983 Attached is the construction status report for Hope Creek Unit 1 statused as of June 30, 1983.
Very truly yours, P.
R.
H. Landrieu Project Manager - Hope Creek Engineering and Construction HPCadf Attachments CC:
Mr.
L.
E. Tripp - IE, Region 1 8504120400 840606 PDR FOIA KILLEFEB4-367 PDR M P 82 117/11 The Energy People
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CONSTRUCTION STATUS REPORT PAGE NO:
2-065 NUCLEAR POWER PLANTS STATUS AS OF: 6/30/83 HOPE CREEK 1 PLANT CHARACTERISTICS:
KEY FERSONNEL:
DOCKET NO:
05000354 CORPORATE CONTACT:
T. J. MARTIN - VICE PRESIDENT CP NO. & DATE ISSUED:
CPR-120 / 11/04/74 ENGINEERI NG AND (X)NSTRUCTION CP EXPIRATION DATE:
12/31/86 CORPORATE ADDRESS:
80 PARK PLAZA APPLICANT:
PUBLIC SERVICE ELECTRIC & GAS 00 NEWARK, NEW JERSEY 07101 PLANT LOCATION:
IE REGION:
1 CORPORATE PHONE NO:
(201) 430-8316 AE:
BECHTEL NRC LPM:
D. WAGNER NSSS:
GENERAL ELECTRIC IE PRINCIPAL INSPECTOR:
CONTRACTOR:
BECHTEL
-CONSTRUCTION:
W. H. BATEMAN (RESI DE NT INSPECTOR)
REACTOR TYPE:
-TEST AND STARTUP:
DER (NWE):
1067 IE RESIDENT INSPECTOR:
INSPECTION STATUS:
FUEL LOAD DATE CHANGES AS REPORTED BY UTILITY:
TIME PERIOD REPORT NEW REASON FOR CHANGE DATE SCHEDULE REPORTED BY UTILITY REPORT BEG DATE END DATE NUseBER OF INSP.
OF INSP.
04-00-75 06-00-82 DELAY IN OBTAINING STATE OF NEW JERSEY COASTAL AREAS FACILITY PEmlT.
05-00-76 12-00-82 REEVALUATION OF DELAY CAUSED BY N. J.
COASTAL AREAS FACILITY PERMIT.
10-00-76 11-00-83 RE-EXAMINATION OF THE EFFORT REQUIRED TO (X)MSTRUCT THE PLANT.
02-00-80 11-00-84 NO REASON GIVEN.
08-00-80 06-00-86 LOWER THAN ANTICIPATED ELECTRICITY SALES GROWTH, CONTINUED INFLATION, AND RECESSIONARY TRENDS IN ECONOMY.
08-00-82 01-00-86 TARGET FUEL LOAD DATE.
LOCAL PUBLIC DOCUMENT ROOM:
SALEM FREE PUBLIC LIBRARY 112 WEST BROADWAY SALEM, NEW JERSEY 08079 M P83 11/04 1-srd
y CONSTRUCTION STATUS REPORT PAGE NO:
2-066 NUCLEAR POWER PLANTS HOPE CREEK 1 STATUS AS OF: 6/30/83 CONSTRUCTION STATUS:
APPLICANT'S CURRENT ESTIMATED FUEL LOADING DATE:
01-00-86 APPLICANTS (DNSTRUCTION COMPLETION ESTIMATE AS APPLICANT'S PREVIOUS ESTIMATED FUEL LOADING DATE:
11-00-84 DEFINED IN CP: (EARLIEST)
APPLICANT'S ESTIMATED FUEL LOADING DATE AT CP ISSUANCE:
06-00-81 (LATEST) 12-31 APPLICANT'S CURRENT ESTIMATED COMMERCI AL OPERATION DATE:
06-0G-86 CURRENT ESTIMATED PERCENT CONSTRUCTION COMPLETE: 71.20%
COMMENTS REGARDING CURRENT CONSTRUCTION STATUS: NONE t
ESTIMATED ACTUAL ESTIMATED ACTUAL ESTI MAT ED START START COMPLETION COMPLETION 5 COMPLETE MOBILIZE AND PREPARE SITE:
02/76 03/76 08/77 08/77 1005 PLACE STRUCTURAL (X)MCRETE (REACTOR BLDG. TO. RPV PEDESTAL):
07/77 08/77 10/79 09/79 1005 INSTALL REACTOR PRESSURE VESSEL:
11/80 11/80 12/80 12/80 1005 81%
INSTALL-LARGE BORE PROCESS PIPE:
04/79 04/79 07/85 63%
INSTALL LARGE BORE PIPE HANGERS, RESTRAINTS, AND SNUBBERS:
04/79 04/79 06/85 35%
INSTALL SMALL BORE PIPE:
12/81 07/81 08/85 855 INSTALL CABLE TRAY:
08/79 08/79 07/85 46%
INSTALL EXPOSED METAL CX)NDUIT:
09/81 05/81 07/85 10%
INSTALL PONER, CONTROL, INSTRUMENTATION, AND SECURITY CABLE:
02/83 11/82 09/85 15 INSTALL ELECTRICAL TERMINATIONS:
03/83 02/83 11/85 05 CONDUCT REACTOR CODE HYDROSTATIC TEST:
05/85 05/85 0%
12/85 CONOUCT COLD FUNCTIONAL TEST:
12/85 OS 01/86 CONDUCT PREOP AND ACCEPTANCE TESTS NECESSARY FOR FUEL LCAD:
09/85 T
N P83.11/04 2-srd r
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HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST AGENDA I PRESENTED BY: OPENING REMARKS P. R. H. (Pete) La'ndrieu PSE&G A. Management Team Project Manager l B. Project Team Organization C. Hope Creek Overview and History D. Status Swamary 1. CONSTRUCTION OVERVIEW P.J.(Pete)Kudless PSE&G A. Introduction Project Construction Manager B. ConstructionPercent(%) Complete C. Milestone Schedule D. Short Term Goals E. Problems / Solutions F. Sumary a 2. ENGINEERING W. G. (Bill) Gailey PSE&G A. Introduction Chief Project Engineer B. Engineering Status (- C. Commodity Status D. Design Enhancements E. Problems / Solutions F. Sumary 3. PROCUREMENT R. W. (Dick) McGowan BPC A. Introduction Procurement Manager B. Commodity Status C. Major Equipment Status D. Major Purchase Orders & Contracts To Be Awarded E. Problems / Solutions F. Sumary J 4. CRAFT WORK FORCE .P.J.(Pete)Kudless PSE'G A. Introduction Project Construction Manager B. Overtime Percent C. Total Manpower Forecast D. Critical Craft Manpower Forecast E. Craft / Contract Status F. 1983 Labor Negotiations G. Problems / Solutions H. Sumary ( f NRC 1 (A-1)
- 9
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NRC Caselrad Fcrecast Ag:nda Page 2 PRESENTED BY: 5. PIPE HANGERS M. C. (Mike) Henry BPC ( A. Introduction Field Project Engineer B. Large Pipe Hanger & Snubber Status C. Restraint Status D. Hanger & Restraint Enhancements E. Sumary 6. PROJECT SCHEDULE R.J.(Bob)Kyle PSE&G A. Introduction Project Control Engineer B. System Schedule Transition C. Critical Path Analysis D. Schedule Flexibility E. Sumary 7. BULK COMMODITIES J. R. (Bob) Kyle PSE&G A. Introduction Project Control Engineer B. Bulk Commodities Status Sumary C. Bulk Comodities D. Sumary 8. STARTUP J. C. (John) Cicconi PSE&G A. Introduction Project Startup Manager B. Program Status C. Integration of Test Activities with C Construction D. Manpower Plan E. Problems / Solutions F. Sumary 9. LICENSING REQUIREMENTS W.G.(Bill)Gailey PSE&G A. Introduction Chief Project Engineer B. Problems / Solutions
- 10. 10 CFR 50.55 W.G.(Bill) Galley PSE&G A.
Introduction Chief Project Engineer B. Problems / Solutions C. Sumary
- 11. CONSTRUCTION /STARTUP J. C. (John) Cicconi PSE&G A.
Introduction Project Startup Manager B. Organization Interfacing C. Sumary 12. SITE TOUR & OBSERVATION OF P. R. H. (Pete) Landrieu CONSTRUCTION ACTIVITIES PSE&G Project Manager ( A. Itinerary NRC 1 ( A-2 )
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i m e n HOPE CREEK GENERATING STATION l PROJECT TEAIR ORGANIZATION PSE86 AND BECHTEL i PROJECT MANAGER P. R. H. LANDRIEU (PSE&G) B. G. MARKOWITZ (BECHTEL) I I I I OUALITY ASSURANCE PROJECT ENGINEER COST / SCHEDULING ANA A. GIARDINO W. GAILEY P. KUDLESS R.KYLE (PSE&G) (PSE&G) (PSE&G) (PSE&G) G. MOULTON K. BURROWES C. TURNBOW S. DARU (BECHTEL) (BECHTEL) (BECHTEL) (BECHTEL) STARTUP LIC ENSING PROCUREMENT J. CICONNI R. HUNTER (PSE&G) B.PRESTON (PSE&G) R. McGOWAN C.DORSEY (P S E&G) (BECHTEL) (BECHTEL)
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n.._ .-.- -. _, ~.. - -... ~.,, _ _. ~.. _... - ~ -._._._..--__ --._ _.~. - - ~. - f m p. LEGEBID: V SCHEDULE O FORECAST DIOPE CREEK GEIIEAATHIS STATICII T ACTUAL WeOf1T TEgens enas a COINTHUCTICIe STATUS: 3/2743 IE3 IT W SOMACE .N N M JABI FES IIAR APIt IIAV JufdE A8LV AUG WPT OCT SIov OEC IIS. g armaCUWWE """' LF W CGWUIT INSTALLED V OE C T $7 tEt m ST 88 TALL OF FREfAS. CASLE O ter V OE C T W _i-- -~_=_ae EAa*** = "amma r ^2 r as TV TV e nam _m gagyg ym ga gaggg pyg gIASIGERSIBISTALLEO m amm a dasawE m"ma LF W t*** 8 TRAV IISTALLEO TV pg man m CRIAVE "*"'"LF OF LAAW FWE ESTALLEO TV F2 WI7510htm CM eft. Cinc. WWW 88M' STS. CIVIL COIICnETE TV 73 WEBI, - IEWrLEW ImWIIDIW "m_me EL.17F TOE 1'P q rg pg ass - -- -- -_ n w -a 1 PV ga 76 WILE GRMUE 8'2'E LF W MSWE WALLEO 78 se m ""=' mem ema 88. LAAGE PWE - IIWW EL. ter V U 77 "a_m_r CRIEWE W W as ammmaa a aggyggTE V 30 WI7mEBISE WW NIX SIS Cm Mt. W pc nam na SELOW EL.12r V 78 M W.see,iin. WWTen a _CyT. CMIIE OF - - LGu PIPE V U N 3I7WI1W95 WT " "'" IM V EA Esusus. _ _ _ T ^aasa g V st _= r _ __ CIW5ME CMMALL CINSEE. VERT. MIE ABIIIMIIC 7 W SE836 EB N CPT. SM TWINM pWE S SIICISAIM - --i V V ' et 'am a tRWWE ""m = LF M & **** 8 CIme - 018E8 85 "ma' = CuevE a smamanL a IIyAc aIIct u S E a a man, d V G V-W SULE CUWWE W LF N1451188IISTALLED V W CPT. T4 - '-- T 99WIS W tE12="=ams CIWraOL CEM
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n + m p 1. CONSTRUCTION OVERVIEW ~ j E. PROBLEMS /SQLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CtstRENT STATUS
- 1. -Drywell The Drywell is the most conges-Continue to increase engineering Home office pipe design engineers
.i ted area on the project con-support and maximize project visi-and the design model are being re-i taining the most critical fluid bility of problems restraining . located to the jobsite to assist in i systems with intricate physical efficient production. expediting problem resolution. i configurations. As construction 1 - continues, the ability _to manload Continued emphasis on detailed A Drywell team of design and Field to previous levels decreases as scheduling and work preplanning the space becomes more confined. combined with utilization of mul- ~ Engineering and Supervision is located in a central area is in existence for Significant itants of concern are: tiple shift installation to max-close coordination of problem resolu-imize interdiscipline coordination. tions. 2 .[ Maintaining Drywell effective A detailed list of construction manpower density and earned restraints and critical items has manhours at scheduled levels. been developed with frequent updating jointly by the responsible field and Drywell jet impingement barrier home office parties. j design will be completed in June, and could impact installation of A detailed long-term schedule has 4 J small pipe, conduit,.large pipe been developed to plan and monitor i supports, and restraints, basic sequencing and manloading of work. l A very detailed 13-waek schedule, updated weekly, is in use. A l-week pipe work plan by component is in use. This schedule is main-tained daily to assist in the installa-1 tion problem. } l i q INtc 1 (A-8) (continued) 2 . - = -. - _ _.-., - _ ___ -___ -._. + __m.
,r% _ ~&- b~ 1. CONSTRUCTION OVERVIEW E. PROBLEMS /SQLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 1. Drywell - (Continued) i A preliminary design of the jet impingement barriers is currently being reviewed for constructibility at the jobsite. The results of this review will be incorporated into the final design. I CONCLUSION: The Drywell is receiving the required engineering and construction attention. Currently the Drywell system turnover requirements are supported. 2. Control Complex i Prefabricated cable installation A detailed recovery plan was developed Prefabricated cable installation is is currently behind schedule. showing construction to be back on working to the recovery plan. Ter-- This is due to late equipment schedule by mid-April. minations have begun and will deliveries. Bailey equipment continue. Bailey equipment is deliveries remain critical to being received and is forecasted to l the schedule. complete delivery by July 1983. [ i t CONCLUSION: Control Complex equipment deliveries and prefabricated cable will support a Control Complex turnover 12/83. [ i NRC 1 (A-9) j r i e
. _.. _ _ _ _ _. _. ~ _ _ 7. _-. 9 m 1. CONSTRUCTION OVERVIEW E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 3. North Radwaste Solidification 4 System Turnover J Changes to the radmaste solid-Expedite vendor equipment deliveries A recovery schedule has been devel-ification system resulted in to meet field priorities. oped to expedite and monitor engi-late engineering design and neering and construction and is . equipment deliveries which Expedite engineering design and have. being reviewed. have impacted the start of close interfacing with large pipe i construction, fabrication. Vendor supplied materials are scheduled to complete June 1983. Develop large pipe bulk installation I. recovery schedule. CONCLUSION: With vendor equipment and engineer-ing being expedited, construction recovery will be made in 1984 and will support radwaste solidification system turnover to startup in May 1985. a i 4 i NRC 1 (A-6) i b
s _O l. CONSTRUCTION OVERVIEW E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 4. Electrical Installation Cycle Raceway installation (conduit) A one year schedule has been devel-Seven additional experienced field is presently 6 weeks behind oped to present visibility to con-engineers have been assigned to schedule and is currently. truction restraints and to maxi-support installation resolutions. impacting wire and cable instal-mize installation lation and terminations. Recovery plans are documented in Field Engineering is increasing the one year schedule and recovery manpower to support conduit design is planned in the 3rd quarter of availability and problem resolution. 1983. Construction is to utilize multiple Areas of conduit congestion are shift installation where possible, being worked with multiple shifts. Wire and cable pulling has started and is progressing slower than the (IPS) project plan. The current project plan is to work under the philosophy of maintaining a slower initial cable pulling effort until a sufficient backlog of raceway is installed; thus minimizing the coiling of pulled cable and its potential problems. CONCLUSION: A recovery plan is in place and will be monitored. NRC 1 (A-4)
ij ^ r m 1. CONSTRUCTION OVERVIEW E. PROBLEMS / SOLUTIONS DESCRIPTION OF PR08 TEM' CORRECTIVE ACTION ~ CURRENT STATUS-5. Contractor Performance (HVAC) a) The contractor's-difficulty .a) 'Very shortly after the contractor The contractor has implemented in-adequately planning and mobilized it became evident that all the corrective actions; organizing their work to .they did not have the resources to and this month, for the first support the required be able to effectively interface time, exceeded their scheduled installation rates. with and support Bechtel installation to date required quantities. efforts. A group of 8echtel personnel Further, their current instal-b).. was assigned to help them direct lation rates are exceeding In the initial' stages of the contract, sufficient design ~their efforts, and assumed some of the required rates. was not released to provide ~ their_ administrative responsibilities. the contractor flexibility I in fabrication and installa-b) Construction requirements were
- tion, coordinated.with Engineering, and a program of walkdowns prior to fabri-c) ~The contractor's difficulty cation was instituted.
in performing at the rates established in the contract c).In the spring of 1982, it was decided jeopardized their financial -to convert them from a lump sua stability. -contract to a time and material contract for-installation work..In d) Contractor's offsite fab addition an incentive for their CONCLUSION: shop capacity was inadequate performance was established based to support installation. on actual work available to them. Corrective actions taken to date have resolved the problems d) Contractor established a second shop and contractor is on schedule. -for fabrication. t NRC 1 (A-19)
1. CONSTRUCTION OVERVIEW L( - F.
SUMMARY
The Project Team continually evaluates all aspects of the Integrated Project Schedule to determine that the overall schedule requirements are being met. To date performance in terms of progress achieved, percent complete, and resolution of problems and implementation of their corrective actions fully supports the construction and startup schedules. This review and evaluation is an ongoing effort and will continue to be effectively utilized in early identification and resolution of areas requiring management action to ensure schedule performance i which wi11' support the January 14, 1986 fuel load date.
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j /' f NRC 2 (B-1) 1.9
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST 1. CONSTRUCTION OVERVIEW ( Question: Overview of project construction schedule including progress and major milestones completed, current problems and any anticipated problem areas that may impact the current projected fuel load date. A. INTRODUCTION The Hope Creek Generating Station has essentially completed the civil phase of construction and is now well into the critical bulk installation phase which will continue into mid-1984. Concurrently, preparations are being made to make a smooth transition to a system basis to support the startup effort. Based on actual installed quantities through March,1983, con-struction stands at approximatelygpercent complete in support of the January 14, 1986 feel load. The statusing of the Integrated Project Schedule (IPS Rev. 3) as of the end of March reflects all commodities; except conduit, wire and cable and terminations as being on or slightly ahead of schedule. These schedules are at the facility and elevation level and were recently reviewed in depth as part of the develop-ment of a one year schedule. No major problems were uncovered. Recent installation rates have been slightly ahead of schedule requirements and are being performed under budget. At the same time application of overtime has continued at approximately two (2%) percent. The following major milestones have been accomplished to date: a. Start site preparation 03/76 b. Start structural concrete 08/77 c. Completed Reactor Building basemat 01/78 d. Air test Drywell and Torus 06/79 e. Set RPV 12 /80 f. Completed turbine generator pedestal deck 08/81 g. Set polar crane 11/82 h. Set dome liner 11/82 h 1. Rig in last Diesel Generator 01/83 NRC1(A-5) .' l.1 h
HOPE CREEK QENERATING STATION A W M 1983 JOS 10866 CONSTRUCTION % COMPLETE 1982 1983 1904 1985 ( JF MA MJ JA SO NO JF MA MJ JA SO NO JF MA MJ JA 80 NO JF MA MJ JA SO NO l 100 FUTEE9WI J , ap>
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_se 90 f l p i idi Al / j 2 i SDH DCLHN f W i T r i O N r t g / w I ,/ r-ACTUAL / 1 y J F M A M J j i ( J L F i D 1 p llCHED.SECH1EL i Q C IRECT S' 1 o I I ACTUALv n** =** .,d m E aapis** { j j m .l 5 m O so l H I sedP\\ O Millis8 B/C BCllEC. (. i w8!T I m r ' ACTUAL I N H I I CUMULATIVE % COMPLETE 1982 1983 O N D J F M A M J J A S TOTAL ACTUAL 67.82 50.14 00.86 82.41 64.01 08.03 INCREMENTAL % COMPLETE 1982 1983 O N D J F M A M J J A S BECHTEL SCHEO. 1.38 1.38 1.71 1.30 1.30 1.83 1AS 1AS 1.82 1.81 2.02 1.81 DIRECT ACTUAL 1.3 1.30 1.88 1A5 1.00 1.90 i SCHEO. 2A0 2A0 3.00 1.37 1.88 2.30 2.13 2.13 2.08 1.85 2.35 1.85 SUSCONTRACT ACTUAL 3.31 1A3 2.20 2.07 2.00 2A1 SCHEO. 1.54 1.54 1.92 1A0 1A0 1.75 1.50 1.50 1.94 1.05 2.00 1.06 TOTE ACTUAL 1.71 1.32 1.11 1.58 1.00 2.02 1.2
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} c n i 2. ENGINEERING E. PROBLEMS / SOLUTIONS l DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS i 12. Radwaste System Changes i Gaseous Radwaste' System The design, equipment selection, Gaseous Radwaste design is layout of equipment and award of proceeding according to la July 1981 HCGS replaced new purchase order was accelerated. schedule. the cryogenics off-gas system design with a charcoal Specification to Bid 09/22/81 treatment system as a result Award 12/30/81 j cf industry experience. Design freeze April, 1983, i ~ Complete equipment delivery ,l scheduled for May 1983. ,co Solid Radwaste System Solid Radwaste design proceeding
- g according to accelerated System procurement delayed schedule.
to allow for use of the latest available technology, that would include volume Specification to Bid 03/31/81 reduction. Award HPD 11/15/81 W&P 11/15/81 Design Freeze April, 1983. i Equipment delivery started December 1982. Complete equipment delivery scheduled for June 1983. I With the schedule outlined above l resolution of this issue will j support the Integrated Project Schedule. l NRC 4 (A-14)
2. ENGINEERING ( F. SUP9%RY The foregoing discussion of the engineering status and ongoing activities demonstrate that the engineering design effort and support to construction, licensing, and startup are consistent with the needs of the overall project schedule. The home office, site engineering, and resident engineering organizations are structured to provide maximum and timely support to construction to minimize resolution of construction related problems. Further, all known licensing requirements have been addressed, and where applicable, have been factored into the plant design. ( NRC4(A-30) 2.19
I HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST 2. ENGINEERING Question: Detailed review and current status of design and engineering effort (by major discipline) including any potential problems that may arise from necessary rework. A. INTRODUCTION The discussion to follow in this section is intended to demonstrate that: a. Engineering is significantly ahead of construction in most areas and supports the IPS schedule in all areas, b. Engineering has the organization, staffing and tools in place to support the balance of construction and licensing of the plant. ( B. ENGINEERING STATUS The home office engineering percent complete as of March 25, 1983, is M. The significant portion of the remaining 185 consists of engTneering field support and licensing support. The bulk status summary sheet, shown on the next page, and bulk commodity curves (Section 7-C) show the engineering percent complete for the major design commodities. In recognition that the completion of the engineering design also involves detailed tracking of systems, a series of engineering mini-schedules are maintained and monitored to track design and procurement progress of specific systems and/or issues on the project. S aples of these are discussed laterinSection%.q, It should be noted that the engineering bulk schedules and mini-schedules were developed using construction "early start" dates. A comparison of average lead times between the design release-for-construction curves, and the fuel load date with other major Bechtel projects (Seefollowingsheet)demonstratesthattheHopeCreekbulk design supports the project schedule. The home office engineering work is transitioning from an area / elevation " bulk" mode to a startup system completion punch 11st mode. The engineering facility organization, ( NRC 1 (A-12) 2.1
i 2. ENGINEERING { 8. ENGINEERING STATUS (Continued) ( i which has been in place in the home office for the last several years, i has used facility punchlists as a vehicle to close out major facility j open items. PSE&G's engineering organization is structured to provide close interface and support to the Bechtel engineering team. Monthly Engineering / Construction Interface meetings are been held on site to review a detailed Construction Restraints List to resolve open items. By the third quarter of 1983, all of these open items will be formally folded into startup system punchlists. At that time the engineering organization will have been reconfigured to a discipline type structure. I 1 j EngineeringtoFuelLoadComparison(inmonths) i a HOPE CREEK HISTORICAL ENGINEERING ENGINEERING ENGINEERING COMODITY % COMPLETE TO FUEL LOAD TO FUEL LOAD
- i Large Pipe SOA 76-45
) 90A 45 33' I Large Pipe SOA 70 54 Hangers 90A 38 31 Small Pipe SOA 49 51 l 90F 32 30 l Cable Tray 50A 57 49 90A 45 32 Conduit 50A 45 40 90A 34 24 i Wire & Cable 50A 39 32 90F 25 22 j I Terminations 50A 33 42 i 90F 21 26 i t
- 8ased on a survey of recent Bechtel projects.
1 1 NOTE: F= Forecast, A= Actual ( NRC 4 (8-21) 2.2 .__._a._, . a e
hy s m. l 2. ENGINEERING C. COMMODITY STATUS (. RELEASED PERCENT TOTAL T0-DATE COMPLETE i HOME OFFICE: LargePipe(LF) 195,700 193,500 99% Large Pipe Hangers (EA) 15,100 14,718 97% SmallPipe(LF) 107,400 94,700 88% CableTray(LF) 121,000 119,980 99% Conduit (LF) 375,000 347,200 93% Wire & Cable (CABLES EA) 24,000 16,930 71% i Terminations (EA) 231,800 119,400 52 % HVAC(LBS) 2,904,000 2,617,000 90% InstrumentOrawings(EA) 335 32 0 96% i FIELD: SmallPipeLayout(LF) 230,000 130,400 57% ConduitLayout(LF) 375,000 280,000 75% D. DESIGN ENHANCEMENTS The timing of the Hope Creek design work relative to the other major Bechtel projects has yielded several advantages to this project, j both in terms of availability of qualified personnel (present and future) and experience feedback. Some of the specific activities that have enhanced the design work are: 1. Design Model - The entire plant was modelled to a scale of 1/2 in. = 1 ft-0 in. All design drawings were checked against the model prior to issue for construction thereby minimizing the potential for rework due to design (- interferences. The drywell model is now being used as a construction' aid at the jobsite. NRC1(8-1) 2.3 t
-2. ENGINEERING D. DESIGN ENHANCEMENTS (Continued) f (- 2. Computerized Interference Elimination (CIE) Program - The entire drywell has been modelled using the CIE program i thereby providing further assurance that interferences and rework in the Drywell will be kept to a minimum. This program, with modifications, was also used as an aid in the jet impingement review. 3. Bechtel Raceway Program EE580 - This interactive program, 4 accessible to both home office and the field provides automatic raceway network development as the design i progresses consistent with separation, service level and tray fill criteria. 4. TMI modifications, Seismic II/I, ALARA, Safety Separation Reviews and Fire Protection Reviews - These items have been factored into the design of the plant so that backfit and modifications at a later date will be kept to a minimum. 5. Skid Mounted Equipment - A conscious effort was made early i in.the design of the plant to maximize the use of skid 4 mounted equipment thereby minimizing field work. 1 a j 6. System Isometrics - To permit a single type of drawing to be used by the mechanical design, stress, pipe support, ( construction and pipe fabrication groups, system isometrics have been generated for Hope Creek. This also has the advantage of precluding the need for separate stress isometrics. 7. Weld Size Optimization Program for Hangers - Bechtel Computer Program ME-120 has been used to optimize hanger weld sizes and lengths. A comparison with other major Bechtel nuclear projects indicates that a significant 1 reduction in quantity of welding has been achieved with j a savings in craft labor. 8. Constructibility Improvement Program - An ongoing program of. meetings between Bechtel (home office and construction) and PSE&G (engineering and construction) has yielded a i number of improvements in the area of more constructible ' designs and improved construction methods., t i 4 i ( NRC1(A-13) I 2.4 ... _ _ _ _. _..... _. _.. -. _ ~, _.. -. _ _. _. _, _
l I 2. ENGINEERING L ( D. DESIGN ENHANCEMENTS (Continued) r 9. Design Freeze and Change Control - To date all P& ids (a total of 184 sheets) in engineering have bee 6 frozen with the exception of the Low Volume and Oily Waste Treatment System (2 sheets) and Standby Liquid Control System (1 sheet), both of which are scheduled to be frozen by May 13, 1983. These and other previously frozen P& ids support the overall project schedule. Changes to the design subsequent to the freeze will only be allowed if it is a requirement to license or operate the plant. All proposed changes are presented at weekly engineering meetings for disposition. If approved by engineering,- they are subsequently presented to the project change control board for consideration. This detailed screening keeps design changes to a minimum.
- 10. Resident Engineering Team - In addition to a site engineering organization, a number of home office design engineers are resident at the jobsite. Their role.is to facilitate rapid turnaround and disposition of field problems. The composition of this team is continually reviewed and adjusted to match the current emphasis for construction. Also, dedicated resident. teams are being uniquely assigned to
( . specific plant areas such as the Drywell and Control Room j Complex.
- 11. BWR Owner's Group - Both PSE&G and Bechtel personnel participate in the BWR Owner's Group meetings with the benefit of obtaining knowledge of the industry wide approach to the generic BWR issues.
- 12. Bechtel Staff Group - The Bechtel home office staff engineering organization is available to Hope Creek as required. This staff provides services in such areas as monitoring other NTOL's for new requirements, reviewing industry activities for applicablity to Hope Creek, and engineering _ expertise in engineering specialist areas.
1 P ~^ .x n i NRC1-(A-14) F 2.5 t.z ....-..---.--u--- A -- - l
2. ENGINEERING k E. PROBLEMS /S0LUTIONS During the course of the project, a number of issues have arisen and have been dispositioned. These are discussed in three sections of this report. 1 1. Past problems / solutions related to design / engineering i requirements. These items are discussed in this section l and are: ALARA Seismic II/I Separation Review Jet Impingement Review Environmental / Seismic Qualification of Equipment Service Water Intake Structure Added floor at el 163'-6" of the Diesel Building fBlockwalls IGSCC PUA Unit 2 Cancellation Radwaste. System + 2. Licensing issues are addressed in Section 9. These are: _(. TMI Related Items \\ Appendix R ATWS 3. 10 CFR 50.55 (e) - Items are addressed in Section 10. As can be seen from the current status of the foregoing, both past and current issues have either been successfully dispositioned or a strategy developed whereby resolution will be forthcoming in a timely manner. In all cases the approach outlined supports a fuel load of January 1986. NRC 1 (A-15) 2.6
i n ,m ,n i - 2.; ENGINEERING E. PROBLEMS /SQLUTIONS' DESCRIPTION OF PROBLEM CORRECTIVE ACTION ' CURRENT STATUS 1
- (ALARA) As Low As Is Reasonably Achievable (Regulatory Guide 8.8)
Maintain the annual integrated Establish a formal ALARA design The ALARA program is nearly. d:se to station personnel and review program, which evaluates complete.. 4 to individuals working at the each system and radiation area station ALARA. .to reduce radiation exposure A total of 234 ALARA action items to ALARA. were identified and all but 4 are complete. t .ALARA program for the.CRD maintenance area, solid and gaseous radwaste [ systems is planned to be completed June 1, 1983. il.p2 -a 11 A final ALARA report is to be completed December 1, 1983, including close out 1 of the remaining 4 minor action items, d With the schedule outlined above resolution of this issue will support the Integrated Project Schedule. 1 N I t r e L 9 ] NRC 4 (B-23)
-1
- i 2.
ENGINEERING q
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' E. PROBLEMS /SQLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 2. Seismic Category II/I Design _(Regulatory Guide 1.26) R.G.1.26, Position C.2 In 1976, the project issued de-As bulk. layout drawings were issued requires that those portions sign criteria D7.2, Seismic Classi-for construction, they were cf structure system or com-fication and Seismic Design, that reviewed for Seismic II/I ponents whose continued identified the Seismic II/I design considerations and were included function is not required but requirement. The DITS also in the design. l whose failure could reduce the ideatified the QA requirements '1 . functioning of any Seismic as required by R.G. Position Large Pipe' 907, complete Category 1~ plant feature to C.4. HVAC Layout complete , l !* 'an unacceptable safety level Lighting Layout complete should be designed and con-In 1981, we also issued ' Plumbing complete 0" structed so that the SSE Design Criteria, D7.9, Field would not cause such a failure. Routed Procedure, that A formal separation review program identifies the Seismic II/I addressed the Seismic II/I issue,
- l criteria for field routed as well as other issues, on a
- L commodities.
room-by-room basis. L < Reactor Bldg. Review complete Aux. Bldg. Review complete docu-g mentation close- -out 5/83 1 Identify Seismic II/I on l Pipe Index 6/83 Arch. Wall Drawings 6/83 Hanger Drawings 6/83 The resolution of this issue will support the Integrated Project i Schedule. NRC 4 (B-24)
4 2. ENGINEERING i E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 3. Separation Review (Regulatory Guide 1.75, l? SRP 9.5.1, SRP 3.6.1)- Verify that systems and compo-A comprehensive separation review Review of the Reactor Building nents important to safety are was conducted, began January 25, 1982, and was completed August 13, 1982.
- designed for the effects of Results of this review revealed internal missiles, pipe breaks, that the effects of internal exposure fires, and Seismic II/I hazards would not impact the without loss of capability to safe operation of the plant, or perform their safety function.
degrade the ability of the plant to achieve and maintain i cold shutdown. w Review of the Auxiliary Building began September 15,1982, and is scheduled to be completed June 15, j 1983. Preliminary results have revealed no internal hazard that would degrade the safe operation of the plant. With the schedule outlined above resolution of this issue will support the Integrated Project Schedule. NRC 4 (B-25) 1 I
~~ 2. ENGINEERING E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 4. Drywell Jet Impingement,- SRP 3.6.1, 3.6.2 General design criteria 4 - Perform an analysis to ensure that In December 1982, PSE&G informed states that components safety related equipment is not sub-the NRC of the number of barriers-important to safety be ject to jet impingement or protect required and suggested that a PRA appropriately protected it from the effects of jet (probabilistic risk assessment) against dynamic effects of impingement. And LBB (leak before break) meth-pipe break.that may result odology would obviate the need for from equipment failures. HCGS began in 1981 an extensive pro-certain barriers. gram of defining break locations based on' preliminary stress PSE&G continues to feel that PRA calculations, determining impacted and LBB would justify the adequacy P' systems, structures and components of HCGS design without jet impinge-5 using a computer model of the ment barriers, but the schedule Drywell volume and determining if implications of pursuing a favorable those items are safety-related response from the NRC leads us to given the pipe break event. install the barriers now. Barrier design has continued in parallel with this activity. Barrier installation is scheduled to start in the fall of 1983 and will be complete November 1984. With the schedule outlined above resolution of this issue will i support the Integrated Project Schedule. I NRC 4 (B-26)' N l
e n p L 2. ENGINEERING E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 5. Equipment Qualification (Regulatory Guide 1.89. Rule 10 CFR 50.4, NUREG -0588. Regulator Guide 1.100) Assure that components Implement seismic and environmental HCGS purchase specifications important to safety are testing / analysis to demonstrate include seismic and environmental compatible with normal, qualification. qualification test requirements transient environmental and for safety-related electrical equipment. The review program dynamic affects. is in progress. HCGS will have seismically qualified all safety-related mechanical equipment. s, 25 E.Q. documentation should be avail-able for NRC review approximately six months prior to fuel load. Any field changes required because of NRC review must be evaluated later a for any impact on construction and licensing. With the program outlined above this issue supports the Integrated Project Schedule. ? ? NRC 4 (B-27)
n ^ m 2. ENGINEERING E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 6. Service Water Intake Structure (SWIS) l The design of.the SWIS called for The design was revised to The NRC was notified of the planne'd . placing tremie concrete to the top , accommodate placing the tremie ' modifications to the design, and cf green-gray Vincentown-at el 35 ft. concrete deeper, to the top no further action.is required.
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~ (average) with a key extending to of the green-gray Vincentown el 20 ft. During excavation, it was strata. !l-determined that the top of this strata was at el 23 to 29 ft. 9 f%) N. 7. Additional Floor'(163 ft. - 6 in.) in Diesel Area (Regulatory ~ Guide 1.97,ATWS NUREG-0737) i' Lack'of available space for Add additional floor at el 163 ft. - All related redesign is- !i Control Room panels on-6 in, of the Diesel Building. complete and the additional el 102 ft. - 0 in to accom-floor has been constructed. modate the equipment that resulted from new regulatory-i l requirements such'as ATWS, Regulatory Guide 1.97, NUREG-0737, new design requirements such as the revised alarm philosophy, and changes in the main control board indication lamp voltage.
- [
- j NRC 4 (B-28)
-. ~ A o ^ '2' ' ENGINEERING E. -PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 8. Seismic Analysis of Blockwalls (Bulletin 80-11) IE Bulletin 80-11, required an Evaluate the use of masonry block The evaluation of the seismic design evaluation all masonry walls walls in the plant. of block walls is complete and shows that no block wall's failure can impact fer their structural integrity the safety-related system needed for and, in the event of failure, a safe shutdown. .the effect on safety-related systems. Reactor Building All masonry block walls have been changed to concrete poured walls and p are designed as seismic Category I y n> structures. h ha 4 Containment 's s There are no block walls in the J-structure. i Auxiliary' Building y Masonry block walls have been changed to concrete panel walls which are designed as seismic Category I j structures. !+ U Turbine Building The Turbine Building is a non-seismic Category I structure and block walls in this building are designed as non-4 seismic Category I. a Intake ' Structure There are no block walls in this' 1; structure.
4 m R. r, !i 2. ENGINEERING E. PROBLEMS / SOLUTIONS j CURRENT STATUS CORRECTIVE ACTION l DESCRIPTION OF PROBLEM 9. Intergranular Stress Corrosion Cracking (IGSCC), Regulatory Guide 1.44. UGSI-A42 NUREG-0313 Regulatory Guide 1.44 requires'
- Safe-ends and thermal sleeves.
All corrective actions have been plants to reduce the IGSCC 1. Recirculation return lines completed. i! susceptibility of BWR piping a. Replaced SS 304L safe-end with SS 316L. .i increased level of reactor b. Replaced SS 304L thermal coolant pressure boundary sleeve with SS 316L. and engineered safety i features system integrity. 2. Feedwater inlet lines. iF a. Replaced _ welded safe-end and thermal sleeve with triple-sleeve, interfer-ence fit design. m !m b. Replaced 304L thermal j l
- sleeve with SS 316L.
c. Replace safe-end carbon h steel with partial SS 308L ID clad. 3. Core spray lines. a. Replaced SS 304L. safe-end with carbon steel. b. Replaced SS 304L thermal sleeve with SS 304. ~ f
- 4. 'CRD return line'(high-cycle thermal fatigue not IGSCC).
a. Cut off SS 304L safe-end and thermal sleeve and capped nozzle with Inconel cap. Return flow diverted to RP (SV 121) in HCus. 1 (Continued) NRC 4 (B-29) j
2 ^. ENGINEERING E.. PROBLEMS / SOLUTIONS / DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 9. Intergranular Stress Corrosion 4/- Cracking'(IGSCC), Regulatory (Continued) p!' Guide 1.44. UGSI-A42, NUREG-0313 l
- Re' circulation pipe (SS 304) 1.
Shop welds solution heat-treated (SHT). 2. Corrosion resistant cladding (CRC) applied to all field weld ends and to several shop weld ends. These shop welds could not be made prior.to na SHT because of SHT tank size a-limitations. i.; i 3. Deleted bypass line (pump dis-charge shutoff valve bypass) and plugged suction pressure point (PP) weldolets prior to SHT.
- Replaced CRD collet' housing during manufacturing.
i i
- Core spray piping changed from stainless steel to carbon i
steel. f 1 NRC 4 (A-11)' O
.l A 6 m lI'~ l ['! ll !~ 2. ENGINEERING l' E. PROBLEMS /SQLUTIONS l. DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 'I '10. -Plant Unique Analysis NUREG-0661 I In July 1980,-the NRC issued Perform a PUA (Plant Unique Modifications include: j{ the SER for the Mark I Long-Analysis). Define torus modifica-Term Program defining the tions needed to meet stress limits.
- Stiffeners at the torus bay acceptable methodology for Perform modifications.
j'unct ions. F defining pool swell.and -[ bubble oscillation loads on
- Mid-span supports with a partial the torus.
{ ring girder. j
- Ring header, vent line and kdowncomersstiffeners.
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A contract with NUTECH was signed E* in 1980 for the PUA. The PUA is ,;(: in process and will be completed ) by January 1984. Additional minor i! ( modifications that may result i \\ from the PUA will implemented by June 1984. With the schedule outlined above resolution of this issue will support the Integrated Project Schedule. 4 i }, 4 ^ NRC 4 ( A-12 )
? m m e i l 2. ENGINEERING E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT' STATUS 5 i! .11. Unit 2 Cancellation - Reactor Building & Turbine Building l In December 1981, Unit 2 The " Plant Cancelled Area", Unit 2 Reactor Building tas cancelled. At that formerly the Unit 2 Reactor Build-time, Unit 2 Reactor - ing area, is being enclosed at Design drawings for completing the and Turbine buildings were roof el 132 ft. This area will exterior walls and cylinder walls partially constructed. have no function and will be to el 132 ft. have been issued. unoccupied. The floor slab at el 102 ft. has also been issued. The Unit 2 Turbine Building exterior is being completed. The roof design will be finalized by June 1983. 1 ,ro Portions of the interior space q will be utilized. Unit 2 Turbine Building f.' Deletion of Unit 2 will have no Design drawin'gs for concrete slabs, . I impact on the safe operation of walls and structural steel con-l Unit 1. version are issued for construction. i! i 4 ] 1 l NRC 4 (A-13)
f-m O e 2. ENGINEERING L l E. PROBLEMS / SOLUTIONS I DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS ',i - 12. Radwaste System Changes . t, - Gaseous Radwaste System The design, equipment selection, Gaseous Radwaste design is layout of equipment and award of proceeding according to In July 1981 HCGS replaced new purchase order was accelerated. schedule. the cryogenics'off-gas system design with a charcoal Specification to Bid 09/22/81 treatment system as a result Award 12/30/81 of industry experience. Design freeze April, 1983. i I complete equipment delivery scheduled for May 1983. p Solid.Radwaste System Solid Radwaste design proceeding g according to accelerated System procurement delayed schedule. to allow for use of the. latest available technology, 03/31/81 that would include volume , Specification to Bid reduction. Award HPD 11/15/81 'l W&P 11/15/81
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, Design Freeze April, 1983. t.' Equipment delivery started December 1982. Complete equipment delivery scheduled for June 1983. i i With the schedule outlined above i resolution of this issue will support the Integrated Project Schedule. i -l I r NRC 4 (A-14) iI i
2.- ENGINEERING (- F. SUPNARY The foregoing discussion of the engineering status and ongoing activities demonstrate that the' engineering design effort and support to construction, licensing, and startup are consistent with the needs of the overall project schedule. The-home office, site engineering, and resident engineering organizations are structured to provide maximum and timely support to construction to minimize resolution of construction related problems. Further, all known licensing requirements have been addressed, and where applicable, have been factored into the plant design. l l . ( NRC 4 (A-30) 2.19 .,.. ~ _ _,._....;_.
4 2w2m E3 8 i = . a. t$ M h
l HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST 3. PROCUREMENT 4 e + Question: Detailed review and current status of procurement activities including valves, pipe, instruments, cable, lL major components, etc. A. INTRODUCTION 6 7.* A 3 Procurement activities for the _ Hope Creek project are carried out by dedicated procurement organizations which have been integrated into the project team. Rechtel's h=a office is + responsible for the ourchaca af anni m ad nermanent olant-_ 'emncT;at and enain=ared bulk en-dities, as wel' ac majni- _ construction contract formation._ Construction contracts are transferred to the field contract administration group after formation. Bechtel's field procurement organization is responsible for purchasing non-engineered material and equipment, bulk commodities, and consumables in support of construction. Public Service has contracted directly with General Electric for the nuclear steam supply system and the turbine generators. Although commercial responsibility is maintained by Public Service, technical administration has been assigned to Bechtel to facilitate the balance of plant design. Public Service has also retained responsiblity for purchase of material for the switchyard and for the fuel contract. 2. Most major plant equipment was purchased in 1976 through 1979. With the rapid swings in the economy and the evolving body of. regulations, this approach proved to be sound as evidenced by the permanent plant equipment delivered to date. On the other hand, certain system procurements such as the radwaste volume reduction system, off-gas treatment system, -hydrogen recombiner, containment instrument gas compressor, p and radiation monitoring were handled differently to take advantage of licensing developments and latest technology of-the major system suppliers. The major-systems to be delivered were awarded in 1981 and 1982. t Thecontractualdeliverydates(siteneed'datdarepredicited on bulk installation schedules. Generally, the site need date is established as six (6) months prior to the early start of bulks in an area / elevation. This provides adequate time for receipt, inspection and correction.of any non-conformances, minimum impact on construction in the event of vendor problems, 4 and flexibility to construction with a backlog of _ equipment. I NRC 'l (B-2) - m= .-==:.
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~ 3. PROCUREMENT B. COMMODITY STATUS Below is a tabulation of the total bulks required to construct the plant, based on Forecast 3, against quantities procured and delivered. Q.d I ( b - - l TOTAL REQUIRED ORDERED RECEIVED EngineeeredValves(EA) - Large (over 2-1/2") 2,249 2,381 2,244 Small (under 2-1/2") 8,047 9,476 9,379 ControlValves(EA) 5,808 4,-145 3,603 Local Field Mounted Instruments (EA) 3,848 4,262 2,2 92 HVAC Dampers (EA) 1,034 1,062 871 Pipe - Large (LF) [ Incl. Radwaste Drain] 379,300 354,000 354,000 - Small (LF) 230,000 239,000 93,760 - EngineeredCable(LF) 5,632,000 6,820,000 7,002,000 1 Conduit (LF) [ Rigid and PVC] 818,000 942,130 847,917 Cable Tray (LF) 121,000 118,800 106,200 i Excess Unit 2: 4 Large Valves (EA) 1,161 Small Valves (EA) 6,171 Engineered' valves include only large and small valves procured by Bechtel's home office. Bulk conunodity and catalog valves are procured in the field and have not presented a problem. Approximately 99% of the large valves and 116% of the small valves required have been delivered to the site. The overage _in small valves is due to allow-m ances included in the initial purchase. In addition a large quantity of. engineered valves ordered for Unit 2 had been delivered and are available as construction spares. E The forecast quantity of control valves is lased on estimates and historical data. Actual drawing take-offs are being conducted to confinn the quantity. With approximately 62% of the estimated quantity delivered, sufficient backlog exists to support con-struction until final quantities are defined. ( L NRC 2 (B-4) 3.2
9 3. PROCUREMENT B. C020DITY STATUS (cont.) k Instruments include only local field mounted instruments. Instruments mounted in panels or in skids delivered as part of an assembly are, not included. Approximately 59% of the required quantity has been delivered. i \\ i Cable quantities delivered are compared to actual installed lengths. i Due.to tolerances in the purchase orders, delivereo quantities exceed nominal ordered quantities. Delivered quantity currently exceeds installed quantity by 25%, generally considered sufficient to off-set construction losses. An additional 149,200 feet (nominal) of cable is on order, scheduled to be delivered by June 1983. Although Control Room interconnecting cable assemblies, totalling approximately 290,000 feet, are included in total required, they have not been included in the ordered and delivered quantities. These are -procured as pre-cut assemblies rather that in bulk lengths. Of the 2,452 assemblies required 2,182 have been delivered. The balance scheduled to be delivered by July 1983. All required dampers are on order to satisfy current requirements. Approximately 84% of the dampers have been delivered. The large pipe orders were originally awarded to Dravo who fabricated f' approximately 90% of the required pipe spools. The remaining large (~ _ pipe requirements are being completed at the off-site fabrication shop to provide flexibility and minimize. lead times. About 93%.of the required large pipe has been fabricated. Small pipe is procured from a number of suppliers on blanket orders-based on estimated quantities. Requisitions are issued to suppliers for_ required quantities. Fabrication is completed in the off-site fabrication ~ shop as necessary to support' construction. With short lead times being experienced, quantities delivered are limited to that necessary to support fabrication. Conduit and cable tray purchases are on schedule to support the construction schedule. b 3.3 NRC 2 (B-7). . ~. . ~ ~ -
3. PROCUREMENT C. MAJOR EQUIPMENT STATUS ~k . Below is the delivery status of major pieces of pennanent plant [ equipment. DELIVERY INSTALL: Primary Condensate Pumps 03/78A 06/78A 11/79A 12/79A RACS Heat Exchangers 11/79A-01/82A SAC Pump Motors Condensate Demineralizer System 03/80A 05/80A Bioshield -10/80A 11/80A SACS Heat Exchangers 10/80A ll/80A Main Condensers 12/80A 12/80A Auxiliary Boilers 12/80A 08/82A SACS Pumps 06/81A 01/82A Circulating Water Pump Motors 07/81A 05/83F-Main Transformers 01/82A 01/82A Reactor Feed Pumps 04/82A 05/82A Reactor Building Polar Crane 06/82A 11/82A Service Water Pump Motors 06/82A 04/83A . Circulating Water Pumps 10/82A 05/83F i Service Water Pumps ll/82A 04/83F Diesel Generators -- /82 A; 02/83A Station Service Transformers 01/83A 01/83A t Radwaste Volume Reduction System 06/83F-06/83F ~ Charcoal Off-Gas Treatment System 05/83F 7 06/83F {-. Hydrogen Recombiner 09/83F' 10/83F Containment Instrument Gas Compressor 09/83F ' 09/83F Radiation Monitoring 02/84F' 02/84F Station ~ Security System-11/83F-01/84F-i Major milestones related to component procurement include delivery and installation of the main condensers, emergency diesel generators, j upper and lower bioshield, main transformers, and the Reactor Building polar crane. Procurement effort is currently directed toward maintaining contract delivery dates for major systems and the Control Room Complex. The radwaste volume reduction and solidification system is being procured from Werner & Pfleiderer and HPD, Inc. Various components have been delivered and are scheduled to be complete by June 30, 1983. A potential problem exists with HPD's delivery of the compressor skid. d A major expediting effort is underway to assure delivery within the available construction window. The charcoal.off-gas treatment system, procured from Koch Process Systems, is on schedule for delivery by May 1, 1983. Ten absorber vessels have been delivered to the jobsite. Rockwell International is currently on schedule to meet the September 1983 site need date for the' hydrogen recombiner. The control cabinets were delivered on schedule in February 1983. Bechtel has negotiated .{ a delivery incentive to better assure completion on schedule. NRC 2 (B-10)l 3.4
3. PROCUREMENT C. MAJOR EQUIPMENT STATUS (Continued) ( Engineering and material procurement for the containment instrument gas compressor is essentially complete. Miscellaneous valves are the only remaining components to be received by the supplier. Seismic-testing is scheduled in June 1983. The forecast delivery will support the construction schedule. The radiation monitoring system has been ordered from TEC. The software development program for the radiation monitoring system is the critical path item to delivery on schedule. To date, seller is 95% complete with the first of three phases for the software development effort. Work has commenced on the second phase which is scheduled for completion June 1983. The third and final phase which includes software coding and software integration is scheduled to occur June through December 1983, allowing the final month and a half for factory testing. Excess computer capacity of the system will be utilized for the emergency response facility date acquisition system. Close_ coordination between Public Service, Bechtel and TEC is required to maintain the software schedule while incorporating these changes. 4 The station security system was awarded to TERA in September 1982. Bulk shipment is scheduled for January 1984. System shipment breakdown is as follows: { Consoles and Terminals 11/83 ( Data Management 11/83 Intrusion Detection 09/83 m Personnel and Material Screening 06/83 Closed Circuit Television 09/83 Communications 10/83 Engineering and component procurements are proceeding to meet this r schedule. Computers have been received by supplier. Control Room Complex: Plant Computer 06/82A 10/82A Annunciators . 08/82 A 10/82A Remote Shutdown Panel / 06/83F 06/83F Vertical Boards 05/83F 05/83F Console 05/83F 05/83F Termination Cabinets 09/82A '10/82 A Analog / Digital Non-1E Cabinets 03/83A 03/83A t Analog IE Cabinets 05/83F 06/83F j Digital IE Cabinets 07/83F 07/83F (, i NRC 1 (A-30) 3.5 ....t
^ i r 9 3. PROCUREMENT C._ MAJOR EQUIPMENT STATUS (Continued) ( The Control Room Complex is scheduled for integrated testing in January 1984. Major suppliers include Honeywell, supplying.the plant computer; General Electric, the NSSS panels; and Bailey Controls, the Control' Room. The plant computer was installed upon delivery but subsequently removed to be checked out with the simulator. It will be reinstalled in the summer of 1983. The GE panels have all been delivered. Since September 1982, Bailey has shipped 63 of the required 161 cabinets. Thirteen (13) more cabinets complete awaiting further design revisions. The balance of cabinet shipments-will continue from May through July 1983. The console and vertical board sections will ship from early April through_May. Bailey's timely shipments will support the site-installation schedule. As a result of Three Mile Island, many design improvements, modifications, and additions were made to the Control Room Complex equipment being supplied by Bailey. These changes fall into three major catagories: TMI related; Reg Guide related; and Human Factors Improvements. The specific items in each of these catagories are shown below: 1. TMI related improvements 1 a. Lamp test capability b. Implementation of emergency response facility c. Safety relief valve indication i _ ( d. Protective interlocks in test 2. Reg Guide related modifications i a. Reg Guide 1.97, Revision 2 signals and extended range of signals b. Branch fusing of individual analog circuits 3. Human Factors Improvements a. Motor operated valve overload and power failure detection b. Alarm philosophy revision and consolidation to reduce the total number of annunciator windows and. increase extent of computer alarin monitoring _. c. Rearrangement of module locations in logic cabinets for ease of installation and improved maintenance / service d. Change all indicator lights on vertical boards from 125V to 24V to intrisic safety purposes. The remote shutdown panel being supplied by Comsip is the only major components'which poses a problem. Although forecast delivery exceeds scheduled installation by six (6) weeks, it is not expected to delay integrated testing. Due to the size, however, a wall must be held open until installation and a workaround has been implemented. Auxiliary equipment for the Control Room integrated test, such l as batteries, chargers,--auxiliary electrical panels, and operator - ( monitor _ consoles, are on schedule to support construction. NRC 1 -( A-29) 3.6 w= -. 2.. r..-..: "
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i '~~ ~~~ ~~ 2,._ 2 ~ ~~ s 3. PROCUREMENT D. MAJOR PURCHASE ORDERS AND CONTRACTS TO BE AWARDED f ( Permanent Plant Equipment to be Ordered FORECAST SITE NEED i l COMPONENT AWARD DATE STATUS Radiation Shield Doors 07/83 02/84 Solicit bids 4/8/83 Ultrasonic Level Transmitters 04/83 '09/83 Bids being evaluated Acoustic Monitors 05/83 10/83 Recomendation to PSE&G 4/8/83 Emergency Load Sequence Panels 05/83 02/84 Bids received 3/28/83 Wastewater Lift Stations 06/83 01/84 Bids due 4/18/83 Spent Fuel Storage Racks 09/83 05/85 Bids due 5/31/83 ( Major Construction Contracts to be Awarded FORECAST SITE NEED DESCRIPTION AWARD DATE STATUS Torus Painting 08/83 06/84 Bids received 4/1/83 Penetration Sealing 08/83 06/84 Bids due 4/26/83 Non-Metallic Insulation 09/83 02 /84 Bids under evaluation Mortar Lining of Circulating 07/83 12 /83 Engineering revising Water Pipe specification-us Modif. 05/83 '08/83 Bid m eived and under Outfa11LDischarge 05/83 07/83 Bechtel engineering revising specification for resubmittal to PSE&G. Chain Link Fence (Security) 01/84 04/84 Issue bid package for PSE&G approval 08/83 NRC 1 (A-27) 3.7 =.. . = =- - i
4 5 9 3. PROCUREMENT [ E. -PROBLEMS / SOLUTIONS J The current purchasing environment presents unique problems for providing and maintaining a flow of material in support of + construction of a nuclear generating station. Four generic industry problems warrant discussion: I
- 1) With the decrease in nuclear power plant construction activity in the United States, traditional suppliers of 1
nuclear grade equipment and material are abandoning the industry. Fewer available sources means less competition i - and longer lead times.
- 2) As a reaction to TMI, suppliers are increasingly concerned with the contractual rights and obligations attendant to
- providing permanent nuclear plant equipment. Warranties, e
liability, and nuclear indemnification have become particularly sensitive areas in preaward negotiations, taking on an importance equivalent to price and delivery. -3) Stricter qualification requirements have significantly 4 increased costs and lead times. Lengthy qualification programs often exceed fabrication time spans. Many suppliers are utilizing third parties (test labs and f consultants) to resolve issues normally handled directly . ( between engineering. departments. I
- 4) Finally, high inflation rates followed by the current recession have found many firms understaffed to adequately l
administer orders for. nuclear equipment. In addition, j. decreased shop loads have made it more difficult to absorb the costs of maintaining a nuclear quality assurance program. j Hope Creek.is well positioned to deal effectively with these problems. Of 278 purchase orders for permanent plant equipment, i - 272 have been awarded to qualified sources. To the extent possible, additional quantities of similar equipment are being E added to existing orders to maintain qualification. Additionally, L the cancellation of Hope Creek Unit 2, WPPSS, SNUPPS, and TVA plants provide a large inventory of equipment and material . which is readily. available. Accordingly, Hope-Creek is less dependent on market conditions to complete plant requirements than previous plants at this' stage of construction. The " purchase early" philosophy has provided adequate time to incorporate changing requirements into the orders. Seismic and environmental qualification requirements have been kept l current in existing purchase orders. Programs are either ~ completed or in process for all required equipment. ( )NRC4(A-15)' 3.8
b l l 3. PROCUREMENT E. PROBLEMS /S0LUTIONS(Continued) Finally, PSE&G and Bechtel has a staff of personnel available 4 to assist suppliers. Expertise in qualification, planning, + quality control, purchasing and expediting, manufacturing engineering and production control can be dispatched to solve specific problems or augment,-temporarily, supplier personnel. Specific problems currently being addressed in procurement are on the following pages. ( ( NRC 4 (A-16) 3.9-
m p r-3. PROCUREMENT E. PROBLEMS /S0LUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 1. Late seismic qualification Piping is being installed with Wyle Laboratories to complete of 27' operator mounting design spacers in line. seismic testing by May 30, 1983. on large nuclear. butterfly BIF to issue final report valves supplied by BIF is Bechtel is working with BIF June 27,1983. impacting pipe installation. and its subsuppliers to complete seismic testing. Valves in assembly Complete delivery of most critical Bechtel expediting BIF and valves by June 20, 1983. sub-suppliers. BIF has been authorized to ship upon satisfactory completion of test. j p, i i i g f 17)
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4 '3.. PROCUREMENT E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 2. Late design and supplier Bechtel and'Comsip developed Panel deliveries range up to production control problems a punchlist to resolve open 8 weeks beyond site need have delayed delivery of-items. Bechtel engineering date. Bechtel and PSE&G . safety related remote panels meets with Comsip every other working to improve deliveries and HVAC panels by Consip. week. Bechtel assigned to minimize impactoon primary engineering and construction. i procurement contacts to streamline communictions with Comsip. Bechtel assisting Comsip with expediting sub-vendor deliveries. {> Resident expediter was assigned.
- Project Supplier Quality Supervisor visited Comsip week of March 21, 1983, to assist in resolving documentation f
problems and establish a system for minimizing future problems. Bechtel 's procurement manufacturing engineer visited Comisp week of March 28, 1983, to assist in shop loading.and scheduling. { e Il 4 l Nor A. ( A 10) 4
h e< .+ L e4 .4_ 4 a h.,. .t 4 A h.--E.s L 4.- m--- - - - ' ' - - " " ' ~ ' - - - - g ^ n 3. PROCUREMENT E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS - 3.. Sub-vendor delivery slip-Bechtel assisting suppliers HPD has improved forecast pages are' impacting completing to expedite sub-vendors. deliveries 2 to 6 weeks. of radwaste volume reduction Delivery to be complete by and solidification system Bechtel met with hPD manage-June 20,1983. being provided by Werner & ment week of March 14, 1983, to. Pfleiderer and HPD. obtain firm delivery commitments. Werner & Pfleiderer is currently forecasting Bechtel assigned coordinator deliveries within incentive to HPD to monitor equipment time frames. Delivery complete delivery commitments, by June 15, 1983. a-i. s i .ij e 1 4 85 NRC 4 (A-19) 1 4 4 9
'{ 3. PROCUREMENT-F.
SUMMARY
Procurement is sufficiently ahead of construction, both with a -large inventory of bulk materials and permanent plant equipment, to support the construction schedule and provide flexibility. Participation in the monthly Engineering / Construction Interface meetings provides construction with early warning of potential problems so '. hat alternate construction sequencing can be developed to n.inimize the impact of any late deliveries. Procurement activities support the Integrated Project Schedule. (s 4 i L \\ =. i L(; i NRC 4 (A '20) 3.13 -,... _. - ~ _ _ - _
l i O - E O u. M E O - R - H
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~ i i HOPE CREEK GENERATING STATION -(. NRC CASELOAD FORECAST 4. CRAFT WORK FORCE Question: Actual and proposed work force (by major craft), craft availability, productivity, potential labor negotiations and problems. A. INTRODUCTION 4 Currently there are approximately 2,600 Bechtel and 600 contractor equivalent manual men at the Hope Creek jobsite. The manpower s forecast will _ peak in mid-1983 at approximately 3,700 equivalent d /p men. The majority of the trades are drawn from the New Jersey, skills, such asO1pefftter weldersi are being recruited from ad[ Pennsylvania, and _ Delaware tri-state area. Crafts with special much larger area. Spec 171c actions have uwen ano are being successfully taken to provide the required welders. 1-Overall the Bechtel direct hire crafts are working at a level of performance which is consistent with the current project budget. Since August 1982, overtime has been held to a level of approximately 2 percent. (See attached chart) During this period site population has remained relatively constant and some improvements in productivity have been noted. As specific areas have become critical, overtime and shiftwork are being applied on.a case by case basis. : The project is continually reviewing, evaluating, and if applicable,' implementing f l (- revised work methods and techniques to enhance and improve overall productivity. In addition, the project has recently begun implemen-tation of a Team Building Program involving all jobsite personnel, both manual and non-manual. -The objective of this program is to unify all involved in the construction of the plant into a cohesive team dedicated to meet the project schedule requirements within the prescribed levels of productivity. The most inanediate area of concern with the craft work force is the expiration of nine labor contracts in 1983, including both the pipefitters and electricians. It should be noted that even if an 4 individual craft may refuse to work during contract negotiations, the other crafts continue to work. Since 1978,-no work stoppages have resulted from construction labor picket lines, d i i i q l t k NRC - 1 ( A-21) c f 4.1-l ~ o
HOPE CREEK GENERATING STATION OVERTIME PERCENT ( CUMULATIVE FROM INCEPTION 10 - s 8-6- 5.28 4-2- 0, 12/81 1 2 3 4 1 2 3 4 i 1982 1983 ~ QUARTERLY OVERTIME PERCENT 11 - 10.81 3 32 10 - 8.11 ~ 8-6.31 6-4- 2.64 ~ 2.18 2-f 0 l l l 1 1 I I I i s 12/81 1 2 3 4 1 2 3 4 1982 1983 4.2
o. f D N o N leu O lie h S c h A. s s A D 6 J A 89 J O 1 's L M 8xE t L A E 5L U M N U F O D F E V ,iM DH J O D L g*~ S EC SS E A R N u'mT T B D 9 O O Y vN N H S R E A O 8 h ,m O D 5 J T i CS C 9 J b 1 AT V M V A >,T RN \\ T E K M \\ NM 2 F g OE 7 E C R J I o Z D i k &U 1 u G N l .\\' L Q l U A T A E R O L ~ U R L E N S t s t NG E A u t L' AN T 4 b I 9 1 \\ MF 8 J J r L LF 1 /\\ ,i EA M TT T}/ .3 A EHS t M t /3 LC F A' T TE I J i .7 T'B h D <A b N M w' O U i t A n *% lu %',.' tl S yt i A n A T 3, A l u 3 a 3 h~ 0. l t u ) 8 J T t k O 9 O Ln. f I C V J TEA E 1 e i EQ M 1 v R r a R S$ U a m' A t_ UP g M p 2 W a I' 1; l i ii 1:' i' OI S F
- lg
~ s 3 f~ Y a J N i D / A C P / N a 'u NM F e / OO O T IT C S a iT f A S / i" T A A S G 28 G J D 9 M NI N J 1 M ? U TA T A C A E C RI ER A M NT EC F GEL J K E EE EC R I CV ER PE Os HC tsu P s g 0 0 0 0 0 0 i 0 0 D Q 0 0 0 0 n Y y 0 n 0 0 0 0 0 0 v 0 0 0 u 0 0 0 0 n 0 n ^ 0 6 4 2 0 8 6 4 0 8 8 4 2 5 a 2 q 2 n 3 2 2 2 4 2 1 1 1 j 1 a B 5 4 A O 8 J 0 1 G# >59-k= ES o t t t p*"
- +
6 g, 'o !',j1 iI ,j:l<! j j4 4 )
.7 ,n. r i YENERGlZE 7.2 KV VCODE HYDROY FUEL LOAD 1982 T7 1983 1984 1985 1986 J F M A M J J A S O N D 1 l 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 900 800 700 l 'EAl"EBE I $o 600 E = uj z yp b .. f =, % - = < o. 600 l 3$ ELI C ff K IJ N i 5 Qg 400 h N h l q m m mlp u 1 j i i 300 SCO EI)L LI t A:1 U M 200 % n. 100
- =.,, *
- a i.iOO 4
A $ '= i 12 ' 1,000 N r' =< f m g U f j PE F T 'ERI % q g,, ,' N "j E 1 h 9h h 600 El :N E 34 IL E -' 2$ I 6, 8$ 500 m m i 400 l g A c rt iA L 3ag 200 ) ', g 4 l 100
- *.,,' ms l
O JOB NO HOPE CREEK SOURCE: TITLE: BECHTEL MANUAL NOTE: huo. 4 /e.~. GENERATING STATION s y 3 ELECTRICIAN AND PIPEFITTERS BASED ON 6x8's SCHEDULE I l'Wie hics Electric & Gee Co. S/U REV. 01 STAFFING REQUIREMENTS shese of
.~.. ~. ~.. ~ m m m .i i 4. CRAFT WORK FORCE E. CRAFT / CONTRACT STATUS . CURRENT l' CONTRACT ON ROLL AS OF 3/25/83 EFFECT OF.- EXPIRATION 8ECHTEL PROLONGED STOPPAGE - CRAFT LOCAL DATE 1st 2nd 3rd TOTAL CONTRACTOR TOTAL 1983 EXPIRATIONS . Heavy Laborers W 2/28/83 7 2 17 12 29 Settled-No impact 18 Minimal Bricklayers 7 4/30/83 18 18 ' Carpenters 393 4/30/83 205 -52 -257 47 304- ' Substantial Pipefitters 322 4/30/83 611 118 72 9 18 747 . Major
- [
Pipefitter Welders 322 4/30/83 330 76 406 406 Major . Settled-No impact Sprinkler Fitters 699 4/30/83 i Sheetmetal Workers 19 4/30/83 68 68 234 302 Substantial None Roofers 30 4/30/83 ] *I -17 17 Minimal Wharf & Dock Builders-454 6/30/83 Electricians 592 -9/30/83 52 8 144 6 678 11 689 Major Painters .1331 2 /2 9/84 13 18 31 4 35 [' Cement Masons 699 4/30/84 38 25 63 13 76 Laborers 222 4/30/84 283 61 3 .347 47 394 i; Ironworkers 399 6/30/84 191 25 216 35 251 Operating Engineers 825 6/30/84 112 41 6 159 36 195 -Asbestos Workers 42 7/14/84 , Boilermakers 28 7/31/84 40 40 16 56 i Teamsters 676 4/30/85 42 6 48 34 82 i 63 11 74 56 130 Other . TOTAL 2557 559 .35 3151 580 3731 F l NRC 2 (A-1) i. ,..w.
4. CRAFT WORK FORCE B. 1983 LABOR NEGOTIATIONS Although 1983 craft negotiations include nine (9) trades, the pipefitters and electricians are included and must be considered the most critical for Hope Creek. Bechtel and Public Service management have developed contingency plans and strategies to minimize the likelihood of any disruptive work stoppages. Influencing these are some of the below considerations:
- 1) No problems are anticipated for these trades:
Roofers are not presently on site. Sprinkler fitters have already settled for a one year contract. Heavy laborers continued to work and settled on March 16 (retroactive to March 1) on a three year contract. Wharf and dockbuilders traditionally settle without a strike. The last strike was in 1958.. (
- 2) The electricians current contract includes a no strike clause.
If this is honored, no problems would be anticipated.
- 3) While not a Hope Creek union, the IBEW in Camden made a settlement in advance of their October 1983 expiration.
The amount of their increase is of concern as some trades had been communicating low percentage increases.
- 4) Unions have been losing work to non-union forces moving into New Jersey.
~5) Currently there is full employment for major crafts in the area, so that they could get other work. 4
- 6) Previous multi-year agreements include increases which may s
adversely influence negotiation. With one month to go, negotiations have not given any indication of settlements or serious bargaining problems. Work through agreements are possible, however, at this time such a recommendation cannot be made until some trend in bargaining develops. i Labor Relations will continue to monitor all contract negotiations and will provide' input to the contractor associations. ( NRC :1 (A-22) -4.6
1 m r '. i f 4. CRAFT WORK FORCE I G. PROBLEMS / SOLUTIONS l DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 1. Labor Contract Negotiations Nine individual craft labor Implement new labor contracts fpr Strategies and approaches are being contracts expire in 1983. the following crafts: developed. l Pipefitters (4-30-83) and electricians (9-30-83) are Expiration among the nine. Date i i Heavy laborers 2/28/83 Settled-no impact ia Bricklayers 4/30/83 Negotiations underway Carpenters 4/30/83 Negotiations underway y I Pipefitters 4/30/83 Negotiations underway 1 Sprinkler fitters 4/30/83 Settled-no impact l Sheetmetal workers 4/30/83 Negotiations underway Roofers 4/30/83 Negotiations underway Wharf & dock builders 6/30/83 Electricians 9/30/83 I i NRC 1 (A-24)
m m (. 4. CRAFT WORK FORCE G. PROBLEMS / SOLUTIONS li DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 2. Critical Crafts Availability of pipefitter welders Continue with programs currently Pipefit'ter welders were assigned and the ability to retain qualified underway. critical craft status in welders is an area of concern. September 1982. .c Onsite programs are in place to
- j.
provide booth time for welders lt with upgradable skill potential. Il CURRENT STATUS (Continued) Local NCA/UA training facility is Project welding criteria has been j! y thoroughly reviewed and revised to Onsite welder utilization being 4, m permit the use of stick welding in closely monitored to assure max-lieu of heliarc in all applicable imum utilization of welders areas (e.g., small pipe). qualification, do.b Selected offsite pre-qualification \\ g CONCLUSION testing being utilized. iI The actions taken to date have As piping installation work at i;i increased the -jobsite welder Susquehanna completes in June / July, population 100% since 200 qualified welders will become 'l September 1982, to over 400 and available for work in the area. i! will increase to 460 in mid-i i 1983. I l' (Current Status - Continued at left) i! 1 i j 11)
p a ^ 4 4 CRAFT WORK FORCE i G. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 3. Training Jobsite training was' identified 1. Expand the scope of the jobsite la) Near term training topics for as an area of concern. training activities, both manual and non-manual personnel.have been identified 2. Establish the position of a full and training materials are f time jobsite training coordinator being prepared. i to administer all training activities. lb) An overall training plan is being prepared which will ll outline the total problem. . !P 2. The position of a full time iF= training coordinator has been established and the coordinator is on site. CONCLUSION Sufficient training will be provided. s j 4 NRC 1 (A-10) 4'
a l l l l 4. CRAFT WORK FORCE H.
SUMMARY
The ability to successfully man the project to the levels required to support the Integrated Project Schedule is reinforced by current schedule progress and productivity. Some concern exists in the area of pipefitter welders, but over the last six months the project has demonstrated that qualified welders can be obtained and/or trained. At this time there are no indications that 1983 labor negotiations would result in any jobsite work stoppage. However, through the combined actions of Bechtel and Public Service, action will be taken to avoid any work stoppages which would result in schedule delays. s. NRC 1 (A-25) A, 4.10 '~
4 I 0 2: W0 I uJ 4. 9
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST 5. PIPE HANGERS
- Question: Detailed review and current status of all large and small bore pipe hangers, restraints, snubbers, etc., including design a
rework, procurement, fabrication, delivery and installation. A. INTRODUCTION ~ The current status of large nine hangers at Hope Creek is as follows: Design 96% complete Procurement 87% complete g 1 Material Receipt 81% complete A } Installation 58% complete < Final Acceptance 50% complete / Installation Rate .g/Mo. Actual vs. 435/Mo. Scheduled. ~ last 3 months Installation reflects hangers reported complete but not yet accepted by Field Engineering. Final acceptance status applies to completed hangers (with pipe) that have been inspected and accepted by Field ( Engineering. Final acceptance status does not include shimming or final setting of hangers. The rework of accepted hangers due to subsequent design changes is about 4%. - Hanger rework due to design changes has been and will be minimized because of: extra load carrying margin which was included in original design; essential completion of design freeze systems, including flow calculations; essential completion of water hammer and transient analyses; and an aggressive change control j program. The current status of pipe whip restraints is as follows: I Design 96% complete i. Procurement 96% complete Material Receipt 95% complete Installed and Final Accepted 64% complete l Small pipe hangers are t"acked as part of small pipe installation. i i NRC 3 (B-2) s 5.1
1 1 t h t? E @ f bMN 2Lt 9qwam 85 4 h s w G- - j p (.e+r.) 299 +- '\\, s d i ( i f l t {
I 5. PIPE HANGERS 8. LARGE PIPE HANGER'AND SNUBBER STATUSIII ( ' Number Of Hangers DESIGN DESIGN MATL MATL FINAL REWORK FACILITY FORECAST ISSUED ORD. _ RECD INSTALL ACCEPT (2) REQ'D Turbine Bldg. 5,393 5,381 4,831 4.612 3,615 3,303 150 -Reactor Area 3,909 3,853 3,535 3,386 1,961 1,575 101 Primary Containment 801-765 693 600 158 71 2 Radwaste 3,400 3,185 3,099 2,915 2,517 2,239 27 Control 227. 211 162 85 73 67 14 i
- Diesel 1,000 851 699 552 387 277 17 i
Yard 570 472 225 202 127-119 7 Total (EA) 15,300 14,718 13,244 12.352 8,838, 7,651 318 I C. RESTRAINT STATUS Weight of Steel (pounds) l DESIGN-MATL INSTALLED & FACILITY FORECAST ISSUED RECD INSPECTED Turbine Sidg. 147,600 128,262 128,262 117,226 j Reactor Area 563,400 562,960 550,304 363,637 i Primary Containment 495,800 472,200 463,026 292,935 Total (LB) 1,206,800 1,163,422 1,141,592 773,798 ~ (1) Small pipe hangers are considered part of the small pipe design, installation and acceptance cycles. (2) Final acceptance includes pipe installed in hanger. E l i i NRC 2 (A-2) 5.2
S. PIPE HANGERS. D. HANGER & RESTRAINT ENHANCEMENTS h' Since the beginning of the design effort, the following actions have been and continues to be taken to assure pipe hanger and restraint installation meets schedule: 1/2" scale plant design model helps minimize interferences. I Computeriezed interference program is applied to congested areas. I Hanger designs and construction procedures reflect numerous reviews of other projects for improvements and enhancements. Furthermore, our design process will assure minimum design rework as previously discussed. Specifications have been reviewed for constructib1111;y. The hanger purchase orders are field administered through three separate vendors for maximum responsiveness and flexibility. ' Inventories of surplus materials are maintained to provide an additional material source. Field engineers perform detailed reviews of hanger drawings prior to installation. Most material and constructibility problems are resolved prior to start of installation. f-Field engineers train superintendents and crafts in ( specification requirements. Early and complete field engineering inspections of hangers provide early warning of hanger installation problems. E.
SUMMARY
Large pipe hanger installation is ahead of schedule. Numerous steps have been taken to assure this trend continues. These steps address early identification and resolution of hanger installation difficulties. and will preclude rework. 1 I l [ 1 NRC 3 (B-3) 5.3 7... - -
4 J 3Ow I Or 0W 8 m a. b 1 I I l
4-m i HOPE CREEK GENRATING STATION NRC CASELOAD FORECAST 6. PROJECT SCHEDULE Question: Detailed review of project schedule identifying critical path items, near critical items, amount of float for various activities, the current critical path to fuel loading, methods of implementation of corrective action for any activities with negative float, and provisions for contingencies. The estimated project percent complete as of March 31, 1983. A. INTRODUCTION TheIntegratedProjectSchedule(IPS)combinesengineering, con-struction, and startup logic into one overall project plan and is the baseline for measurement of schedule performance. The IPS contains craft manhour and quantity resources as defined by the project's current forecast. Implementation schedules at the working level (e.g., mini-schedules and discipline work plans for Engineering and the One Year and Short Term Construction Schedules) are developed to meet or exceed the IPS. Activities in the implementation schedules are developed from their applicable IPS activity. The project plan has been developed to maintain a bulk installation ( mode of construction through 1983. In parallel, a system completion schedule has been developed which will allow a smooth transition from the bulk mode to a system /punchlist mode of operation. This is scheduled to begin in the latter part of this year. As of the end of March 1983 the project is approximately 66% complete, calculated from the actual quantities installed. Based on IPS, the I project will achieve 90% completion by the end of July 1984, 17-1/2 months prior to fuel load. A matter of concern is those areas in the powerblock where limited work area is available and there is a substantial scope of work to be accomplished. Specific details on the Drywell and other areas of the project schedule are continued in the following section. 6.1 . NRC 4 (A _27) i -. __. w --. =. -
r _r ^ . HOPE CREEK GENERATING STATION SYSTEM SCHEDULE TRANSITION BULKS i SYSTEM i j i e PREPARE
SUMMARY
SYSTEM COMPLETION SCHEDULES i, i N 12-15 MONTHS PRIOR TO INTEGRATED ENGINEERING, SYSTEM TURNOVER, CONSTRUCTION,STARTUP REVIEW SYSTEM STATUS-ENGINEERING l (IPS) d 6-9 MONTHS PRIOR TO SYSTEMS TURNOVER, 4 l REVIEW SYSTEM STATUS - I CONSTRUCTION 4 PREPARE IND[VIDUAL SYSTEM COMPLETION H SCHEDULES
.m i -O b i a 'i 6. PROJECT SCHEDULE C. CRITICAL PATM ANALYSIS -TOTAL FLOAT (oAv5) PATM DATE LAST THIS
- NO.
PATH BESCRipTION DESCRIPTION OF PROBtEM -IDENT. lEINTH IEINTH CORRECTIVE ACTION CIARENT STATUS 1. Complete the design, construc-Design and construction of 11/82 -74 -74 Continue to evaluate sub-Bechtel has made recom-tion, and turnover of the the CRO piping was delayed contractors construction sendations for schedule centrol red drive system in to perform an engineering schedule to compress piping compression which are to the Reactor Building. Supact evaluation assocle-Installation activities in be formally transmitted to'- ted with water hammer load the Dryuell and Cylinder the contractor in mid-criteria. Area. Ayrtl. 2 Complete the design and - Delay in the completion of W/83 -22 -22 Maximize the lastallation.. Vendor has received egulpment . delivery of solid radmaste the design and delivery of of. specific bulk commoditles and piping priorities from the piping and egulpment to solid radmaste equipment has based on current egulpment field. A recovery schedule is support bulk lasta11ation impacted completion of large and piping delivery schedule, presently being developed for completion in the North pipe. 1ssuance in late April. Radmaste Building. E. 3. Camplete Service Hater Civil construction is 01/83 -23 -13 Emphastre cespletten of Contractor has reviewed the Intake Structure civil behind schedule, civil activities through reseguencing of bulk activl. activities to el 122' in el 122'. Reseguence specific ties and can support the order to release major bulk activities (large pipe construction schedule com-bulk installations. and equipment) in order to pression. compress the bulk construc-' tien activities. 4. Fabricate, receive and Belay of panel delivery to 12/E -g 0 Continue to monitor and Certain pieces of equipment install Centrol Couples incorporate TMI changes enredite equipment delivertes, are being delivered appront-egulpment and associated at the vendor's shop, mately 4-5 weeks ahead of pre-f abricated cable, schedule. In additlan, pre-fabricated cable installation has begun.
- 5.. Completion of Dryuell smell-
- en schedule. '02/83 +4 +1 Schedule will centinue to - On schedule, pipe lastallation to support be maintained through maa. Bryuell systems turnover. laum use of shiftwork and overt ime. 6. Bellvery of G. E. mainsteam Delay in hanger delivery 10/82 -5g +20 Requested G. E. approval to-G. E. approval was received large pipe hangers to was forecasted by supplier. perform closure welds 3/14/83. support closure to utillaing existing temporary reactor vessel. hangers. e
m. -m 6. PROJECT SCHEOULE C. CRITICAL PATH ANALYSIS IPS REV. 3 0 - MARCH 28,1983 STATUS PATN NO. 1 (% TOTAL FLOAT LAST MONTH: -74 ACTIVITV DESCRIPTION: Mobilize Control Rod Drive Contractor ACTIv1TY C00E: IC11000CR0/1811102E58 TOTAL FLOAT THIS MONTH: -74 FACILITY / ELEVATION: Reactor Building Cylinder el 102' and Drywell PATH DESCRIPTION / PROBLEMS CORRECTIVE ACTION CINtRENT STATUS Contract (M-097) design, construct and
- 1) Decision to restart design effort was
- 1) Piping design has restarted without turnover control rod drive system. Design made February 1983.
Incorporation of water hammer load criteria. Site mobiltration is planned of this system was delayed to perform i an engineering lupact evaluation associated for 8/29/83 i with water hammer load criteria.
- 2) An independent analysis of water 2 a) Portions of the analysis are complete.
hammer loads is being performed by The entire analysis is currently Teledyne to determine required design estimated to complete by July 1, 1983. y
- load, m
b
- 3) Contractor to fully recover schedule
- 26) Upon completion of the analysis, any
. delay by compression of construction design changes identified will be schedule. Incorporated within the engineering and construction cycle to minimize SupelmRY LOGIC OIAGRAM schedule impacts. t ^ l
- 3) The contractor's schedule has been
'i J revleued for schedule compression. A e meett with the contractor was held U """8 - 3/22/8 to review full schedule i N""8'E ) FOR TURNOVER { recovery plans. g.g ,,, eu en,,,,. p _._ _. g I CunnEseT 8 STATtS com m ot uss N m 'u n' ots p l Sechtel will make a formal request for h-a contractor to comment on the schedule [ ryg l compression proposals. The letter is to be submitted by mid-April 1983. h*A'f ~ .m a mL 1 SupstATION: Upon evaluation of contractor's sub-l mitted schedule, the schedule can be { ~ enEu cdM 7 ----, sufficlently compressed and/or resequenced
3 i
p l MECOVERY to support system turnover. The water 4 ( MOkkh- - )' hammer load criteria evaluation fladings t ldT _) P 1 use are key to supporting the contractor's i [ Q%* design completion and timely incorporation a ]sjgy of any changes required. 8 l L
^ l l I i 6. PROJECT SCHEDULE C. CRITICAL PATH AIIALYSIS IPS REV. 3 0 - IWWICH 28, 1983 STATUS PATel 110, 2 ACTIVITY DESCRIPTIGII: Deliver and Install Solid Radweste Equipment TOTAL FLOAT LAST month: -22 ACTIVITY CODE: POMI37A10/gD09102404 TOTAL FLOAT THIS M011TH: - -22 FACILITY /ELEVATI0ll: north Radweste Building el IW' - 137' PATM DESCRIPil0N/PROBLEstS CORRECTIVE ACTION CINIRENT STATUS Remaining radweste solidificatten system equip-
- 1) Prierttire and empedite remaining vendor
- 1) Venders, Werner & Pfleidfer (ll-137A)'
ment delivery is affecting egulpment and equipment f abrication and delivery. and 15'0, Inc. (ft-1379) have' forecasted associated piping installation. . June 1983 for completion of equipment and piping delivertes. Construction is awaiting large pipe design to support f abrication and lastallation.
- 2) Ensure prompt engineering interfacing with Z a) Field Piping Engineering has received
. large pipe f abrication upon design iso's for approximately 605 of the solid f completion. radweste system piping. The remaining 40E is forecasted to be issued in April.
- 3) Review the vendor's forecasted deliveries and develop a recovery schedule.
2b) 250 LF of solid radmaste system piping is in the Fab Shop and should be avalla-ble for installation early April. un 2c) 800 LF of vendor (1580) supplied piping is forecast for 6/83. p:
- 3) Presently reviewing lapact of current equipment delivertes
- all uork plans for schedule recovo, are being evaluated based on the prioritization of equipment SupeutRT LOGIC OIAGRAfl delivertes and associated bulk Installa-t ions. Schedule to be issued in April.
./ gN h). veneen soupes.st.,4,W.S BeuvenY gg h4 -45 I---j'"nic'.L. I I = cunnEur SUfetATIGII: Vendor equipment and engineering is 8 7 ([ annu semes, p53 being expedited with construction recovery 2 w----.l naamasse soume,ecarioss ouut eenstatances t . l l
- pected during 1g04 to support redweste solidification system turnover to startup
,"'E j l h j'es"re"se d ' ? In 1985. ' ~ ~ - ' w n.au .v. v L j ,.4 1 g r---- i M"r.o InEcOVEftY I e-4 #, '5 r. [- I + e l l 8 I '- KM---l 1l l i -.- o..o,' h ~ va soI,os,eEr~m~oidst atUrsos~e~~~ w,_{ ~------------------, n .,an u _i TFSitesG t
~ ~ ,R p 6. PROJECT SCHEDULE C. CRITICAL PATH ANALYSIS IPS REV. 3 D - ItutCH 28, 1983 STATUS i PATH NO. 3 ACTIVITT DESCRIPTION: Construct and Place Walls to el 120' and 126' TOTAL FLOAT LAST MONTH: -23 TOTAL FLOAT THl$ MONTH: -13 ACTIVITY CODE: 9N79tES10K FACillTT/ ELEVATION: Service Water intake Structure - el 120' t l PATH DESCRIPTION / PROBLEMS CORRECTIVE ACil0N CistRENT STATUS Late completion of J. R. Steer's (contractor)
- 1) Contractor to submit a recovery schedule.
- 1) Contractor has issued a revised construction schedule that shows civil construction is affecting the release of major construction bulk installation in the laterf acing with Bechtel bulks i
service water intake structure el 122'. Bulk
- 2) Contractor to assign a senior level and civil schedule enhancements.
.i installation is required to support service supervisor to the jobsite to ensure water system turnover, recovery plan is successfully implemented.
- 2) Senior level supervisor arrived in
- March, i
- 3) Bechtel to reevaluate bulk Installation schedule and fomulate recovery plan.
- 3) Bechtel recovery plans to be issued l
in April. At present, specific belt lasta11ations have been started in SUP9tNtf LOGIC DIAGRAM parallel with the civil activities. .m REQUHeED I senvece maten avmas_svuuciune - cow't i Fon TunesOVER I etsv en constava svnuctune 7 J l SipetATION: Major Bechtel constructfon bulk CtmRENT sutm emstattAriose installation is scheduled to STATUS [ g l start 4/25/83. Schedule recovery h Ldsvanitek' veeruse will be accesplished prior to h startup system turnover. F s.enne maveT.,uevEs sinu vuiie ~c E 1 y s- - - _- _ - - - - - _ _e).. ,. _ L_ce-s1= r'se== i sr l 8 Outa tsusfattATeces - i, s.__-______--__-__-.--_, I ECOVERY stanw R _P_LA_N_j i t I 1 b t %1
m e-l. 6. PROJECT SCHEDULE C. CRITICAL PATH ANALYSIS IPS REV. 3 D - MNICH 28, 1983 STATUS PATH NO. 4 ACTIVITT DESCRIPTION: Install Control Complex Equipment and Pref abricated Cables TOTAL FLDAT LAST MDNTH: -9 ACTIVITY CODE: 1E 1210284A/ IE 12137848/1E 12 '.11270A/1E 1213770G TOTAL FLOAT THIS MONTH: 0 j FACILITY / ELEVATION: Control Building - el 102' - 137' PATH DESCRIPTION / PROBLEMS CORRECTIVE ACTION CINtRENT STATUS Installation of Control Complex equipment and la) Continue development and use of detailed
- 1) Prefabricated cable installation is 4-prefericated cables to support Control prefabrication installation / recovery currently behind schedule; recovery is Complex turnover, schedule.
expected by mid-April 1983. Installa-tion of pref abricated cable has been
- 2) Continue expediting and monitoring the restrained due to late delivertes of the Control Complex equipment fabrication Control Complex panels and revisions to through delivery, the associated raceway. Pull packages inich specify cable code number, race-way vlas, and footage have been devel-oped and support the requirements of the recovery schedule.
! N
- 2) The remaining Bailey equipment is on SUNWtf LOGIC DIAst#t5 schedule and is forecasted by July 1983.
+ I y cessinot coarLEX i L TunseovEn SUMETION: Control Complex equipment delivery and g d prefabricated cable installation will contnotcomen eauwemer omnv 7 sgport Control Complex turnover in [ e December 1983. l } i stant ensemenscAveo constats enesmesucarso [ casts susvattatiose casta navattavions svantw l CURRENT vesrews j STATUS h 1 r e e
A .A ^ i i I 6. pfMWECT SCM DULE C. CRITICR PATH ANALYSIS Ip5 REY. 3 D - MARCH 28, 1983 STATUS I pATM No. 5 ACTIVITT DESCRipTIOu: Install Drywell Small pipe TOTE FLOAT LAST MONTH: +4 ACTIVIIT CODE: ICl100055A TOTE FLOAT THIS M)MTH: +1 FACILITY /EtEVATIom: Reactor Sullding - Drywell el 86' - 121' ) pATM DESCRIPTION /pADSLEMS CIMRECTIVE ACil0N CIRRENT STATUS Installatten of Drywell small piping to support la&b) Design of Drywell small pipe has re-
- 1) Small pipe installation in the Drywell Drywell system turnover. Slyilficant items celved maximum emphasis and f abrica-is on schedule.
editch have potential to affect small pipe tion has been expedited. The Drywell lastallation efforts are: model and designers are being relocatd to the fleid to assist in timely resolu-Timely hanger design release and tion of installation problems. f abrIcatlon. 4 Ic) Detailed small pipe and laterfacing work Design revisions due to finaltzing plans in relation to other bulk commodities jet layingement barrier design. are being implemented, which will allow daily monitoring of all activities. , os Drywell congestion problems due to b increasing bulk installatlen, such as Id) Effective etIllaatton of mult1-shift concurrent conduit lasta11atten and lastallation effort is continuing. jet layingement lasta11ation forecasted in iget. SiseWulf LOGIC DIAERAM I manso ton T7 SUMATION: Currently Drywell small pipe completion conspsen nstemen a, will support the planned system turnover E"e*a'""us'n'"s %} requirements, n t _ surrenT-rnoeLeelfTasELY na.m -) i J J .11 monum minunnan 11 I f-( anVmELL CURRENT 5TATtg gs,gg,, e T l I. ' stent.ur ] usn.a i
O ps 6. PROJECT SCHEDutE C. CRITICAL PATH ANETSIS IPS REY. 3 D - MMtCH 28, 1983 STATUS PATH NO. 6 ACTIVITT DESCRIPTION: Mainsteam and Recirculating Systems Hanger Delivery TOTAL FLDAT LAST MONTH: ACTIVITY CODE: POM001XX0 TOTAL FLOAT THIS MONTH: +20 FACILITY / ELEVATION: Reactor Building - Drywell PATH DESCRIPTION /PRottEMS CORRECTIVE ACTION CURRENT STATUS By G. E. specification, closure of the 1)
- 6. E.'s approval has been requested to 1). Affirmative response was received from 2
malasteam systen to the RPV cannot take take advantage of temporary deadweight G. E. on 3/14/83. Schedule recovery place until all permanent deadweight hangers that were lastalled during pipe has been achieved through resequencing hangers are lastalled. Subseaguent erection sequdace in lieu of permanent work activities. 1 closure of MSRV discharge lines, hydo hangers as required to support closure testing of those lines, and lastallation
- schedule, of quenchers on those lines cannot proceed until the permanent mainsteam hangers are
- 2) Expedite costletion of hangers. Priort-
- 2) Vendor completion of hanger shipment delivered and installed.
tire deliveries so that partial shipments has been expedited from 6/30/83 to can be made. 5/15/83. In addition, hanger manu-i I f acturing and delivery will be priort-SUPOWWtf LOGIC DIAGRAMS tired and partial shipment will com-mence immedIately. so St#9mTION: Mainsteam closures to the RPV will be e,,,,g, TUfW10VER achieved as planned. Dellverles of l aansa steAss a nscuee mainsteam supports will have little I Hassesnoe m M \\ or no tapact to the overall Drywell 8 schedule. J. sesETALL Lance Pere .1 r" J j I INSTALL LAnGE PI PE HafeGEnS r" 1 i (+ OnviuBL I Ct3RRENT STATUS ys,rg I i l
i i t 6. PROJECT SCHEDULE D. SCHEDULE FLEXIBILITY The Integrated Project Schedule (IPS Rev. 3) does not contain a j specific schedular contingency as part of the baseline plan leading to a January 14, 1986 fuel load. However, the bases for implementation of the plan are conservative in addressing total site population,. shiftwork, and overtime; and therefore, provide a wide degree of flexibilty. Current performance is enabling the project to take advantage of this latitude. Minimal overtime (approximately 2%) is being worked, site population has been held down (2,648 equivalent men) and shiftwork is low (19%); while at the same time we are meeting our overall schedule requirements. Combinations of additional overtime and/or shiftwork will be applied to critical areas where effective. In addition, the project is evaluating other construction work schedule alternatives, which could further increase labor resource flexibility. The engineering and procurement efforts have been, and continue to .be, sufficiently in advance of the overall construction requirements and provide a substantial backlog of available work. This provides further flexibility in that productive work can be accomplished if problems are encountered requiring reassignment or workarounds. In the near future, several other Bechtel nuclear jobs are nearing completion, which will provide a pool of experienced and qualified technical personnel. They can be mobilized rapidly to respond to any ( emergent issue. This may be of particular benefit during the startup program, where PSE&G's permanent forces could be supplemented to 4 advantage with additional experienced personnel. e i f l i 1 (; 's NRC 3 (B-1) l 6.10 = _ - - r r -w
6. PROJECT SCHEDULE (f 'E.
SUMMARY
In sumary, the Integrated Project Schedule provides ready visibility of the overall plan _ and progress. Through the constant monitoring of the plan, the project will identify deviations and, if necessary, utilize the flexibility inherent in the plan to accomplish corrective actions. This flexibility in all phases of the project yields a high . degree of confidence in the ability to support the January 1986 fuel i load.' 4 9 e
- {-;'
NRC 2 (B-2) ' 6.11. ...--.z-...
s, p ^ i HOPE CRt:t:EK GENERATING STATION l lPS GROUP BLOCK DIAGRAM ENGINEERING & STARTUP & TEST CONSTRUCTION LOGIC LOGIC PSE&G l BECHTEL l o INTEGRATE A INTEGRATED m PROJECT PLAN i m i L r ENGINEERING and/or ENGINEERING and/or STARTUP CHANGES CONSTRUCTION CONSTRUCTION / ONLY l CHANGES ONLY STARTUP CHANGES l APPROVED IPS GROUP EVALUATION I DISAPPROVED EXECUTE PER BASE PLAN
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HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST (' \\- 7. BULK COMMODITIES Question: Detailed review and current status of bulk quantities including current estimated quantities, quantities installed to date, quantities scheduled to date, current percent complete for each, actual versus forecast installation rates, in cubic yards /mo., linear feet /mo. or number /mo., and basis for figures. A. INTRODUCTION The bulk quantities for the project were reviewed and updated for current design information during Forecast 3 preparation. Following completion of the forecast, the project controls quantity changes through the Project Change Procedure. Over the six months since the forecast there have not been any significant quantity changes identified. The project has a high confidence level in maintaining the forecast quantities. The Forecast 3 quantities have been loaded into the Integrated Project Schedule. The resource leveled schedule has defined the following bulk installation curves. The to-go installation rates are on tne high end of the history spectrum, but the project is confident in achieving them. The curves have been statused through March,1983. (- B. BULK COMMODITY STATUS Quantities Installed TOTAL TO DATE COMMODITY ESTIWATED SCHEDULED ACTUAI~ VARIANCE CPT. LARCE PIPE (LF) 310,800 227,000 230,900 +3,900 74 LARGE PIPE HANGERS (EA) 15,300 8,2G5 8,840 + 635 58 SMALL PIPE (LF) 230,000 53,400 58,500 +5,100 25 CABLE TRAY (LF) 121,000 82,400 89,400 +7,000 74 CONOUIT (LF) 375,000 152,670 127,700 .-26,910 34 WIRE AND CABLE (LF) 5,632,000 304,360 172,200 -132,160 3 TERMINATIONS (EA) 231,800 6,790 0 -6,790 0 HVAC (LBS) 2,904.000 1.070,000 1,120,000 +50,000 38 4 NRC 2 (A-12) 7.1
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- 7.. BULK COM 001 TIES
~ C. BULK COMMODITIES Large Pipe: Currently large pipe is approximately 3,900 LF ahead of schedule with 230,900 LF installed to date or 74% of the total 310,800 LF. Large pipe installation will be over exceed 90% complete by the end of 1983. 1 ' i NRC 2 (A-18) 7.3-
i i 6 I i I ?. ElI S. :: I I " s a g *~ ] e x s a i s I A --,v a g a a I 3 = g g L a a r tif .I g 5 I 3 i g s e e s ! I :g3 a.__ + 8 2 v z z a a t e s g g -e= n ____ g s s 1 g. l g t 5 - c 3 C' W ' 'y. E g l g 5 g i a e e l v, l l l g 4 g *, L \\ 3 'i \\ } 3 \\ t t \\[ e6 0% i i i 5 Ie i g3 o f' Nj's. 5 [ D.NE I I I E J O 'hd { t i 3 WA t i gg 13i ? V% 1 6 4 $2 i O tt-I W,s t g E !M tN it EW 3 I ti i i i 49: s ii n '<a's i Wil 'A i ii j i y& V e i >W 3Qg i i i 3 \\\\* e i 1% l l IYL tb 6'd A i a l o a \\ i i a i 6% i m. i a it i i o 'i l 6 \\_ i i 2 i i i t e iT [' 1N = \\ t t I I l \\ 4 4 j ( gi i I (s l 1; i x U' e s i 4 i il 1 ii \\ "g g og 3 I 1 i 1 4 9 i til I I \\.' 8 e 4 \\ I ~4\\ I t\\ l l b -g Se O i \\ i. 4\\ o Ie t '1.1 t i O8 = 1 t i 7 i i\\ 58 4 i t a g i !+ g i V g 'l t t ~ a 1 3 ( g E o a \\ E. 0 \\ s 155 h 11 8 ll It ll l l ll 11 Il at -g 5 a m mu rmna R E R Iv I l!l" 7 I g' E E s k i n { m 8 o 8 E g t p g i d'l4l ! 8 I )E E W ( g e w w 7.4 . +.... -.
7. BULK COMMODITIES k~ C. BULK COMMODITIES Large Pipe Hangers: Currently large pipe hangers are 635 hangers ahead of schedule with 8,840 hangers installed to date or 58% of the 15,300 total hangers. As displayed in Section 5, 87% of the hangers installed to date have received final acceptance status. The IPS program has 80% of the-large. pipe hangers installed by the end of 1983. The project, however, is working to a one year consruction schedule which will achieve approximately 87% installation by the end of 1983, No major problems are anticipated which would restrain the planned IPS installation. d t 1 NRC 2 (A-19)- 7.5 74
<} j;i ,I '[ 0 0 0 A 0 00 ll Iy \\' D E 0 0 0 T 0 00 ll I 9 7 2 D 4 51 9 4 6 3 95 T 0 + il 0 O 0 5 5 9 9 S 0 F . 0 j A e 3 e 2 0 0 0!l3 J t 0 5 5 0 0 N 5 0 9 2 0 C O 9 S 5 49 !l/ 2, 2 I 3 J 1 8 I 5 8 5 Il H F 8 S S 1 1 l a + T v M ) F E A E I L ) R F ll ) L O E F ( ll / M L M T I N N A D F D E O O ll O ( ) F L T ) I s J O A F T E F t ) ) T 0 ll 0 R. I F (LllM A ( 1 9 T D L )% L F C E C 0 D M D D R O U T 8 U ) ( 1 J D T E (L E T R N N E H N E E L C T R L ClIS N O O T c I I A R O U L N S P U L N lIO A A A H T R C T R R M to N D A A I I T T O L D A A D A ,P_ E U I C A E U S 8 C C A T H T RlI A y, E U U S A V O C C A lI L T S A V S D D D. / 4 J / 9 9 1 J 3 / 7 [ 5 2 ~ _ M ~ - A / J M f F J L J / j b E D I-TCP N F;/ E I P N c s J O Fr '7 p O [ a / R L P F S L L b
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7. BULK COMMODITIES-( C. BULK COW 40DITIES Small Pipe: . Currently small pipe is approximately 5100 LF' ahead of the IPS requirements with 58,100 LF installed to date or 25% of the total 230,000 LF. The IPS plan will result in a small pipe installation status of approximately 57% complete by the end of 1983. As with the large pipe hangers, the one year construction schedule has established a small pipe work plan which will yield a 5% acceleration over the 1983 IPS requirements. No major problems are anticipated which would restrain the planned IPS installation. 4 0 l ~f NRC 2 (A-8) 7.7
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=. .7. BULK COMMODITIES C.- BULK CO M DITIES A Cable Tray: Cable tray-is approximately 7,000 LF ahead of the IPS requirement with 89,400 LF installed to date or 46% of. the total 121,000 LF. Over 90% - of the tray quantity will be installed by the end of 1983. Planned installation rates will be maintained. ~ i i ....----a. L ( 2 i i NRC 2 (A-6) - 7.9
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'7.. BULK COMODITIES 4 - C. BULK COMMODITIES . ( Conduit: Conduit is 26,970 LF behind schedule with 125,700 LF installed to date or 34% of the total 3M,000 LF. As discussed in Section 1, recovery actions are being implemented. These actions include assignment of additional'experinced field engineers tc support the installation efforts and planned increases in shiftwork. These actions and the- ];' ~ detailed work sequencing are incorporated into the one year construction schedule and will provide a recovery to the IPS plan by the third quarter of 1983. 4 i j i i f d t t 4 I NRC 2 (A-9) 7.11 + w w w. ,----,y-
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II 7. BULK COMMODITIES 7 C. BULK COMMODITIES Wire & Cable: Wire & cable is 132,160 LF behind schedule with 172,200 LF installed to date or 3% of the total.5,632,000 LF. - This status excludes an additional ~ 60,000 LF of switchyard cable which has been pulled but is not considered part of the generating station. The j initial cable pulling installation rates are lower than planned primarily due to the current raceway status. Raceway recovery actions are being implemented and wire & cable rates will begin to show improvements. Although cable pulling is behind schedule, pull package preparation is proceeding. To date approximately 1,400 pull packages (1,600,000 LF) have been prepared. The individual pull package includes a listing of outstanding raceway sections which must be completed in order to release the package. These individual raceways are being given special emphasis as part of the raceway installation effort. The current project plan is to work under the philosophy of maintaining a slower initial cable pulling effort until a sufficient backlog of raceway is installed; thus minimizing the coiling of pulled cable and its potential. problems. The IPS planned cable installation will be recovered in the 3rd quarter of 1983. ' NRC 2 (A-10) 7.13 y
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l 7.' BULK COMMODITIES C. BULK COMMODITIES { Terminations: Although teminations were scheduled in the IPS to start in January 1983, the effective start will be delayed until May 1983. This delay is due to the delayed status of wire & cable and the project's desire to have a sufficient backlog of terminations available prior to starting This delay in the start of terminations will not have an adverse impact on the overall plan and will not delay any scheduled system's turnover dates. e o em omenm mmm s 8 j k i i NRC 2 (A-20) 7.15
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- t# E gM i
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7. BULK COMMODITIES C. BULK' COMMODITIES HVAC: HVAC duct & supports are 50,000 lbs. -ahead of the IPS requirement with 1,120,000 lbs. installed to date or 38% of the total 2,904,000 lbs. This current status reflects the successful implementation of corrective actions to bring a problem area back in line with the overall schedule requirements. The HVAC progress will continue to be closely monitored as work continues towards the planned 90% completion in early 1984. 4 f I 5 l NRC 2 (A-21) 7.17
l l 7. BULK COMMODITIES -( D.
SUMMARY
L Progress on the piping bulk commodities is meeting or exceeding the plan required to support fuel load. Although this effort is expected to continue on or ahead of plan, it will be closely monitored for any indications of potential problems. Cable tray installation is in the advanced stages and ahead of the project plan. Conduit is currently behind schedule but recovery actions have been implemented and this commodity will be back on schedule by August of this year. Wire & cable and terminations, while experiencing a slower than anticipated start, will recover to the IPS plan before the end of 1983. Due to the advenced completion of both cable tray and conduit which will be achieved in the later half of 1983,' the sustained wire & cable and termination rates will be supported. In total, the project at this time expects bulk commodity installations to support the startup operations. NRC 2 (A-22) 7.18
li -M a
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST y
- 8.
STARTUP \\." Question: Detailed review' and current status of preparation of preop and acceptance test procedures, integration of preop and acceptance 4 l' test activities with construction schedule, system turnover-schedule, preop and acceptance tests schedule, current and proposed preop and acceptance tests program manpower. ~A. INTRODUCTION j The Startup Group at Hope Creek is responsible for testing and maintaining components and systems after turnover from construction until fuel load. It is an integrated group comprised of Public Service engineering, construction and operations personnel as well as Bechtel,-General Electric and other contract personnel working within a single organization. Technical craft support.is provided by Public Service operations personnel supplemented by contract personnel who also work within the startup group organization. At this point, the startup program is well established. Administrative i procedures are approved in place; a testing schedule was formulated i and integrated with the construction schedule; system scoping and turnover boundaries are being finalized; generic procedures are now in the approval cycle, and preoperational procedures are being drafted. ( The program places priority on early planning, highly experienced ( testing personnel, and maximum utilization of.our operating department i personnel. 1 The following listing provides clarification of interface responsibil-ities through the-startup phase.. Generally, Phase I is construction verification, Phase II is initial operation and preoperational i testing, and Phase III is the fuel loading and power ascension phase. PHASE I l a. Perform Hydro Tests
- b. -Megger Cables and Equipment j
c. Rotation Equipment Alignment and Coupling l d. Initially Energize and Calibrate Circuits (PSE&G craftsmen) e. Perform Walkdown and Turnover PHASE II i a. Initially Energize Power Systems b. Perform Cleanness Verification Flushing c.. Run-in and Test Rotating Equipment d. Perform System Preoperational Tests PHASE III a. Fuel Load and Critical Items b. Power Tests l MtC 3 (A-1) ~ 8.1 -. = ~
'8. STARTUP l C 8. PROGRAM STATUS i Summary Status - Test Group Activ'ities i A summary of our current test group activities is provided on the next page. The major thrust at this point is the completion of the generic test procedures, and initial draft of the preoperational test procedures. Station operations procedures related to operations, instrumentation and controls and chemistry are also in progress and targeted to support testing. Also illustrated is the progress made in purchasing test equipment and the projected early testing activities. The Auxiliary Boiler House will be turned over early to completely exercise the construction completion, turnover, testing, outstanding items, and configuration control programs. The Integrated Project Schedule includes the early turnover of the Control Room Complex in December 1983. This represents a turnover of most of the plant systems' controls and will permit early resolution of problems so that subsequent system turnovers will incur minimum control system related delays. t As illustrated, the remainder of plant testing will commence with turnover (- of plant DC system in the first quarter of 1984. Switchyard testing is expected to commence this summer and energization is scheduled for May 1, 1984. NRC 3 ( A-2 ) 8.2
1 O [ \\, HOPE CREEK GENERATING STATION TEST GROUP ACTIVITIES SCHEDULE 1 ACTIVITIES 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 STARTUP GROUP PROCEDURES ADMINISTRATIVE PROCEDURES COM'LETE (6/82 i GENERIC TEST PROCEDURES "A 9/82 PREOPERATIONAL PROCEDURES _ar,A7,A ,,A,,,,,j 3/82 SYSTEM SCOPING NUCLEAR DEPARTMENT PROCEDURES - STATION ' ? OPERATIONS w OPERATIONS 11/82 -ra mmmmm FMAFmmmmad rad ihC 12/82 mvosvamm vammemamammda 11/82 -,sya,r,,r,ay,ay,aysser s syrs,yss CHEMISTRY POWER ASCENSION m vmammammmmma MAlNTENANCE 1183 varavaravmavms waswasvaravs.vs,am. FUEL HANDLING rmeramme PURCHASE OF TEST EQUIPMENT -mmmmmmmmm BOILER HOUSE TESTING V I FUEL CONTROL ROOM COMPLEX TESTING LOA 0 PLANT TESTING
8. STARTUP B. PROGRAMSTATUS(Continued) Startup Administrative Procedures There are currently 24 startup administrative procedures (SAP's) which define and provide administrative direction to the Phase II test program. Twenty-three (23) are approved, in place, and make up the Startup Administrative Manual. Following is a list of the procedures in that manual. SAP NO. TITLE 1 Test and Startup Program Introduction and Outline 2 Organiation and Responsibilities 3 Bechtel/Public Service Startup Interface Activities i 4 Administrative Manual Procedure Control 5 Component / System Turnover and Jurisdictional Tagging 6 Startup Quality Assuance Program Interface 7 System Test Plan 8 Startup Safety Tagging Procedure 9 Corrective and Preventive Maintenance 10 Startup Deviation Report Program 11 Startup Work Authorization (' 12 Design Change and Retest Control 13 Vendor Services Control 14 Preoperational Test Review Committee 15 Personnel Certification 16 Document Control ano Records Receipt 17 Startup Correspondence and File Control 18 Temporary Modifications Control 19 Measuring and Test Equipment Control 20 General and Detail Test Procedure, Format and Instructions 21 Contractor /Public Service Startup Interf ace Activities 22 General Work Procedures (under review) 23 Design Information Request 24 Preoperational Test Procedure, Format and Instructions j l 5 NRC3(A-3) 8.4
8. STARTUP B. PROGRAM STATUS (Continued) s Generic Test Procedures Our general test procedures provide generic test instructions, s criteria and objectives. These will be utilized for those types of activities which have the same testing requirements from system to system. Following is a list of our general.est procedures and their review / approval status. STATUS 1 General Flushing and Cleaning Procedure Issued fo'^ Comment r 2 General Instrument Calibration Procedure for Field Devices Issued for Approval 3 Instrument and Control Functional Loop Calibration Issued for Approval !~ 4 General Field Pressure Leak Test Procedure Issued for Comment 5 HVAC Pressure and Leak Rate Testing Issued for Comment 6 HVAC Testing and Balancing Issued for Comment 7 Cable Continuity and Integrity Testing Issued for Comment 8 Motor Operated Valve and Controls Issued for Comment Functional Checkout 9 Rotating Equipment and Controls Issued for Comment 10 Heat Trace Testing Issued for Comment ( 11 Computer Point Checkout and Verification Issued for Comment 12 Air Operated Valve / Damper Issued for Comment 13 Control Room Integrated Testing / Initial Issued for Comment 14 Digital Control Circuit Checkout Issued for Comment Engergization of Electrical Equipment 15 Illuminated Window Type Annunciator Test Issued for Comment Procedure 16 Vibration Analysis Issued for Conment h u NRC 3 (A-4) 8.5
..u =. u- ~. L ~8. STARTUP B. PROGRAM STATUS (Continued) -(: a j' System Turnover Plans Our system turnover plans provide a comprehensive review of turnover boundary requirements. On the basis of flushing needs, test boundaries, or-other special boundary considerations, system scoping is reviewed, i-revised, and maintained on drawings and equipment indices. The initial scoping effort was completed in mid-1982. This current - review, which includes both field construction and startup personnel, is expected to be complete by May 1,1983. The result is a turnover boundary for each system which is clearly ~ defined and understood by the construction and testing forces, and directly related to the integrated-schedule. ~ Preoperational Test Procedures [ Preoperational test procedures are the highest order of technical procedures in the Phase II test program. It should be noted that at Hope Creek " Acceptance Tests" are titled "Preoperational Tests". These procedures are being drafted on site. l Data packages, which include drawings, specifications, and sorted equipment indices, are being prepared, assembled in conjunction with f 5 engineering-and forwarded to the site. This effort is more than half complete. These packages will reduce the field development time while maintaining the advantages of site preoperational procedure deveopment. This approach is expected to minimize overall procedure preparation and approval time. 4 i NRC 3 (A-5) 8.6 v -y-r-w w r-9--m-9 -e-- - - + - se w-i-- ---ww e-rw=--w-- ,1 7 e sm- +c--= ="'
- m
P / 8.. STARTUP l B. PROGRAM STATUS'(Continued) Integration of' Test Activities with Construction The testing schedule of systems from turnover to fuel load was first . produced on a system basis, with appropriate restraints with related systems..It was produced as a stand alone schedule using the expertise and experience from Public Service Electric & Gas, Bechtel, General Electric, and other project's startup managers. This schedule was then integrated with the project schedule and became part of the Integrated Project Schedule. SYSTEM TURNOVER AND PREOPERATIONAL TEST SCHEDb.E~ DATES TEST SCHEDULED PRE 0P TEST NUMBER DESCRIPTION TURNOVER DATE START DATE AB-1 . Main Steam 02/85 08/85 AC-1 Main Turbine 01/85 07/85 AD Condensate 12 /84 08/85 AE-1 Feedwater 12/84 08/85 AF-1 Extraction Steam, Vents & Drains 12/84-08/85 AK-l' Condensate Demineralizer 01/85 08/85 ('- AM-1 Fresh Water Supply 02/84 11/84 AN-1 Demineralized Water Makeup, Storage & Transfer 07/84' 08/85 AP-1 Condensate Storage & Transfer 11/84 08/85 ~AQ-1 Condensate & Feedwater Chemical Control-(AE) 08/85 -BB-1 Nuclear Boiler & Recirculation 01/85' 09/85 11/85 88-2 Integrated ECCS Loss of Power 09/85 BB-3 RPV Internals Vibration Test BC Residual Heat Removal. 02/85-09/85 BD-1 Reactor. Core Isolation Cooling 02/85 06/85 BE-1 Reactor. Core Spray .02/85 05/85 BF-1 ' Control Rod Drive. 04/85 10/85-BG-1 Reactor Water Cleanup 01/85 05/85 BH-1. ' Standby Liquid Control 02/85 06/85 'BJ-1 High Pressure Coolant Injection 02/85 07/85 BN _ Refueling Water Transfer 09/84. 03/85 CA ' Turbine Sealing Steam -12/84 07/85 CB-1 Main Turbine & Generator Lube Oil 01/85 05/85 CC Generator Gas Control 12 /84 06/85 'CD-1; Hydrogen Seal Oil 01/85 '06/85 1CE-1 Stator' Cooling - 12/84 ~ 02/85 CF-1 Lube Oil Sturage, Transfer & Purification 12 / 84 03/85 'CG-l' ~ Condenser Air Removal-12 /84 06/85 CH-1 'MainTurbineControl-011'(EHC) 03/85 05/85 CJ-1 RFP Turbine Lube Oil 12 /84 08/85 DA-1: Circulating Water 12 /84 _08/85 J DB-1 Cooling Tower '11/84 05/85 DD Circulating Water Hypochlorination 02/85 03/85 DE-1 . Circulating Water Acid Injection 11/84 03/85
- DF-1 Cooling Tower Breakdown. Dechlorination (EA) 08/85
' Station Service Water ~10/84 08/85 EA-1. Mtc 3I(A-6) 8.7
'8; STARTUP~ 8. PROGRAM STATUS (Continued) - System Turnover and Preoprational Test Schedule Dates (Continued) TEST SCHEDULED PREOP TEST NUMBER DESCRIPTION TURNOVER DATE START DATE EC-li Fuel Pool Cooling & Cleanup 02/85 03/85 ED-1 Reactor Auxiliaries Cooling 11/84 12 /84 EE-1 Torus Water Cleanup 01/85 08/85 EG-1 -Safety & Turbine Auxiliaries Cooling 11/84 08/85 EP-1 ' Service Water Traveling Screens & Screenwash 10/84 11/84 EQ-1 _ Service Water Hypochlorination-03/85 05/85 FA-1 Auxiliary Boiler 09/84 08/85 GA-1 Plant Heating 11/84 02/85 GB-1 Plant' Chilled Water 12 /84 08/85 GC-1_ Administration Building HVAC 11/84 03/85 GD-1 -Fire Pump House HVAC 11/84 12 /84 GE-1 Turbine Building HVAC-12 /84 05/85 GF-1 Miscellaneous Buildings HVAC 11/84 12 /84 - - GH-1 Radwaste Area HVAC 05/85 07/85 LGJ Control Area Chilled Water 05/85 07/85 GK-1 Control & Wing Area HVAC 04/85 07/85 GL-1 Service Area HVAC 08/85 09/85 GM-1. Diesel Generator-Area HVAC 05/85 07/85 GP-1 . Primary Containment Leakage Rate Testing 08/85-11/85 (. GQ-1 Intake Structure HVAC 10/84 -11/84 GR-1 Reactor Building HVAC 02/85 07/85 GS-1 Containment Atmosphere Control 04/85 05/85 GT-1_ Drywell Ventilation 01/85 06/85 GU-1 Filtration, Recirculation & Ventilation System (FRVS) 02/85 05/85' HA-1 Gaseous Radwaste 11/84 10/85 HB-1 Liquid Radwaste 11/84 - 10/85 HC-1 Solid Radwaste 05/85 10/85 HD-1 Decontamination Facilities 05/85. 09/85 HH-1 Radioactive Laundry 07/85 08/85 .JA-1 Auxiliary Boiler Fuel Oil Storage & Transfer 09/84 10/84 JE-1 Diesel Fuel Oil Transfer'& Storage 07/85 08/85 KA-l~ Service Compressed Air. 07/84 12 /84 KB-1. Instrument Compressed Air 07.84 12 /84 KC-1 Fire Protection 10/84-12 /84 KD-1 Domestic Water 11/84 03/85 -KE _ Fuel Handling & Reactor Vessel Servicing - 01/85 03/85 KF-1 Cranes, Hoists & Elevators 11/84 07/85 KG Breathing Air (XX) 05/85 KH-1 Plant Service Gases 06/85 07/85 KJ-1 Emergency Diesel Generators-. 04/85 09/85 KL-l' Primary Containment Instrument Gas 11/84 06/85 KP-1 MSIV Sealing 05/85 07/85 LA-1 Building Sewage 11/84 11/84 'LB-1 Storm Drains 09/84- -06/85 NRC3'(A-7) 8.8
m 4
- 8. 'STARTUP
- 8. _ PROGRAM STATUS (Continued)
[, System Turnover and Preoperation Test Schedule Dates (Continued) 4 - TEST SCHEDULED PRE 0P TEST -NUMBER DESCRIPTION TURNOVER DATE START DATE *~ I-LD-1 Chemical Waste 09/85 10/85 LE-1 Oily Waste 11/84 12 /84 LF-1 -Normal Drains 09/84 10/84 LG-l' Floor Water Collection (LF) 10/84 MA-l ' Main Generator' 08/84 06/85 2-1 --
- Switchyard Buses, 13KV, 500KV, EHV Phase I 02/84 05/84
, 2-2 Outgoing EHV Lines, Phase II 06/84 09/85 i NA-1 7.2KV Station Power 07/84 09/84 L N8-1 4.16KV Station Power 06/84-09/84 NG-1 ~480V Unit Substation Power. 06/84 01/85 4 NH-1 !480V MCC Power 06/84 10/84 NJ-l' 250V DC Power 10/84 11/84 NK-l' 125V DC Power 03/84 09/84 NQ-1 120V AC Power - 05/84 10/84 P8-1 4.16KV Class 1E Station Power 06/84 08/84 PG-1 480V Class 1E Unit Substation Power 06/84 10/84 PH-1 480V Class IE MCC Power .06/84 02 /85 - PJ-1 250V DC Class IE Power 05/84 07/84 l PK 125V DC Class 1E Power 03/84 08/84 l -PL-1 24V DC Power 09/84 10/84 f; ' PN-1 Class 1E 120V AC Power 05/84 '08/84 QA-1 Normal Lighting (120/280V & 480/277V. Power) 11/84 -04/85 \\ ~ 08-1 Essential.&-Standy Lighting ~06/85 07/85 QC-1 Yard, Roadway & Security Fence Lighting 11/84 11/84-QF-1 In-plant Communication ' 10/84 05/85 n 'QG-1 Grounding (XX) .11/84 11/84 QH-1 Cathodic Protection 11/84 11/84 QJ-l Freeze Protection-11/84 12 /84 .QK-1 Fire / Smoke Detection & Alarm 08/84 05/85 [ RC-1 Process Sampling ~ 03/85 09/85. RD-1 Meteorological Instrumentation. 08/84 09/84-RF-1 Environmental Monitoring - 08/84 09/84 ~ RG-1 Plant Security 05/85_ 09/85 RJ-l PlantComputer(RA) 12 /83 05/84 S8-1 Reactor Protection. 12/84 06/85 1 SC-1 Reactor Instrumentation 04/85 05/85 F SD-1 -; Area Radiation Monitoring- .04/85 05/85 [ SE-1 Neutron Monitoring 12 /84 02 /85 SF-1 Reactor _ Manual Control ' 12 /84 06/85 SG-1 Seismic' Instrumentation 04/84 05/85 .SK-1 ' Plant (Steam) Leak Detection. 05/84-06/85' SL-1 ~ Reactor Building Pressure Relief (GU) 05/85 SM-1 . Nuclear Steam Supply Shutoff 02/85 06/85 t SN Automatic Depressurization 04/85 05/85
- SP-1 Process Radiation Monitoring.
07/85 08/85 SS-1 Rotating Machinery Vibration Monitoring '11/84-12 /85 10/84 7 ST-1 (Transient Monitoring l NAC3-(A-8)' L 8.9
8. STARTUP B. PROGRAMSTATUS_(Continued) System Turnover and Preoperation Test Schedule' Dates (Continued) + System turnovers not requiring preoperational testing. TEST SCHEDULED PREOP TEST NUMBER DESCRIPTION TURNOVER DATE START DATE Stahdby AC Power (PEA) 10/84 OffsiteCommunications(QEA) 11/84 -Offsite Communication (QLA) 08/84 Motor Operated Doors (QMA) 11/84 Closed Circuit TV (RHA) 08/85 Storm Drains (LB). 09/84 Normal Drains (LF) 09/84 i I ([ NRC 3 (A-9) 8.10
4 '~
- 8. 'STARTUP C.
PROCEDURES REQUIRED FOR FUEL LOAD Below is a listing by type, total number"and status of procedures required for. fuel load. Total Number of Procedures for Fuel Load IN NOT PROCEDURE TYPE TOTAL,APPRVD REVIEW STARTED STARTED Startup Procedures Startup Admin. Procedures SAP 24 23 1 0 0 System Flush Outlines 64 64 System Turnover Plans 1 32 98 34 Generic Procedures 16 13 3 Preoperational Test Procedures 12 4 1 65 - 58 Station Procedures Adminstrative Procedures 29 1 5 7 16 Station Operating Procedures Admin./ Directives / General 37 37 Operating Procedures / Instructions 151 10 8 133 (' Surveillance / Alarm Responses To be scoped Abnormal / Emergency Procedures 42 42 Station Technical Procedures I&C Administrative Procedures 14 J-6 8 I&C Calib./ Test Surveillance Proced. 950 41 5 904 2 I&C Maintenance Procedures 50 50 Chemistry Administrative Procedures 9 -2 1 6 Chemistry Calib./ Test / Emergency 95 18 1 76 Chemistry Sampling Procedures 82 1 81 Chemistry Miscellaneous-69 3 ~1 65 Technical Document Control 25 25 i Technical Miscellaneous 17 17 Fuel Management 6 6 Power Ascension Tests 39 39 4 5 NRC 3 (A-15) +. 8.11 s
8. STARTUP C. PROCEDURES REQUIRED FOR FUEL LOAD (Continued) ' ( Total Number of Procedures for Fuel Load IN NOT PROCEDURE TYPE TOTAL APPRVD REVIEW STARTED STARTED Station Maintenance Procedures Administrative Procedures 13 1 10 2 General Procedures 24 14 10 Corrective / Prevent. Maint. Procedure 1 72 1 1 170 Welding Procedures 26 26 Surveillance " 30 30 Calibration 19 19 Fuel Handling 13 13 Station Radiation Protection Procedures Administrative / Training 36 1 35 Calibration / Surveillance / Abnormal 52 52 Operating /0verall 87 87 Preventive Maintenance 17 17 Nuclear Dept. Support Procedures ( Security Procedures Procedures presently in place at Emergency Plan & Procedures. Salem will be modified and Quality Assurance / Quality Control expanded. In-Service Inspection 4 F 1 NRC3(A-10) d 8.12
8. STARTUP D. MANPOWER PLAN ~ The following is the current and projected manpower to support the. Preoperational Test Program (Phase II) to fuel load: CURRENT PROJECTED Startup Group Senior Supervisors 7 9 Test Engineers 17 56 / T/A Clerical Support 5 10 Contract Technicians 0 40 Station Group Tech. Dept. Supervisors 7 8 Tech. Dept. Technicians-15 26 Tech. Dept. Assistants 12 23 Maintenance Dept.- Supervisors 6 9 Maintenance Dept. Electricians 10 16 Maintenance Dept. Machinists 5 10 Maintenance Dept. Mechanics - 10 45 Operations Dept. Supervisors 20 20 (. Operations Dept. Operators 32 55 TOTAL 146 32 7 NRC 3 (A-12 ) ' 8.13
.m p ~. 8. STARTUP E. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEMS CORRECTIVE ACTION CURRENT STATUS
- 1) Aggressive testing rchedule
- Early turnover of Control Room
- 0n schedule for 12/15/83.
Complex for early problem resolution
- Reduce schedule compression
- IPSG review in progress.
- Minimize construction overlap
- Current schedule calls for after turnover.
90% construction complete at 4KV energization. 4.
- Reduce test document support
- Computer facilities in place duration through maximum use of 1st week of April 1983. Software computer being developed.
- Provide early turnover of electrical
- Administrative procedures partially
- ,m and instrument & control components approved, remainder under review.
g for expedited problem resolution This basis is included in IPS.
- 2) Project learning curve
' Advancement of turnover of the
- Early walkdown and resultant associated with new Auxiliary Boiler to August 1983 problem / action list being startup program to exercise administrative, technical developed and work procedures l
4 NRC 3 (A-13)
n p 8. STARTUP E. PROBLEMS / SOLUTIONS (Continued) i i i DESCRIPTION OF PROBLEMS CORRECTIVE ACTION i CURRENT STATUS
- 3) Shortage of qualified
- Aggressiverecruitmentof! permanent.
- Currently 21 of 24 test engineers personnel temporary, and experienced personnel.
and supervisors in the startup group are permanent employees and have prior nuclear experience.
- Make arrangements for temporary
- 0ne individual is temporarily assignment of personnel to plants assigned to the Limerick startup currently into testing, group.
- Supplement PSE&G startup with
- Current completion of Susquehanna experienced personnel (BPC, and Limerick is consistent with G.E. and others).
this approach.
- 4) Increasing scope of testing
- Maintaining communication with other
- Currently attending Limerick
?" by regulation or plant sites, and other avenues such as monthly startup meetings. E; experience Notepad (INPO) to insure early Maintaining communications notification and planning for other. sites. Member of Notepad any increase in scope. service, all applicable notepad entries are reviewed CONCLUSION The project's early planning and identification and resolution of problems has established a program [ which will support the January 1986 ~ fuel load. NRC 3 (A-14)
~. -8. .STARTUP G..SumARY-The project startup. program is well established.- Administrative . procedures are in place, generic procedures are in the final approval cycle, and preoperational procedures are being drafted. System scoping has been established and turnover boundaries are being finalized. A testing schedule has been established and is integrated with the engineering and construction plan in the Integrated Project Schedule (IPS). Close working relationships between construction and startup have been established and will continue in.the future. The combination of these factors has resulted in a viable startup program which will support the January 1986 Fuel Load. i 1 NRC 4 (B-22) A -8.16
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HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST -9. LICENSING REQUIREMENTS Questions: Detailed discussion of potential schedular influence due to change attributed to NUREG-0737 and other recent licensing requirements. A. INTRODUCTION The schedule influence of the following licensing requirements are addressed. 1. THI (NUREG-0737) ITEM NO. DESCRIPTION I.D.1 Control Room Design Review I.D.2 SPDS/ Safety Parameter Display System 11.8.3 Post Accident Sampling System II.D.3 SRV Position Indication II.F.1 Accident Monitoring Instrumentation II.F.2 Instrumentation for Detection of Inadequate Core Cooling II.K.3.18 Modify ADS - Logic III.A.l.2 Upgrade Emergency Support Facilities ( 2. FireProtectionReview(AppendixR) 3. ATWS ? NRC3(B-10) 9.1
.m 9. LICENSING REQUIREENTS 8. PRO 8LEMS/ SOLUTIONS I DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 1.- TMI (NUREG-0737) General ~ ^ PSE&G will be taking an integrated apprach to the implementation of Emergency Response Facilities.. (TMI items. I.D.1, I.D.2 and III. A.I.2 ). The development of SPDS and E0Ps, the implementation of a CRDR, and the creation of' the TSC and EOF are interrelated and are being carried out concurrently. Provisions for these features are now incorporated isto the plant design. After the integrated approach is verified, the results will be validated on the Hope Creek simulator. This will be an iterative process where refinements to the program can be investigated without disrupting t plant operations. NUREG-0737 ITEM NO. 4 ~ N I.D.1 Control Room Design Review Im September 1977 an Operability Essex Corp. will perform the i (CROR) Analysis was performed using a Control Room Design Review. full scale mock-up. The review Scheduled start is April 1983, was conducted by PSE&G Bechtel, and completion is projected for G.E., and Peach Bottom (Philadelphia December 1984. (The Control Room Electric) operations. We have also must be complete to finish the reviewed the Human Factors surveys review.) _ We expect no great performed by Essex Corp. for the impact from the review since we NRC at Salem and other plants. The have been aware of human factors concerns addressed in those reports concerns for some time. were included in our design. i i t 6 r .j 1 i t CC 2 (8-5)
m s ,+ l TMI I.D.1 CONTROL ROOM DESIGN REVIEW FIELD REVIEW CONSULTANT TO BECHTEL REVISE DRAWINGS IMPLEMENT EVALUATE RECOMMENDATION DEVELOP TO REVIEW TASKS 1 TOIMPLEMENT DESIGN OUT FOR SID - BIDS , AND AWAR% PROGRAM PLAN PROGRAM PLAN THRU 9 DESIGN CHANGEN CHANGES O m n n v v v v v A 2/28/83A 4/11/83 4/24/83 8/12/83 8/15/84 10/1/84 12/84 .w TASKS
- 1) DEVELOP DETAILED SCHEDULE
- 2) CONDUCT OPERATING EXPERIENCE REVIEW
- 3) DEVELOP C/R INVENTORY
- 4) SYSTEM FUNCTIONAL REVIEW AND TASK ANALYSIS
- 5) CONDUCT C/R SURVEYS
- 8) VERIFICATION OF TASK PERFORMANCE CAPABILITIES
- 7) VALIDATION OF C/R FUNCTIONS
- 8) HUMAN ENGINEERING DISCREPANCY (HED) ASSESSMENT
- 9) FINAL REPORT NOTES:
- DESIGN CHANGES TO BE IMPLEMENTED WILL BE BASED ON SCOPE OF HED'S AND COMPLEXITY OF ACCOMPLISHMENT.
- 1) 12/82 DATE PER BLP 13878
- 2) THIS ITEM ASSUMED TO BE AN EXCLUSION FROM THE TURNOVER OF THE CONTROL COMPLEX FOR INTEGRATED TESTING (INCENTIVE FOR MILESTONE NO. 4)
.=. R ,~, ~ 9. LICENSING REQUIREMENTS B. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS I.D.2 Plant Safety Parameter SPDS will be implemented through The Owner's Group is continuing Display System (SPDS) the existing Control Room to refine the displays. Their Integrated Display System (CRIDS). program should be complete by The displays will be based on the the end of the year. We expect displays developed by the BWR these refinements of consist of Owner's Group. Most of the of only software changes, variables required are already incorporated into CRIDS design. Bechtel has been directed to incorporate the few remaining variables. / b NRC 2 (B-3)
A i TMII.D.2 PLANT SAFTEY PARAMETER DISPLAY SYSTEM (SPDS) ~(ERFDAS/RMS/CRIDS INTERFACE) i o i ENGINEERING FOR DEFINE ADDITIONAL PSE&G DIRECTION i TO ADD INPUTS BECHTEL DESIGN DATA BASE EQUIPMENT & REQUEST EVALUATE & FOR SPDS EVALUATION ADDITIONS SOFTWARE OUOTE APPROVE FAB & DEllVER b n m n n m j g v v v v fu A 4/15/83 / 5/15/83 8/15/83 7/1/83 9/1/83 8/28/83 ( i'
- om 3/13/83
/ ~___/ I INTERFACE BID REQUEST 1 BECHTEL REVIEW . BID EVALUATION A INTERFACE DEFINITION DSD CODING & UNIT TEST SYSTEM TEST n n n j ev v v v A A ' 5/15/83 7/3/83 7/17/83 10/30/83 2/12/84 2/27/83 3/13/83 l l SOFMARE FUNCTIONAL DESIGN 1 I wism w22/83 l DETAILED SOFTWARE l _ _ _ _ _ _ _ _ { DESIGN Q i 4 8m/83 8/3/83 l 1 I i 1 I 1
..-4.. ~ ,A, 9. LICENSING REQUIREENTS B. PROBLEMS /SQLUTIONS i DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS II.B.3 Post Accident Sampling System The regulations require the plant Design a sample system. HCGS has the GE Posti accident to have the capability to sampling station and the GE sample primary coolant and equipment is on site. 1 the Drywell air space for radiation and certain chemical The attached schedule shows that resolution of this-issue will analyses. support the Integrated Project Schedule.- ' On I 1 i l NRC 2 (B-6) j i
HOPE CREiEK GENERATING STATION POST ACCIDENT SAMPLING (SRW ELEV. 54*. X:909(GE) - M-001) ITEM RESP. 6/28/82A
- 1. ISSUE P&lD M38(2 SHEETS)
CS 9/1/82A 08TAIN CLIENT APPROVAL FREEZE & ISSUE Pal 0 (Rw.0) CS
- 11/1 A
- 2. G.E. VEN00R DRAWINGS APPROVAL CS ALL DW3 RECEI /ED: PAhELONSITE 8/82A
- 3. lSSUE FOUNDATION / SUPPORT DWGS CIVIL 2
- 4. ISSUE CONCEPTUAL LAYOUTSKETCHES PD FINALIZE EQUIPT. LOCATION DWG PD i
12/15A 12/29A 48/83F 5.lSSUE VENT /HVAC DRAWINGS HVAC im FIR EPROTEC Ti m ? S. ISSUE SMALL MMNG DRAWINGS PD PIPipG DWGS ) -(DEMIN. WATER SYST/N2 SUPPLY. II/ISA 2Nh SAMPLING & RECIRC. LINES) gtccg ISSUE SWALL CO4D01T p Aapau 1/ 043A I _ FIRE PFOTECTION DWGS 7.lSSUE SMALL CONOUlT DWGS ELEC SCHEMES ) I' q BLOCK DIAGRAMS & SCHEMES ELEC. C, 2 12/15/82A 12/1 W82A l S.lSSUE DRAINAGE SYSTEM DWGS PLBG g l S. ISSUE DITS No. D5.18 (Rw.) CS C
- ,j, l
- 14. ISSUE FSAR (SECT.1.10 & S.3.2)
CS
- 12/nA i
- 11. INSTALL BULKS ON MODEI, PD C
O 12.lSSUE FIRE DETECTION DWGS MECH n <) AND / OR CRITERIA 2/ IIB 3Aj 4/25/83F
- 13. ROUTE TUSING FROM STATION FIELD FIELD REOUESTS S.P. DWGi,3/10/82A C
- )
14.lS$llSHIELD DRAWINGS (CPWI CIVIL ^ ^ 5/1/83F 15.lSSUE MEMO TO FIEpi FOR CS ACTUA.lZED 8/5/B2A lEMF0219281,1 P (GUIDELINESIN ROUTING / STRESS I %E ALYSIS) A ROVE DWG. VEND.DWi.
- 16. ISSUE LOGIC DIAGRAM CS RFO& ::
2 12, 10A & FAB 1 TE J203 FREEZE N,( INSPI CT
- 17. PROCURE PANELS ACS12 & 8C512(PACSj 5/1/83S CS n
T]/29/83F 4/T6F 4/MF 6/llF 7/lF 2/4/83A e n an.e.
p 9. LICENSING REQUIREE NTS 8. PROBLDtS/ SOLUTIONS DESCRIPTION OF PROSLEM CORRECTIVE ACTION CURRENT STATUS II.D.3 Safety Relief Valve (SRV) Position Indication The NRC requires the plant to Design a valve position monitoring HCGS is evaluating bids for an have positive indication of system. acoustic monitoring system to the open/ closed status of provide position indication. cach safety relief valve. ?m 0 NRC 2 (B-9)
A e JOB 10056 ~ HOPE CREEK GENERATING STATION ACOUSTIC MONITORS (SRVPIS) J-800Q WRITE SPEC I SPEC REVIEW m BY PROJECT,, a l 7/1/82A' " ' '10/29/82A I I INPUT FROM e OTHER DISC. I CLIENTS RESOLVE , COMMENTS & CLIENTS u APPROVAL
- COMMENTS % 6 a
12/21/82A 10/29/82A 12/24/82A I I BID CLIENT AWARD 1/14/83A II ' ' ' C ^ 2/23/83A 4/8/83F 5/8/It3F TS/13/83F 1 1 I / ~ VENDOR FA8 & DEL 7 5/13/83F 8/17/83F 9/15/83F i Sf it' l AM cis 4ou
p ,.m 9. LICENSING REQUIREENTS B. PR08LEMS/SQLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS L l i II.F.1 Accident Monitoring l Instrumentation The NRC requires instruments with Procure instruments with the proper All extended ranges have been increased ranges.so that the plant
- ranges, incorporated into purchase orders.
can monitor post LOCA conditions.
- noble gas effluent monitor
- iodine and particulate monitor t
- containment pressure monitor.
- containment level monitor
- containment Hydrogen monitor 8
4 i NRC 4 (A-21)
p, m TMI H.F.1. ACCIDENT MONITORING INSTRUMENTATION O i PURCHASE CONT. H2O LEVEL MONITOR U-359) & PRESSURE MONITOR (J301) DELIVER INSTALL O v A 6/83 12 M I ? O PURCHASE HIGH RANGE RAD. 4 DELIVER INSTALL MONITOR (J-371) n g 12/84 A 2/84 5 1 ] t
l g 9. LICENSING REQUIREENTS 8. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS l l II.F.2 Instruementation for Detection of Inadequate Core Cooling ( The NRC is interested in additional Provide a description of any HCGS incorporates the BWR Owner's instrumentation to supplement additional instrumentation or controls Group recommendation to use analog I existing instrumentation to measure proposed to supplement instrumentation equipment in place of mechanical RPY coolant level, to provide an unambiguous level level indication equipment. The indication. BWR Owner's Group is working with j the NRC to arrive at a final acceptable resolution. When agree-i l ment is reached with the NRC for l HCGS and other operating BWR's, PSE M will assess what hardware modifications, if any, are required and will define an implementation schedule. e U II.K.3.18 Modify ADS Logic The NRC requires increased auto-Study design of ADS and formulate G.E. had performed a study for matic response of the ADS to recommendation. the BWR owners group and submitted a report (NEDO-24951) to reduce reliance on the operator the NRC on March 31, 1981, to initiate core cooling in The NRC is reviewing the issue some event sequences. and schedule.1 a safety evalua-tion in May 1983. If a modif1-cation is required for Hope Creek, it would involve a circuit modification supplied by G.E. with minimal construction impact. CONCLUSION: All TMI items have'been identified and a schedule implemented which supports the Integrated Project Schedule. - NRC 4 (A-22)
>w g 9. LICENSING REQUIREENTS 8. PROBLEMS /SQLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS III.A.1.2 Upgrade Emergency Support Desiped the Emergency Support The Technical Support Center (TSC) is Facilities Facilities to comply with NRC a two-floor structure located in the requirements. corner of the Reactor Building. The room arrangement has been finalized. Two CRIOS, CRT's and a Meteorological and Radiation Monitoring System CRT will be installed in the facility. The Emergency Operations Fact 11ty (EOF) will be located in the Training Center. which is scheduled for completion in July 1983. The required data will be F transmitted to the EOF via microwave C with a computer telephone line back-up. The above items will support the Integrated Project Schedule. 4 NRC 4 (A-24)
~~ .- s n 9. LICENSING REQUIREE NTS B. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 2. Fire Protection Review 10 CFR 50, Appendix R Evaluate the capability of Define fire zones, design fire The HCGS fire protection evaluation the plant to shutdown given barriers, fire protection system performed in 1977 allowed the a transient combustible fire, and fire detection system. definition of fire barrier design, fire loading and fire zones which Perform safe shutdown review for are now defined in FSAR, Appendix 9A. a fire in each fire zone. Further fire protection reviews In 1977, PSE&G performed a fire were conducted as new requirements, protection evaluation in response became evident and accounted for our to Branch Technical Position 9.5.1. experience at Sales and other ,e . plants. A confirmatory interaction analysis is underway and will be completed 1 by June 15, 1983. Problem areas 4 ' will be corrected in time to support system turnover. HCGS will meet the requirements of 10 CFR 50.55, Appendix R as documented in the FSAR. With the schedule outlined above resolution of this issue will support the Integrated Project Schedule. i I NRC 4 (A-25) /
p m NIONS HOPE CREEK GENERATING STAT!ON FSAR-FIRE PROTECTION EVALUATION (APPENDIX R) COMPLETE COMPLETE ROUTING OF CABLE FIRE RATED WALL DESIGN IN CONTROL & D.G. O (MECH) 12/2/82 (ELEC) 3/28/83A i REVIEW FIRE RATED WALLS O (ELEC) 4/28/83S REROUTE CABLE TO ACCOMODATE THE SHUTDOWN ANALYSISCOMPLYING WITH APPNDX R FIRE PROTECTION EVALUATION m ELECT. MECH. 8/15/83S 5/3 /83S I l IDENTIFY PROSLEMS WITH FSAR 9A COMPLI ANCE MODIFY HVAC PANELS TO ELECT. ISOLATE PREPARE & (QSSUE AMMENDMENT No.1 (PRODUCE COLOR CODED DWGS)' CIRCulT FOR REMOTE OPERATION m / J/28/83A 8/ /83S 9/ 3S I I REVISE & ISSUE ELECT. DWGS FOR CONTROL & A DG 8LDGS. (77*,102* 124* 154') n IMPLEMENT REVISIONS 5/ [/83S CONSTRUCTION 12/84 RECOMMENDATION ON COMMUNICATION SYSTEM CLIENT DECISION IMPLEMENT FOR REMOTE SHUTDOWN -ISSUE BLP & RESPONSE RECOMMENDATION n n (ELEC) 5/[M3F PSE&G (ELECT.) 5 3S to 3 REVIEW & REVISE DITS (D6.12) FOR REMOTE SHUTDOWN PANEL. O (CONTROL SYSTEMS) 5/1/83F l C/S 4086 A .i l
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~.. I p. p 9. LICENSING REQUIREMENTS 8. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 3. ATWS Modification The NRC is~ concerned that the HCGS will include a NUREG - 0460 All functional control diagrams, probability of common mode alternative 3A with manual initia-elementary diagrams and interfacing-failure of the SCRAM system tion. This includes: documents have been issued by should be reduced by various GE. All Bechtel P&ID design modifications. Adding a Redundant Reactivity modifications are completed except . Control System for: for the SLC system, which will One proposed solution is be frozen by May 1983, alternative 3A from NUREG - a. Alternate rod. insertion 0460. b. Recirculation pump. trip 8 out of 14 scram instruments have c. Main steam.line isolation been shipped. The remaining d. FW runback instruments to be shipped 2nd quarter of 1983. The solenoid, Modifying the SCRAM discharge needle valve, vent and drain -a volume with redundant instruments -valves are delivered. and valves. 4 Resolution of this issue will Modifying the standy liquid support the Integrated Project control' system with 2 injection Schedule. pumps in concurrent operation at 86 gpm total. 1 t l 1 NRC 4 ( A-26)
s. A m HOPE CREEK GENERATING STATION ATWS SCHEDULE (EXCLUDING CONTROL PANELS) STANDBY LIQUID CONTROL INSTRUMENT LOC. DRAWINGS ~ i 11/ /82A I I REVISE P&lD FREEZE P&lD l ISSUE S.P. & HANGERS (DISCHARGE) M48 M48 l-T7/2/82A 5/6/83 2/2Y/83A I I I l I e STRESS ANALYSIS ( ISSUE L.P. W i PIPE LAYOUT (COMMON CALC) (SUCTION) m r ir i I DESIGN & ISSUE 0 .P. SUPPORTS (SUCTION) 0 L 1 4 I C/S 4046A
4 j ATWS SCRAM DISCHARGE VOLUME APPROVE FUNDS GE RESUME SUBMITTAL OF FDI 5/15/83 l 6/83F G I I l l l BECHTEL ENG. MODIFY PANELS FIELD MODIFY PANELS 6/15 8/15 12/15/83 4/5/83
nW .i ATWS REDUNDANT REACTIVITY CONTROL SYSTEM (RRCS) 8 NRC DECISION - REQ'D FIX. DRAFT RULE FINAL RULE n 3 7[83 12/83 / DELIVER PANELS INSTALL PANELS GE PANEL MODS n 3A FIX-CHANGES INC. ON P&lD n 3 s w v v A 7/83 10/83 F I E I 8ECHTEL FIELD GE FDl'S FDDR'S PANEL MODS I O n v l 6/83 6/84 I I RRCS QUALIFICATION AND MANUFACTURING RELEASE 5/83 > GENERIC ACTIVITIES I EQUIP QUALIFICATION BY VENDOR TESTING s 5/83 NOTES: @ AFFECTS SYSTEMS: CRD, NS, FW, SLC. RE-CIRC. e @ FW TURNOVER 12/84 @ FIX MAY AFFECT PANELS, INSTRUMENTATION
9. LICENSING REQUIREMENTS I[- C. SUPNARY Resolution of all ten licensing requirements will be accomplished on a schedule that supports the Integrated Project Schedule. 1 i a
- a NRC 4 (B-5) 9.21
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{' -10, 10 CFR 50.55 Question: Discussion of schedular impact, if any, regarding potential deficiencies. reported in accordance with 10 CFR 50.55 (e). A. INTRODUCTION The schedule influence of the following 10 CFR 50.55 (e) ) outstanding items are addressed: MCAR NO. NRC OIL NO. DESCRIPTION 1. MCAR - 25 81-00-04 Limitorque Motor Operator Deficiencies 2. MCAR - 31 81-00-10 HPCI & RCIC Swing Check Valves 3. MCAR - 38 82-00-06 Grout in Drywell Air Gap 4. MCAR - 40 82-00-08 GE I&SE Weld Filler Material 5.. MCAR - 41 82-00-09 0-Rings on Robertshaw Valve (Diesel Generator) 6. MCAR - 42 83-00-01 Scribe Lines on Small Bore Pipe (' 7. MCAR - 43 83-00-02 Weld Defects in Bailey Controls-Cabinets k NRC 4 (A-29) y 10.1 ~
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- 10. 10 CFR 50.55 B.. PROBLEMS /S0LUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS i
1. MCAR #25 Limitorque Motor Operator Deficiencies - Numerous deficencies have been - Suppliers have been requested - Corrective actions will be identified in Limitorque Motor to correct specific deficiencies. completed as part of construction's' completion Operators which include: - Bechtel Supplier Quality Repre-of cable termination of '* improper use of fiber shims sentatives have been directed to all safety-related under contact screws apply expanded inspection criteria operators. (Guidelines for Limitorque Operator
- poor wiring practices Inspection) during inspection'per-formed at valve supplier facilities.
- use of unqualified electrical equipment
- Bechtel Field Engineers will'in-spect all safety-related operators ca ' km
- improper handling of' electrical prior to cable termination.
Inspec-parts tion and rework will be performed in accordance with SWP/P-E-18.
- incorrect use of shaft keys'
- Limitorque Motor Operators are used in many systems required for fac-ility safe shutdown. The deficien-cies noted could cause the operator to fail to function, therefore the problem has been reported under 10 CFR 50.55 (e). 4 .NRC4(B-1)
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- 10. 10 CFR 50.55-B.
PROBLEMS / SOLUTIONS F DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS '2. MCAR #31 - HPCI & RCIC Swing Check Valves Failure of: swing check valves in HPCI To prevent disc failure, the The supplier, Anchor / Darling and RCIC Turbine Exhaust lines has existing hinges will be replaced Valve Company, is in the process bren experienced at other plants. The with hinges of a special design, of modifying the hinges at their failures were the result of excessive such that the open impact is taken facility. The modified hinges fluctuations in exhaust flows, on the hinge rather than on the will be shipped to the jobsite resulting in violent impacts of discs disc stud and nut. in May 1983. on bodies, and ultimate failure of i discs. Modification of the hinges will be controlled by NCR 1439. The problem has been reported under i 10 CFR 50.55 (e). '? 3. MCAR #38 - Grout in Drywell Air. ' Gap After completion of the " Gallery" The deficient condition was docu-Construction will complete -9 rout placement, grout was observed mented on NCR-1815. removal of the grout and inside the air gap sleeves of eight laitance by April 15, 1983. -l i (8) penetrations. As this may have Construction used fiberoptics to ) been caused by a leakage.of grout identify and map the grout and An analysis to determine if into the two inch drywell shield laitance in the air gap system. restoration of the shield wall air gap, blockage of the. air wall is required is under-gap may have occurred.. Project Engineering's evaluation way. 1 of the as-built condition deter-The problem has been reported under mined that removal of the grout 10 CFR 50.55 (e). 'and laitance was required. 4 r NRC 4 (B-2)
s 10.' 10-CFR 50.55 B. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS l 4. MCAR #40 - GE I&SE Weld Filler Material Four (4) CRD Housings were partially GE issued NCR-49 to document and-Corrective actions are complete. melded to the RPV tube stubs by GE/ control the discrepancy. The
- I&SE' personnel, using 308L (stainless affected welds were ground out.
steel) weld filler material instead The CRD Housings were reinstalled of ER-Nicr-3-(Inconel), as required using the correct weld filler by the welding procedure.- material. The condition has been reported under GE/I&SE has replaced the wire issue 10 CFR 50.55'(e). station attendant and color-coded .the identification flags on Inconel wire..GE/I&SE has also provided f' additional instruction to responsible personnel in weld filler material control. 5. MCAR #41 Rings on Robertshaw Valves (Diesel Generators)- Robertshaw Controls Company iden-The 0-rings.were removed from Construction began reworking tified a potential problem with the the poppets of the Robertshaw the equipment on March 22, 1983. / 0-rings on the poppets of:thermo-thermostatic valves on the Corrective actions were / static valves which are used on diesel generator sets located at completed March 28, 1983. diesel generator sets. ;If cooling the jobsite. water is contaminated by diesel fuel, the fuel may cause the 0-ring to swell, resulting in sluggish opera-tion or jamming of the valve. r This condition has been reported under 10 CFR 50.55 (e). NRC 4 (B-8)
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- 10. : 10 CFR 50.55 i
B. PROBLEMS /SQLUTIONS i DESCRIPTION OF PROBLEM CORRECTIVE ACTION ' CURRENT STATUS 6. MCAR #42 -Scribe Lines on Small ' Bore Pipe Proper depth of socket weld fitting A Nonconformance Report (NCR-1939) Actions to correct.the hard-is required to be marked on pipe. was issued to contrc! the hardware ware deficiencies will be prior to installation. discrepancies. completed by April 29, 1983. A tubing cutter was used to scribe Field personnel have determined the The revised General Welding . lines on small bore pipe, resulting extent.of the problem and are cur-Standards were issued on in sharp discontinuities in the pipe, rently repairing and inspecting the March 22,1983. 4 l and, in one case, violating minimum scribe lines, as necessary. wall-thickness.- An evaluation to determine reportability will be g This item has been reported to the Project Engineering will evaluate completed by April 30, 1983. NRC as a'potentially reportable item the condition to determine if it is under 10 CFR 50.55 (e). reportable under 10 CFR 50.55 (e). i 7. MCAR'#43 - Weld Defects in' Bailey Controls Cabinets Bailey Controls Company, the Control-Project Engineering has been re-An evaluation of reportability Room Complex supplier, has notified quested to determine if the con-per 10 CFR 50.55 (e) will be Bechtel of' potential weld defects in dition is reportable under complete by April 15, 1983. Class IE termination cabinets. Per 10 CFR 50.55 (e). L Bailey Controls' request, Bechtel ' The four bay assemblies were returned four bay assemblies for Verify completion of investigation satisfactorily repaired at investigation and repair. and repair of all'affected cabinets Bailey Controls Company, and i at Bailey Controls. have been returned to the The cabinets were supplied to Bailey jobsite. by Systems Controls Company, who is a subject of NRC IE Information Notice 82-34. t i NRC 4 (B-12)
6. i j
- 10. 10 CFR 50.55 C.
SUMMARY
l Resolution of all seven of the outstanding items listed above will be ' accomplished on a schedule that supports the Integrated Project Schedule. J t 2 ( ? 4 NRC 4 B-13) 10.6 '~~ ~ e.
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HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST
- 11. CONSTRUCTION /STARTUP INTERFACE Question: Overview of current construction startup management organization showing interfaces between the two.
A. INTRODUCTION i The attached diagram illustrates the interface relationships during the testing program. In order to alleviate potential communication problems with construction, several paths and several levels of interface are identified. The Bechtel Project Startup Engineer is located at J the site. His primary purpose is to minimize communication problems between all startup and construction groups. As previously noted, the interface with PSE&G.0perations is a working relationship. The Nuclear Department personnel peform technical craft support functions for the test group as well as preventive and corrective maintenance activities. ( NRC 3 (A-11) 11.1
~ ) n - s. HOPE CREEK GENERATING STATION CONSTRUCTION /STARTUP INTERFACE CONSTRUCTION STARTUP f --- FUNCTIONALINTERFACE PROJECT. PROJECT CONSTRUCTION LINE REMMUNG S CONSTRUCTION l MANAGER MANAGER (SECHTEL) (PSE&G) GNRR CANAGER HOPE CREEK g g STARTUP l l HOPE CREEK MANAGER OPERATl0NS im&Gi im&Gi --p--------- nonCT _a STARTUP ENGINEER s --= l ENGINEER (SECHTEL) l (SECHTEL) i L _, _, _, _, - - - - - -,! s FIELD MANAGER OA PROJECT ENGINEERING & STARTUP I STARTUP SUPERINTENDENT CONSTRUCTION COORDINATOR I HOPE CREEK (PSE&G) (BECHTEL) (BECHTEL) o STATION ] OEPARTMENT g T --_ -- _I I I l eSE&Gi PRINCIPLE PRINCIPLE l QA STARTUP ,RINCIPLE ENGINEER FIELO INTEGRATED ADMINISTRATOR gl l TESTING TESTING l (PSE'8G) IPSE&G) (PSE&G) (M&G) I l l. l I I l l t l STATION TEST l* L~~~~~~~' CRAFT GRDUP l SUPERVISION LEADERS im&Gi n im&Gi ii
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HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST ('~ 12. SITE TOUR Question: Site tour and observation of construction activities. A. INTRODUCTION A tour of the site facilities has been arranged which highlights the status of construction progress and the completion of work. B. ITINERARY 4
- 1) Turbine Area
- 2) Control & Diesel Area
- 3) 1Radwaste Area
- 4) Reactor Area
- 5) Yard Area - Cooling Tower
- Cire. Water Pump Structure - Fire Water Pumphouse - Sewage Treatment Plant - Service Water Intake Structure NRC 4 (A-28) 'is 12.1 ?%., t. --}}