ML20134L051
| ML20134L051 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/26/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20134L040 | List: |
| References | |
| NUDOCS 8509030037 | |
| Download: ML20134L051 (200) | |
Text
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,Enclosure 2 f
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HOPE CREEK GENERATI\'G STATION 4
O PSEG Public Service Electric & Gas Co., New Jersey 9
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NRC CASELOAD FORECAST >
June 26-27,1985 l
I 8509030037 850826 '
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& =s, .- 4 - , .4 HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST AGENDA RESPONSIBLE PSE&G PRESENTER OPENING REMARKS P.R.H. (Pete) Landrieu Project Manager A. Project Overview B. Management Team Enhancements
- 1. CONSTRUCTION OVERVIEW P.R.H. (Pete) Landrieu Project Manager s A. Introduction
':$ B. Construction Percent (%) Complete
,5 C. Major Construction Milestones Accomplished Since Last Caseload
~j-.
- 0. Problems / Solutions E. Summary
- 2. ENGINEERING STATUS C. W. (Chuck) Churchman
, Site Engr. Manager A. Introduction B. Design Change Package Status C. Independent Design Verification Program W. (Bill) Gailey 7 0. Equipment Qualification Chief Project Engineer i' E. Documentation Close-Out F. Startup and Operations Support G. Response Coordination Team H. Problems / Solutions I. Summary
- 3. PROCUREMENT P.R.H. (Pete) Landrieu Project Manager A. Introduction B. Radiation Monitoring System C. NSSS Equipment Delivery Status D. Operational Spare Parts Selection E. CORE Team Activity F. Problems / Solutions G. Summary 4 CRAFT WORK FORCE E. C. (Gene) Logan Gen. Mgr. - Constr./ Site Mgr.
A. Introduction B. Manual Staffing Levels C. Labor Contract Status
- 0. Problems / Solutions E. Summary NRC 5 (A-1)
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NRC Caseload Forecast Agenda Page 2
- RESPONSIBLE PSE&G
,' PRESENTER
+
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- 5. PIPE HANGERS R. (Bob) Kirk .
Asst. Chief Design Engr.
A. Introduction
! 8. Status of Large and Small Pipe Hangers C. Summary 3
'i 9 6. PROJECT SCHEDULE P.R.H. (Pete) Landrieu Z Project Manager 3 A. Introduction is B. Critical Path Items 1 C. Project Milestones /Short Tenn Goals
- D. Summary 4
j 7. BULK COMMODITIES E. C. (Gene) Logan Gen. Mgr. - Constr./ Site Mgr.
A. Introduction B. Bulk Quantity Status
. C. Summary f
g
- j 8. STARTUP J.(Jim) Carter s ~
Project Startup Manager
. A. Introduction 3 'T B. Release for Test Program C. System Turnover Program
,, D. Procedure Status *
. E. Preoperational Test Status F. Release from Test to Hope Creek Operations 3 G. Test Program Schedule and Critical Path ,
< H. Staffing Plan
, I. Problems / Solutions J. Summary t, 9. LICENSING STATUS 8. (Bruce) Preston
. Project Licensing Manager A. Introduction B. Operating License Application Status L. C. Impact of NUREG 0737 R D. ACRS Commitments l'
E. Open Safety Evaluation Report Items F. NRC Audits G. Summary
- 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55 A. E. (Art) Giardino Manager - QA Engr. & Constr.
A. Introduction
! 7 B. Deficiencies Reported C. Summary NRC 5 (A-2) i
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- 11. CONSTRUCTION /STARTUP INTERFACE E. C. (Gene) Logan Gen. Mgr. - Constr./ Site Mgr.
A. Introduction t B. Management / Team Concept C. Summary
- 12. SPECIFIC ISSUES C. W. (Chtck) Churchman Site Engr. Manager 3
A. Introduction s
- 8. Specific Issues
, a. ATWS-3A Design Changes (d b. Appendix R Design Implementation
- c. NSSS Loads Adequacy Evaluation
[(1 ; d. High Energy Line Break
- e. Moderate Energy Line Breaks
- M
- f. Control Rod Drive System
- g. Primary and Secondary Containment i '
- h. Control Room Panel Modifications
- i. Pipe Stress (As-Built) (See12/8/n)
, J. N-Stamp Certification Program (See12/8/n) r,
- k. Updating Drawings and Specifications a to As-Built Condition
'i ;f' " ' ? 1. Envirorcental Qualification of
? -
Safety-Related Equipment i m. Seismic Qualification of Safety-Related Equipment i n. Hanger Reconciliation Program R. (Bob) Kirk 9
Asst. Chief Design Engr.
C. Problems / Solutions D. Summary J
J 13. ROOM TURNOVERS E. C. (Gene) Logan 9 Gen. Mgr. - Constr./ Site Mgr.
A. Introduction i 8. Room Turnover Problems / Solutions C.
D. Summary
- 14. INCOMPLETE ITEMS AT THE TIME OF LICENSING P.R.H. (Pete) Landrieu A. Introduction
- 8. Potential Items Exposures 1, C. Summary 4
e NRC 5 (8-1)
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Page 4
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j RESPONSIBLE PSE&G PRESENTER q (
a M- 15. OPEN PUNCHLIST ITEMS P.R.H. (Pete) Landrieu A. Introduction B. SDR Status C. NCR Status D. Problems / Solutions
-; E. Sumary jj 16. SEISMIC II/I REVIEW C. W. (Chuck) Churchman 4' Site Engr. Manager A. Introduction
'j B. Status and Schedule Lj C. Sumary A
17.
" POWER ASCENSION AND OPERATIONAL PROCEDURES W. H. (Bill) Schel1 Power Ascension Test Director A. Introduction B. Power Ascension Test Procedures and Operational Procedures C. Power Ascension Program Acceleration O. Problems / Solutions E. Sumary
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- 18. STAFFING, TRAINING AND OPERATOR LICENSING R. (Roger) Salvesen
. .! Gen. Mgr. H.C. Operations I-l A. Introduction B. Staffing, Training, and Licensing C. Operational Readiness Considerations
. D. Sumary
- 19. SITE TOUR P.R.H. (Pete) Landrieu Project Manager
,, A. Itinerary and R. (Roger) Salvesen Gen. Mgr. H.C. Operations NRC 5 (8-2)
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HOPE CREEK GENERATING STATION ; ,
PROJECT TEAM ORGANIZATION PSE&G AND~BECHTEL . I PROJECT MANAGER HOPE CREEK {
OPERATIONS P. R. H. LANDRIEU (PSEE) R. SALVESEN B. G. MARK 0WITZ (PSEE)
(KCHR) F QUAUTY ASSURANCE ENGINEERING CONSTRUCTION COST /SCHEDUUNG A. GIARDINO W. GAILEY E. LOGAN T. BRAUCHLE (PSEE) C. CHURCHMAN (PSEAG)
(PSE&G)
G. MOULTON K.BER ES W. MOURER S. DARU (KCHR) mECMED (KCHR) (KCHR)
STARTUP UCENSING PROCUREMENT J. CARTER A. RAMIREZ (PSE&G) 8. PRESTON (PSEac)
J. ZE RUCHA (PSEac) R. McGOWAN (KCHR) (KCHE)
I ACAD/04 ART 17A
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST
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- 1. CONSTRUCTION OVERVIEW t-Question: Overview of project construction and preoperational testing schedule, including progress and major milestones completed,
.. current problems and any anticipated problem areas that may
~! impact the current projected fuel load date.
i A. INTRODUCTION During 1983 the projected bulk commodity schedules were met or exceeded.
As a result, in early 1984 a reassessment was made of the to-go schedule and it was determined that a target fuel load date of December 1, 1985, was a viable and reasonable date, although requiring very aggressive 2 efforts on the part of the Project Team. Accordingly, all working W schedules were revised to reflect this date which preshortened the
., construction period by four weeks and the startup period by two weeks, 3 taking advantage of preassembly of the RPV internals. This established i the code hydro milestone on March 9, 1985, which was met and exceeded by one week.
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]~ During 1984 the project continued to track to the target schedules and d .m to meet the aggressive milestones that had been established, further l *3 developing a history of credibility. In this period the transition was
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successfully made from a bulk installation mode to a system and room turnover mode. One hundred and fifty-three systems (153) out of 209 (or 73 percent) have been turned over from Construction to Startup for testing. Two hundred and sixty-six (266) rooms have been turned over to date and 237 have been accepted out of 890 rooms. This effort is further enhanced by the release for test (RFT) program which makes components available to Startup prior to formal turnover.
At the end of 1983 construction of the project had achieved 81 percent complete and by the end of 1984 was greater than 95 percent. Currently it is nearly 99 percent. These included the effects of increases in some commodity quantities and final cleanup of system installation work.
Startup was 40 percent complete at the end of 1984 and is now greater than 66 percent complete. The preoperational testing schedule is addressed in detail in Section 8-G.
,' In addition to system and room turnovers, a major effort in the remainder of 1985 will be the completion of post turnover activities. The principal vehicle for accomplishing this will be the System Deviation Report (SDR) program which has been established and is in place. All SDRs are identi-fied to their applicable system and scheduled accordingly. Additionally there are other reports which identify any outstanding items; such as the non-conformance reports (NCRs), Seismic II/I reports and a regular schedule of walkdowns. These are all closely monitored and weekly project team meetings have been implemented to expedite resolution of any concerns.
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- 1. CONSTRUCTION OVERVIEW i ,
- 8. MAJOR CONSTRUCTION MILESTONES ACCOMPLISHED SINCE LAST CASELOAD (Refer to Section 6-C for complete list) 1983 Milestone Milestone 3 '.
Number Description Schedule Actual ~
y 83-79 Complete closure of large recire. 04/15/83 08/28/83A pipe in Drywell 83-91 Auxiliary Boller Facility turned 08/01/83 08/19/83A over 83-94 Start main condenser hydro 09/15/83 09/25/83A 83-102 Control Room Complex turned 12/15/83 12/15/83A l
over
. 84-21 Turnover Administration Building 07/02/84 06/07/84A 84-24 Four million feet of wire and 08/01/84 07/16/84A cable pulled 84-26 14,500 large pipe hangers 09/07/84 09/02/84A installed 84-30 Complete cooling tower- 10/31/84 10/05/84A 84-37 Turnover diesel generators 12/12/84 12/18/84A 85-07 Start integrated flush 03/14/85 02/11/85A 85 -1 1 Code hydro of vessel start 04/09/85 03/0'2/85A 85-12 Complete main turbine tube oil 04/22/85 01/07/85A flush i NRC 5 (A-10)b 1.3
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- 1. CONSTRUCTION OVERVIEW D. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM . CORRECTIVE ACTION CURRENT STATUS I 1) RESOLUT0N OF PROBLEMS IDENTIFIED i IN LAST CASELOAD ;
i.
) a) Drywell The Drywell is the most con- Problem resolved. Schedules necessary to support gested area on the project turnovers leading to code hydro j containing the most critical were maintained by concentrated
!' fluid systems with intricate efforts by supervision and field physical configurations. As engineering combined with careful construction continues, the planning.
! - ability to manload to pre- i i i vlous levels decreases as i the space become; more -
l . confined. Significant i
- items of concern are
- Maintaining Drywell effec- '
l tive manpower density and earned manhours at scheduled levels.
i j Drywell jet impingement .
] barrier design will be completed in June and j could impact installation
- of small pipe, conduit,
- large pipe supports, and ,
- restraints.
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- 1. CONSTRUCTION OVERVIEW D. PROBLEMS /SQLUTIONS DESCRIPTION OF PR08LEM CORRECTIVE ACTION CURRENT STATUS
- 1) RESOLUT0N OF PROBLEMS IDENTIFIED
- IN LAST CASELOAD (Cont.)
b) Control Complex Prefabricated cable instal- Problem resolved. The control complex was turned lation is currently behind over as scheduled on schedule. This is due to December 15, 1983.
late equipment deliveries. :
Bailey equipment deliveries F remain critical to the
- schedule.
c) Electrical Installation Cycle Raceway installation (condult) Prpblem resolved. The scheduled requirements for is presently 6 weeks behind all electrical commodities were schedule and is currently exceeded, including unanticipated c impacting wire and cable growth in quantities. ;
installation and termina-i tions.
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- 1. CONSTRUCTION OVERVIEW D. PROBLEMS / SOLUTIONS -
DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS
- 2) CURRENT PROBLEMS a) Radiation Monitoring System The original radiation Assign personnel to a project Task force reporting to project monitoring vendor Techno- task force to monitor supplier managers established, logy for Engergy Corp., performance, resolve problems +
has failed to meet its expeditiously and coordinate obligations. activities with Engineering, ;
Constuction, Startup and i.
F Operations.
m Issue design of system required Initial design issued for construc- s for licensing. tion on June 14, 1985.
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Obtain materials on an expe- Local processor for new fuel criti-dited basis. cality has been delivered. Re-mainder of equipment is scheduled ;
to support subsequent site activ- '
itles Commence construction of new Activities have commenced to modify system, existing installations.
b) Material Deliveries Support of Startup and Establish 4 Procurement CORE A CORE Team has been setup and i Operations. Team which is able to rapidly is supporting startup requests, process procurement documents, .'
resolve problems and expedite ,
delivery. '
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- 1. CONSTRUCTION OVERVIEW D. PROBLEMS /SQLUTIONS l DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS
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- 2) CURRENT PROBLEMS (Cont.)
j c) Contractor Performance (HVAC)
I Completion of installation Personnel have been dedicated to HVAC systems GRA, GKA and GUA have ,
i and leak testing of HVAC establishing all open items and all been completed and released -
l systems to suppurt the priorities for their completion to Startup for testing and will l PLRT and NLRT tests. to minimize delays in system support the PLRT nd NLRT tests.
turnovers. Extended overtime
- authorized to ensure completion.
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[d d) Completion of Post Turnover Work i
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i Timely completion of Continued emphasis by Construc- Visibility of the 50R program is i.>
- construction work tion and Startup to identify, obtained through a data base solely i j identified on 50Rs or prioritize and close out SDRs. devoted to these items. Additional E
! other vehicles to support personnel have been added to process '
release from Startup. and close out SDRs expeditiously. .
) e) Close Out of Software :
- An extensive amount of Aggressive schedules have been The milestone schedule for large i sof tware material must established. N-5 packaging, and small pipe hangers is on , :
J be packaged and formally A8R submittal and QC final buy- track and an increase in the '
l recorded prior to offs are closely monitored on submittal rate of ABRs is being .
4 completing construction. all commodities. experienced. , ,
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- 1. CONSTRUCTION OVERVIEW D. PROBLEMS /SQLUTIONS DESCRIPTION OF PROBLEN CORRECTIVE ACTION CURRENT STATUS
- 2) CURRENT PROBLEMS (Cont.)
i f) Radwaste Solidification .
System Turnover ;
A radwaste system manager has been !
A change in the method A recovery schedule for RFTs of solid radwaste pro- and system completion is being established and Construction is cessing resulted .n late closely monitored. currently tracking to requirements.
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engineering and material -
T delivertes which impacted
- Construction's ability to complete installation ;
on schedule. :
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- 1. CONSTRUCTION OVERVIEW
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E.
SUMMARY
Full advantage has been taken of other projects' experiences and early emphasis placed on identification and resolution of known problem areas. Management has provided for the establishment of dedicated system teams to provide the vehicle for insuring that the startup schedule is fully supported.
In parallel other programs have been initiated to provide maximum schedule flexibility to the project as a whole. Some of these are the Release for Testing (RFT) program, a CORE Team for expedited procurement, and corporate management involvement on a regular basis.
The remaining construction effort will support the December 1,1985 fuel load date.
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- 2. ENGINEERING STATUS v
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 project engineering initial design activity is essentially complete. The significant portion of the remaining engineering work consists of as-built reconciliation, field and startup support, and licensing support (including support of NRC walkdowns).
In addition, engineering is responding to requests for infonnation and observations which arise from an Independent Design Verification Program (IOVP) being conducted on the project.
Initial engineering design is complete as of June 1985. Several generic design considerations, such as hydrodynamic loads on the Mark I torus, TMI lessons learned, CR0 water hammer effects and human factars have been factored into the initial design. Thus these industry wide concerns were addressed relatively early in the project schedule and will not be a source of future design changes. Current engineering activities include the following:
N .' l. Final sign-off of stress reports for as-built reconciliation it of piping / hangers and final assessment of walls, slabs and a beams for load verificaction and cut rebars.
- 2. Licensing support for resolution of SER open items. C.r pletion 3 _
of ongoing Seismic II/I and other hazards evaluation walkdowns.
- 3. Issue of remaining design change packages.
- 4. Closecut of outstanding documentation including vendor information.
- 5. Field support for the review and disposition of Field Change 3 Requests (FCRs) and Field Change Notices (FCNs).
- 6. Support to Startup by reviewing preoperational test procedures and dispositioning Design Information Requests (DIRs), Startup Change Requests (SCRs), and Startup Deviation Reports (SDRs).
- 7. Support to Operations by responding to field questionnaires (FQs).
These activities are proceeding on schedule in support of a December 1985 fuel load.
As the engineering support activity has shifted to the jobsite, Bechtel has expanded its Resident Engineering group since the last caseload from approximately 25 to 90 people, and concurrently PSE&G has relocated its home office engineering activities to the jobsite.
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- 2. ENGINEERING STATUS
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3 W B. DESIGN CHANGE PACKAGE (DCP) STATUS The Design Change Package (DCP) program is implemented for a system 10 weeks prior to system turnover. All identified changes are reviewed to determine whether they are necessary and forecast dates are issued as appropriate. As of May 31, 1985, 531 OCPs have been identified, 489 have been issued to Construction, and 184 have been closed out by Con-struction. The remaining 42 will be issued by July 1985. DCPs are m reviewed by Startup and are planned for in their schedules. Weekly reviews of DCPs are held to aid engineering in the rapid resolution of items restraining ;ystems completion and turnover to Startup. In addition, a weekly telephone conference is conducted between San Francisco and the *
- Hope Creek jobsite (Resident Engineering / PSE&G Site Engineering /Ccn-struction/Startup) personnel to resolve areas of concern and assign priorities needed to support Construction and Startup. These conferences have assured that matters requiring coordination between entities are properly identified and promptly acted upon.
C. INDEPENDENT DESIGN VERIFICATION PROGRAM (IDVP)
. Public Service has undertaken an Independent Design Verification
- Program (IOVP) to provide additional assurance that the design of the
- ;; Hope Creek Generating Station meets all its licensing requirements,
, _. through a review of the technical adequacy of selected systems and the v3 design process. The IOVP includes walkdowns, which also include reviews of the application of the as-built verification program to 0;: those systems within the scope of the IDVP.
d, Fl The independent auditor selected to perfom the IOVP is Sargent li and Lundy. Formal kickoff for the review was April 1, 1985. The h IOVP final report is to be issued in August 1985.
. '!< Over 5,000 project documents are being reviewed by approximately 50
- , members of the review team. Implementation of the IDVP program plan
,.i has required team member visits to the home offices of PSE&G and Bechtel, as well as the jobsite. A number of observation reports q has been submitted by Sargent and Lundy and resolution of these is e; underway.
q
. D. EQUIPMENT QUALIFICATION The SQRT and PVORT audit was conducted May 7-10, 1985, the results of
~w hich are discussed in more detail under Section 12 (m). The environ-mental qualification audit is scheduled for the week of July 15, 1985.
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) () d E. DOCUMENTATION CLOSE-0UT a.t 3
3 Project engineering has established goals for the closecut of engineering i documentation open action items (open correspondence, etc.). The present trend of working off items is gaining momentum and we are confident that our goals will be achieved on schedule. Change authorizing documents (FCRs, FCNs, etc.) are required by procedure to be closed out/ incorporated within 90 days. Vendors are also being expedited to close out open comments on their documents. 4 F. STARTUP AND OPERATIONS SUPPORT Bechtel and Public Service engineering is providing startup support by:
- 1. Reviewing preoperational test procedures.
- 2. Dispositioning Design Information Requests (DIRs), Startup Change Requests (SCRs), and Startup Deviation Reports (SDRs).
- 3. Coordinating design completion activities and issuing Design Change Packages (DCPs) by startup system to support startup efforts.
~ F*. 4. Maintaining and augmenting onsite engineering groups to provide i
day-to-day support for construction completion /startup require-1 ments; and
~;} 5. Responding to Field Questionnaires (FQs) in support of .
operating procedures preparation.
G. RESPONSE COORDINATION TEAM (RCT)
The Response Coordination Team (RCT) is Hope Creek's mechanism for monitoring and dispositioning NRC, IMPO and GE notices, generic letters, bulletins and reports pertinent to the Hope Creek Generating Station. This team's effectiveness has been reviewed by the NRC for adequacy.
The effort continues to be a significant one at this time. A major push has been on to address a number of backlog items to support Hope Creek Operations' procedure writing activities. This is a living
,, program, with as many as 100 new RCT items being received per month. I Constant attention by all Public Service site organizations, par-
, I ticularly Site Engineering and Operations, is required.
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nEMS acouWtED 2.652 nEMS EVAWA1ED 1.615 _, .....-
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nEMS CLOSED 1.292 "*'
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j SIL SAL TIL AfD IN GL 8 C SER SOER O&MR OE GE NRC . . INPO SIL - Service information Letter IN - Information Notice SER - Significant Experience Report SAL - Service Advise Letter GL - Genwie Letter SOER - Significant Opwating Experience TIL - Tecticical Information Letter 8 - Bulletin Report. Recommendation
- AID - Application Information Document C - Circular OaddR - Opwation k Waintenance Reminder -
OE - Opwoting Expwience ,
'"* m zarnoe av m:- w := naw = m l ,_g _ R R,T S T A T U S 0855 q -MP
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- 2. ENGINEERING STATUS H. PROBLEMS / SOLUTIONS DESCRIPTION OF PROSLEM CORRECTIVE ACTION CURRENT STATUS
- 1) RESOLUTION OF PR00LEMS IDENTIFIED "
IN LAST CASELOAD l1 a) (ALARA) As Low Is Reasonably -[i Achievable Maintain the annual integrated An ALARA review for each system A verification walkdown is complete. h dose to station personnel and and radiation area is complete. The walkdown findings were minor i-to individuals working at the -
and the corrective actions are station ALARA. being accomplished within the :
integrated, project schedule. 'f f* b) Seismic Category II/I Design ,
m This item is discussed in detail in Section 16. '
c) Separation Review ,
Verify that systems and com- A comprehensive separation Pipe break / jet impingement / internally ponents important to safety review was conducted. generated missiles: '
are designed for the effects of internal missiles, pipe The preliminary drywell review was ,
breaks, and other hazards. completed in January 1983. L without loss of capability to perform their safety The preliminary review of the function. reactor building was completed before June 15, 1983.
(Cont.)
NRC9A(A-1)
- z. .. . x~..=.c .- . . . . , .a ,; .: ~ b;w .. . R. . - . . , . . :. a% L '
- '. f %,,
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- 2. ENGINEERING STATUS t H. PROBLEMS /SQLUTIONS s I
DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS m h
- 1) RESOLUTION OF PROBLEMS IDENTIFIED b.
IN LAST CASELOAD (Cont.)
7 c) Separation Review (Cont.) A May 1985 plant walkdown confirmed h the previous scale model and drawing ;
review and identified the possible need for a few additional barriers i to ensure that no internal hazards [
will impact plant safety. .
An evaluation is underway and, if .
required, the barriers will be I designed by July 1965 and installed
m by October 1985. p
- t. -
With the schedule outlined above, resolution of this issue will support the integrated project schedule.
d) Equipment Qualification Assure that components impor- Implement seismic and environ- Safety-related mechanical and elec-tant to safety are compatible mental testing / analysis to des- trical equipment is identified in with normal, transient environ- onstrate qualification. -
a detailed master listing showing mental and dynanic ef fects. qualification report and equipment '
installation status. Over 901 of safety-related mechanical and electrical equipment qualification reports have been completed and over 90% of the equipment has been installed.
~
(Cont.) ' ' ' ~
NRC 9A (A-2)a
'~ - -- ' " " -
- e.
rl Y g) ~'
. ?-
Y
- 2. ENGINEERING STATUS if H. PROSLEMS/SQLUTI0h5
[.
DESCRIPTION OF PROSLEM CORRECTIVE ACTION CURRENT STATUS t'
i 1) RESOLUTION OF PROBLEMS IDENTIFIED 1 IN LAST CASELOAD (Cont.)
i d) Equipment Qualification (Cont.) The results of the SQRT/PVORT audit ?'
, are discussed in detail in If Section 12 (m). 1 Environmental qualification is b discussed in Section 12 (1). ;
e) Service Water Intake Structure
, (SidIS) +
" The design of the SWIS called The design was revised to accommo- The tremie concrete, as well as the for placing tremie concrete to date placing the tremie concrete SWIS superstructure, has been ,
the top of green-gray Vincentown deeper, to the top of the green- successfully completed, at el 35' (average) with a key gray Vincentown strata. c extending to el 20'. During l excavation it was determined that the top of this strata '
was at el 23' to 29'. l f) Additional Floor (el 163 ft. 6 in.)
in Diesel Area Lack of available space for Con- Add additional floor at el 163' 6" All related redesign is complete and trol Room panels to accommodate of the Diesel Building. the additional floor has been con-the equipment that resulted from structed.-
i new regulatory requirements such as ATWS, Reg. Guide 1.97, NUREG-0737, new design requirements i such as the revised alaria philos-ophy, and changes in the main -
control board indication lamp voltage.
hRCSA(A-3)a .
C':
- p?.))
- re y
,& 19 ._
.I
,B
- 2. ENGINEERING STATUS N. P900 LENS /50LUTIONS .'<
DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS ,
e
- 1) RESOLUTION OF P900 LENS IDENTIFIED ;
IN LAST CASELOAD (Cont.) 3 g) Seismic Analysis of Blackwalls .'
IE Sulletin 80-11 required an Evaluate the use of masonry block- There are no masonry block in evaluation of all masonry walls walls in the plant. seismic category I areas.
for their structural integrity -
and, in the event of failure.
the effect on safety-related systems.
F h) Intergranualar Stress Corrosion Crack _ing (1650C)
Regulatory Guide 1.44 requires Make appropriate material changes All material changes have been
- plants to reduce the IESCC. to reduce IGSCC susceptibility. completed.
- 1) Plant Unique Analysis
!' In July 1980, the NRC issued Perform a PUA (plant unique The PUA has been completed and a l the SER for the Mark I long- analysis). Define torus modifi- report has been submitted to the term program defining the cations needed to meet stress NRC.
l acceptable methodology for limits. Perform modifications.
l defining pool swell and The modifications uhich have been i bubble oscillation loads completed included adding local .
on the torus. gussets to ring girders, stiftening certain penetratton nozzles, adding S/RV quenchers and supports, adding pipe supports, modifying certain pipe supports and strengthening connections of torus columns to shell.
NRC 9A (A-4)
.. 7
. . ., u . :: e. . .T . - , . :. w., e s1.:: a.:. 6 . L x. w .w. c.
l') )
- 2. ENGINEERING STATUS .'
N. PAGALENS/ SOLUTIONS DESCRIPTION OF PA00LEN CORRECTIVE ACTION CURRENT STATUS
- 1) aF M UTIGN OF P900 LENS IDENTIFIED 15 LAST CASELOAD (Cont.) .
j) unit 2 Cance11atten - Reactor
! Building & Turbine Building In December 1981, Unit 2 was The " Plant Cancelled Area", for- Design and construction of all cancelled. At that time the merly the Unit 2 Reactor Building Unit 2 cancellation areas have Unit 2 Reactor and Turbine area, is at the roof of el 132' been completed.
Buildings were partially This area will be unoccupied.
constructed. -
The Unit 2 Turbine Su11 ding l: exterior is completed. Portions
'I P* of the interior space will be 5 utilized.
Deletion of Unit 2 will have no l tapact on the safe operation of
'> Unit 1.
k) Radmaste System Changes .
Gaseous Radmaste System - The design and installation System turnover to startup -
In July 1981 Mope Creek was accelerated. End of June 1985 replaced the cyrogenic eff-gas system design '
with an ambient charcoal -
treatment system as a re- ' '
suit of industry experience.
Solid Radmaste System - The design'and installation Systen turnover to startup -
System procurement delayed was accelerated. End of June 1985 to allow for use of the latest available techno-logy that would include
, welune reductlon.
i
. w u.a w u ww. ..e a :ui..rn:s. -
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, j
- 2. EaGlaEERING STATUS X. PAGALENS/SQLUTIONS DESCRIPTION OF P900LEM CORRECTIVE ACTION CURRENT STATUS
- 2) CuaAENT PROBLENS a) Radiation Monitoring System (TEC-RNS)
The original radiation mont- Procure an RMS system from another The project has issued a purchase .
toring systen vendor, Tech- vendor (s). order to GA Technologies (Sorrento nology for Energy. Corpora- -
Electronics) for a standard RMS j tion, has failed to meet system.
, its obligations.
The project is negotiating with ['
WS for management of the inter-F face between Sorrento's RMS system '
O and TEC's sof tware and harduare for i; report generation.
Assign personnel to a project Task force reporting to project task force to monitor supplier managers has been established.
performance, resolve problems expeditiously and coordinate activities with Engineering, Construction Startup and Operations.
Develop minimal requirements Engineering, Startup and Construc-' i for RMS for fuel load (mint- tion groups have established re-system). quirements. ;
Issue design of system required Initial design issued for Con-for licensing. struction on June 14, 1985.
MC gA (A-6)a
. . . . - - - _ _ ..x... __
t . ;
l .
- 2. ENGINEERlWE STATUS N. PAMLENS/SQLUTIONS DESCRIPTION OF PAAAIEN CORRECTIVE ACTION CURRENT STATUS l i l
- 2) CumaFNT P900 LENS (Cont.)
l b) As-Sullt Reconciliation Program
?
This item is discussed in detail -
in Sectton 12/8/n.
9
' ~ ~ '
.....~ . . . . . .
t E
l l
i i
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MC 94 (A-7)a
l
- 2. ENGINEERING STATUS
- I 1.
SUMMARY
The foregoing discussion of the engineering status and ongoing activ-ities demonstrate that the engineering design effort and engineering support to Construction and Startup are consistent with the nceds of the overall project schedule. The Home Office Engineering, Site Engineering, and Resident Engineering organizations are structured to ,
provide maximum and timely support to construction to expedite reso- !
lution of construction related problems. Further, all known licensing i requirements have been addressed, and where applicable, have been factored into the plant design.
4 l
l i
1 NRC 9 (A-6)a 2.13
, , . . _ . . u. _.. . .
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST f
- 3. PROCUREMENT Question: Detailed review and current status of procurement activities including valves, pipe, instruments, cable,
, major components, spare parts, etc.
- A. INTRODUCTION
, With the completion of delivery of all bulk materials and principal t
components, the remaining activity consists of the resolution of .
- i the radiation monitoring system, procurement of operationarl spare J parts, and support of the startup effort. A centralized CORE Team
- established to expedite materials to support Startup and Operations.
There are no major purchase orders for permanent plant equipment or major construction contracts to be awarded.
... j
- 8. RA0!ATION MONITORING SYSTEM j The radiation monitoring system was awarded to TEC on July 30, 1982. On 1 April 2,1985, having delivered only the control room panel (enclosure)
. and miscellaneous brackets and hardware TEC was notified of its default.
' PSE&G and Sechtel developed a contingency plan based on the monitoring requirements to bring fuel onsite and to permit fuel load. The result
> was a demand schedule which was utilized to solicit an alternate supplier.
8echtel has awarded an order to Sorrento Electronics, a division of General Atomics Technologies, with delivertes *lch support the demand schedule. In addition, 8echtel is negotiating with NUS to provide material and services to manage the Interf ace between Sorrento Electronics'
. standard system and TEC's hardware and sof tware for Reg. Guide 1.21 report generation.
Sorrento Electronics delivered the local processor for new fuel criti-cality on May 22, 1985, approximately 3 weeks earlier than needed by the demand schedule. The balance of processors required for fuel load are scheduled for delivery by September 1,1985. NUS has committed to deliver the hardware and sof tware for non-RMS functions required for i fuel load, such as spent-fuel temperature monitoring and drywell leak !
I detection system by September 15, 1985. Construction can accommodate these deliveries without impact on the ready-for-fuel load date.
In order to assure continued performance of both suppliers and resolve interf ace problems quickly, PSE&G and Bechtel both have assigned resident engineers to the supplier's facilities and established a separate project task force to coordinate design developments and monitor performance.
NRC5(A-20)b 3.1
- 3. PROCUREMENT
(< i l
C. NSSS EQUIPMENT STATUS Delivery of the NSSS equipment is essentially complete. Components
. .not yet delivered, are on schedule in accordance with the fuel load
] schedule.
In order to expedite deliveries of repair and replacement parts, vr ^ Bechtel has contracted with General Electric to station an engineer o onsite to requisition parts through General Electric's FDI/FDDR system.
- In this manner, the normal delays in spare part requisitioning is 4 avoided. Further, a project-dedicated employee of General Electric is 1 assigned in San Jose to expedite internal activities and subvendor activities. Lead times have been reduced significantly since imple-mentation of this expedited ordering system. .
- i
} 0. OPERATIONAL SPARE PARTS SELECTION The spare parts selection process has four distinct phases:
- Review of technical consideration I
- Selection and quantity determined
- Engineering and QA evaluation
/ ,- 4
- Review and approval of vendors' quotation The selection process is tracked on the basis of purchase orders for original plant equipment. Each order usually contains several line items which cover the various pieces of equipment purchased via that purchase order.
Maximum utilization of Unit 2 equipment has been made in selection of
, operational spare parts.
e a 3.2 NRC5(A-21)b
. ._ .. ..i- x.... .>: -
, x -
3 e..
1984 1985 JAN FEB WAR APR WAY EN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JJN JUL AUG SEPlOCT NOV DEC j' 103i2 P.O. LINE 11EM ORIGINAL REMSED /
REQUIRED 8.393 10312 p 9.000 -
COMPLETED -
8772
~
tl772 /
- REWAINING -
1540 - 2[
/8393
[lf,"j j
8.000 j g -
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7.000 I
f m 'y v d /'
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?
m z 5.000 # /
u ~3
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/ /"
4.000 --
/ -
- 3ooo
//
/f uore.
P.O. LINE ITEM IS 2.000 - - ,/'/ ONC OR MORE PIECES
' [/
g/ / OF EQUIPMENT FROM AN ORIGINAL P.O.
,.000 -
- /
O
" " *" * '" "" "" *^* "
"._Tomcux samu "5 PARE PARTS
- - u se so m E m catrx NAMMAM C 10855 ,
- " " SELECTION
- c.%, by P.O. UNE ITEM i ., i aam
... , - . . . . .u w- - +.-
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- 3. PROCUREMENT J.I n E. CORE TEAM ACTIVITY q :- .
t To provide materials / parts to support our project's startup testing program expedited procurement and delivery of, it was determined that d a PSE&G/ Bechtel composite procurement group (" CORE TEAM") would be set
? up. Their sole function is to expedite the procuremert of startup j materials.
'4 Ej This is a group of 19 dedicated Public Service and Bechtel engineers,
- procurement clerks, QA, buyers, expediters, and receiving personnel c; who have been centrally located. Special streamlined procedures
- canpatible with the PSE&G Purchasing department procedures have been i established to facilitate this effort'. .
This group will utilize whatever avenues are available to them to obtain the needed material, such as new orders, existing construction material, Operations' spare parts already received, vendor / subcontractor materials, Unit 2 retained parts, Salem or other utility parts, etc.
l Approximately 80 percent of all new purchase requisitions are prepared
,I in less than 3 days from the time its need is identified, via an SDR,
, many in less than 1 day. This includes Material Order / Item Classifi-
> cation (MOIC) preparation, classification, vendor discussions /negotia-q tions, etc.
j f.. For approximately 60 percent of all new purchase orders, the material is actually delivered to the site in less than one to two weeks from the
<- time its need is identified via an 50R. ,
Weekly summary reports that track the CORE Team activities and results
.< are distributed to the site managers.
.i i
4 1
i i
1 NRC 5 (A-25) a 3.4 l
-.~. .. ._. __
~
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- 3. PROCUREMENT F. PROBLEMS /SQLUTIONS
. DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS 1
- (1) RESOLUTION OF PR08tEMS IDENTIFIED IN LAST CASELA00 a) Late seismic qualift- Problem resolved. Mounting arrangement redesigned; cation of BIF '
valves successfully tested and butterfly valvqs. have been delivered and installed. .
b) Late delivery of HVAC d Problem resolved. Panels have been delivered and remote panels. Installed.
c) Late delivery of Problem resolved. Some equipment was delivered late; i solid radwaste construction workarounds employed :
equipment. to support system turnover.
{
b P
(2) CURRENT PROBLEMS a) Radiat_fon Monitoring System The original radiation moni- Procure an RMS system from another The project has issued a purchase toring system vendor, Tech- vendor (s). order to GA Technologies (Sorrento ' -
nology for Energy, Corpora- '
Electronics) for a standard RMS .
tion, has failed to meet system.
Its obligations. l.
The project is negotiating with NUS for management of the inter -
face between Sorrento's RMS system i and TEC's software and hardware for i report generation. :
(Cont.)
NRC 5 (A-27) a .
> .2 -
^
m .
i .. ,
- 3. PROCUREMENT F. PROBLEMS /SGLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS
- 2) CURRENT PROBLEMS (Cont.)
a) Radiation Mogitoring System (Cont.) ,
I Assign personnel to a project Task force reporting to project l task force to monitor supplier managers has been established. ,
performance, resolve problems expeditiously and coordinate activities with Engineering, Construction, Startup and !
Operations, i s
, u
- Obtain material on an expedited Local processor for new fuel criti- '
basis, cality has been delivered. Re- t mainder of equipment is scheduled !
, to support subsequent site activ- !
ities.
L Obtain vendor's manuals / procedures Existing manuals are currently :
to support development of test being submitted.
and operating procedures. ,
b) Support of Startup/ Operations f. f e
During the turnover and Implement a Procurement Task Force The CORE Team is in place and , .
startup/ operations phases (CORE Team) dedicated to processing supporting requirements. >
material will be identi- all phases of procurement in the fled which is missing most expeditious manner. ,
or requires replacement. .
NRC 5 (A-7) a 4
(
. . . - < - % m..a-- - . . - s . '. 4 m ..L, ,w. ....m m .-.
- 3. PROCUREMENT G.
SUMMARY
Procurement activities are essentially complete. There are no current procurement problems which are unique to Hope Creek Generating Station.
Problems typical for the construction /startup effort at this stage of 1
the project are being resolved with innovative solutions which have proven effective. Current procurement efforts will support the Startup/ Operations program.
e n e
e--*
II 4
d 1
i, 8
. o I
T NRC #5 (A-28) 3.7
- . . _ ._.c..- u.__ . . . . _ ,
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST 4 CRAFT WORK FORCE Question: Actual and proposed work force (by major craft), craf t availability, productivity, potential labor negotiations and problems.
A. INTRODUCTION The Bechtel direct manual manpower has held at about the 3,000 equiva-lent man level for the last two years. The level has been based on achievement of schedule requirements at the most reasonable cost. At this stage of the project it is extremely difficult to measure craft productivity as so much of the effort is driven by immediate resolu-tion of short term requirements. This has the effect of increasing the overtire being applied which in turn increases the equivalent manloading.
Subcontracters have stayed at a level of approximately 600 equivalent men. ,
While there has been the normal craft turnover, there have been sufficient supplies of the critical crafts such as pipefitter welders and electricians to support a balanced work load.
~
No craft manning problems are anticipated through fuel load.
.. Since 1982 no work stoppages have been encountered and with only one
, contract expiration by fuel load this is not considered to be a problem.
In May 1984 wage agreement addenda were signed with all unions on site
, P, providing the capability to perform maintenance work under the General Presidents Project Maintenance Agreement guidelines. This staffing level has steadily increased and now represents 581 of the 2,820 craft on roll.
.i NRC 5 (A-11) j 4.1 l
1
, , ... -- u. . :.-~ . .
a_. . . . . . . . .. . . . .
- 4. CRAFT WORK FORCE
,'~~ 8. MANUAL STAFFING LEVELS
- 1. Manual on Roll - June 14. 1985 _
CRAFT CONSTR. GPPMA TOTAL . . .
Asbestos Workers 116 11 127 Boilermakers 0 17 17 Carpenters 164 34 198
, Cement Masons 34 0 34 Electricians 538 94 632 Iron Workers 99 17 116 Laborers 325 86 411 Mi11 wrights 40 44 84 Operating Engr. 88 8 96 Pipefitters 748 238 986 Sheetmetal 0 24 24 Teamsters 35 6 44 Painters 24 0 24 Other 28 2 30 Total 2,239 581 2,820
. . - s.
v
\;5'
,' 2. Shift Distribution (Percent) _ _ . _ . _ ..
- j CONSTR. GPPMA TOTAL 1 First Shift 77 71 75 j Second Shift 21 19 21 Third Shift 2 10 4
- 3. Manual on Roll by Organization Bechtel - Directs 2,239 .
- GPPMA 581 Subtotal 2,820 Subcontract 351 Subtotal 3,171 GSA 204 Total 3,375 NRC5(A-24)b 4.2
. - ;. . .~. ~ . _ .
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< i Y CODE HYDRO I V FUEL LOAD 1985 JAtt FEB MR APR FRY JtN Jtil AUG SEP OCT NOV DEC f _ __ __ _
3500 ___ ___ _ _ __. _ . _ _ . _ _ . . _ _ .. _ . _ _ _ _ __ __ _ _ _ _ __.
1 i .
1 ,
l _._ _ _ _ _ _ _ .
3000 __ _ _
s
- 1 . 4* -
i 2500 . _ _ __ , _ _
, g 2000
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g .
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cv . i ma _ ___ _ _ ._ __ ._ _ _ _ _ . . _ ___ -_ _ __ _ i
_. i l .
1000 - - -- --
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t i _ _
, i 500 **.. ;
g _
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_ 'Is., _ ___ __. _ _
I2 _-_____.Q_
_ _. ._ .._ u - - _ .. _ _ - - - _ _-. - - - - .- -- -- - - - - - - - -
! TITLE '
LEGENO:
h SOURCE:
- JOB NLPOER
!lI :1985 MANUAL STAFFING PLAN "Ju? """k"'I !
' "" F i ! status oATuns -e I , !
' $HEET OF s 08011 7/80 i
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- .a. - ~ . . u. .w . . . .w a . ...~..u ...a,. w ..
s p 4. CRAFT 'JORK FORCE t
C. LA30R CONTRACT STATUS F
The only remaining contract to be negotiated before fuel load is Local #28 of the boilermakers. No problems are anticipated in the negotiations.
Below is a listing of those contract successfully negotiated since the last caseload.
CONTRACT EXPIRATION CRAFT LOCAL DATE Heavy L6borers 172 02/28/83
,, Bricklayers 7 04/30/83 Carpenters 393 04/30/83 Pipefitters 322 04/30/83 pipefitter Welder 322 04/30/83 c Sprinkler Fitters 699 04/30/83
.j Sheetmetal Workers 19 04/30/83
., Roofers 30 04/30/83
.' - Wharf & Dock Builders 454 06/30/83 Electricians 592 09/30/83 Painters 1331 02/29/84 Cement Masons 699 04/30/84 caborers 222 04/30/84 Ironworkers 399 06/30/84
.; Operating Engineers 825 06/30/84
. Asbestos Workers 42 07/14/84
. Boilemakers 28 07/31/84 Painters 1331 02/28/85 Sprinkler Fitters 669 04/01/85 Sheetmetal Workers 19 04/30/85 -
' Teamsters 676 04/30/85 l
4.5 NCS(A12)d
-- --+ - _ - _ , - _ , __ _. _ _ _ - . _ _ _ _ . , _ . ,
-w.- .- -m- c ,7c.--.__
' - ;, a
- .- ... . . . = .~ 2; . . ~
, . . . ,. . ,- . .:.m
+
( -- c.m (g, -a e
- 4. CRAFT WORK FORCE D. PROBLEMS /SQLUTIONS .
I f s-DESCRIPTION OF PRO 8LEM CORRECTIVE ACTION CURRENT STATUS 3
- 1) RESOLUT0N OF PROBLEMS IDENTIFIED 1
, IN LAST CASELOAD [
y
- ^
a) Labor Contract Negotiations Nine individual craft labor Problem resolved. All contracts negotiated with no ,,
contracts expire in 1983. work stoppages or loss of time.
Pipefitters (4/30/83) and F electricians (9/30/83) are [
.# among the nine. i-l'* ;
b) Critical Crafts ['
Availability of pipefitter Critical crafts recruited Sufficient pipefitter welders.ob- [
~ welders and the ability to and trained. -
tained to support schedule.and: : . . . . . + -
retain qualified welders turnover minimized. P-is an area of concern. F, I c) Training 7 w
! Jobsite training was iden- Increase training program. Training coordinator established !;-
tified as an area of con- and programs initiated, cern. ,
h i
- e NRC 5 (A-19)d
F' . < .
I
. :.. . ., . . = :. 9 :, .- . . :a a ;a :2/a ~:'... a.: a . . . .- ~~ --
t e
3
,.. 4. CRAFT WORK FORCE q<
- /
(J ND, E.
SUMMARY
gj . g 1 At this time the work force is not a factor in supporting the target
/
fuel load date. Adequate supplies of skilled crafts are available and -
no work stoppages are anticipated.
HAY na
, ;n
, .3
[~ i
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I .
s G
J.i o
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- p. *I ?. - .y ' .4<
3
! 2 ep f .,
- 1. 9 ly .
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? -
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\.
2 b
i
'.4 NRC 5 (A-23)b
\- .
?
4.7
, .~. . . . _ ... .- _ . . . . ..
?
y 71 1 HOPE CREEK GENERATING STATION
'! NRC CASELOAD FORECAST {
.m j E."
- 5. PIPE HANGERS I
Question: Detailed review and current status of all large and small bore
, pipe hangers, restraints, snubbers, etc., including design 1 rework, procurement, fabrication, delivery and installation, q
A. INTRODUCTION l d.
-d The Hope Creek pipe hanger effort has been a key program to construc-d tion completion. A major effort has been devoted to complete the .
j construction of large and small pipe hangers and consequently has y positioned Hope Creek ahead of dere other projects were six months
,j prior to fuel load.
t?
d There has been very little rework of large and small bore pipe hangers,
'I as a result of the As-Built Reconciliation (ABR) program. Very
{ few changes have been found necessary to date and those were of a minor nature. Sufficient material is on site to support any anticipated future modifications.
(:;
~
j ,% B. CONSTRUCTION STATUS AS OF JUNE 18, 1985 9 ' + ' T4 j \ ll fj - Restraints - - Snubbers -
} Large Pipe Small Pipe Inside Outside Large Small i Hangers Hangers Drywell Orywell Pipe Pipe
-~
Li b Total 15,714 21,578 149 70 1,195 149 L
. Installed 15,515 20,940 146 58 1,195 135 To Go 199 638 3 12 0 14 -
1 C.
SUMMARY
l Based on the foregoing and the construction status above, as well as, the status of the As-Built Reconcillation program discussed in Section 12, hanger installation supports a December 1,1985, fuel load.
p.
e-NRC 6 (A-1)d (s
~
5.1 e-
y . a:
u
- .~
- ~a .s.=..... . . . ~ . . .
4 HOPE CREEK GENRATING STATION
- ] NRC CASELOAD FORECAST iC?, 6. PROJECT SCHEDLLE
- Question
- Detafled review of project schedule identifying critical
- j path items, near critical items, amount of float for s; various activities, the current critical path to fuel G loading, methods of implementation of corrective action
,; for any activities with negative float, and provisions a for contingencies. The estimated project percent y comalete as of May 31, 1985.
F.6 1
$w A. INTR 000CT1]N fi The project plan to maintain a bulk installation mode of construction through Ic83 was successfully implemented. In 1984 two significant changes we re made. The remaining scheduled activies were evaluated with the object of setting the most aggressive schedule for completion i of all in:;tallation work leading to system and room turnovers in an orderly f.1shion. This resulted in advancing fuel load by six weeks to December 1, 1985, and code hydro four weeks to March 9, 1985. The e latter was accomplished one week early. The other change was the creation of eight system teams with dedicated personnel from supervision, T., engineering, QC, and planning. Each team was given the responsibility j for ensuring that their assigned systems were turned over on schedule j with minimum exceptions.. This concept has since been expanded to add
] g a startup engineer and planner to each team for integration with startup.
D
~
1 Turnovers and preops were levelized to eliminate peaks in the programs.
l A release for testing (RFT) program was initiated to turnover components 7 to Startun in advance of complete systems to provide them maximum flexi-bility. To date 1,301 out of 1,373 RFTs identified have been complete.
Problems of other projects were evaluated and systems such as the diesels
- were advanced to allow fqr them. j While no contingency per se is included in the schedule, weekly meetings are held between Construction and Startup to identify any changes in the critical paths and at that time workarounds are developed to support the requireme nts. -
As of May 31, 1985, Construction is 98.4% complete. The four critical paths are listed below:
FLOAT THIS MONTH TO 12/1/85 FUEL LOAD
- 1. Comoletion of NSSS preoperational tests. 0 1 2. Recaipt of equipment and construction completion 0 to +1 wk.
7 of the radiation monitoring system.
, 3. Construction completion and turnover of HVAC 0 to -1 wk.
- i. syst ems. (Including GRA, GUA, GKA and GHA).
- 4. Cons truction completion and turnover of the O to 11 wk.
soli.1 and liquid radwaste systems.
NRC 6 (A-3)a 6.1
- , - . =- - .. = __ _ ____ - _ . - _ - - . . _ _ _ - - - _ _ _ - _ _ . - . . _ - _ , .
,e 'w i i
.s.. . . - . 1f . . .. _j ,
Ed , , , . \*" E V .MoSn T r.EMIV 1985 no.T,9 U[ fair .Las y vig,3, UMb Z8 ogeca.ersa.\a.o JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC wip 2 /. . 3/gs gfag it af 4 293 S/.28 .o 25 8./. 3 3 82 /8 8 0 , T 6/a Y 3ita senT 1%.S#IsA V T7 7 I '
....... nusen.u... ...uiuun . ..u...uiu . . .u u n.. ... .u.Te nuu..' \
l NSSS I I iCMull iO j g
, Id ees.S f. H5 3/JS TO.Ma$ CPI'N . p 3/Taa f
.ss .o/3s CPT Co L 1 uCI.C 6
n/S 9/M
,tia sanat s at u.po J ug unopuu..no.tuno. st F
j _5' tea Ifst g
, _ ...........o -____
acAcim eumonuo s/.. .g . . ... ./ u d cpi. CONS l RUCi.O I
,,G/ 0. 4. .e. . . . . .
8/ 07. l }
,,,,,A mro f L.it u.a..T.E.S.i.. .
.n./.S. . . . u . . Op ..pg.gy...O........
O .t. .a.t. O. .()
2 HVAC g .tutg tw .j
- - Y. . . . , _____
G ia ,
S/2 & g gt mL SI
' " " ' ' ' - ....tif l' f'9
....onun ,uthuunu d'.'.Suug.'.".'.'a.!! A' .oon.uSjj r" c"* '""'
coninot eua.oeuo ',
P0tt Liam
. 8 4 f
- % QWE818.u.. 9 _ _ __ < g ca a rmat at.P. saI f CPI. Ci Simesri.0 n PNLOP pgggg gggy gg j RADW AST E BUILDING o nu...8./30f).uuQuan un nu n/S unun Opu u eu...u..uu O p.guQu 7 7
c.n .
to I
- , .ssus is s.cm. raou at uals a - 8 enu.()...u. st.a.n. u . a.t.e. n. .s. . u . . .g)a.s.i.t.u.
n . a.ou.ie.{)c,a.t..m.a.a.i.T.,,.u..u.....(fg
, n 3 mm RAD /
oeuvtav :Hu o.r. .sanu ou*.m..a.i..u .- . . . . . . . . . u .)> '!'uve "'o i
g l
j FUEL R :CEIPT REOJIRED EOulfMENT g WILL BE TESTE.) DY 9/1/i l5 l i .
- Wa-D O httfast LIQulO RADESTE #'"*""*' "" -
"M. . . . .. . . . i . . . . . . . . . . . . . . , ...........u.i *
, s .. . . . . .. . . .f.$..IQ Q< !.*.O..@ - ,
aca s/ns */3s atte er io.co ,
, Cei. <.O sna>Ci saio HAomsic , 0, ,.,;;..- .u.......nu ...u.........' O . a u .,.,.,. ,. . .......On. un.u O -
4 RADWASTE i
I Joe NO*
HOPE CREEK g tcmN : samus PROJECT GENERATING %sf Osrsic=><a v " ies acv 4x CRITICAL PATH 15EG --- c a...a i
SUMMARY
"'y i'
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- . .. . . . . ....m.. ~ - -
_ w. .. e.
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pf k
/ 3: -
i - . . ... . . . . . -
" ' ' '"~ '
- 6. PROJECT SCHEDULE B. CRITICAL PATH ANALYSIS IPS REV. 4 Q - MAY 26, 1985 STATUS PATH NO. 1 -
NSSS PREOPERATIONAL TESTS TOTAL FLGAT LAST MONTH: 0 TOTAL FLGAT THIS MONTH: 0 l ........................................................................................................................
PATH DESCRIPTION / PROBLEMS CORRECTIVE ACTION CURRENT STATUS In vessel NSSS preop testing Evaluate critical path and implement Critical path has been reviewed .
I in support of operational hydro, priority changes as required. in detail. The critical activ- !
ities are those preop tests that
! require use of RPV.
NSSS preop testing is on schedule. !
as The critical control rod drive preop is paced by modification to j valve seats. Modification work '
, and checkout to be completed by i the early July 1985 preop start.
i .
t j PATH NO. 2 - INSTALLATION OF RADIATION MONITORING SYSTEM TOTAL FLOAT LAST HONTH: TBD j TOTAL FLOAT THIS MONTH: 0 - +1 wk.
The original radiation monitoring Procure an RMS system from another The project has issued a purchase system vendor, Technology for vendor (s). order to GA Technologies (Sorrento' ,
- Energy, Corporation, has failed Electronics) for a standard RMS to meet its obligations. system.
The project is negotiating with NUS for management of the inter-face between Sorrento's RMS system and TEC's sof tware and hardware
- for report generation. -
NRC 6 (A-5)
(Cont.)
.- , . . -.:,.-,. - ~~ . . . :. , . - = , . . ~ ~ .. ,
- 6. PROJECT SCHEDULE i .
l B. CRITICAL PATH ANALYSIS (Cont.)
IPS REV. 4 Q - MAY 26, 1985 STATUS PATH NO. 2 -
INSTALLATION OF RADIATION MONITORING SYSTEM TOTAL FLOAT LAST MONTH: TBD (Cont.) TOTAL FLOAT THIS MONTH: 0 - +1 wk.
PATH DESCRIPTION / PROBLEMS CORRECTIVE ACTION CURRENT STATUS 1
.{
Assign personnel to a project Task force reporting to project '
task force to monitor supplier managers has been established. >
performance, resolve problems ;
expeditiously and coordinate i activities with Engineering, '
?* Construction, Startup and
- Operations.
i F
Develop minimal requirements Engineering, Startup and Construc- '
for RMS for fuel load (mini- tion groups have established re-system). quirements. ;.
Issue design of system required Initial design issued for Con-for licensing. struction on June 14, 1985.
Obtain materials on an expedited Local processor for new fuel criti-
, basis, cality has been delivered. Remain-der of equipment is scheduled to i support subsequent site activities'.
Commence construction of new Activities have commenced to modify system, existing installations.
Obtain vendor's manuals / procedures Existing manuals are currently being
- to support development of test submitted, and operating procedures.
,! NRC 6 (A-6)a i
i
- ,. 2. .. . ;: .: = -
- 6. PROJECT SCHEDULE
- 8. CRITICAL PATH ANALYSIS (Cont.)
IPS REV. 4 Q - MAY 26, 1985 STATUS i
i ........................................................................................................................
PATH NO. 3 - COMPLETION OF HVAC SYSTEMS TOTAL FLQAT LAST MONTH: 0 - I wk.
l TOTAL FLDAT THIS MONTH: 0 - I wk.
, i ....................................................................................................................... !
PATH DESCRIPTION / PROBLEMS CORRECTIVE ACTION CURRENT STATUS 1
Balancing and testing of the HVAC Expedite the release of the critical Checkout and rough balancing of f i ! in support of turnover to Opera HVAC systems to Startup. the major systems is underway.
i tions and Fuel Load.
Radwaste HVAC system (GHA) is the '
f" remaining critical system to be l-released from construction. This system is being worked two shifts. ,
Installation of spring kits for .
Reactor Building HVAC systems (GRA l and GUA) have been released to Startup. Testing of the sytem is being done on a two-shift basis in support of the NLRT scheduled for .
j October 1985. .
I Control Building HVAC system (GKA) has been released to Startup.
Testing has commenced in support of the PLRT scheduled.for October.1985.
NRC 6 (A-7) 9 9
. , . .. ... .. .s ...
4
- 6. PROJECT SCHEDULE B. CRITICAL PATH ANALYSIS (Cont.)
, IPS REV. 4 Q - MAY 26, 1985 STATUS Y
1 PATH NO. 4 - COMPLETION OF SOLID AND LIQUID RADWASTE SYSTEMS TOTAL FLGAT LAST MONTH: 1 wk.
, TOTAL FLOAT THIS MONTH: {1wk.
PATH DESCRIPTION / PROBLEMS CORRECTIVE ACTION CURRENT STATUS i
t Radwaste systems functional test Increase emphasis on release for Liquid radwaste systems were and preop testing. test and installation completion turned over for functional i of radwaste systems (11guld and checks June 14, 1985. [
! fa m solid).
Exteneded work week and multiple shifts being worked on solid ',
, radwaste systems.
Completion by construction paced by piping and equipment installa- <
tion.
I NRC 6 (A-9)a
- , m
. .' , ,t -
' T 4
4 3 STA1US - 5/31/85 0ATES 1984 up. DESCBIPTIOE senseMan C O 8818 E as T S TA80ET APPAaENT J_
r N A M J J A S O N D 84-04 Eastatt 12,600 Large Pipe Nangere Sullivan Cmpleted ahom$ of m:hedule.
SPC 08/13/84 01/07/34 T 04-02 Issue Fire Masards Analyele Henderson Cmpleted on schedule.
j sfC 01/16/84 01/16/04 9 44-01 Iseue Puh to meC Pedersen Campipted deal of mehedule.
l sPC 02/15/84 02/10/84 T foralbNtm NT)O /N FC 02/18/84 02/86/04 Y so-as publish Draft sea preston Cmple t ed .
petsG 62/28/e4 03/06/s4 VO se-06 naster sealpment List Caputer Program operational cielo complet.d .a .a ut es;a.euus e .
46teu ud/Je/u4 02/J7/04 Y i 84-07 Insta!! 340,000 17 conduit samlas Cmpleted aheal of echadule. ,
sec.
is 3/01/84 02/12/84 99 04-06 Cmolete Phase I of the vendor Ibcamentation cielo Copleted on schedule.
verificetton ssE6C 03/15/04 03/15/84 T g
l 84-09 umC SEA /m Cold License Certification Complete connor Completed aheal of e-hedule. i
- IEE6G 03/29/04 03/02/04 T on 34 10 Install 166,000 17 amall Pipe Sullivan Cumpleted aheal of schedule.
t#C 03/30/84 03/26/84 T N
84-!! tastalt 2.5 Mit!!an Founds of Duct tsark n 9 3
- 04/13/84 07/13/84
! e4-12 Install 100,000 is Instruent Teig moral Completed aheat of echadule.
DFC 04/20/84 04/06/04 T 84-13 Ckanplete Switchyard Step 1 for service Floyd Cepleted aheal of echadule.
Ist&G 05/05/84 04/11/04 9V 44-14 anosglee Switcaverd 125 WDC areten Floyd Completed aheat of echadule l 1 sessG 05/04/s4 02/01/84 9 9 l Completed sheas of schedule.
i 84-15 glegDe g la a modifications seeed cui seenderson gg Cmpleted on schedule.
04-14 g gtgg!! meer Deelga includire EDS rigt 9 Preston Copleted aheat of schedule.
84-17 usC % -Prodict Llannee 39 pessG 06'15/04 05/31/84 84-10 podereen Campleted aheal of echadule.
I Ener. to Dewetohthe outstandlag Ose First Iseuse 100 E/II runch!Isto on SfC 04/10/04 03/30/04 9 9 m3rms 3. ArtaamIT IETE WI15 IEEWSS $ 113875r13 mVISION. messa boss M
- 3. tasse 1aamT AIED Aremmert 31aT38 Amt IDAsTICAL, oss.r V Tea m T BhTS o .-am,, en =""='"=""- ,,,g g g =gr w e
- 3. V Om e lessCATm a assessTm sinissionis. ~
PtB Id StprICE E1ECTRIC 6 GAS GBtPANT j {
ano neerigone4ruggDepartment
- Dra.,n 2 Deto w .d D.te l
E PG3 124/21 1/3-erd Pro). L'ontr.%7d sCh l Cost Div.
- BSTABLISSED IN 1983 1
8 4
. _ _ _ . _ . . . - _ . __ _ ___ _ _ _ -. _ __ -. -_ . . , . , ~ _
.I
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1 STA1us -5/31/05 me. 9ESCaIPTIOu msnma DATES. 1984 *S S TAaGET APim8007 A a J J & o a p J y n C0555WTS 84-89 TM 4.16 IE Stattan pueser systeam t4uer Q apleted aheat of schedule.
~~-
afC e6/19/84 e5/31/64 EV e4 20 Caplete Qantrol shme Complea Imtegrated Test Colleman ermpaeted ahead of schedule.
SE86G 06/28/84 M/el/84 5 SE Quplete Aeninistration guilding Eagheseer g Completed aheat of schedule.
SE laetalt 440.000 W Conduit he -=
sec 3 V
~ ~~
Counpieted aheat of schedule.
e7/e6/e4 e5/2e/s4
' ~ ~ ~ '
44-23 Install 3G8.tes W amall Pipe seat van C o pleted.
07/13/54 42/17/05 V 3 44-24 saetalt 4.0 att!!an W of estro and Cable soudas Omapleted aheat of schedeale. '
1 SBC se/el/94 81/86/04 ~
EV
~ ~ ~~~ ~ '
. 84-25 TA 49er It substation poeser tasr C m pleted ahead of schedeale.
, BBC 08/07/94 46/2e/84 I V I 84-26 lasten! 14,500 Earge Pipe mangere g,ggg,,, Cepleted ahead of schedule.
88C et/81/84 00/02/64 g
'C.4 27Iseum Draf t gewiramental (heellfication Eheport tardateuskt Qapleted aheal og esingule.
55864 00/14/g4 agf,4,g4 gy 84-28 Sleestator Available FW Operator Trainig wg Completed.
USEaC to/98/84 11/05/84 Vg .
{
j
. 4-29 pelleen ytaal sta Preeean Qg Capleted.
q 3584G 88/12/84 88/99/34 3
! Ch g4 3g Co8 Plate Cooling Tower em !
- y Copletes ahead er schee,se ,
asC le/31/s4 tensg4 j-a e4-31 saetall 13e, , ,,,,,,,,,, ,,89 senrol
- C II/82A4 ee/24/s4 g y C=88**=8 shoes se sches.ne.
l ! e4-32 TM station service sent.r get. start Completed ahead og -raw.m n.,
I SSC 11/15/54 48/34/s4 y '
Mj Mg1eh Pinel snutreamental Impact statement - - -
[
f g Cool Gg Ompleted. l 11/16/04 12/19/34
' so-34 T M Qaid machine semp ,,, C"8 8* tat ahome of scheduto.
l -
sec II/2e/e4 sofol/s4 8V -
e,735 .
M_8 trit **e * *"' to 's"g8 -Polishias *"t--
Flumb or
'"#C ** iema. i / ./.4 , C-.iaed *e duie.
.4-u On ,iete i.3.5 Te mimaio.e ooge C=* a d * ' d =ha t -
,,,,,,,4 ,,,,,,,4 . v
.o 1 1333 mgass 1. Ar9heum? 1R3R INW mensa $ 3655 MBS3008. f fem %T
- v == '-
Er'M m X"mE =" " " '"'
o '.a"='
m.m.T .= ,,,m em8,,
i I
- 2. T Cs e Imacarse a amesse assamus. ,e e , . ,c, ,e ,an, es,,,,,
neer .a.gor a const.ruct
. . wetan,Departamat C eaed t.
El PGA 124/214/6-erd ora 4 oase u .
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ETAfue - 5/31/05 SATES ' e'4 1985 E ' t TAacst Aprea.gf O N O J F N A # J J A S i 44-37 T A energsacy Diesel Gomeratore secs aman Completal.
- ~" ""*********** **
"$E' 42/27/e4 e2/2Ves 9 3
- es-en TA mapreeston pool ass * * * * " " " " ' * * '
asc 48/02/05 82/31/e4 39 es-e3 oglete circnolettag pg structure sle Capleted aheat of scensdule.
i g g
'# '""I'*"*'**"'**""
"EaE ea/II/es e vla/es VE #"**** "'*# " *'" "' ***"' ** * *" * " "'C' eS-44 TA sua system,Ismetas Centalmesmas neu
, ,, , y,, y C-pleted ahees of actiedule.
es-45 start pre-ap ear Turtles aus, amolles syntes les-83 CN sa/as/es e6/2e/es 9 0 '***'W I'"* Se pollelse flush and flow enlease.
8 ,-ee . . .I t. .a.,
C- not .
- . u.. .w ./s, ,
. > . , =.r. 1.t r.t .4 ,, , Ca,, e, Capleted shoad of schedule.
8SEEG e Vle/e5 02/Il/e5 $Q SS-ee TA ruel pool and stol Caeltag System g g Completed ahead of scitadule.
es-4, l.a1.t. ma u,,,e,,
ij .T'Wi3*g- , **g '*"'-
, e e c, ei
,y,,,,, ,,,,,,es 9 a H'J"h*g
=
- en y Iisf. "act ir m g L
.n M. '4%*W.
. losase ayer ten Tra'Else Eagram tegen /7. en.ir
- i e5-84 Gedelt Tech. Spec. to esc Prestan completed ahead of schedule.
988a4 GV39/05 84/87/oS I 9 l
l SS-Bl Code ayero of theael aos Campleted ahead of echmoule. i
- not et/us/m3 #4/wJ/eb I9
- GS-4 2 Camplete mala Tiarblas ladte Olt Flueen er g g Completed ahead of acInedule. !
N 85/30/05 45/25/05 5 i es-l4 etart pre-eps for Fuel suol Coollag System Carter Campleted aheet of echadule, j sesac evas/es avas/es W eS-Is ceplete arymell anac pre-ep imettas Caster een work of f restralmed empletion of this milestems.
~
peanc e6/ eve 5 e6/le/85 9 i es-a i,- a,se.t i ! on = r- gg y = r-.i. - oc eduie.
- e. 3. -_._l: gegyl.
v--
oe-2.
w,ar.m s um." . -
,_.e.
missima si-r our ,
2- V = * ==ic== = ===== = ===e==. C, .C . . ,
t , ,
. neer ,,s.&.Casetaset.
a .. ~ aten-
.- " ^
- e i craun i este4+ss (1hecked gate .
m ,ei la4/al vo-ord
' woj. e-tr.sts C== ow.
e
.6_Ru _f4 e -Q......,. _ _: . ~ _, c-.: - . . . . _
i i
pa7ss atos status - 5/31/85 89e6 Ta8EET APPARENT J J A $ 0 asD J F M A .
- 4v11 TA turt.ime suildise garage sec 47/85/05 49/13/es V D Tur.awer algped as a seult ei the revised rom tur.-
w
.2 eo.Q.Let.
p g , g a g g 4
- gc,g gT g ,,,
g evie . e na.t s,eciei. soca a.mar ei.
s g;.4 ,,,,,,,, ,y ,,,,, , ca gi.tsa vvas. an.e a sci dui..
l es-i, r.. a. T- i c ,
cagg, ,,,,,,,, ,y ,,,,, g 9 on ,m, ..: un t e., o aout a,. ,.cs., it.,s.
'"" """*"*d'*** ' ~ ~
! '*Em" n/ eves e/ eves T 4vu rt co 8 .c i.e. T t - n = c e c.gg, ,,,,,,,, ,,,,,,,, , 9 e tr. i i., .~ a m , a. m.ie, ,s.r.
ev22 setanish puman=== esaat s.cwier s veta =
es-2
- M se/ sun n/en/es 0V Tm smiactor ausadise
, sigc ,,,,,,,, ,,,,,,,, ,M, am,a lgs=d,g ar coegi.t o. a i.e.{25.g;u,i,g a the [ge,gg g,o,,,= =
. ,fI .tfo*.
45-24 Perform 3.tegrated imak mate Test eS-25 emitchyard Step 2 Bealy for Service can 0 V On stillea.
PSE6G 82/le/e5 e4/el/05 * *campleted e-t-e5 ahead of schedule.
e5-24 !aeus F&aal seeironmentaa Quetiiicat to. Report eerg ek1 0 V i
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- 6. PROJECT SCHEDULE <<
O.
SUMMARY
5 '
3 The Hope Creek Project has d'emonstrated an historical pattern of j establishing schedule targets that are aggressive, but not unreal-
'.j istic, and being able to identify and apply the necessary resources
> to support their fulfillment. This is borne out by the findings of
~) the Theodore Barry & Associates management audit in 1984 which stated
- that with continued aggressive actions attainment of the fuel load q schedule is reasonably achievable. <
The project has completed its bulk installation phase within a timetable j which was established in 1983 and is tracking to the target fuel load i schedule established in 1984. The' project has the flexibility to
- 3 respond to any construction items developed during the final startup/
operation phases. At this time the target fuel load of December 1,1985, is fully supportable by Construction.
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i NRC 6 (A-8)b 6.11
HOPE CREEK GENERATING STATION
, NRC CASELOAO FORECAST
- 7. BULX COMMODITIES Question: Detailed review and current status of bulk quantities, including current estimated quantities, quantities installed to date, quantities scheduled to (. ate, current percent complete for each, actual versus forecast installation rates, in cubic yards /mo.,
. linear feet /mo., or number /mo., and basis for figures. Also indicate what percentage has been QA inspected and accepted.
A. INTRODUCTION ..
While the rates established at the time of the last caseload were very aggressive, they were met and the bulk installation phase is now essentially complete.
Remaining commodities being closely monitored are penetration seals and pipe and equipment insulation. The former is being driven by room turnovers and is currently out ahead of the effort. The latter is dependent on final hanger acceptance, which is currently being completed and which will release the remaining insulation. The remaining rates to go have been met previously and no problems are anticipated.
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l NRC10(A-1)c l
7.1
/
- 7. BULK COPMODITIES B. BULK QUANTITY STATUS COMPLETE RATE --- % COMPLETE ---
TOTAL 3/83 COMPLETE PER MONTH QC ACCEPT.
COPM0DITY FORECAST CASELOAD 06/14/85 SUSTAINED INSTALL. Q ONLY LG. PIPE HGRS (Q/NON-Q) (EA) 15,714 8,814 15,515 480 99 99 -
LARGE PIPE (LF) 299,200 230,900 298,666* 4,530 100 74 SM. PIPE HGRS (Q/NON-Q) (EA) 21,578 N/A 20,940 2,240 97 70 SMALL PIPE (EXCL. CRD) (LF) 218,000 59,208 216,599 7,270 99 89 CABLE TRAY (LF) 125,000 89,400 124,877* 3,530 100 99.9 560,000 126,006 555,026 16,000 98 95.9
{ CONDUIT (LF) <
WIRE & CABLE (LF) 7,030,000 199,423 6,862,221 312,400 97 93
{
I HVAC (PCS) 24,150 N/A 23,887 680 99 92.5 INSTRUMENT TUBING (LF) 199,000** 20,000 183,871 6,200 92 84 TERMINATIONS (EA) 293,000 N/A 262,024 10,400 89 88.2 PENETRATION SEALS (EA) 14,000 8,916 920 64 64 1,425***
INSUL. PIPE / EQUIP (OFC) (SF) 153,000 91,285 '
(JM) 33,200 28,039 186,200 119,324 11,500 64 N/A
- Through 5/2Ci85
- Quantities under re-evaluation
- To support room turnover ,
NRC 7 (A-16)1
. . - . . . . . . . . - . . . :. . . .n :: ... . . . ._
- 7. BULK COMMODITIES C.
SUMMARY
Remaining bulk commodity installation will support system and room turnovers.
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O NRC10(A-2)a 7.3
- -- . :.:. .. . _ . ~ . . - . ~
HOPE CREEK GENERATING STATION .
NRC CASELOAD FORECAST
, 8. STARTUP Question: Detailed review and current status of preop and acceptance test procedures, integration of preop and acceptance test activities with ccnstruction schedule, system turnover schedule identifying each system and status, preop and acceptance tests schedule identifying each test and status, current and proposed preop and acceptance tests progran manpower.
A. INTRODUCTION The Startup Group at Hope Creek is responsible for testing and maintaining components and systems turned over from construction until released from testing to operations. 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 supple-mented by contract personnel who also work within the startup group organization.
At this point, the startup program is 66 percent complete and well established. Administrative procedures are-in place. A testing schedule integrated with construction has been in place since late 1983. System scoping and turnover boundaries are finalized; generic procedures are complete and preoperational procedures are being q ,
finalized.
The program places priority on early planning, highly experienced ,
- testing personnel, and maximum utilization of operating department personnel.
The following listing provides an overview of test program activities through the startup phase. Generally, Phase I is construction -
verification, Phase II is initial operation and preoperational testing, and Phase III is the fuel loading and power ascension
- phase.
PHASE I 1
- a. Perform Hydro Tests
- b. Megger Cables and Equipment
- c. Rotation Equipment Alignment and Coupling
. d. Initially Energize and Calibrate Circuits
- e. Perform Walkdown and Turnover PHASE II I l
- a. Initially Energize Power Systems i
- 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 NRC8(A-1)b 8.1
. . . _. . .. , 1
'- 8. STARTUP A.) INTRODUCTION (cont.)
. With the majority of Phase I testing complete, emphasis has shifted ~ to
- Phase II testing with particular concentration on performance of l i ; preoperational tests.
Progress to date includes the successful turnover and integrated testing of the Control Room Complex ahead of schedule. This milestone
- was followed by plant energization, which was completed on schedule with the completion of both condensate polish flush and NSSS integrated L flush / code hydro ahead of schedule. The project is now confident of achieving a December 1,1985 fuel load. -
B. RELEASE FOR TEST PROGRAM The release for test (RFT) program was designed and implemented to expedite testing and provide for the identificatior, of system problems and resolutions. The RFT program allows Phase I and limited Phase II testing to be conducted prior to system turnover from construction.
The planning process for RFTs is usually initiated 18 weeks prior to '
system turnover. Approximately 10 weeks prior to system turnover Startup is able to begin testing. The RFT program, therefore, effectively adds 10 weeks to the startup testing duration.
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- 8. STARTUP l B. RELEASE FOR TEST PROGRAM (cont.)
Typical Testing Activities Conducted Under the Release for Test Program Energized testing, calibration and inspection activities performed by
- j the Startup organization under the Release for Testing (RFT) program.
G
- PSI Nuclear Class 2 Examinations
- Initially energize and calibrate analog circuits
- Inspect, test and calibrate instruments -
- Bump motors for rotation
- Test power transformers and major electrical equipment
- Initially energize and functionally check digital control circuits
- Perform high voltage insulation tests
- Run-in and vibration test motors uncoupled
- Calibrate meters and relays
"! c.
- Install temporary startup test equipment
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- Megger cables and equipment j
- Stroke control valves, dampers and mechanically set limit switch
- Electrically operate MOV's
/
- Run-in and vibration test rotating equipment
)
- Cleanliness flushing on selected piping systems j
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- 8. STARTUP
/[ ' ,
,- .7 C. SYSTEM TURNOVER PROGRAM Phase I and II testing not conducted under RFT is performed by Startup
, after system turnover. At 8 weeks prior to the scheduled system turnover, the initial system walkdown occurs. During this walkdown system completeness is established and the remaining work is identified.
t
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1 A 8. STARTUP 3
j S;;,1 D. PROCEDURE STATUS
[; All Phase I and II tes't program procedures required for fuel load have
- ., been started and completed with the exception of preoperational tes't procedures.
Below is a listing by type, total number and status of procedures
[] required for fuel load.
a Ji Total Number of Procedures for Fuel Load _
g -
Startup Not Started But In Procedure Started" Not In Review Review Approved Total
]3
- f.! Startup Admin.
i' Procedures (SAP) 0 0 0 26 26 3 System Flush
,, Outlines 0 0 0 64 64 System Turnover Plans 0 0 0 132 132 h Generic Procedures 0 0 0 28 28 s
- j c.
- % Preoperational b w Test Procedure 0 20 48 79 147 M
i, Total 0 20 48 329 397
]
j Preoperational Test Procedures (PTP's) are the highest order of i technical procedures in the Phase II test program procedure development l
is proceeding in support of a December 1,1985 fuel load date. All PTP's have been drafted. Preop procedures cover both "Q" and "non-Q" systems and are being written and approved on site. All preop procedures are planned to have final approval by October 15, 1985. The following
. logic sequence has been implemented to provide a thorough review:
Steps: (A) (B) (C) (D) (E) (F)
Issue Issue Test Issue Preop Preop Rough Final Review For Meeting Test Draft Draft Board Preop Start Typical Duration: 4 weeks 2 weeks 1 week 2 weeks 9 weeks (Qsystems)
A recent enhancement to the preop test development program has been the establishment of a Test Review Board (step "C"). The test review board, an integrated. body, is comprised of highly experienced personnel
/ representing startup, engineering, operations, and QC. The review board perform an in depth review of the "Q" PTP's for technical adequacy.
- . This review process has resulted in a high quality procedure which
'O minimizes the amount of system retesting.
{ NRC 8 (A-6)a 8.9
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R H C D E F 6 PilEOPl O IDESCRIPTION ICOMMENT IDATR I ISSUE I COMMENTS I ISSUE I TRS I TYPE / l PORC I PREOP IC NO. I I I I I ROUGH I INCORP 4 FINAL I MEETING IISSUE FOR I MEETING I DATE SH ^
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I I I IFCST I i 120-Jun-96 125-Jul-95 I ISTATuSICOMPLETE ICOMPLETE 8 I I I I I I 8 8 116-Jul-95 129-Jul-95 806-A g-96 819- A g-85 126-Aug-65 I KE-1 I lgpEATH RIR I ISCHED l i I IFCST I 121-Jun-86 128-Jun-86 I I I I [
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'" QH-1 8 ICATHODIC PRDTECB ISCHED 8 I I I I i 127- Ag-85 8 ,
J 8 IFCST I I I B12- Ag-95 I I I I l 8 ISTATuSICOMPLETE ICortPLETE SCtatPLETE I sconPLETE ICOMPLETE I I ,
I I l ED-1 80 leACS BREVIEW ISCHED I I I I I i 129-A g-85 I I ICYCLE IFCST l I 104-Jul-86 I I I I I I i I l 3 3 I ISTRTuSICOMPLETE ICorFLETE ICOffLETE I810-Jun-95 ICOMPLETE 117-Jun-95 ICOMPLETE I IO1-Jul-05 150-Ng-85 8 i GK-1 IQ BCNTL/ WING HVAC IHOLONG ISCHED I I I I I I IFCST 8 I i 126-Jun-95 101-Jul-95 111-Jul-85 8 8 8 ISTATUSICOrtPLETE SCOMPLETE ICOMPLETE I 8 I I I -
8 8 SK-1 10 IlEAK DETECTION I ISCHED 1 1 127-May-96 810-Jun-OS 817-Jun-95 101-Jul-65 150-Ag-05 I ,
l I IFCST B 125-Jul-96 101-Ag-96 112-Aug-85 111-Ag-66 428-Ag-85 I I
! I I i 1 I I I ISTATUSICortPLETE 8 8 8 I I I .
I SE-3 IQ I m MF RAD MON I ISCHED I I I I I i 150-Ag-86 8 ,
8 8 8 IFCST I I i 109-Ag-96 I I e i I 8 I ISTRTuSICOMPLETE ICOMPLETE ICateLETE 8. ICOMPLETE ICOMPLETE a i SE-3 10 IPOWER RHD ftON I ISCHED 8 8 8 8' I I 8 50- Ag-85 I ,
I I I IFCST I I I IO9-A g-96 I I I I i 8 I I 8513TuS ICOrtPLETE ICOMPLETE IColfLETE I ICOMPLETE ICOMPLETE I 8 HC-2 8 0 ISOLID RAD COLL INEW PREOP ISCHED 822-Jun-95 8 820-Jul-96 105-A g-96 110-Ng-66 121-Aug-05 158 -Ag-85 I l I I i I I I IFCST I I I I 1 -
I ISTATuSB t t l I I I 1 I 8 HC-1 IQ litW auk BLR R ISCHED 8 1 129-May-96 111-Jun-96 lle-Jun-85 102-Jul-05 851-Ag-85 1 6 t
0 01 8 8 8 IFCST I 8 08-Jul-96 816-Jul-96 121-Jul-e6 801-Ag-95 115-Ag-65 8 8 8 8 8 ISTATUSICOMPLETE I I I I 8 8 8 .
HC-1 le Illu CONCENT FEED 8 ISCHED 850-Apr-e6 8 129-May-96 111-Jun-96 Ile-Jun-95 102-Jul-OS 851- Ag-95 i f 09 I I I IFCST 4 8 8 111-Ag-95 115-Ag-OS 122- A g-65 I I l 0
8 8 8 ISTATUSB 1 I g I , 8 8 8 ,
DURATIONS 8-C=1 WEEKS.C-D=2 WEEKS.D-E t WEEE,E-F=2 WEEKS,F-6:60 DRYS FOR O i
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)i IES. I I I I I pouGH I INCOIIP I FINAL 8 #EETING IRSSE FOR I MEETIME I DATE IH I I I I I DitMT I I DitMT I 8 POIBC 8 I IN t
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te-E 4e iRW AESIN REGEM iSEME5 ISCHED I I I 50-Meg-SEE 813-Jun-85 820-Jun-SS 809-JuI-86 102-Sep-95 g ,l r
8 8 8 IFCST I i 124-Jun-85 805-A g-85 IB2-bg-85 126-b g-85 8 8 1 4 8 8 I ISTAtuSICOMPLETE ICorrLETE 8 I I I I 8 ,
? GR-1 le ISM StOSDWRC 8 ISCHED I 8 150-Meg-GEE I15-Jun-M 1;O-Jun-SEE 809-Jul-96 IO2-Sep-85 I ;
8 8 8 IFCST 8 828-Jun-86 I05-Ju!-95 iL7-Ju!~*5 824-Ju!-95 107-A g-85 8 I [
8 8 I ISTATuS8CGerLETE I B 3 : I I e !-
7 SC-E le litM IIIST LPM i ISCDED 8 I I I I 8 805-Sep-95 I .
3 I 8 8FCST 8 8 8 8 8 8 I I ..
I I I ISTATuSICOerLETE ICOMPLETE ICarLETE IM/A ICOerLETE ICOMPLETE I 10i i
OK-1 10 SFIstE/See: DETECit ISCHED I a 802-Jun-GS tl6-Jun-85 825-Jun-86 IO7-Jul-85 IO5-Sep-95 t i.t 1
8 8 8 IFCST I I25-Jun-85 129-Jun-SS IO9-Jul-85 116-Jul-85 850-Jul-95 I i i 8 8 I ISTATuSICorrLETE I I I I I I I
', GF-5 8 ienstitmeSE twAC 8 DELETED 8SCM D I I I I I i I05-Sep-85 I i I 8 IFCST 8 8 8 I I 8 IEELETED
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! .32 8 8 8 IFCST I 125-Jun-95 IOR-Jul-85 8 82-Jul-SEE I I I I . i' 8 8 8 ISTAtuSICoprLETE I I 8 I I I I '
t l Dec-1 le imed REPtWILT SYS 8 ISCHED 8 8 804-Jun-e5 tie-Jun-95 8 25-Jun-GE5 809-Jul-85 IO7-Sep-85 8 ,
.09 I I I IFCST I 850-Jun-85 I t5-Jul-95 IOR-bg-SEE lO7-Ag-85 820- A g-85 8 8 's '
4 8 8 8 ISTAtuSICorrLETE I I i i I I i -
flC-4 80 IPDST ACCID SPLElHOLD ISCHED I I IO6-Jun-95 120-Jun-96 127.-Jun-96 811-Jul-95 IO9-Sep-95 1
~ l I I IFCST I I 814-Jun-85 I I I I I ;
8 8 8 ISTATusiCorrLETE IConFtETE I I I I I I ~i l WG-1 10 854 m DWRC I ISC6ED 8 I 806-Jun-05 120-Jun-SE5 127-Jun-06 I t t-Jul-85 I O9-Sep-SE5 I .1 R
- I B 1 IFCST I 121-Jun-85 IOL-Jul-85 813-Jul-e6 8 8 8 !
. I 8 I ISTATuSICoprLETE 8 8 8 . I I e s ;_
est-4 10 BOIESEL HWRC SGHOSE 8SCHED I I i 128-Jun-85 I I 810-Sep-eE5 8 I I I IFCST 8 8 9 121-Jun-95 I I I I I I I ISTATUSICorrLETE ICerLETE ICGFLETE I ICoorLETE ' - ICOerLETE 8 I GL-1 1 ISV m HWRC I ISCHED 8 8 I 3 5-bg-SEE 8 I I IO-Sep-SE5 a i l i B B IFCST I 8 i i15-bg-eEE I 8 . I 3
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i CC-3 8 ISEM ens CTL I 85CHED 8 8 8 I I I B20-Sep-85 le ' i
"- t I IFCST I i 3 I 8 8 : I I I I I ISTATUSICarFLETE SCOfrLETE SCGWLETE IN/A ICOMPLETE ' ICOMPLEIE I i l SE-4 1 4TEP 4 ISCHED 8 8 gos-h g-e5 la y 650-b g-95 It3-Sep-85 120-Sep-SES B 8 I 8 SFCST 8 I I99-J.ee-85 8SS-Jus-eE5 8 8 8 8 8 8 8 ISTAtuSICGerLETE ICaprLETE B e I I I I j DutRTIONSa A-C=1 ursrc.C-O=2 WEEKS.D-E=1 NEEK.E-F=2 4EEKS.F-6=60 ORYS FOR O , i
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____I___I ______I ______t I -_ _ 8 _ =l__________I_ - - __i__________Is
.i DC-4 80 les Ow*ee CafGE I BSCHED I I I SS-Jun-85 te2-Jul-85 809-Jul-85 125-Jul-85 828-Sep-85 8 I i .82 I I I 8FCST 8 B 25-Jun-85 129-Jm-e5 405-Jul-95 8 8 8 I l l 8 8 ISTATuSICOestETE I I I I I i 8 ,
! DC-1 le OEMiam-EVfr/ PERI 8 SCDED I I sle-Jun-SE 102-Jul-95 809-Jul-85 825-Jul-95 128-Sep-85 8 ;-
- .e5 8 I I IFCST I 450-Jun-45 toe-Jul-85 IOF-A g-SS tl6-b g-85 150- b g-85 I I if ;
l I I I ISTATuSICOMPLETE I I I a 8 8 8 i~
- CH-1 B IIst Taste CEDs OILI ISCHED 8 I I 8 I i 125-Sep-85 i b{
I I l IFCST I I 8 8 I I I I 8 8 3 -
t iSTATuSICOMFtETE ICEmePLETE ICOMPLETE 8M/A 8COfrLETE ICOMPLETE I I ?
CJ-2 le IEsER stESP COfW" 8 BSOED I i 120-Jun-e5 IO4-Jul-85 818-Jul-e5 125-Jul-85 125-Sep-85 8 1 8
I I
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, I I IMCdiefde 8FCST I 8 8 814-Jun-85 I I I I w' 1 8 I 8 55iATuSICorWtETE ICENWEETE ICOMPLETE 8 8 I I l l
HC-1 1O Iau CENTRIFUGE I ISCHED I I 825-Jun-85 I09-Jul-85 II6-JuI-95 550-Ju4-85 829-Sep-85 8 i G' co .65 8 8 I 8FCST I 127-Jun-85 Ice-Jul-95 IO9-bg-e5 816-bg-85 850-Ag-85 I I 8 8 8 ISTATust i 8 I 8 I 8 8 i e De-2 le IDEM P90 CESS I ISCHED 8 8 127-Jun-e5 Int-Jul-85 lle-Jul-85 IOt- b g-95 150-Sep-85 8 T- !
I I I 8 8FCST I 127-Jun-85 ace-Jun-SS It9-Jul-85 126-Jul-85 Il5-hg-95 I I i i l 1 3 ISTAluS8COfWtETE I 8 8 I I i 8 De-4 le am smuTafL I ISC4ED 8 8 127-Jun-e5 Ill-Jul-85 lle-Jul-85 IOt- b g-95 150-Sep-95 8 '
8 8 8 8FCST 8 IO9-Jul-45 836-Jul-45 850-Jul-85 IO7-b g-85 128-bg-85 I I i
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l 8 8 I ISTATuSICapWLETE 8 8 8 8 I I I i ;
De-5 iG IW FLom IMinlM i iSCHED.I I I27-Jun-85 113-Jul-95 Ite-Ju!-95 80t-Ag-85 850-Sep-85 8 '
I 8 8 IFCSI I I I20-Jun-95 855-Jul-85 I I I i j t 8 I ISTATuSICOMPLETE ICOMPLETE I I I I 4 e i te-6 8G leu CONCENTinATORBluHist iSCHED 8 8 I I I I I50-Sep-85 I l 8 8 8 DELETED 8FCST I I I B 1 8 8 I I i i ISTAluSI I I I 8 8 4 i SF-4 8 IltEPte.T STS HWRC4 ISCHED I 8 I I 8 1 150-Sep-95 1 '
8 I 8 SFCST 8 8 8 8 8 I 8 I I I I ISTATuSICOpePLETE ICINEPLETE ICQpWLETE IN/A ICGeeLETE 8 COMPLETE I i 4 fE-2 le IFEECBWITER t vedetts ISC4ED 8 I I i 4 8 IO2-Oct-85 le 8 I I IFCST 8 I I I I I I L i I 8 I ISTAiuSICCsWtETE ICGestETE ICerLETE ICofrLETE SCoestETE ICOfWLETE I I .
WS-1 80 IILRT I ISOED 8 8 ion-Jul-85 ISS-Jul-SE 122-Jul-95 805-bg-95 IO4-Oct-85 8 l 1 I I 8FCST t 805-Jul-85 Il9-Jul-85 126-Jul-85 IO5-b g-85 117-bg-85 1 8 -
8 8 8 IS1ATuS8COfWLETE 4 I I I I I i t i SA-1 le leeCS I ISCtED 4 I IOR-Jul-e5 Il5-Jul-85 122-Jul-85 IOS-Ag-95 IO4-Oct-95 8 t 8 8 I 8FCST I Il5-Jul-45 125-Jul-85 IO7-b g-85 lli-b g-85 129- A g-e5 8 I I 8 8 ISIRTuSICDsqPLE1E I i i i I 8 8 69-3 le teu EGutP OpintM i ISCHED I 8 IO4-Jul-85 8te-Jul-95 125-Jul-95 IOG-Ag-95 IO7-Oct-e5 I e 8 I IFCST I 808-Jul-85 iBO-Jul-85 lle-Jul-95 I I I I 8 8 8 851AfuSICopePLETE I I I t I I I DisIATIOM5s A-C=4 6EEKS.C-D=2 NEEKS.D-E=1 NEEK.E-F=2 wars.F-6:60 OfWS FOR Q
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A 8 C D E F G t core 1ENT IDATA 8 ISSUE I COrtMENTS 8 ISSUE I TRS I TWE/ 8 PORC i PREOP IC i PSEOP3 O IDESCRIPTION ~
MD. I I I I 8 ROUGH I INCORP I FINAL I MEETINS IISSUE FOR I MEETING B DATE SH B I I EMAFT I I DRHFT I 8 PORC i I IN l i I I ~I I I I I I ~IG II 829- N g-66'I82-Sep-86~ll19-Sep-e6 In-1 8 8<SE0pS phi i ISCUED l 8 IO5-Oct-86 810-Oct-06 I '
3 8 IFCST I 115-Jul-66 151-Jul-86 416-Ng-86 8 I I I ,
5 I I I ISTATUSICOrtPLETE I I 8 I I I I IF-1 le illeLsesT COpel 8 ISCED I L l 8 i B llO-Oct-86 I i I t RFCST 8 I i 128-Aug-86 8 I 8 8 i I i I lSTATuS1CartPLETE ICOMPLETE ICOMPLETE I ICOMPLETE ICOMPLETE I B RC-5 10 litM SLD6 SarrLE I ISCED 8 8 114-Jul-66 128-Jul-86 IO4-A g-86 Ile-A g-86 B17-Oct-96 I I I I IFCST l IO5-Jul-66 110-Jul-86 826-Jul-86 I I I I 8 8 8 ISTATuSICOMPLETE I I I I I I I ,
SP-2 IQ IPROC RAD MONIT BHOLD ISCHED 817-Jun-86 8 816-Jul-96 129-Jul-86 IO6-Ag-86 119-Ag-86 118-Oct-86 8 8 I I IFCST I I I I I I I 8 5 I I ISTATuSt 1 8 8 I i I 8 88-5 IG RECCS L(P l ISCHED 817-Jun-66 I I!5-Jul-66 829-Jul-66 IO6-rbg-86 119-A g-86 118-Oct-86 8 1 I I 8FCST 819-Jul-66 IO9-Ag-95 416-bg-66 150-Ag-85 IO7-Sep-06 121-Sep-86 I I i I I ISTATuSB 8 . I I I I I 8 SC-1 B 1 ALM BLD SarePLE leHATLEY ISCHED 8 8 8 824-Sep-86 IO1-Oct-86 Il6-Oct-96 822-Oct-86 8 !
I B IHOLD-DIR IFCST 4 I 8 tol-Jul-86 8 a l I am i I I ISTATuSicorFLETE SCOMPLETE BCarrLETE I I I I I ;
120-Jul-86 IO3-bg-86 110-A g-86 124- N g-86 125-Oct-86 8 y HC-1 10 ISLDS TR/ FEED 8 ISCHED 122-Jun-86 8 o OSS I I I 8FCST I I I IO1-bg-86 I I I I I I I 85TATust I I I I I I I AC-2 8 BTisle SAMPLE I ISCHED i l ll2-Sep-46 126-Sep-96 IO3-Oct-86 137-Oct-96 124-Oct-86 I ,
I I I IFCST I I 122-Jul-96 150-Jul-86 8 I I I ,
8 I I ISTATuSicortPLETE ICortPLETE I I I I 8 i AC-1 IG IMAIN TURSINE 8 ISCHED I i 121-Jul-86 IO4-bg-86 813-Ag-86 525-Ag-06 124-Oct-96 I I I I 8FCST I 312-Jul-86 821-Jul-96 IO2-A g-86 I I I I I I I ISTATuSICOMPLETE I I I I 1 8 i 50-1 Ie I ARetS ION ItuLD 8SCHED l21-Jun-05 I I22-Jul-86 506-bg-SM
- 12 esug-66 8 26-Ag-96 125-Oct-86 i B I l IFCST 8 8 8 8 I I l 8 I I I ISTATust I l i I I I I HC-1 le litbl FILL. STrtTIONS ISCHED I I B25-Jul-96 IOS-bg-S6 835-Ag-86 129-Ag-06 126-Oct-06 I 0 06 8 I I IFCST I B15-Jul-86 126-Jul-66 IO6-A g-86 I I I I I I I ISTATuSICOMPLETE I I I I I I. I sec-5 8 G Im.la au Evne INEu PkEOP BSCHED 804-Jul-95 5 808- A g-86 IS6- A g-S6 122-Ag-66 IO6-Sep-06 IO4-Nov-96 I I I I IFCST I I I I I I I I I I I ISTATuSI i i 8 i I I I 8
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- 0. PROCEDURESTATUS(cont.)
. The preoperational test procedure writing group is comprised of highly U experienced personnel. Staffing levels supporting the procedure
,;j issuance schedule have been achieved by individually selecting personnel p from within PSEWi's organization as well as Bechtel, General Electric,
'J and other contractors. .
I ,
Procedure quality has been assured by an integrated Test Review Board.
9 Adherence to the procedure development schedule is monitored on an y ongoing basis assuring timely completion.
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,- 8. STARTUP E. PREOPERATIONAL TEST STATUS 4 .
,l System preop testing is well underway. Testing continues to support L: within the early/ late start requirements of the project integrated
',' schedule. With procedures in hand, detail schedules are developed to
<, identify test prerequisites. Daily schedule review meetings are conducted by integrated construction startup team members (discussed i
in Section :,1). Meetings review outstanding scheduled. activities and review readiness.
l The last of the 147 preops are planned to be complete by November, one month prior to fuel load. Currently, preops have started and completed on most all of the electrical power supply systems (earliest construction turnovers). Additionally, many tests have started and completed on the service systems. With the integrated flush, RPV code hydro and reactor internals now complete preoperational test emphasis is centered around starting the nuclear related preops.
Test progress is indicated on the following pages.
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- 8. STARTUP
- . F. RELEASE FROM TEST TO HOPE CREEK OPERATIONS As an extension of the preop schedule advancement in support of an i early fuel load, an enhanced release from test to Hope Creek Operations 1 schedule was developed. This schedule allows for a period of four weeks from preop test completion to release from test. A number of .
activities, supported by both Startup and Operations personnel, are i scheduled into this time frame.
g , RESULT 5 _ .
a _ . . . .. APPROVED
'. TEST FIELO , RELEASE TO . .
COMPLETE , PRELIMINARY PACKAGE HC0 SE'IT TO HC0
, RECEl4E AND _
~
O!SP0$! TION COMMENTS _
j i
- Schedule progress is tracked both in the integrated project schedule 1 (IPS) and by 5tartup in a weekIy pro
forecast dates against the schedule.gress report reflecting current
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e i 8. STARTUP
- ,s.3 F(a). PACKAGESRELEASEDFROMTEST(ACCEPTED)
.l 4
RESULTS RELEASED QUALITY 9' DESCRIPTION PROGRAM APPROVED FROM TEST
,i AM-1 Fresh Water Supply 08/03/84 01/18/85 NO FA-1 Aux. Soiler 11/14/84 01/24/85 N0 GO-1 FirePumphouseHVAC 11/20/84 03/06/85 N0 m
GF-1 Aux. Soiler 81dg. HVAC 02/15/85 03/27/85 N0
]
j GF-2 CWPH HVAC 01/22/85 02/27/85 NO KO-1 Domestic Water 02/27/85 04/01/85 N0 MC-1 Switchyard Buses & 13.8 12/18/84 01/24/85 NO NA-1 7.2 KV Station Power 11/09/84 01/18/85 N0 NS-1 4.16 KV Station 02/19/85 05/10/85 N0 1
4 y
N NS-2 4.16 KV Station 02/19/85 05/10/85 N0 !
U NS-3 4.16 KV Station 02/19/85 05/10/85 NO I NH-1 480 V MCC 04/16/85 05/08/85 NO NJ 1 250 VOC Non-1E 04/02/85 05/17/85 N0 NK-1 125 VDC 04/26/85 05/15/85 N0 L
P8-1 4.16 KV Class 1E 04/12/85 05/10/85 YES l
{ PH-1 480 V Class 1E MCC Power 04/19/85 05/08/85 YES d PJ 1 250 VOC Class 1E 04/04/85 05/17/85 YES PK-1 125 VOC Class 1E 04/19/85 05/15/85 YES i
l, NRC8(A22)c l .
I 8.27 ,
~ .
s
- 8. STARTUP i F(b). PACKAGES RELEASED FROM TEST (OPEN ITEMS ON ACCEPTED SYSTEMS)
TEST EXCEPTION STATUS It#GER OF REQUIRED DESCRIPTION EXCEPTIONS CLOSURE DATE COBOENTS FA-1 Aux. Boller Complete DTP-FA-0001.
l GF-1 Asa. Soller Dutiding 50R-GF-0047 07/31/85 Perform system air balancing per !**
MAC GTP-25.
GF-2 CHPH MAC SDR-GF-0040, 07/31/85 0040 (perform system air balance) '
GF-0046 0046 (computer pt. input D4170 '
displays normal when CWH HVAC panel 00C590 trouble and abnormal j
j= condition exists).
4 m ,
I*
kH-1 480 V MCC SDR-NG-0114 07/31/85 Computer PTS D4600 & D4607 were found I not to be wired in..
i W-1 250 VOC Non-lE SDRs W-0009, 07/31/85 W-0009 250V DC 100170 A/M should ,
! W-0010. NJ-0013 be center scale, track replacement.
j W-0010 battery 100141 cell i connection not in spec. NJ-0013 remove temp power feed to batteries.
]
) NK-1 125 VOC SDR-IK-0079 09/01/85 Replacement battery. cell required I and factory retest to the criteria of
. the PTP. .
\
! NRC 8 (A-26)b j -
i
! t
., 2 :. . . .. . .~. . .. ~ - -
- 8. STARTUP F(b). PACKAGES RELEASED FROM TEST (OPEN ITEMS ON ACCEPTED SYSTEMS)
TEST EXCEPTION STATUS NUMBER OF REQUIRED DESCRIPTION EXCEPTIONS CLOSURE DATE ColetENTS
- PJ-1 250 VOC Class IE SDRs PJ-0026, 07/31/85 PJ-0026 intercell connections for PJ-0033, RJ-0129 the cells do not meet spec. ,
PJ-0033 remove temp power feed to batteries, RJ-0129 test ERF computer points per GTP-3 for '
system interface.
PK-1 125 VOC Class IE SDR-PK-Oll7, 09/01/85 PK-Oll7 replace battery cell #19 SDR-PK-0119, and perform capacity and recharge
? SDR-0120 test. PK-0119. perform hydrogen y concentration test, PK-0120 replace feeder breakers to battery I charger and perform functional test, PK-0119 retest to be performed IAW quarter for PK-1. '
t
?
9 h
NRC 8 (A-28)b
[
5 4
1
- 8. STARTUP 4
l F(c). PACKAGES RELEASED FROM T5ST (SU8MITTED) j TEST EXCEPTION STATUS ,
i , ,
NUMBER OF REQUIRED DESCRIPTION EXCEPTIONS ,
CLOSURE DATE C0f00ENTS
- AN-2 Demin. Water & Transfer SDR-AN-0039 07/31/85 PORC action item 51001, upon rework of impeller and wearing rings of DAP-135 PMP, route the
- j affected portions of the test ;
through PORC approval cycle.
~
- GA-1 Plant Heating SDR-GA-0098, 09/01/85 0098 flushing TPR GAM-09, 109, 0057, 0063, 112, 114 not complete. i
) 0093, 0097 0057 permanent inst. lAPTE-2047/
I Po IGATE-2047 not inst.
j 8; 0063 heating steam pressure req. >
j Station not in service. i i 0097 temp control loop is not '
1 working properly. -
! 0093 VLVS shown on drawing not inst, in field. t<
] GE-0041 GTP-25, GE-0041 engineering
! resolution that system operates 1 i
1 as designed.
{
l GQ-1 Intake Structure HVAC SDR-GQ-0049, 11/01/85 TE #8 GQ-0049 perform prelim- ,
GQ-0046 inary and final air balance, j TE #2 PSE&G Eng. to review i ICD set points.
i NRC 8 (A-23)c 1
I '
?
.s .
- 8. STARTUP i
F(c). PACKAGES RELEASED FROM TEST (SUBMITTED) l TEST EXCEPTION STATUS
, NUMBER OF REQUIRED l DESCRIPTION EXCEPTIONS CLOSURE DATE COMENTS JA-1 Aux. Boller Fuel Oil SDR-JA-0075 09/01/85 Flow rate is obtained by ,
throttling gate valve V019..
- This is not acceptable. The '
system should be supplied with a properly sized orifice
- plate to provide flow rate required to inlet of the tank. ,
1 NG-1 480V Substation Power TE-10 SDR-NG-0111, 07/31/85 TE-10 computer PT 03704 co TE-11 SDR-NG-Oll4 read 52-10411 change to g read 52-10404. TE-11 computer PTS D4600 & j' D4507 not wired in.
.. PG-1 480 V Class IE SDR-PG-0109 08/31/85 PG-0109 TPR packages PGE-0013, 0058, 0062 remain open. ;
SG-1 Seismic Instrumentation SDR-SG-0022 09/01/85 Playback battery failed to achieve 25 minute playback, replace battery, retest sec. 8.2 and route retest ,
, through PORC revlew. PORC action L,
, item 57.1. ,
NRC 8 (A-24)c i
j #
. _ _. _._ . . . . . a .- m. .
__ m . .. ~ .
i n i !
j
- 8. STARTUP ,
G. TEST PROGRAM SCHEDULE AND CRITICAL PATH ',
- The initial startup schedule for Hope Creek was developed to be '
generally consistent with other recent Boiler Water Reactors (8WRs). .
A team of experienced personnel was organized initially to prepare a l stand-alene logic network. Team membership included representation f, from PSE&G PECO, GE, and Bechtel as well as other contract personnel.
Upon completion, the network was integrated with the construction o schedule to develop the overall project plan.
d The plan is continually monitored and updated. Updates include status j and logic enhancements as a result of better activity definition.
The following listing represents the current schedule for system
[j turnover from construction (Col. A), system preop start (Col. 8) and
- release from test (Col C) as of June 10, 1985.
+1 ,
,' (A)
Constr.
(8)
Preop (C)
Release e
i Subsystem Preop Description T/0 Start From Test A8A A8-1 Main Steam 02/26/85A 07/15/85 09/01/85 i ACA AC-1 Main Turbine 05/06/85A 10/24/85 11/15/85 i
- ADA AD-1 Condensate 09/05/84A 07/12/85 09/04/85 l 1
- AEA AE-1 Reac. Feed Pmp Turb. 01/11/85A 08/16/85 10/05/85
- H -
-2 AES AE-1 RFPT Lube Oil 04/03/85A 08/16/85 10/05/85
'. AFA AF-1 Extraction Steam 04/12/85A 07/08/85 08/16/85 AKA AK-1 Condensate Domin. 09/13/84A 07/28/85 09/04/85 0 AMA AM-1 Fresh Water 02/16/84A 06/06/84A 01/18/85A
' ANA AN-1 Domin. Wtr. Makeup 03/12/85A 07/28/85 09/04/85 M AN8 AN-2 Domin. Wtr. Transfer 05/16/84A 11/02/84A 05/10/85A ii APA AP-1 Condensate Storage 07/31/84A 06/21/85 07/24/85
, 888 88-1 Nuc. Boiler Recire. 03/07/85A 07/20/85 11/15/85 i 88A 88-2 Recirc MGs 12/31/84A 04/15/85A 11/15/85 888 88-3 Nuc. Boiler Recirc 03/07/85A 10/18/85 11/15/85 1 888 88-4 Nuc. Boiler Recire. 03/07/85A 04/19/85A 11/15/85 3 888 88-5 Nuc. Boiler Recirc. 03/07/85A 06/06/85A 11/15/85 l BBC N/A NT Gen. Set Vent 10/04/84A 04/15/85A 11/15/85 7 BCA BC-1 Resid. Heat Removal 01/23/85A 07/15/85 CV/27/85 4 BCS BC-1 RHR Control 02/01/85A 07/15/85 09/27/85 80A 80-1 Reac. Core Isol Cool. 05/24/85A 07/04/85 08/16/85 1 8EA BE-1 Core Spray 01/15/85A 06/15/85 07/28/85 BE8 BE-1 Core Spray Control 01/28/85A 06/15/85 07/28/85
- - 8FA BF-1 CR0 Hydraulic Supply 11/27/84A 08/03/85 09/27/85 8F8 8F-1 Cnti Rod Supply 03/18/85A 08/03/85 09/27/85 SFC 8F-1 CR0 Hydraulic Units 03/22/85A 08/03/85 09/27/85 BGA BG-1 Reac. Wtr Cleanup 03/08/85A 06/24/85 08/11/85 j BHA BH-1 Standby Liq. Cntl. 03/01/85A 05/26/85A 08/07/85 .
8JA BJ-1 High Pres. Cool. Inject. 05/31/85A 07/25/85 09/06/85 8NA AP-1 Refuel. Wtr. Transfer 06/18/84A 06/15/85 07/24/85 i- CAA CA-1 Turb. Seal. Steam 02/25/85A 07/08/85 08/30/85 1- CBA C8-1 Turb./ Gen. Lube Oil 04/12/85A 07/22/85 08/30/85
! CCA CC-1 Gen. Gas Control 05/17/85A 09/20/85 10/25/85 NRC8(A-10)f t
8.32
. _ _ ___,_._____ ___,_ _ __. _ _ _ _ _ ~.
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- . . ..s. ._,;;
i ', .
. s.
- 8. STARTUP G.
TEST PROGRAM SCHEDULE AND CRITICAL PATH (cont.) , . '
(A) ! (8) (C)
Constr. Preop Release Subsystem Preop Description . T/0 Start From Test _
- . _ CDA CD-1 ' Gen. Seal Oil 04/12/85A 07/15/85 08/22/85
_ CEA CE-1 Stator Cooling 05/17/85A 07/31/85 09/01/85 CFA CF-1 Lube Oil Stor/Trns/Purif. 04/11/85A 07/15/85 08/28/85 i CGA CG-1 Condenser Air Removal 12/19/84A 08/02/85 09/11/85 CHA CH-1 Main Turb. Cntl. Oil 01/29/85A 09/23/85 11/04/85 1 OAA DA-1 Circulating Water 11/16/84A 06/11/85A 07/23/85
,., 00A 00-1 Circ. Wtr Hypochlor. 11/27/84A 03/22/85A 07/21/85
,j' DEA N/A Cire. Wtr. Acid Inject. 10/26/84A N/A 07/23/85 EAA EA-1 Sevice Water 11/14/84A 06/30/85 08/07/85 ECA EC-1 Fuel Pool Cooling 01/10/8fA 05/27/85A 07/04/85 EDA ED-1 React. Aux. Cooling 11/30/84A 08/29/85 10/04/85
, ED8 ED-1 Racs to Rad. Extruder 07/11/85A 08/29/85 10/04/85
? EEA EE-1 Suppression Pool 12/31/84A 06/02/85A 07/07/85 EE8 EC-1 Torus Cleanup 12/06/84A 05/27/85A 07/04/85 EGA EG-1 Turb. Aux. Cooling 03/15/85A 07/13/85 08/30/85 i
EQA EQ-1 Service Wtr. Hypochlor. 11/16/84A 05/03/85A 07/01/85
- FAA FA-1 Aut. Steam Generators 08/02/83A 02/21/84A 01/24/85A FAS FA-1 Aux. Steam Gen. Part II 08/17/84A 02/21/84A 01/24/85A J GAA GA-1 Plant Heating Part I 08/03/84A '04/16/85A 08/01/85 GA8 GR-1 Plant Heating Part II 08/16/84A 09/02/85 11/08/85 Plant Heating Part III GAC GK-1 08/17/84A 08/30/85 11/22/85
, G8A G8-1 Chilled Water 03/04/85A 06/30/85 08/09/85 g' GCA N/A Admin. Bldg. HVAC 06/01/84A Vendor 06/30/84A GDA GO-1 Fire Pump House HVAC 06/26/84A 09/05/84A 03/06/85A GEA GE-1 Turb. Bldg. HVAC 05/24/85A 07/15/85 11/22/85
, GEB GE-1 TBCE & T80E 02/01/85A 07/15/85 11/22/85 t GEC GE-2 T885 & T88E 02/14/85A 03/21/85A 04/19/85A 4 GF8 GF-1 Cire. Wtr 81dg HVAC 07/13/84A 12/13/84A 03/27/85A j GF8 GF-2 Circ. Wtr Bldg. HVAC N/A 11/28/84A 02/27/85A GFC GF-3 Guardhouse HVAC 03/31/85A N/A 09/16/85 J4 GFA GF-4 Asphalt Stor. Bldg. HVAC 05/20/85A 09/30/85 11/02/85
.a GHA GH-1 Rad. HAVC Sup. & Exhst. 06/30/85 09/09/85 11/22/85 GH8 GH-1 Radweste Tank Vent 06/03/85A 09/09/85 11/29/85 GJA GJ-1 Cntl. Area Chilled Wtr. 06/18/85 08/20/85 09/22/85 GKA GK-1 Cntl. Rm. Supply & Exhst. 06/03/85A 08/30/85 11/22/85 a GKB GK-1 Cntl. Eqpt. Rs. HVAC 06/20/85 08/30/85 11/22/85
'! GKC GK-1 Cntl. Area Bat. Exhst. 02/25/85A 08/30/85 11/22/85 i GKD GK-1 Wing Area Sup. & Exhst. 06/14/85A 08/30/85 11/22/85 GLA GL-1 Service Area HVAC 06/21/85 09/10/85 11/22/85 GL8 GL-1 Chem Lab Exhst. 07/16/85 09/10/85 11/22/85 GMA GM-1 Diesel Area Sup. & Exhst. 06/15/85 09/10/85 11/15/85 GM8 GM-1 SWGR & Gen. Rs. HVAC 05/13/85A 09/10/85 11/15/85 NRC8(A-11)f 8.33
.. . . . . . x , . . . .w - -- a ,
- n. - -
- 8. STARTUP E
G. TEST PROGRAM SCHEDULE AND CRITICAL PATH (cont.)
I (A) (8) (C)
Constr. Preop Release
. Subsystem Preop Description T/0 Star _t From Test ,,
GMC GM-1 Diesel Area Bat. Exhst. 05/24/85A 09/10/85 11/15/85 GPA-2 GP-1 Leak Rate Test Eqpt. 08/01/85 -~10/04/85' 11/15/85 - - - - <
GPA-1 GP-2 Leak Rate Test Eqpt. 06/30/85 03/14/85A 11/15/85 GQA GQ-1 Intake HVAC 11/16/84A 04/29/85A 06/28/85 GRA 1 GR-1 Reactor Bldg. HVAC 04/12/85A 09/02/85 11/08/85 ARA-2 Reactor Bldg. HVAC 05/28/85A 09/02/85 11/08/85 GSA GS-1 N2 Stor. & Transfer 05/22/85A 07/24/85 08/31/85 GS8 GS-1 Containment Atmos Cntl. 05/23/85A 07/24/85 08/31/85 GTA-1 GT-1 Orywell Ventilation 03/22/85A 06/12/85A 10/21/85 GTA-2 Orywell Ventilation 04/05/85A 06/12/85A 10/21/85 GUA GU-1 Filtration /Rectre, & Vent 06/08/85A 08/10/85 11/22/85 HAA HA-1 Gas Radwasta 06/27/85 10/10/85 11/15/85 H8A H8-3 Liq. Radweste Collection 05/31/85A 10/07/85 11/04/85 H80 HB-2 Chemical Radwste 06/03/85A 09/30/85 11/22/85 H88 H8-5 Liq. Radwaste Processing 06/03/85A 09/30/85 11/17/85 H80 H8-4 Chemical Radweste 06/03/85A 09/30/85 11/22/85
, H8C H8-1 Rad. Domin. Regen. 05/28/85A 09/02/85 10/28/85 H80 H8-6 Chemical Radwaste 06/03/85A 09/30/85 11/22/85 HCA HC-1 Sol. Rad. Col *. & PH Proc. 06/11/85A 09/02/85 10/21/85 HC8 HC-1L Sol. Rad. Vol. Reduction 06/20/85 07/09/85 10/30/85 HCB HC-1G Sol. Rad. Vol. Reduction 06/20/85 08/17/85 09/21/85 HC8 HC-1A Sol. Rad. Vol. Reduction 06/20/85 08/31/85 10/12/85
,, HC8 HC-1K Sol. Rad. Vol. Reduction 06/20/85 08/31/85 10/01/85 HCB HC-II Sol. Rad. Vol. Reduction 06/20/85 08/31/85 10/19/85 HC8 HC-10 Sol. Rad. Vol. Reduction 06/20/85 09/07/85 10/05/85 HCB HC-1H Sol. Rad. Vol. Reduction 06/20/85 09/21/85 11/09/85 HCB HC-1E Sol. Rad. Vol. Reduction 06/20/85 10/23/85 11/23/85 HCB HC-1C Sol. Rad. Vol. Reduction 06/20/85 09/28/85 10/28/85 HC8 HC-1F Sol. Rad. Vol. Reduction 06/20/85 10/28/85 10/28/85 -
HC8 HC-18 Sol. Rad. Vol. Reduction 06/20/85 09/21/85 10/26/85 HC8 HC-1M Sol. Rad. Vol. Reduction 06/20/85 10/25/85 11/22/85 HOA N/A Decon Facility 06/25/85 N/A 11/17/85 HGA-1 N/A Bldg. & Eqp. Rad. Orains 07/01/85 N/A 11/12/85 HGA-2 Bldg. & Eop. Rad. Orains 09/01/85 N/A 11/12/85 HG8 N/A Ofly Rad. Orains 08/01/85 N/A 11/12/85 l HHA HH-1 Rad. Laundry 07/14/85 09/24/85 11/01/85 JAA JA-1 Aux. Oil Storage 07/03/84A 03/06/85A 06/07/85A '
JEA JE-1 Osl Fuel 011 Trns & Stor. 11/02/84A 05/02/85A 07/01/85 KAA KA-1 Service Air 07/05/84A 07/01/85 08/15/85 K8A K8-1 Instrument Air 06/29/84A 07/08/85 08/23/85 KCA KC-1 Fire Wtr Supply 04/24/84A 08/19/85 09/26/85 KC8 KC-1 Wet Sprinkler System 10/19/84A 08/19/85 09/26/85 KCC KC-1 Fire Protect. Deluge 05/10/84A 08/19/85 09/26/85 KC0 KC-1 Auto Pre-Action Wtr Spray 02/01/85A 08/19/85 09/26/85 NRC8(A-12)f 8.34 ,
i
. w . = .s s*
og s
^
- 8. STARTUP G. TESTPROGRAMSCHEDULEANDCRITICALPATH(cont.)
I i (A) (8) (C) l Constr. Preop Release ;
Subsystem Preon Description T/0 Start From Test -
Pre-Action ~ Sprinkler Sys. 07/13/84A 08/19/85 KCE KC-1 09/26/85 KCG KC-2 Fuel Oil Foam Fire Prot. 06/29/84A 06/30/85 09/26/85 KCF KC-3 Fire Protection 05/31/84A 07/19/85 08/16/85 KDA KD-1 Domestic Water 09/06/84A 07/18/84A 08/30/85A KEA KE-1 Fuel Hnd & Reac Ves Serv 03/22/85A 07/01/85 09/20/85 KE8 KE-2 Fuel Hndig Under Vessel 06/11/85A 08/08/85 09/20/85 KFA-1 KF-1 Cranes Hoist & Elevators 07/30/84A 07/15/85 11/16/85 KFA-2 Cranes Hoist & Elevators 10/11/84A 07/15/85 11/16/85 KFA-3 Cranes Holst & Elevators 02/01/85A. 07/15/85 11/16/85 KFA-4 Cranes Heist & Elevators 04/04/85A 07/15/85 11/16/85 KFA-5 Cranes Holst & Elevators 07/01/85 07/15/85 11/16/85 KGA KG-1 Breathing Air 08/15/85 08/26/85 10/04/85 ,
KJD KJ-1 Standby Diesel A 12/17/84A 07/28/85 08/30/85 KJC KJ-2 Standby Olesel 8 11/20/84A 07/13/85 08/15/85 KJ8 KJ-3 Standby Diesel C 12/04/84A 07/01/85 08/03/85 KJA KJ-4 Emergency Olesel Gen. 0 11/06/84A 06/15/85 07/11/85 ;
KLA KL-1 Primary Cont. Instr. Gas 02/28/85A 08/12/85 09/20/85
, },
KPA KP-1 MSTV Sealing 02/26/85A 07/15/85 09/01/85 y L8A N/A Storm Orains 10/01/85 N/A 10/28/85 j LDA N/A Chemical Waste 07/23/85 N/A 11/19/85 '
LEA-1 N/A Oily Waste - 81dg. Sewage 06/26/85 N/A 11/19/85 LEA-2 Oily Waste & 81dg. Sewage 10/15/85 N/A 11/19/85 LFA-1 N/A Normal Orains 06/26/85 N/A 11/12/85 LFA-2 Normal Orains 10/15/85 N/A 11/12/85 M4A MA-1 Main Generator 06/06/85A 08/09/85 09/30/85 MCA MC-1 13.8 KV Stn. Pwr. Trnsf. 02/23/84A 11/03/84A 01/24/85A ,
MA N/A Switchyard Bus Group 1 01/10/8dA N/A 11/11/85 M8 N/A Switchyard Bus Group 2 07/23/84A N/A 11/11/85 MEA N/A Switchyard 125 VOC 01/10/84A N/A Internal MFA N/A Switchyard Lighting 03/02/84A N/A 01/24/85A '
MHA N/A Outgoing ENV Ties $4K 01/31/84A N/A 01/24/85A MHO N/A outgoing ENV Ties New Free 10/21/85 N/A 01/24/85A
-NAA NA-1 7.2 KV Power 05/15/84A 10/09/84A 01/18/85A NSA NS-1 4.16 Stn. Power Aux. 81r. 06/01/84A 10/09/84A 05/10/85A N88 NO-2 4.16 Stn. Pwr. Bik/ Admin. 04/04/84A 09/06/84A 05/10/85A NB8 NO-3 4.16 Stn. Pwr. 81k/ Admin. N/A 09/06/84A 05/10/85A NGA NG-1 480 V Unit Subpwr Grp 1 07/02/84A 11/03/84A 04/12/85A NGS NG-1 480 V Unit Subpwr Grp. 2 04/11/84A 11/03/84A 04/12/85A NHA NH-1 480 V MCC Pwr Grp 1 07/10/84A 11/03/84A 05/08/85A -
NHO NH-1 480 V MCC Pwr Grp. 2 06/22/84A 11/03/84A 05/08/85A NJA NJ-1 250 VOC Power 08/16/84A 12/01/84A 05/17/85A ;
MA M-1 125 VOC Power Supply 02/28/84A 07/31/84A 05/15/85A l 4
28 E-1 125 VOC Power Distr. 02/28/84A 07/31/84A 05/15/85A MC 8 (A-13)e 8.35
. .. .- _ .. ~~ , 2 .b,u a .
.i l
- l
, l
, [.!. 7 8. STARTUP G. TEST PROGRAM SCHEDULE AND CRITICAL PATH (cont.)
(A) (8) (C) f Constr. Preop Release Subsystem Preop Description T/0 Start From Test NLA NL-1 24 VOC Power 11/06/84A' 03/25/85A - 06/21/85-NQA NQ-1 120 BAC Supply Power 07/16/84A 04/29/85A 07/04/85 NQS NQ-1 120 VAC 01strb. Power 07/20/84A 04/29/85A 07/04/85 PBA P8-1 4.16 KV 1E Power 05/31/84A 12/15/84A 05/10/85A PGA PG-1 480 1E Sub Stn. Pwr. Grp 06/01/84A 03/25/85A 04/26/85A PG8 PG-1 480 1E Sub Stn. Pwr. Grp 06/21/84A 03/25/85A 04/26/85A PHA PH-1 480 1E MCC Power Grp. 1 05/17/84A 03/25/85A 05/08/85A PH8 PH-1 4801E MCC Power Grp. 2 07/17/84A 03/25/85A 05/08/85A PJA PJ-1 250 V DC 1E Power 03/30/84A 01/09/85A 05/17/85A PKA PK-1 125 V DC 1E Sup. Power 03/09/84A 02/22/85A 05/15/85A PKB PK-1 125 V DC 1E Distrb. Pwr. 03/07/84A 02/22/85A 05/15/85A PNA PN-1 120 V AC 1E Sup. Pwr. 06/28/64A 06/24/85 08/01/85 PNB PN-1 120 V AC'1E Distrb. Pwr. 07/05/84A 06/24/85 08/01/85 QAA N/A Lighting Group 1 07/23/85 N/A 11/19/85 QA8 N/A Lighting Group 2 09/03/85 N/A 11/19/85 QAC N/A Lighting Group 3 09/03/85 N/A 11/19/85
- 08A 08-1 Standby Lighting 07/29/85 08/19/85 09/21/85
' * (. %,
088 08-1 Essential Lighting 08/27/85 08/19/85 09/21/85 l OCA N/A Yard Lighting 08/13/85 N/A 10/01/85
- QEA N/A Public Offsite Comm. 09/12/85 N/A 11/25/,85 1
QFA QF-1 Inpint Comm Cntl. & Diesel 05/01/85A 10/10/85 11/12/85
- QFB QF-1 Inpint Comm Radwaste 09/26/85 10/10/85 11/12/85 QFC QF-1 Inpint Comm Aux Bldg /Ory. 09/26/85 10/10/85 11/12/85
, QFD QF-1 Inpint Comm Turb. 81dg. 02/01/85A 10/10/85 11/12/85 QFE QF-1 Inpint Comm Admin. Bldg. 09/26/85 10/10/85 11/12/85 QFG QF-1 Inp1nt Comm Admin. Bldg. N/A 10/10/85 11/12/85
. QHA QH-1 Cathodic Protection 08/13/85 08/27/85 09/29/85
) QJA QJ-1 Freeze Protection N/A 08/01/85 09/03/85
,; QKA QK-1 Fire /Smke Detec. Yd. Stre. 10/18/84A 09/05/85 10/08/85 QK8 QK-1 Fire / Sake Detec. Cnt1/01e. 05/21/85A 09/05/85 10/08/85 QKC QK-1 Fire /Smke Detec. Radweste 07/18/85 09/05/85 10/08/85 QKO QK-1 Fire /Smke Detec. Turbine 04/12/85A 09/05/85 10/08/85 QKE QK-1 Fire /Seke Detec. React. 04/10/85A 09/05/85 10/08/85 11/25/85 QLA N/A Private Offsite Comm. 09/16/85 N/A
,, QMA N/A Motor Operated Doors 08/01/85 N/A 10/17/85
?
QM8 N/A Lab / Shop Eauipment 08/01/85 N/A 10/17/85 QMC N/A Weld /Pwr Recepticles 08/01/85 N/A 10/17/85 RCA RC-1 Supling Aux. Bldg. 07/30/85 10/22/85 11/08/85 RC8 RC-2 Sepling Turb. B1dg. 07/30/85 10/24/85 11/08/85 RCC RC-3 S upling Reac. Bldg. 07/30/85 10/17/85 11/08/85 RCD RC-4 Contain Post Acc. S up1. 07/08/85 09/09/85 10/12/85 NRC8(A-14)e 8.36
- a. :. - . .c . . . - . = -..a n.::l:isk!?b.x 4 -
.j I
- 8. STARTUP 7-G. TEST PROGRAM SCHEDULE AND CRITICAL PATH (cont.)
(A) (B) (C)
Constr. Preop Release Subsystem Preop Description T/0 Start From Test
> RDA N/A Meteor Inst. 09/26/85 N/A 11/08/85 RGA RG Plant Security 05/07/85A 08/02/85 09/09/85 RGB RG Intru.& Access Security 07/17/85 07/19/85 08/27/85 RGC RG TV Monitoring Security 05/07/85A 03/09/85 09/16/85 RGO RG Comm Security 05/07/85A N/A 08/10/85 RGE RG Grdhs/ Diesel Gen. Security 05/07/85A 08/09/85 09/16/85 RGF RG Tech. Support Center N/A N/A 08/10/85 RHA RG Closed Circuit TV N/A N/A 11/12/85 RJA RJ-1 Plant Computer Part I 08/12/83A Ongoing 09/15/85 RJ8 RJ-1 Plant Computer Part II 12/09/83A Ongoing 09/15/85 RJC RJ-2 Computer Dnergency Resp. 09/02/85 09/23/85 10/26/85 RLA N/A CRC Pnis, & Cable 12/09/83A N/A 09/15/85 SAA SA-1 Redundant Reac. Ctrl. 12/09/83A 10/04/85 11/15/85 58A 58-1 Reac. Protection 04/18/85A 07/01/85 09/25/85 S8A 58-2 Reac. Protection N/A 08/05/85 09/25/85 SCA SC-1 Reac. Instrumentation 08/06/85 09/03/85 10/11/85 SOA SD-1 Radiation Monitoring 12/09/83A 10/25/85 11/22/85 SEA SE-1 SU/Intermed Rng Neu. Mon. 07/24/85 08/30/85 10/25/85 1 .
SED SE-2 , Reac. Orv Con Neu. Mon. 07/24/85 09/06/85 10/25/85
\ ~
SEB SE-3 Pwr Rng Neu. Monitoring 07/24/85 08/30/85 10/25/85 l 1i SEC SE-4 Tip Neu. Monitoring 07/24/85 09/20/85 10/25/85 o SFA SF-1 Reac. Manual Control 03/22/85A 06/20/85 10/25/85 i
o SGA SG-1 Seismic Instrunentation 04/01/85A 04/24/85A 05/10/85A SKA SK-1 Leak Detection 08/20/85 08/30/85 10/12/85
, SMA SM-1 NSSS Shutoff 05/03/85A 07/03/85 10/23/85 3 SNA SN-1 Auto. Depressurization 06/13/85A 07/23/85 08/25/85 SPA SP-1 Proc. Non-Safety Rad Mon 07/05/85 07/19/85 11/22/85 SPS SP-2 Proc. Nuc. Safety Rad Mon 10/04/85 10/18/85 11/22/85 STA N/A TransientMonitor(GTARS) 07/01/85 N/A 09/01/85 SVA SV-1 Remote Shutdown 12/09/83A 08/12/85 09/13/85 o
a t
e e
> l NRC 8 (A-15)g 8.37
. . _ ... . _ _ ... x ." . . . ..a .
- a j
j 8. '5TARTUP m
b, .')s G. TEST PROGRAM SCHECULE AND CRITICAL PATH (cont.)
a
[j In sumary, the project has developed a high quality integrated 74 project schedule. The schedule is updated on a continual basis to i provide the most up-to-date information and enhance the overall U product. Monitoring of the schedule provides continual feedback
- t to management and high visibility on the project's four most critical paths
- the completion of the NSSS/ECCS system's ~preopera-tional test and operational hydro, the Reactor Building HVAC system completion and testing, the Installation of the radiation -
monitoring system and subsequent testing, and completion of the solid radwaste system.
Management actions are taken immediately as required. It is this problem identification / resolution process that gives us confidence in managing the project to a successful completion.
H. STAFFING PLAN The following is the current and projected manpower to support the Preoperational Test Program (Phase !!) to fuel load:
- .3 j (.2 STARTUP GROUP CURRENT PROJECTED - .
4 Test Program Supervisors 20 20 y
Test Engineers 130 159 PTP Support 55 55 T/A Support 192 216 Contract Technicians:
GPPMA 110 140
!&C 98 114 The projected figures above represent additional staffing which has recently been authorized. The vacant positions are expected to be filled by early July 1985.
s A
NRC 8 (A-17)b 8.38
.-. . . wh a . .:w2 .a . . ..= a:n . w z 2l<.. a c. : . a. . .. :.: .u .. a;..-:a. La
~. .- 1
. t - >
- 8. STARTUP I. P908tEMS/50LUTIONS DESCRIPTION OF P908tEMS CORRECTIVE ACTION CURRENT STATUS
- 1) RESOLUTION OF PROBLEMS IDENTIFIED IN LAST CASELOAD a) Aggressive testing schedule. Closely monitor startup progress. To date we have met the challenge of an aggressive schedule. This '
is evident in the following:
- An early turnover of the CRC f
- An early. integrated flush
- An early code hydro
- An advancement of the preopera- i tional test schedule
?
8 b) Project learning curve Develop training and communication The progr a is in place and associated with new programs. functioning well. j[
s startup progran.
c) Shortage of qualified Increase staffing as needed. Well qualified personnel have been L personnel, and continue,to be hired by PSE&G i on an as needed basis. I' ;
The current Startup group staff has .
been aided by the availability.of l:'
- very strong 8echtel personnel with 6 current experience from Limerick, Susquehanna, etc., in addition to the acquisition of experienced personnel from other sources.
s" hRC 8 (A-18)a , ;
b
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- 8. STAR 10P I. PRO 8LEMS/ SOLUTIONS DESCRIPTION OF PR08tEMS CORRECTIVE ACTION CURRENT STATUS
- 1) RESOLUTION OF PR08LEMS IDENTIFIED
( IN LAST CASELOAD (Cont.)
d) Increasing scope of testing Improve lines of communication. Strong communication with other :
by regulation or plant facilities undergoing startup ahead !
experience. .
of Hope Creek has helped identify and incorporate new requirements into ,
our program. t .
- 1 The project continues to use services such as INPO note pad. 3 i i cn i l 'g There is a tracking system in place I and functioning addressing new testing I issues and concerns. .
h The Startup group has been staffed with personnel who have had recent t
- 2) CURRENT PROBLEMS a) Accumulation of many preop Develop a levelized testing A levelized preop schedule has been k tests at certain periods of schedule. developed and is in place. This is
. time. continuously monitored and adjusted as necessary to maintain our overall, !:
startup goals.
b) Backlog of preoperational Increase staffing. Additional procedure writers with - l.
test procedure preparation, experience in writ.ing and conducting .
preop tests have been added to the -
Startup staff. This group has been i successful in improving the quality of procedures as well as the rate of production.
MRC 8 (A-19)a .
- .. ... v;a v ,. '
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- 8. STARTUP I. PROBLEMS /SQLUTIONS DESCRIPTION OF PROBLEMS CORRECTIVE ACTION CURRENT STATUS
- 2) CURRENT PROBLEMS (Cont.)
c) Backlog of I&C calibrations increase staffing and improve Additional technicians, supervisors, +
and loop checks. production. and test engineers have been acquired. ,
This has resulted in an increase in i the rate of performing the 1&C tests. ,
I.
d) SDR program workoff. Develop a plan based on priority Teams have been developed and are fi in place to coordinate the workoff to close out outstanding SDRs. '
effort. [.. . .
, j.
[
2: Additional engineering and construc-tion supportihas been provided. {;
Priority SDRs have been identified -
- 0. .
l and all SDRsiare scheduled to accommodate the overall plan, j '.
e) Last minute design changes Increase communication between Weekly conference calls take place ,
which impact testing. the home office engineering and with the 8echtel Home Office to field construction and testing permit an early start on developing !
9roups. workaround plans when necessary.
[ -
i A program isii n place to expedite [-
material procurement for modifica- '
l I tions (CORE Team).
i.
NRC8(A-20)b (..
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- 8. STARTUP _
I. PROBLEMS /SQLUTIONS DESCRIPTION OF PR08LEMS CORRECTIVE ACTION CURRENT STATUS i
- 2) CURRENT PROBLEMS (Cont.) I.o p
f) Radwaste testing progran. Estab11sh a dedicated radwaste A dedicated radwaste group has '
9roup. been estab11shed and is functioning. .
This group is staffed with a sufft- b cient number of test engineers and I' F
support personnel to meet the
! schedule. '.
g) HVAC testing critical path. Increase schedule visibility A detailed schedule has been 7 to allow managment to reallocate developed to monitor the final -
~
- P' the project's resources to stages of HVAC work. This schedule .
Ri critical areas and anticipate receives constant management atten- !
Z; problan areas. tion to ensure ismediate problan g resolution. ;
The system teams have been aug- ,
mented to ensure timely response f' to schedule impacting issues. [(.;
(,
h) NSSS testing critical path. Increase schedule visibility A detailed schedule has been devel-
~
to allow managment to reallocate oped for the completion of NSSS/ECCS !?
the project's resources to system testing, operational hydro, iiq critical areas and anticipate TIP system, and NLRT in support of ' '
~;
problem areas. fuel load commencement. The i,
- schedule is updated regularly I and receives daily management attention.
! NRC 8 (A-16)a .
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A
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l
- 8. STARTUP a
o -,
'a GJ!O' J.
SUMMARY
A dedicated effort by Public Service, Bechtel, and other contract personnel has made an earlier fuel load date of December 1,1985, achievable. The pr'oject team approach has been effective in coordi-nating the various parts of the startup program necessary to reach fuel load. A continued, integrated effort by project team members will achieve that goal.
T e
4 S
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NRC8(A-21)b 8.43
., ..= , x = .. ..:.a.. . " J .i . u . & ; . :. . : h. . .- -
HOPE CREEK GENERATING STATION a NRC CASELOAD FORECAST
.3
!.j e. ~
7 Q$,@ 9. LICENSING STATUS Questions: Detailed discussion of potential schedular influence due to change attributed to NUREG-0737 and other recent licensing
- requirements.
l A. INTRODUCTION Since the April 1983 Caseload Forecast Panel Meeting, Hope Creek has achieved a number of fundamental licensing milestones on or ahead of A schedule, and at levels of success equal to the best perfomance of 7,- any other operating license effort over the past several years. These g milestones included issuance of the " Safety Evaluation Report" and the
- " Final Environmental Statement". Other significant licensing milestones a include the issuance of a letter by the NRC Advisory Committee on j Reactor Safeguards, endorsing full power operation of the plant, and a
-l successful independent negotiation of the contentions in the Atomic and
- Safety Licensing Board hearing process resulting in termination of the hearings.
? B. OPERATING LICENSE APPLICATION STATUS 1
j g3 1. March 1, 1983 - Application Submitted
.1 j
W June 29,1983 - Application Docketed 2.
rj
- 3. November 18, 1983 - ASLB Pre-Hearing Conference .
< 4 March 6, 1984 - Draft Safety Evaluation Report
- 5. May 31, 1984 - Byproduct Material License Issued j 6. June 29, 1984 - Oraft Environmental Statement ,
ky 7. October 1984 - Safety Evaluation Report
- 8. November - December 1984 - ACRS Meetings
- 9. December 17, 1984 - ASLB Second Pre-Hearing Conference
. 10. December 1984 - Final Environmental Statement
^
- 11. January 17, 1985 - Technical Specifications Submitted
- 12. March 1, 1985 - ASLB Hearing Terminated
- 13. March 1985 - Supplement 1 to SER
,;n
t.
- NRC 7 (A-1)b i 9.1
z _ _ _ . .: 4 c- , ar i.li7:2 '- - , 9 .i .S df b_. :t -M 2. :w Ez.m mit :. . [h/i. .:.0$1,c.a;zc. / dl.
7, .
l NM W -
a f 9. LICENSING STATUS .
C. THE IMPACT OF NUREG 0731
ITEM 110. p I.A.I.1 Shift technical Hope Creek Generating Station
- TP-303 - approved. Use of SR0s are acceptable. --
advisor will meet requirements by training SRos (13.1.2.1),
to meet STA requirements - see e training procedure IP-303 (due to be '
h complete 3/85) and FSAR sections 13.1 , f and 13.2.1 STA shift requirements F will be incorporated into procedures upon receipt of IIFO - NRC approved ;.
resolution. I I
I.A.I.2 Shift supervisor llesponsibilities are outlined in the VPN-PLP approved. Acceptable (13.5.1.7). ..
responsibilities following policies and or procedures: SA-AP.ZZ-002(Q) - '.
p
'VPN-PLP-01 approved. y
- SA-AP.ZZ-002(Q) OP-AP.ZZ-002(Q) - N' P *0P-AP.ZZ-002(Q) approved. ,
i c. ,
- 3 Also discussed in FSAR section 13.1.2 i
- p
1.A.1.3 Shift manning Meets current NRC policy on maximum OP-AP.ZZ-002(Q) - Acceptable (13.5.1.7). ;
work hours provided in policy approved.
- statement dated 2/11/82 and generic ,.-
! M
- letter 82-12, see FSAR section f
13.1.2 and procedure OP-AA.ZZ-002 (Q). , (q Meet requirements by having all SRO Acceptable - pending receipt i h 1.A.2.1 Immediate upgrading of candidates sit for cold license and and review of simulated !
operator and senior operator by training program supplying equiva-lent of experience the'y require
- training program (13.2.1.4) 01 - 12d submitted 1/7/85 .'
training and see FSAR section 13.2.1.1. to NitC. ; -
qualification. , ,
I.A.2.3 Administration llope Creek Generating Station will Acceptabl'e pending verifica- j of training meet all requirements. tion that requirements have -
i-programs. heen meet' prior to issuance of a license (13.2.1.4).
NRC 7 (A-2)a 9
I
-.- : .. .,. : . . . ~ ,. ., .,
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- 9. LICENSING STATUS i,
C. THE IMPACT Of NUREG 0737 4
ITEM NO. SU8JtCI RE50tuil0N - FSAR DOCUMENTAi!ON RE50tuTIO11 - SER l.A.3.1 Revise scope and Requirements outlined in training IP-305-HC - approved i .-
criteria for procedure TP-305-HC and FSAR Under NRC review (13.2.1.4) ,
s
licensing examina- (01-12d). . ! a sect ion 13.2. j tions i
- e l I.8.1.2 Evaluation of Hope Creek Generating Station meets Acceptable (13.4.3).
organization requirements. Discussed in FSAR in and management. sections 13.1 and 13.4.4. ,
[.
- r. .
I.C.1 Short-ters accident [0Ps will follow guidelines of BWR E0Ps - draft analysis and PGP is under NRC review t
. Owner's Group Emergency Procedures (PGP is 01-14). Response i procedure review, and will be available 3/1/85. f
4 I .C .2 Shift relief and included in procedures OP-AP.ZZ-107(Q) OP-AP.ZZ-107(Q) - Acceptable (13.5.1.7).
turnover procedures, approved.
IU and OP-AP.ZZ-017(Q).
1 OP-AP.ZZ-017(Q) - ' {~ .
draft. '
l.C.3 Shift supervisor included as part of IMI item I.A.I.2. Acceptable (13.5.1.7).
responsibilities. f-t
' I.C.4 Control Room Access Authority delineated in SA-AP.lZ-002(Q) SA-AP.ZZ-002(Q) - Acceptable (13.5.1.7).
and OP-AP.ZZ-002(Q). approved.
g OP-AP.ZZ-002(Q) - l approved. t-t f
NRC 7 (A-3)a
._ :_/ 2.. ~ 'J 'C '. . . . c., c:...L M J. a fe. < ; _ugYlW.ffMt.Y.3E h '? i '. cla ; .: c:;,M ..._ W t
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b V;
- 9. LICENSING STATUS C. THE IMPACT Of NUMEG 0131 !)
y ITEM NO. ' Utijt C I
, RESOLUTION - FSAR DOClM[NIAll0N resol 0!!Oli - $[R !!
1.C.5 feedback of operating the following procelores provide OP-AP.ZZ-105(Q) - approved. Acceptable (13.5.1.7). .
es perience, information on the dissemination of M3-POP-001 - draft,. j c ~
information: IP-3066tC - deleted. .
'OP-AP.Zl-105(Q) IP-301HC - deleted. -
- aq). pop.ool ,
- TP-306HC & TP-301HC replaced by 3 consitment tracking lists.
In additon, an integrated nuclear .
department procedure will be p provided by 3/85, wi.ich will he .x incorporated into Hope Creek ?-
Generating Station procedures (SA-AP.ZZ-041Q - approved).
$9 1.C.6 Verify correct The following procedures provide Acceptable (13.5.1.5). F 4 performance of the required information. ;.
operating activitles. OP-AP.ZZ-10H(Q) - draft OP-AP.ll-109(Q) - drafL OP-AP.ZZ-002(Q) - approved ,
SA-AP.ZZ-12(Q) - approved ;
SA-AP.ZZ-15(Q) - approved ,
SA-AP.ZZ-009 - approve.t SA-AP.ZZ-13(Q) - approved OP-AP.ZZ-011(Q) - draft F
!.C.? NS$$ vendor Hope Creek Generating Station will Acceptable (13.5.2.3). l review of comply.
procedures.
1.C.8 Pilot monitoring Not applicable to Hope Creek Not applicable to Hape Creek -
of selected emer- Generating Stat lon. Generating Station (13.5.2.3).
gency procedures for near-term operating .
license applicants.
litC 7 (A-4)a
..:..., ~~ . wD , <L Lt : n:~:2.l.!, lie.u.:.- . - . . t :.dk.I'.EIOlMO5k"a:. ' . ' L z . 50 : Y..O A ?..: p..
(E p:qi ,~~ W C h 't O
- t. .--
- 9. LICENSING STATUS U
C. THE IMPACI 0F NuitEG 0737 [:
+*
IIEM NO. SUS.lL C T .,_
RLSotuil0N - FSAR DOCUMENIAll0N RESOLUlluN - SER /
1.D.1 Control Roas thiyn Provided CROR summary report to NRC Additional information due 11/85
- Review 8/14/85. to resolve 11/84 audit findings "
(18 SSERI).
7 r.e. I 1.D.2 Plant SPDS SPDS scheduled for sulmaittal to NitC 01-15 si&mitted to mitC 4/10/85.
9/84. (Submitted to NRC 4/10/85), [$
t c, l.G.1 Training during low Hope Creek Generat ing Station will 4
Acceptable (14.2). "
power testing. comply as required during low power ;;?
testing. '
i 11.B.1 Reactor coolant The HPCI, RCIC and/or AHS meet the Acceptable - (15.9.1). IS system vents, requirments.
?
o II.B.2 Plant shielding A post accident shielding design Acceptable (12.3.2). 4 and access review was performed l'
? as r'equired (see FSAft 3 un sectioni 12.3.2). !;
II.B.3 Post-accident Hope Creek Generatinq Station Acceptable (9.3.2),
sampling. design complies (see FSAR section 9.3.2). O II.B.4 Iraining for A training program has hii n 01-12d submitted to NRC mitigating core implemented (see ISAR 1/7/85.
damage. sect ion 13.2).
11.0.1 Relief and safety lest progran analysis submitted to Under leRC review (3.10.2) valve test require- NRC 10/25/83. (01 2b). e ments.
II.D.3 Relief and safety Hope Creek Generating Station Acceptable (7.5.2.2). .
valve position complies - see ISAM section i indicalion. 1.5.1.3.6. 4 NRC 7 (A-5)a I
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- 9. LICEllSileG STAIUS t'
C. THE IMPACT OF NUREG 0731 ,
ITEM 100. SU6Jt CI __ NE50 lull 006 - FSAR DOCist[NTAitost itE50t ultuN - $[R {
ll.E.1.1 Auz. Icedwater (IW) Not applicable to BWRs. ,[
system evaluation. -
t.j: -
.o I I .E .1.2 Aun. FW system Ilot applicale to IMM.
initiation and flow.
ll II.E.3.1 Emergency power for let applicable to Swits.
pr'essurizer heaters, ll.E.4.1 Dedicated hydrogen Hope Creek Generating Station Acceptable (6.2.5).
control penetrations, complies with clarification (1) of IMI Item II.E.4.1.
- II.E.4.2 Containment isolation ibpe Creek Generat ing Station Acceptable (6.2.4),
dependability. complies - see FSAR section 6.2.4. ,
so 6:
h II.F.1 Accident Monitoring Instrumentation a ll.F.1.1 Isoble gas effluent Hope Creek Generating Station compiles - Acceptable (11.5.2).
monitor. see FSAR section 11.5.
II.F.1.2 Sampling and analysis ibpe Creek Generating Station complies - -
Acceptable (11.5.2). '
of plant effluents. see FSAR section 11.S. ,
I I .F .1. 3 Containment higle- llope Creek Generating Station cnnplies - Acceptable (12.3.4.1).
- range radiation see FSAR sect ion 11.5.
monitor.
4 II.F.1.4 Containment liope Creek Generating Station complies - Acceptable (7.5.2.5).
pressure monitor. see FSAR sect ion 7.5.1.
II.F.1.5 Containment water Ibpe Creek Generating Station complies - Acceptable (7.5.2.5).
level monitor. see (SAR section 7.5.1.
I I .F .1.6 Cont altunent Hope Creek Generating Station compiles - Acceptable (1.5.2.5).
hydrogen anonitor, see FSAR sect ion 7.3.
NRC 7 (A-6)a
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- 9. LICENSIIIG STATUS lN C. THE IsePACT OF isuREG 0737 -
ITEM 100. SU8 JECT RE50Lui!ON - FSAR DOCIMENTAT 1000 RE50tuil0N - SER I
II.F.2 Instrumentation for ibpe Creek Generat ing Station endorses l'
Acceptele (4.4.7). F.
detection of results of 8 Wit 0G. Itope Creek Generating '
inadequate core Station to incorporate necessary 11 cooling. modifications den final resolution
- I. ,
is reached with ultC.
- I 1
11.6.1 Power supplies Not applic&le to BWit. -
for pressurizer
[ relief valves. U block valves and '
level indicators.
I II.K.! IE bulletins on t j ;
measures to mitigate t to small break locas "
y and loss of FW breaks.
h II.K.I.5 Assurance of proper Hope Creek Generating Station to final due 7/15. Staf f to verify procedure - -
engineered safety provide procedure by 3/85. satisfies requirements (15.9.2).
features functloning. ;
li.K.l.10 Oper & llity status. Hape Creek Generating Stat ion to Final due 7/15. Staff to verify procedure - - ,
provide procedure by 3/uS. satisfies requirements. (15.9.2). , ,
II.K.l.l? Not applicable to Hope Creek
- Generating Station.
II.K.I.20 ht applic hle to llope Creek Generating Statlon. .
li.K.l.21 ht applic hte to Hope Creek ;
. Generating Station. * ~
II.K.I.22 Proper functioning Hope Creek Generating Station endorses Accept &Ie (15.9.2).
of heat removal HWROG position - see FSAR sys tems. sect ions 5.4.6 and 5.4.7.
l IIRC 7 (A-7)a .
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- r_;CG5.;,sp F. h s ;c
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- 9. LICENSthG STATUS C. itE IMPACT OF HUREG 0131 ITEII 110. SUBJECI __ RE50Luil0N - FSAR DOCistf hTAll0N RE50Luilon . SER I t
II.K.1.23 Reactor vessel water Hope Creek Generating Station provided Accept e le (15.9.2)..
level indicatlon. requested informatlon.
II.K.2 Consission orders Not applic ele to Hope Creek Generatino '
. on R&hl plants. Station. -
II.K.3 Final recommendations of 860 Task Force. ,
ll.K.3.1 Isot applicele to llope Creek Gew rating ,
Station. <
I I .K . 3. 2 Ilot applicele to Hope Creek Generating
! Station.
II.K 3.3 6' Failure of PONV Hope Creek Generating Station provided Accept &le (15.9.3), j
?
co or safety valve requested information.
,to close.
II.K.3.5 Not applic &le to Hope Creek Generating Station.
i ll.K.3.7 Not applic&le to thpe Creek Generating .
Station.
, II.K.3.9 loot applictie to Hope Creek Generating Station. !
II.K.3.10 isot applicele to lupe Creek Generating Station.
- II.K.3.11 Nut applic & le to Hope Creek Generating Station, ll.K.3.12 Ilot applic &le to Hope Creek Generating ;
Station.
IstC 7 (A-8)a '
1 1
.- ; -~
V.
.I l
- 9. LICENSIIIG STATUS C. THE IMPACf 0F NUREG 0737 ITEM le0. Sus.MC I ,_
RE50tulloss - ISAR DoctMENIAllolt RE50tuiloss - SER .
II.K.3.13 Separation of itPCI Hope Creek Generating Statiosi esulorses Acceptable pending verif ication I or RCIC system INROG position. of installation of equipment initiation levels - for automatic restart of RCIC analysis and on low water level. (15.9.3). j implement at ion.
' ,l II .K .3.15 Modify break Hope Creek Generating Station meets Acceptable pending verification ,
detection logic requirements by installing Class IE of installation of relays to prevent time delay relays. (15.9.3). . ,
spurious isolation !
of IFCI and RCIC i systems.
II.K.3.16 Reduction of challenges Hope Creek Generating Station endorses DrafL Accept Ale (15.9.3), i and f ailures of BhlH0G position. In addition, will
- relief valves - provide maintenance procedure e feasibility study by 3/85, and systes mods.
II.K.3.17 Report on outages of ik>pe Creek Generating Station Accept &le (15.9.3). I i ECCS systems license provided their methodology.
- report and proposed tech. spec. changes. ,
9 II.K.3.18 Modification of f95 Ik>pe Creek Generat ing Station endorses C PSE&G to submit , ,
logic. Option 4 of the BWHOG position. verification of installation i of inhibit switch.
II.K.3.21 Restart of core spray isope Creek Generating Station endorses 4ccept ele (1.3.2.8),
and LPCI systems. B INROG position - no changes are 8 required.
t II.K.3.22 Automatic switchover Hope Creek Generating Station complies - Acceptable (7.4.2.2). '
of RCIC suctlon. see FSAR sect ions 5.4,6.1 aiwl 7.4.1.1.2.
leRC 7 (A-9)a ,
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- 9. LICEll511eG STAIUS C. THE letPACT OF 16uREG 0131 11Ett 110. Sus.lECI __ RESOLUTIDII - f5AR DOCUMENTATI001 RE50Luil0N - SER ,
Accept &le (9.4.2).
II.K.3.24 Confirm adequacy ol' lbpe Creek Generating Station complies.
space cooling for HPCI and RCIC systems.
II.K.3.25 Effect of loss of Hope Creek Generating Station endorses . Accept &le (15.9.3). -
AC power on pump lindROG study. ;
seals. l II.K.3.27 Provide commun Hope Creek Generating Station a;ompiles. Accept &le (18 SSERI).
reference level for vessel level lastrument at ton. , [
ll.K.3.28 Verify qualification Hope Creek Generating Station complies - Under itRC review e
of accumulators on see sect ions 6.3 and 9.3.6. (3.10.2). e <
A05 valves. [
o '
ll K.3.30 Revise small bre k Hope Creek Generating Station endorses Acceptable (15.9.3).
loca methods. GC model.
I II.K.3.31 Plant specific Hupe Creek Generating Station provided C-14 semitted 3/1/85 l calculations to show requested information. to IIRC. ;
compliance with i 10CfR50.46.
II.K.3.44 Evaluation of antici- Ibpe Creek Generatioq 5tation endorses Accept &le (15.9.3).
pated transients uith HWROG generic response.
single failure to !
verify no fuel r failure. .
II.K.3.45 Evaluation of depres- lbpe Creek Generat ing Station endorses No changes required. However. '
surization with other thiROG generic rsponse. Hope Creek Generating Station than A05. subjected to requirements of 9/21/82 gemor a on inteerity of vessel wel connecttons.
, (15.9.3).
IIRC 7 (A-10)a 45
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- 9. LICEn$las STATUS C. M IMPACT or staEG 0131 .
t ITEst to. SuSEC T RE50turl0m - TSAR DOClaq[NIAilou RE50tull0E - SEE II.K.3.46 Responding to Hope Creet Generating Station endorses
- i alchelson concerns. GE response to this issue. Accept & le (15.9.3). , i Ill.A.I.! Emergency prepared- thpe Creek Generating Station complies -
ness, short term. see TSAR section 13.3 C-36 additional information to he provided 6/85 (13.3.2.17). ,
Ill.A.I.2 upgrade emergency thpe Creek Generating Station will 1 support facilities. comply - see FSAR sect ion 7.5. C-36 information to be provided +
6/85 (13.3.2.17).
Ill.A.2 Emergency prepared- Hope Creet Generating Station will .
ness. comply - see ISAN sect ion 13.3. C-36 information to be provided 8 6/85 (13.3.2.17). !
111.9.1.1 Primary coolant Hope Creek Generat ing Station complies.
e outside containment. Accept &le - Hope Creek Generating Station to submit
- Inspection procedures and acceptance criteria to I staff within 2 months of 1 startup (15.9.4). l-Ill.D.3.3 leproved inplant Hope Creek Cenerating Station to iodine instruwnta- proveJe information 6/85. C-35 (12.5.2). Information sent June, tion under actident conditions.
III.D.3.4 Control Roon up Creek Generating Station complies -
habit &llity. See f 5AN sect ion 6.4.
Accept &le(6.4).
sac 7 (A-II)a
-a .- _ ._ . . _ _ . . . . _ . . , ... . . __ . . . . _ _ _
r
- 9. LICENSING STATUS O. ACRS COMMITMENTS The Advisory Committee on Reactor Safeguards ( ACRS) Subcommittee and Full Committee meetings were held November 28, 29 and December 13, 1984, respectively. On December 18, 1984, the ACRS issued the Hope Creek Generating Station a full power recommenda-tion letter. Only three items required further attention:
- 1. Turbine overspeed test
- 2. Control Room habitability
- 3. Ultimate Plant Protection System (UPPS)
Pursuant to a December 21, 1984 request by NRC, Hope Creek submitted information on the turbine overspeed test program and the UPPS applicability on April 24, 1985. Hope Creek personnel
, have also been active in aiding the NRC staff with the Control Room habitability item.
r' n.
3 NRC 7 (A-14) 9.12 I
-~_ _. __ _ _ _ . . _ -.- . .. ._ . _ _ . _ .. .. _ . , . _. _ _, . . .
. .: . .- u. _ -2.. . _ . .
i r
j 9. LICENSING STATUS i
, E. OPEN SER ITEMS
~
l . OPEN i ITEM NO. TITLE SUBJECT STATUS
) 01-1 Riverborne Missiles The effects of ships and other debris All responses submitted i
- (24.5,2.4.10,3.4.1, with a draf t of less than 12 feet to NRC by 5/08/85. '-
3.5.1.4,3.5.2,9.2.1) hitting the walls and penetrations of ,
safety-related structures. j
! 01-2 Equipment Qualification Concerns on seismic, pump and valve SQRT and PVORT audits (3.10 & 3.11) operability and environmental qualifi- were held in May 1985.
~
} ,
4 cation of equipment. E.Q. audit scheduled for July 15 - 18. l" i 01-3 Preservice inspection Resolution of comments on the Preservice All comment resolutions i Program (5.2.4 & 6.6) Inspection Program and submittal of submitted to NRC by 3/19/85. !
$ . relief requests. Relief requests to be L submitted in November 1985. '.-
6* Additional info due July. Ij l; 01-4 GDC 51 Compliance Augmented Inservice inspection Program Response submitted to NRC ,
(6.2.7) for feedwater check valves. 03/12/85.
I 01-5 Solid-State Logic Adequacy of Bailey 862 solid-state logic Test plans submitted to Modules (7.3.2.5) modules at Hope Creek Generating Station. NRC June 5. Test results '
4 due July and November.
j 01-6 Post Accident Resolution of comments on the post Resolution of comments ;
i Monitoring accident monitoring instrumentation. submitted to NRC on 5/14/85. I Instrumentation l (7.5.2.3) ;
, 01-7 Minimum separation Provide justification for one inch Justification submitted to
) between non-class IE separat lon. NRC on 4/04/85. Additional !
4 conduit and class lE info due July. <
cabletrays(8.3.3.3.3) ,
NRC 7 (8-2)a ;
l- !
. i i
- - ,: u w : .z~.: . < ..
. ii
- 9. LICENSING STATUS E. OPEN SER ITEMS OPEN
- ~ ITEM NO. TITLE SUBJECT STATUS l
01-8 Control of Heavy Loads , Respond to comments on heavy loads Response submitted to NRC i (9.1.5) program, on 1/18/85. Closea per
- SSER fl. ,
, i 01-09 Alternate and Safe Alternate and safe shutdown capability. Hope Creek Generating Station i Shutdown (9.5.1.4) design under review by NRC.
Safe shutdown to be resub- !
i mitted August. ,
01-10 Delivery of Diesel Delivery and filling of diesel fuel Response included as part Generator Fuel Oil oil and'1ube oil during flooded of Amendment 8. This item i and Lube Oil (9.5.4.2) conditions. closed in SSER fl. i 01-11 Filling of Key Manage- Fill open key management positions and Presentation to NRC in July
? ment Positions provide resumes in FSAR. on organizational changes. .
% (13.1.1.3) l i s 01-12 Training Program Items Resolve comments on training Responses submitted to NRC (13.2.1.1) programs. on 12/28/84, 1/07/85 and 4 4/26/85. i 01-13 Emergency Dose Provide description of emergency Description provided to NRC I Assessment Computer dose assessment computer model. on 1/07/85.
- Model (13.3.2.9) 01-14 Procedures Generation Submit procedure generation package PGP submitted to NRC on !
Package (13.5.2.2 and (PGP) to staff for review. 1/28/85. Supplemental
, 13.5.2.3) information was submitted to NRC on 4/10/85. Additional -
info due July 12.
01-15 Human Factors 1. Provide supplemental DCRDR 1. Report to be submitted to ,
Engineering (18) summary report. NRC in November 1985.
- 2. Provide SPDS safety analysis. 2. SPOS safety analysis -
submitted to NRC on i 4/10/85. Additional NRC 7 (8-3)b
~
. .u . .
- 9. LICENSING STATUS ,
F.
NRC AUDITS
! Item No. Audit / Subject Schedule St_atus PSE&G Sponsor -
i
- 1. Independent Design Verification March - August W. Galley Program - NRR,1&E - QA, Region I A. As-built prewalkdown May 29, W. Galley /J. Blenx
- 8. As-built walkdown June 13 -18, W. Galley /J. Blenx ;
e l l 2 NRC Independent Measurements - Region I April 22 - May 3 Completed F. Barnabei [
- 3. TMI Action Plan - Region I April / June Ongoing A. Giardino
- [
- -4. SQRT/PVORT - NRR May 7 - 10 Completed A. Kao .
S. Emergency Planning Pre-appraisal - May 16 - 17 Completed D. McCloskey Region I, I&E !
- 6. Security - Region I May 13 '17, Completed J. Baylish
!% 7. Fire Protection - Region I May 20 -24, Completed J. Pantazes/ l-W. Pavincich !
- 8. Radwaste - MET 8 -NRR June 19 Completed G. Dalton
- 9. Caseload Forecast Panel - NRR, Region I . June 26 - 27 T. Brauchle
[
- 11. Power Systems Electrical Walkdown - NRR July Tentative R. W. Skwarek/ i ,
! W. M. Pavincich
- 12. Operator License Audit - NRR, Region ! July 8 - 19 J. llagan , ,
l 13. EQ - NRR July 15 - 18 J. Wroblewski/
! C. Lambert
~ '
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- 9. LICENSING REQUIREMENTS ..
F. NRC AUDITS Item No. Audit / Subject Schedule Status PSE&G Sponsor ;
i
- T. R. McGuire i.
- 16. Emergency Planning Appraisal - Region I August 12 - 16 D. McCloskey 1
1-
- 18. Fire Protection - NRR, Region I August Tentative J. Pantazes/ l W. M. Pavincich
- 19. ICSB - NRR Septenser Tentative R. W. Skwarek/ ;
R. W. Rosko j
. 20. Nuclear Material License - Region I Septenber Tentative T. Busch r
- 21. ILRT - Region 1 Octobe'r 18 -19 L. Lake ,'
- 22. Emergency Planning Drill - I&E, FEMA October 29 D. McCloskey i
- 23. Security - NMSS October Tentative J. Baylish !
t
- 24. Operator License Audit - NRR, Region I 4th quarter J. Hagan Security - Region I 4th quarter Tentative
- 25. J. Baylish
- 26. Operational Readiness - Region I 4th quarter S. LaBruna ,
' a) Procedures e) If b) Tech Specs .
f) Maintenance .
c) As-Built Configuration - 9/30/85 g) Operational QA .
d) Chemistry h) Training NRC 7 (A-13)c i
I
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- 9. LICENSING REQUIREMENTS -
F. NRC AUDITS Ites No. Audit / Subject Schedule Status PSE&G Sponsor
- 27. Operating Readiness Visit - director of NRR 1 month prior 8. A. Preston to fuel load i
- 28. Commissioner's Visit - NRC Commissioners; l-2 months prior 8. A. Preston , l to fuel load
- 29. Commission Meeting for Full Power Vote June 1986 8. A. Preston
- f i
f SO . T 1
g k.
l-NRC 7 (A-17)b I
h i-i
~
- 9. LICENSING STATUS
{
I G.
SUMMARY
As in the past, Hope Creek will continue its aggressive pursuit of the closure of the remaining open and confirmatory items. Our basic licensing philosophy of working with the NRC staff reviewers to resolve technical differences of opinion without resorting to undue " appeals" or " claims of backfit" will continue to guide our efforts to resolve all remaining items in support of the December 1, 1985 fuel load date.
O f
n 4
4 NRC 7 (A-18) 9.18
- - _ .. . . . _ . .____g. _ _ _ . - _ .
-. ., . .._ , 2, L ..;. -
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST l
- 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55 Question: Discussion of schedular impact, if any, regarding potential deficiencies reported in accordance with 10 CFR 50.55 (e).
.s A. INTRODUCTION Since the 1983 caseload there have been a number of significant accomplishments in the Quality Assurance Program area. The early completion and acceptance of the large pipe hangers is an example.
- In preparation for ACRS review of Hope Creek, Region I submitted an evaluation to the Hope Creek subcommittee. The report stated the following in part
" Region I inspections indicate the applicant to be: 1) Responsive to facility construction needs and to be providing aggressive management attention to NRC concerns, 2) Improving QA/QC programs and increasing QA/QC manpower, and 3) Recognizing the necessity
- of continuous management attention to assure quality performance.
Region I has developed a high degree of confidence in the Hope Creek non-destructive examination (NDE) program, as a result of the independent verification of the applicant's examination, using the NRC Region I Mobile Laboratory (NDE' Van).
T SALP reports have generally indicated a strong involvement by PSE&G management in their overview of construction. Management 3
has initiated many new and innovative programs to improve o communications and jobsite morale. Examples of such initiatives undertaken by the applicant during the last SALP period assessed have included:
- A transition plan to coordinate orderly transfer of the Hope Creek project from the construction phase to operations. .
- A documentation and record turnover (OART) team, established to identify all records and schedule their turnover, format, and location (storage).
- Bechtel QA review of all past 10 CFR Part 21 reports, for applic-ability to Hope Creek using printouts from the Public Document Room.
" Applicant QA verification that corrective actions taken to correct past violations are still in effect.
NRC 10 (A-12)a J
- 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55 A. INTRODUCTION (cont.)
- An independent program has been developed to receive and evaluate safety concerns of any site employee (past or present).
. The program, initiated at Fermi by Detroit Edison is now being marketed as SAFETEAM and is intended to surf ace and resolve safety concerns at an early date.
As a result, the applicant's strong commitment to quality assurance
. has been reflected by a quality project."
These ir.itiatives are in addition to those such as Response Coordi-
.i nation Team and PRIDE, which were mentioned earlier.
In addition, the NDE van returned to Hope Creek in April for another in-depth NDE review. For the second time no violations were identi-fied at Hope Creek.
Following is the status of the 27 oper construction deficiency reports at Hope Creek. Extensive progress has been made in correcting these items and no schedule impact should result from these issues.
t In fact, 17 of the 27 open items have had the work completed.
Summaries of all 27 are included in the handout. Those with remaining potential exposure, indicated by an asterisk, will be discussed.
,1
- e 4
NRC 10 (A-13)b 10.2
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- 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55
- 8. DEFICIENCIES REPORTED i .
DESCRIPTION OF PROBLEM CORRECTIVE ACTION _
CURRENT STA1US
, 1. 81-00-04 Limitorque Motor Operator ,
Defictencles
- Numerous deficencies have been - Bechtel QC inspected all safety- - Rework completed on all 281 identified in Limitorque Motor related operators prior to cable Limitorque Motor Operators "L l Operators which include: termination. installed in safety related applications. Final report
- improper use of fiber shims scheduled for 7/17/85.
under contact screws
- poor wiring practices ;
- use of unqualified electrical l equipment j O ; o I
la 2. 83-00-08 Faulty Valve Operators -Xomox
- BIF valves reported via Part 21 - The twelve operators were returned - Rework and testing complete.
that a Xomox supplied actuator to the vendor for rework and Valves returned and reinstalled. j had failed seismic testing. seismic qualification-testing. Final report sent 10/6/84. : .:
Twelve (12) siellar valves had I been shipped to Hope Creek.
- 3. 83-00-09 Defective Capstan Springs ,
i
- Several Pacific Scientific - 86 mechanical shock arrestors - Rework complete. Final report mechanical shock arrestors returned to Pacific Scientific sent 8/16/84.
under test revealed broken for inspection / rework. They -
capstan tangs. Stresses replaced capstan springs in 25 induced during spring shock arrestors. The one missing forming resulted in shock arrestor has'been added to cracking during subsequent the N-5 data package checklist
, silver plating. 87 suspect as a control me'asure. -
arrestors had been supplied j; to Hope Creek.
! NRC 10 (A-15)b i
'~
,- ~ .
t
- 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55
- 8. DEFICIENCIES REPORTED (Cont.)
DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS
, 4. 83-00-13 GE Type AKR-30 circuit ,,
Breakers l'
- Numerous f abrication deficiencies - At their Connecticut facility, - Rework completed on 244 AC and .
were noted in type AKR-30 breakers GE performed a complete reinspec- 91 DC AKR-30 circuit breakers.
supplied by GE; to include: tion, rework and test program for Final report sent 11/26/84.
all of the affected circuit r
- Defective and loose switches breakers. [
- Improperly heat treated closing spring prop z.
3; - Loose buffer assembly, loose ' ;i ,
,, screw on "G" switch l-
- Short motor spacers, worn i-driving pawl
- Broken solder joints .
- Broken driving pawl shear pin J - Improperly installed cut-off j switch plate j S. 84-00-01 Jacket Water Check Valves - EDG ,
t j - Colt Industries reported via - Check valves were returned - Rework completed and valves '
j Part 21 that jacket water check to GPE for rework in accord- reinstalled. Final report 1 valves may " disassemble in dance with Colt's Part 21 sent 4/13/84. . i!
4 service". Four of these check Report.
- i valves manufactured by GPE jl controls are installed on our i diesel generators. .l
,i NRC 10 (A-16)b 4 f
)
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- 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55 i
B. DCFICIENCIES REPORTED (Cont.)
DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS
- 6. 84-00-07 Defects in Lube Oil Pump Discharge Nozzles ,
l...
- Colt Industries submitted a - Colt recommended that the face - Rework completed. Final report ! !?
Part 21 report regarding cracks of the bosses be machined down sent 9/28/84. .,
in bosses on discharge nozzles .060 inch to determine the discovered during factory extent of the surface indica- [F testing of a D/G set. Similar tions. This resulted in j' surface indications were found complete removal of indica-on'the Hope Creek units. tions as confirmed by NDE. !
'i 84-00-04 Manufacturing Defects !
- 7. '
in GE HEA Relays
$$ - General Electric Service Advice - Test HEA relays in accordance - Rework completed; 39 relays ca letters PSM-175.1 and PSM-165.1 advised of two potential problems with SAL PSM-175.1 and replace defective relays. Replace were replaced. Final report sent 9/20/84, fl-i-
~
with HfA relays supplied to all suspect relays identified Hope Creek project: failure to per SAL PSM-165.1.
meet specified trip force values -
, and malformed tension springs.
- 8. 84-00-10 Economizing Resistors - EDG i - Resistors installed on our - Basler Electric representative - Rework completed. Final report Emergency. Diesel Generator (EDG) inspected and corrected any sent 7/14/84.
exciter control panels were noted deficiences. Three improperly secured and/or incorrectely sized. Colt resistors were remounted and 2 resistors replaced. --
l' Industries advised Bechtel of the problem as identi-fled by Basler Electric.
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_ f
- 9. 84-00-09 underrated Cable - i k Valcor Solenoid valves p
- A SNUPPS Part 21 Report concerning - Replacement of the underrated - Rework complete. Final report
design deficiency also applied cable with cable capable of with- sent 9/28/84.
to Hope Creek. Cable intended standing the higher operating , i for conductor temperatures not temperatures. All other Valcor L exceeding 90*C for normal oper- solenoids were found correctly !-
ation was used in the connec- wired, tion of Valcor solenoid valves 4 in the instrument gas system.
Cable rated for 150*C should have been specified.
(:
5 -
6 10. 84-00-11 A/D Globe Valves - ! '
Non-Rotating Stems
- NRC I&E Information Notice 83-70 - Per vendor recommendations, the - Rework completed. 59 valves identifies a potential slippage stem collar setscrews will be were checked for collar setscrew checked for tightness. Affected tightness and 27 valves had problem with Anchor Darling globe valves with non-rotating valves installed in systems setscrews locked. ' Final report stems. subject to steady state sent 9/28/84.
vibration will have their setscrew locked,
- 11. 84-00-12 Incorrect Pin Material -
. BIF Butterfly __
- Cleanliness inspection of two (2) - Use nitric acid test to verify - Rework completed and design thirty-six inch valves indicated disc pin material. Problem application at Hope Creek extensive corrosion damage to limited to.four (4) thirty-six rendered the problem not tapered pins securing valve inch valves". Bechtel replaced reportable per 10 CFR 50.55 (e). m stem to disc. Investigation disc pins on the two valves See final report to Region I p; G ',
- determined pin material to installed in Unit No. 1. The dated S/20/85.
be stainless steel rather two stored Unit 2 thirty-six f?
than Monel as had been inch valves have been identified l9 specified. and controlled as non-conforming. yo.,
NRC 10 (A-18)b P
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i 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55
- 8. DEFICIENCIES REPORTED '(Cont.)
F DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS i
- 12. 84-00-13 Wiring in Consip Panels ?
- Consip Customline Inc. supplied - Bechtel replaced the susg.ect - Rework completed. Final report ,i eight electrical panels that wire with wire that meets sent 10/4/84. ,-
contain wiring that does not specified requireme'nts. - - ~
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meet the specified insulation
- wall thickness requirements. .
These panels may not be .
acceptable in harsh environ-ments.
i.
- 13. 84-00-14 Induced Voltage ;'
Actuations - Bailey h
- During preoperational testing. - Develop and install circuit - Modification work completed on incorrect actuations of Bailey modification to the input signal all IE and non-lE circuits for 1 controls Model 862 digital isolation on the Model 862 logic EMI problem. All testing ex- H logic modules were noted in IE card to discriminate between valid pected to be complete by and non-lE circuits. As orig- signals and induced voltages. 10/15/85. Final report sent inally designed, the logic 10/15/84.
module circuitry did not adequately suppress or (ilter .
- the induced voltages.
- 14. 84-00-15 Topaz Inverters -
Incorrect Low Voltage Setting '
- GE advised that Topaz may have ,- GE issued FDI-WTJD providing for - Final report to Region dated set the low voltage cut off at adjustment and testing the 12/14/84 withdrew this item 7 105 volts instead of 100 volts. undervoltage, overvoltage and as not reportable per Hope Creek F Topaz class IE inverters supply restart setpoints for each design. B.
power for the 24 VDC instrument inverter. @
buses for RHR, core spray, HPCI, n.
RCIC, ADS and Leak Detection R
- Systems. h f NRC 10 (A-19)b kp 5
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- 8. DEFICIENCIES REPORTED (Cont.)
i DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS i f
- 15. 84-00-16 GE Ground Break Relays
- General Electric Service Advice - Replace defective relays with - Rework completed. Final report letter 175-9.12 infonned Bechtel acceptable relays supplied sent 12/31/84, that ground break relays Model by General Electric. .
TGSR-12 may have a manufacturing defect.' Bechtel identified eight such relays installed in class lE 480 volt unit substations. t Es 16, 84-00-17 Brown-Bovari Type '
Lo SHK Circuit Breakers
- NRC I&E Information Notice - Inspect ard replace as required, - Rework complete. Final report *
, #83-84 advised of a possible the puffer piston rods in the sent 1/10/85. ),i
- breakers puffer piston push switchgear assemblies. !
rods supplied by Brown- I Boveri. ?
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- 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55 [
- 8. DEFICIENCIES REPORTED (Cont.) }
DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS
- 17. 84-00-18 Incompatible Grease -
Limitorque Operators ,
l
- - During routine maintenance activ- - Inspect and remove the EP-2 grease - 513 of 530 operators reworked. !
ittes, craft personr31 added from the Limitorque operators. Safety analysis complete. Final Exxon Lidoc EP-2 grease to report submitted 1/21/85.
Limitorque valve operators that were shipped from the manufac-turer with Exxon Nebula EP-0, ,
EP-1, or Sun Oil SOEP grease.
,?
I Potential exists for mixture to ;
cake or run out of the operators.
5 Subsequently, PSE&G Maintenance - Inspect and remove the Unirex N-2 - Work in process. Grease has been i>
. Department personnel added Exxon grease from the Limitorque opera- removed from 71 Limitorque oper- F Unirex N-2 to the gear box of tors, ators. Report to be sent 6/28/85.
94 Limitorque operators. This lubricant is incompatible with I(E the existing grease and has y the potent tal for the mixture i to cake or run out of the [.)
operators. E
- 18, 84-00-19 Ruskin Fire Dampers h-
- Ruskin Manufacturing Company - Investigate problem and provide - Working with Bechtel and Ruskin, if l
reported via Part 21 that spring specific system / damper solutions. PSE&G Site Engineering has P 3
closure fire dampers may fait developed specific system / damper ' .
l and/or exhibit reduced perfor- fixes for the problems. Test :j mance under air flow conditions. . results underwriting the efft- fu ciencies of the fixes should P. ,
2 be available by July.
- i NRC 10 (A-21)b l
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- I
!! 8. DEFICIENCIES REPORTED (Cont.)
DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT. STATUS
- 19. 85-00-01 EDG Fuel Pump Valve Holder i - Colt Industries advised of a - Replace all forty-eight of the - Safety analysis completed and i- possible defect in the fuel affected components with accept- submitted in final report dated
. injection pump delivery valve able replacements supplied by 2/12/85. Replacement of com-holders on our Emergency Diesel the manufacturers. ponents pending receipt of :
l Generators. A fatique crack parts. Ship date of 6/30/85 can occur at the filter seat
~
from Colt.
radius and progress to the -
p holder 0.0. There are 12 i.;
potentially defective pump !-
g delivery valve holders on each of the 4 diesel generators.
t o f.
l *20. 85-00-03 Motor Operated Valve - [
[ HPCI Steam Supply Line i
- t. ..
', - During startup testing HPCI steam supply valve 1-FD-HV-F001,
- Replace installed motor with a motor as described on the
- Rework pending receipt of re-placement motor from the vendor.
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failed to operate due to an motor data sheet. Review all Investigation complete and {
-e incorrect D.C. motor in the other DC motor operated valves indicates no additional dis- ;
,l valve operator, supplied to Hope Creek for crepancies. Safety analysis h i :
motor appitcation. provided with interim report k l
dated 4/15/85. Final report F to be sent 6/28/85. E I'
- *21. 85-00-04 Heat Butidup - EDG Cabinets .
p
~' - Louis Allis submitted a Part 21 - Monitor ambient temperature in - To date, Bechtel has not received F j' Report identifying a potential Hope Creek EDG control cabinets, sufficient infonnation from Colt ? j, heat buildup problem within the Coordinate with Colt Industries, Industries, Basler Electric or p.
- ' EDG control cabinets. The source Basler Electic and Louis Allis Louis Allis to perform an anal- i
! of heat is three transformers on resolving problem. ysis of safety implications. An .v i
mounted in the cabinets. interim report was submitted to J Region I on 5/6/85. Final report f[ jj scheduled for 8/3/85. P
- l NRC 10 (A-22)c
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- 8. DEFICIENCIES REPORTED (Cont.)
I CURRENT STATUS DESCRIPTION OF PROBLEM CORRECTIVE ACTION ,
*22. 85-00-05 TOBAR Transmitters -
Signal Drift
- Model 32 series 2 pressure - Investigate concern with vendor. - Investigation in progress.
transmitters supplied by TOBAR, Provide safety analysis report. Additional report to Region ! Inc. of Tempe, Arizona. have scheduled for 6/28/85. exhibited output signal drift !. in excess of allowable I tolerances, apparently as a , result of ambient temperature . changes. p t
- 23. 85-00-07 Air Baffle Cracks - EDG g
{ i ? - Louis Allis submitted a Part 21 - Repair utilizing a continuous - Repairs completed on the four [; j C Report advising of weld cracks in fillet weld backed w'ith a seal Hope Creek EDGs. Final report if the conical air baffles on Emer- weld. submitted on 5/31/85. h
~'
gency Diesel Generators. Public t Service Quality Assurance per- ' ' sonnel inspected the suspect welds p on the Emergency Diesel Generators. ; i On three of the Emergency Diesel Generators, linear indications were found on the vendor stitch welds securing the baffles to the generator shrouds. ,-
*24. 85-00-06 Unqualified Fuses in Comsip Panels -
4
- Consip, Inc. advised Bechtel - Investigation confirmed the pro- - 155 fuses identified for replace-that 1/10,1/4 and 1/2 AMP blem is limited to fuse sizes ment. Final report submitted -
Bussman fuses, installed by identified by Consip. Replace 6/24/85. i Consip in electrical panels fuses with qualified fuses, l supplied to Hope Creek, are not i qualified for class lE service.
!:i NRC 10 (A-23)b 4 i E 'i
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- 10. POTENTIAL DEFICIENCIES - 10 CFR 50.55 -
- 8. DEFICIENCIES REPORTED (Cont.)
l DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS - c25. 85-00-08 Corrosion in Jumpers - in Bailey Type RZ Modules !
- Bailey Controls Type RZ push -
Bechtel Project Engineering is to - Investigation in progress. [5 button modules contain spring provide fix. Field personnel Interim report scheduled for Z steel jumper clips over two to implement fix. submittal to Region I by : terminals of the push button July 5, 1985. p contactor. Oxidation of b several clips has prevented kE
- i. correct initiation of the
, digital and analog logic !r i systems. V 5 26. 85-00-02 Misapplied Sequencer .L N Relays (f
- Manufacturer has indicated - Bechtel will replace 26 affected - Pending receipt of replacement the relay contact gap may relays with replacements qualified relays. Final report sent ..
be insufficient to quench for high loading application. April 30, 1985. k the arc drawn when breaking -l 125 V DC. A total of 144 lc suspect relays are installed
- In Hope Creek equipment. ;
I u 4 9' NRC 10 (A-24)b l I i
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- 8. DEFICIENCIES REPORTED (Cont.)
I' DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS ..
- 27. 84-00-02 EDG Pressure Switches E
.p GE advised that four -
Return suspect switches to GE - Replacement pressure switches I; uninstalled " static-0-ring" for rework / replacement. Installed. Final report sent {." pressure switches probably September 28, 1983. ' are equipped with uncured ' 'k 0-rings that could permit , j?. oil to enter electrical portion of switches rendering {< them inoperable. E I. s i-2! a 8 e 4 e l NRC 10 (A-26)a i
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.d 10.NPOTENTIALDEFICIENCIES-10CFR50.55 4
i C.
SUMMARY
- No potential deficiencies identified to date will have any schedular j impact on fuel load.
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O ,i HOPE CREEK GENERATING STATION $.l
,,, NRC CASELOAD FORECAST
.& J,
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- 11. CONSTRUCTION /STARTUP INTERFACE t ,
I' Question: Overview of current construction and startup management j,4 organization showing interfaces between the two. ,q
,a J.I A. INTRODUCTION q.
U]j ; The Hope Creek Project has adopted an 19tegrated team concept to JJ facilitate communication between the Startup and Construction organi-Q zations. The success of this concept is evident in the 153 system turnovers and l',301 RFT's returned to date. These eight teams are d N chartered with the responsibility of managing systems from the con-1 struction completion stage, through startup testing, and continuing %; until the system is successfully tested and released for operations. B. MANAGEMENT / TEAM CONCEPT Team membership consists of a lead test engineer and construction representatives from field supervision, engineering, quality control, and planning and scheduling. Additional support is provided by the y resident engineering and procurement departments. The lead test
'M e.1gineer is responsible for outlining system testing and sequencing,
,]j CJ,Q construction support reoutrements, and priorities. Supporting the v lead test engineer is a startup planning and scheduling engineer who .;; prepares the schedule for testing and support activities within lj overall project schedule parameters. Construction responsibilities a are focused on supporting the test engineer by coordinating the ij efforts of the construction groups. 3; 4 g L e NRC 6 (8-5)a 1 11.1
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- 11. CONSTRUCTION /STARTUP INTERFACE ,
s B. MANAGEMENT / TEAM CONCEPT .- Construction /Startup Tem Responsibility Susanary -
- - - - - - - - - - PHASE I ------------ --------- PHASE II - - - - - - - - - -
g , PSSUG Lead Bechtel Team PSSUG Lead Bechtel Team Test Engineer Construction Manager Test Engineer Construction Manager
- Prepares release for
- Monitors and coordinates " Directs functional " Monitors ,and coordin-functional test (RFT) discipline activities to testing ates completion of ensure proper RFT and SDRs.
system turnover progress .
- Prepares procedures " Coordinates and expedites
- Directs construction
- Coordinates and activities to support support required for expedites activities PSSUG startup testing activities to support PSSUG.
- Directs functional
- Develop system turnover
- Conducts preopera-testing utilizing package tional test RFT system
" Reviews system prior " Prepares package for to turnover release turnover to opera-tions.
NRC 6 (B-7) a t
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.i HOPE CREEK GENERATING STATION SYSTEMS COMPLETION TEAM TYPICAL ORGANIZA110N CONSTRUCTION STARTUP MANAGER SYSTEMS COMPLETION J. CARTER MANAGER (esE&G)
, D. WEBSTER J. ZERUCHA (BEcH n ) [ TYPICAL l ! TEAM g l CONSTRUCTION PRE-
- RESIDENT MANAGEMENT TURNOVER r
L> ENGINEER STARTOP POST-MANAGEMENT TURNOVER l I . I 8 ) g- - - - -- - - - - - - g- - - - ~ ~ - - - - L OVERALL COORDINATION 8 g I l
.I . ,
i CONSTRUCTION STARTUP SDR FIELD OUALITY PLANNING PLANNING COORDINATION ENGINEERING CONTROL I
- ; AcAo/mtARTux I ,
i
j . . l 4: cz 11. CONSTRUCTION /STARTUP INTERFACE 9 C.
SUMMARY
': The establishment of teams at Hope Creek has provided a network of small groups each having a diverse, multidiscipline membership. Each
/J team has been assigned a manageable group of systems to match the
.' team members' expertise. The result is an efficient vehicle to plan.
H monitor, and expedite activities. The teams are more able to establish
.. joint objectives, to better serve the project, and accommodate on the l spot problem solving. Given high flexibility, the team concept is
, seen as an effective tool capable of getting the Hope Creek Project
; from construction to operations.
t f 9 i , :D3 i .d b l l.
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST J
,7 h 12. SPECIFIC ISSUES /i' Question: Detailed review and current status of design, engineering and q
construction effort; including quantitles, work-off rates, current status and schedule for completion for:
- a. ATWS-3A Design Changes
. :7 b. Appendix R Design Implementation j, c. NSSS Loads Adequacy Evaluation fi d. High Energy Line Break (HELB) /) e. Moderate Energy Line Breaks (MELS)
- f. Control Rod Drive System 98 g. Primary and Secondary Containment
?; h. Control Room Panel Modifications (PGCC) ,
1
- 1. Pipe Stress (As-Built) 9; j. N-Stamp Certification Program
^)
- k. Updating Drawings and Specifications to As-8ullt Condition
- l. Environmental Qualification of Safety-Related Equipment p m. Seismic Qualification of Safety-Related Equipment jj n. Hanger Reconciliation Program A
i'
;J " A. INTRODUCTION The following sections describe the current status of several major areas of interest at Hope Creek. As can be seen, the status of each Issue indicates completion supporting the Hope Creek December 1, 1985 fuel load.
- 8. SPECIFIC ISSUES
- a. ATWS-3A Design Changes The decision to incorporate ATWS 3A fixed was made in 1981.
Design Status - Complete q Construction Status - Complete with the exception of rework
, of input isolators in RRCS panels. Scheduled completion -
August 1985. NRC 9 (A-8)a 12.1
/
- 12. SPECIFIC ISSUES
- 8. SPECIFIC ISS,UES (Continued)
- b. Appendix R Design Implementation The design basis for Hope Creek is SRP9.5-1. (Appendix R is not a design basis for Hope Creek.)
- The NRC Region I and NRR fire protection / safe shutdown walkdown was completed the week of May 20-24, 1985. Thirteen open items will appear in the NRC trip report. None of these
,j items are considered major. , a The potential design changes include:
]
a Adding some additional sprinkler heads and detectors; l Adding a manual suppression system to the control console pit; Adding a panel wall to separate Diesel Generator HVAC panels; Adding some emergency lights. In addition the spurious signal and fire area analysis are to be - included in the shutdown procedures. The schedule for issue of the design for these changes is August 1985. Constructio'n Status - All fire ** protection systems including the above modifications are
' more than 75 percent complete and will be installed and operational by fuel load,
- c. NSSS Loads Adequacy Evaluation An evaluation was conducted to demonstrate design adequacy of essential NS$5 equipment when subjected to various dynamic loads and load combinations (GE new loads program). These dynamic loads result from seismic events and/or annulus pressurization related phenomena.
Design Status - Complete Construction Status - Complete NRC9(A-10)e 12.2
- 12. SPECIFIC ISSUES
- 8. SPECIFIC ISSUES (Continued)
- d. High Energy Line Break (HELB)
Design Status - Complete with the exception of a final (pre-turnover) engineering , walkdown to confinn the installation of barriers and to confirm that I safety related commodities have not been relocated in jet impingement i or pipe whip zones.
, Construction Status -
Complete installation of pipe whip restraf tfts and barriers. ! (Twenty of the 22 required barriers inside the Drywell have been I installed.)
, e. Moderate Energy Line Break (MELB) ,
Design Status - Complete with the exception of a final (pre-turnover) engineering walkdown to confirm the installation of spray shields and to verify -
, . that safety related commodities have not been relocated so as to be impacted by non-safety grade pipe failures.
Construction Status - Complete installation of spray shleids (less than 10) by October 1985.
- f. Control Rod Drive System Design Status -
Complete including consideration of water hammer and failed buffer issues. Construction Status - Complete The system was turned over to Startup on March 18, 1985.
- g. Primary and Secondary Containment
- 1) Primary Containment Design Status - Complete Construction Status - Complete Structural integrity test per ASME Section !!! NE requirement was completed in November 1979. The vessel was N-st aped in September 1983. Torus mods (per Mark ! Owners Long Term Program) were completed in May 1984 The Appendix J 1eakage test is scheduled for October 2,1985.
NRC9(A-11)e 12.3
o
, , . .. - .. - .- a . . . . . . . ~ . . ~
- 12. SPECIFIC ISSUES t .
- 8. SPECIFIC ISSUES (Continued)
- g. Primary and Secondary Containment (cont.)
1 1 2) Secondary Containment
,1
; Design Status - Complete I
] H Construction Status
- Complete
; . Secondary containment leakage testing is ongoing, with results to date below 1,500 CFM at 1/4 inch water gauge. Final documented negative leak rate testing is scheduled for October 1985.
l h. Control Room Panel Modifications , Design and Construction Status - All Design Change Packages (DCPs) resulting from the human factors engineering reviews have been issued and are being implemented prior to fuel load. These changes were minor in
),
nature (e.g. seals changes). (Note: Hope Creek does not have a
- , . PGCC.)
- i. Pipe Stress (AS-Built) , . _ , . ,
2 (SeeSection12/8/nfordiscussion.) .
- j. N-St mo Certification Program
; (See Section 12/8/n for discussion.)
- k. Updatino Drawines and Specifications to As-Built Condition v
i Design Status - Documents are maintained in an as-built condition by the incorpor-ation on a ongoing basis of all Change Authorizing Documents (CAQs) such as FCRs and FCNs as implemented by project specifica-
, tion G-14 By procedure such incorporation is required within a 90 day period from the approval of the CAQs. The effectiveness of this progra has been periodically evaluated and has been found to be satisfactorily implemented.
NRC9(A-12)e 12.4
.. m
. n.
4
._ 12. SPECIFIC ISSUES J f, t j
- 8. SPECIFIC ISSUES (Continued) ,
- ! 1. Environmental Qualification of Safety-Related Equiprient i
<; The Hope Creek Environment Qualification Program includes lQ safety-related mechanical and electrical equipment. Various ;g segments of the EQ program are ongoing and are currently on ', schedule to support fuel load. We currently anticipate the 1 NRC audit on July 15, 1985.
g By July 1985, it is expected that approximately 117 of 128 vendor 6] packages will have been reviewed and approved by PSE&G. The
% remaining package will be completed by fuel load.
- ., m. S_eismic Qualification of Safety-Related Equipment
; The NRC Equipment Qualification Branch conducted the SQRT/PVORT
.; Audit at Hope Creek site the week of May 6, 1985. The NRC Audit a Team, at the conclusion of the audit, stated that the PSE&G Audit was one of the best audits that had been conducted to date.
d D i There were three open items and nine confirmatory issues. None of these are considered major; all will be closed by fuel load. Outstanding Activities - * ([f) Complete resolution of SORT /PVORT audit action items '} 1 [ e' V e t k e lJ 5 1 1 0 w, NRC9(A-13)c r l 12.5 t-L_
- - . . . . .~ . ~~ .
- 12. SPECIFIC ISSUES g m 4
u; W! 8. SPECIFIC ISSUES (Continued) si '2
, n. Hanger Reconciliation Program i
- 1) Introduction
']
i Because pipe stress As-Built Reconciliation (ABR), and N-! 3 packaging are all interdependent (see Pipe Hanger Overview), agenda items 121,12j and 12n are all being addressed here. Stress analyses of process piping systems were performed during j the design phase. Field engineering, upon completion of the j installation of a piping system, sends to San Franciso the field revision of the piping system isometric drawing, along with a list and copies of all Field Change Requests (FCR) and Field ,j' Change Notices (FCN) not yet incorporated in the San Francisco design drawing. San Francisco engineering incorporates all FCRs
'i and FCNs on the piping isometric drawings, including all hanger location and orientation changes. Preliminary stress analysis (Phase I) is perfomed on this infomation to reduce the work required during the final As-Built Reconciliation (ABR). For Q g systems, the Quality Control (QC) group completes their inspection j and final piping and hanger information is submitted to Project 1 Engineering for final stress analysis (Phase II). The attached ti e chart shows the project schedule for this activity, including ,
.j '.s.' final stress calculations and the preparation of N-5 data packages. J When the stress and hanger reconciliation efforts have been j completed the piping isometric drawings are issued "As-Built". 4 2) Status l Total Phase ! Phase II ,i Stress Calculations Submitted Submitted i Q and Non Q 632 460 236 ] Q only 337 202 50 L. ; To expedite hanger completion and subsequent As-Built Reconcili-i ation (ABR) package submittal, milestones were established for QC acceptance of large and small pipe hangers of June 1 and June 30, 1985, o respectively. Construction achieved the large pipe hanger milestone
. and is progressing on schedule to support the June 30, 1985, small pipe hanger milestone.
The rate of issuance of as-built submittals based on final QC acceptance (Phase II) has increased in conjunction with the
; completion of the large pipe hanger milestone.
NRC9(A-16)c i
. 12.6
^
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- 12. SPECIFIC ISSUES
- 8. SPECIFIC ISSUES (Continued) 4 n. Hanger Reconciliation Program (cont.)
- 2) , Status (cont.)
San Francisco Engineering, upon completion of As-Built Reconciliation, provides the following documents to field engineering for inclusion
; in the N-5 data sheet documentation.
'A copy of the as-built isometric drawing of the piping system.
*A copy of the final stress calculation cover sheet.
*A copy of the pipe support details issued to show the loads and
, , movements of the final stress calculation and the as-built configuration within the installation tolerances of 10855-P-410(Q) and 10855-G-014.
Preliminary N-5 processing canmenced in April 1985. A dedicated group at the jobsite develops, coordinates, and packages the documentation required for certification of the required systems. Total Completed Forecast Status Packages Packages Completion 4
- Piping 83 13 November 1,1985 Instrumentation 26 0 November 1, 1985 Hangers ,
65 O November 30, 1985 y Combined Piping / 1 Hanger 5 5 Completed j Total 179 18
- 3) Summary Based on the preliminary ABR work completed as a part of the projects Phase I program described above and the early completion of hanger installation and inspection, both the engineering and construction activities associated with pipe stress as-builts, ABR, and the N-5 package will support a December 1,1985 fual load.
l NRC9(A-17)e 12.7
FUEL LOAD D MAY JUti JUL AUG SEP OCT NOV O 28 5 12 19 26 2 9 16 23 50 7 14 21 23 4 11 18 25 1 8 15 22 29 6 13 20 27 3 to 17 28 i 1 _CQNSTRUCTION C0t4STR CPT ttGRS _. _ _ ._( _ _ _ _ _ _ _ _ _ _._ _ _ _ _ __ E ACCEPT HGRS (P-2JO . t OC ACCEPT HGRS (P-2,10_ __. _ ,_ _. [ _ __ _ FIPML CALC SUBMITTALS
- -()_
^
._ _ __ __. c OESIGN VERIF'S AS-BUILT RECOtJCIL't4
__(),,._. ISStE tooS _k ) CmST/miqC CeT mms b _g_ _ REV.C FitML CALC APVL,
)__
_Q ISSUE FitML STRESS _ _ _ _ __ _ _ _ . , _ _ f) . I 3 _ _ __ __ _. . _ __ _ ._ _ . . _ t . ___ _ .. ._ __ 8 N N-5 PACKAGING , l ._ _ _ . _ _ __ __ _ __ _ ._ _ _ f4-5 PKGS, ROUTE C _ _ _ [_ _ ___ __ _ _ _. _j. ItJCORP COttt tJTS ISStf AS-BUIL T DWGS __ y x {g_ _ _ j l
~
t.GM) SETltGR/11AL Llib
~ ~ ~~ ~~ ~
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C FE FIiMt. CLfARhtJCE ~~
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6 ( :.
'"_ g.
g_. . _ . . __ _- _. . - _ _ OC ACCEPT P-2.00 _,._ _,_(g__ --
).
-m h
FIFML 16R_t{-LSIGtOFF 4 ) t Ti1LE* LEGEND: SOURCE: JOB tJtD0ER PIPE HANGER OVERVIEW "***** loass HANGER COMPLETION / ABR / N-S HGR C L3ATH $HEET OF C8011 h80
;c . . , _ .
4
- 12. SPECIFIC ISSUES C. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS The As-Built Reconciliation
- Management - *As of 6/18/85.
of "Q" piping systems in Established milestones for large support of N-5 package and small pipe support completion. " Construction - signing is an aggressive , Q supports schedule. ' Construction - L.P. S.P. , Modified their organization and Total T,TH T5W ' focused more attention and man- Accepted 6,155 4,779 power to achieving the allestone. To Go 172 1,811
- Engineering - "Large pipe supports are 99%
Modified staffing plans to installed and 97% QC accepted. support the remaining reconcill- Fifty field engineering inspected atton effort. Q calculations have been sub- . E; mitted to S.F. engineering. L3 "To date engineering has been reconciling as-builts, prior to *Small pipe supports are 98% ( QC acceptance in order to installed and 73% QC accepted. expedite the effort. The QC Small pipe isometrics have accepted as-builts will then bee- submitted to engineering. require less time to reconcile. Completion of DC acceptance ! will occur by 6/30/85 and ' submittal of small pipe isometrics by 7/15/85. l
- Engineering -
Thirty large pipe "Q" calcula-tions and 26 small pipe iso- - metrics have been reconciled on a preliminary basis. Completion of reconciliation is scheduled for 10/30/85 and N-5 data packages by the end of November. hRC 9 (A-21)c e
~.- . _. . . . - . . . . - .
' c- a- .. .1-. . . . , . _ _ . . u,_,m , . _ , , ,.,,i _ _ _ ,
n
- 12. SPECIFIC ISSUES D.
SUMMARY
t The foregoing discussion demonstrates that the engineering design effort and support to construction, licensing, and startup are consistent with the needs of the overall project schedule. No potential problems due to design rework are anticipated at this time. The home office engineering, site engineering, and resident engineering organizations are structured to provide maximum and timely support to
, construction to expedite resolution of construction related problems.
Further, all known licensing requirements have been addressed, and
' j, where applicable, have been factored into the plant design.
ht 4 e e 1 l 9
<W e
i NRC 9 (A-15)a l I ( 12.10
o ,- o HOPE CREEX GENERATING STATION NRC CASELOAD FORECAST
- 13. ROOM TURNOVERS Question: Detailed revlew or room / area turnover schedule and status.
- 4. INTRODUCTION fj In early 1985 management assigned a completion team to coordinate and
< expedite room and area turnovers. Although maximum emphasis must
', continue to remain with the systems. completion and startup testing support, the project recognizes that emphasis will move to the room turnover effort as the project approaches fuel load. The room
. . .J turnovers will drive the completion of all civil / architectural work and those commodities and activities not specifically associated with systems. To date 266 rooms or 30 percent of the total 890 rooms have been turned over.
The project has established a room turnover philosophy which maintains a high level of completeness at turnover in order to minimize post ,. turnover construction activities in the released areas. The philosophy has recently taen expanded to address not only the civil / architectural work items, but also any system related items which may be inside the i rooms / areas being evaluated for turnover. For convenience of control, rooms in the same area and of the same priority are grouped together into " packages". These packages are
- ( Identified to building and elevation.
An overall completion plan for room turnover packages has been ',> established and is Integrated with the requirements of all project
. groups (ie. Construction, Startup and Plant Operations). The overall
'l plan is to have all rooms and areas turned over by November 1985. . s { s4 a 1 F NRC 6 (A-10)b 13.1
_+ + . . . . . . . ..
)
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. It isnaisl519 Ms a 3 [3, :si ; @ N g 5
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l , i iit i i y suuta gil o# I $1 i4
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i e i t i I 6 i iiitI l i i i \ i i ]T g a [.et K l i i i iiii i i ,jiiii! i i . iI 6 ]- ' I ,ot Ql l ; i le 6 i !i6i i 'I i i}iiie i!t i i t igl. i! ici 2: g I i i!6 ii '!t i i iji 6 i I i i i i i ; i i Li g: l i .oi #g I i !iii l i 6 i I , tiiii .i i ai @, i ie ieiil !;e
, , i , , , ,,,6 , i i I !i e i,is i ,i Iii!
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i 6i I i i e i li!!Iii i i!I i i N s' g it-! *; i !lIi I'l ,iiI !!I I lo! inil j i i l l e! l l I!l } i I i IIi 1 ei i l i 3 ei l ici 'Al - 1I I tllii! l !eiI ! !
! t i i IM ! l !d l saeaaeaaaasseaaeo
- - - - - - - is
, , ,i,g amm uswno l g 13.2
- ....;.- . . . . _ . .. .. a . u
- f. -
l 13. 200N TURNOWERS 1 l C. PRORLENS/ SOLUTIONS , l DESCRIPTION OF PRORLFM CORRECT 1VE ACTIGN CURRENT STATUS ; Recent progress on room and Complete construction on final pcsp Within the month, the list of area package turnovers has of major systems to allow resources the major process systems will
- heen less than planned. to be. concentrated on room and area be completed and released to ,
turnover efforts Startup. This will allow - additional resources to be assigned to room / area activi- i ties. i' Priority areas required to suppc-1 To-go room turnover plan and Operation's activities must be associated priorities have i . , identified and expedited if been reviewed and integrated i i necessary. neith Operation's requirements
!* for specific areas. Required i areas have and will continue to be expedited as required.
To date all requirements for , specific turnovers have been . met. . i e i e NRC 6 (A-12)
- . _ , .m ,. __ ., ... .. _ - .- . _. , --
. .~- - . - , , , , m -
.....a.
o- ,
' -- 13. ROOM TURNOVERS O.
SUMMARY
The room and area turnover activities are being addressed in a manner which places maximum emphasis on completeness of all work within the areas being turned over. Although this approach has resulted in some delays in the turnovers to date, these delays will not impact the overall schedule. Critical rooms and areas have been and will continue to be turned over to support the project requirements, and all rooms
< and areas will be completed and turned over by the December 1,1985 fuel load.
),,
O f , og
'~
y8
+
a 5
/
I e l ' o l o NRC 6 (A-11)a 13.4
- e. .
a .s a .u-*- . . . . . - . - 4 r *., 4....,%- d E A. i i HOPE CREEK GENERATING STATION 4 NRC CASELOAD FORECAST
\
(a' ..! 14 INCOMPLETE ITEMS AT THE TIME OF LICENSING Question: Projected requests for relief of incomplete items, systems, or test completions at the time of licensing, identifying each.
; A. INTRODUCTION -
The project schedule calls for all systems to be completed and tested prior to fuel load to support licensing. Much emphasis has been placed on fully completing all work and minimizing any exceptions at system turnover or release from test. B. POTENTIAL EXPOSURES Aggressive schedules, supporting fuel load, are in place for" two systems, but they represent a potential expsoure. They are:
- 1) Radiation Monitoring System
- , The current plan is to have completed, as a minimum, all instal-
.: ,e.) lation and testing of the system required to support licensing. 1 - " Enhancements to the system such as data acquisition will be -: incorporated as available. s . J. 1
- 2) Solid Radwaste System
) As the system capacity was originally designed for two units there l l is a certain amount of excess capacity and redundancy. Some exposure does exist that only that equipment required to support j fuel load will be installed and tested with the balance coming s later. - i j C.
SUMMARY
The project is working toward and anticipating that all systems will be completed and tested prior to fuel load and no requests for exception will be required. I a x 7
'k-NRC 10 (A-4)b o
~
14.1
- i. u. a ... . . E b .w .-.. . = . = . . -. . . . - . .. j... ...L.: sh..u i
HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST q Q; -
- 15. OPEN PUNCHLIST ITEMS Question: Review of open punchlist items by category (hardware / paperwork) identifying each and work-off rate versus add on rate.
A. INTRODUCTION The Startup Deviation R'eport (SOR) is the vehicle which identifies every item of work to be performed on a system after Startup accepts a system from Construction. The 50R is generated by the system test engineer and assures closecut of all open issues within a system. The SOR program encompasses items originating from many sources, such as incomplete punchlist items which are exceptions at turnover (T0X), non-conformance reports (NCR), design change packages (OCP), out of calibration reports, retest requirements, equipment failures, etc. Although such items as NCRs and DCPs are tracked in their own categories, they are also tracked in the 50R program for consistency
! and accuracy in reporting project status.
[ u
] As 50Rs are generated they are reviewed for the category of work, Ji schedule requiremencs identified to system and/or room requirements,
'! and applicable system and room designations. These are input into a j dedicated data base for high visibility of status. s Once a system is released from test to operations, station administrative l] procedures (SAP) apply to new work items and will be monitored under a work order system. 2 The project is in the process of reinstituting the category designa-I tion of hardware and paperwork so that statistics are not available ,j at this time. si B. 50R STATUS See following charts. a o a 6 j z NRC 5 (8-5)b i 15.1
r
;! . r5r !I:,[-..(
,.?1* ~i!' \L;' j. i:;: . ,> i .:' <'-).! b ' I' . c.$'t m
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- s t
T C O S
. 'R Y DR T
P SA E S L M AM T U G U OS T
, A Y N ,
L U O I J T 5 xA . 8 9 1 E uS a cgs-T N N I c U ,I-T A = J e *)b .!
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- n e
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, d ne tL 1
V * ,
, S aA TT O oO 2
. N p - i l
b c TT u n.- 0 0 0 0 0 0 0 0 0 O P . 0 0 0 0 0 0 0 0 0 a 0, 6 0 4 0, 2 0, 0 0 8 0, 6 0 4 0 2 0 i E C u-1 1 1 1 R U O M&OMko xWD132 ( S
'u els
. - - ~ - _ . . .. :. .> .r .L. . I m, .
4 s. t
?
1985 JAN FES MAR APR MAY JUN JUL AUG SE P OCT NOV DEC 50 6 Il 2t27 5 le 17 2+ 5 to ilt4 18 7 th?! 28 5 12 19 2h 2 9 16 21 50 7 14 21 21 4 31 II t'S I 8 l5 12 29 6 Il 20 27 5 le li 24 4 8 IS 22 , inre _ _ _ _ _ _. _,3 isso _ ___ _ _ _, _ _. _ _ __ _ _ __ __ _ _,, , , . , _,g, j ggg__.__ _ 99a _.__ _ _._ _ _ _. _. _ _ _ _._ _ __ _ _ _ _ .. _ __ _ _ _ __-._ _.__ _ m _ _ _ _ , , , _y~ - t _ _._ _ _ __ . . _-_ _ _ _ _._. _ __. _ ,-.u _. Soo _ _ _ _ _ _. _ _ _ _ __ _._ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _j- __. _ ___ __ _ _ . .._ __ _ _ _,,, __ _ _ _ _ _ _ _ _.._ _ _ _ ._ _ _ __ _ _ _ _ _._ _ _ _ -. . _e _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ sio _ _ _ _ _ _ _ __ _ _ _ _. _ _ _ .. _ . .
, c _._ _ _ _ _. _ _ _ _ _ _ _ __ _ ._ _ , , ,
. . - - -_ _ , a _.- _ - - _ _ _ - _ _ _J- _
P = Fra _ _. _ .. . .. . . .. _ _ . _ . _ _ _ -- _ _ i _. _ _ . .'W.i -. _. _. _ _ _ _ _ ______ _ _ _ . . _ _ _ _. _ _ _ _% P i w g _ ._ _ _ _ _ _. . . _. _ _ _. _ ._ _ _ -
/.
- _ _ __ _ _ _ . _. _ ._ _ _ _ . _. _ . _ I,/ - _ _ . _ _ _ _ _ _.. ,'> + ,
p 658 - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . g - _. _ _ _ _. _ _ . _ _ _,g,. ! g y _ [: A. y Sso t y _ . _ __ _ .. .. _ _ _ . i 4 , . . '. . _ _ .. . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ __ _ , , g ._ __ _ _ _ _ . _,:_ _ _ _ _ _ . . . _ _ _ _ .. _ _ _ _ _ _ _
= ,
g,,< . _ . _ _ _ _ _ _ _ _ _ _ 65a___ _ _ _ _ _ _ . . _ . . _ _ _ _ _ _ _. _ _ _ _ - i - _
. ._ _ _ _ . _ g _. . _ . _ . . _ _ _. . _ . _ _ _ _ _
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. ., j i - _ , . _ _ _ _ _ _ _ _ .. .. . . _ _ _g, !
_ _ _ . . _ _ _ .. _. .; ; ; j - _ . _i g _ . _ _ _ _ _. _ _ _
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j i " 8 s g 5 [ _ _ _ _ _ _ _ _ . _ _ _ _ _ l 219_ _ . _ _ _ _ . . _ _ _ _ _
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1 _
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- .. : E.
g I g g _. . . _ .. ., k , i
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l
- 4 g ! -
l 'i : E- - i - i- - - - -- _ U c o ;iE l ' ' 11 ! n - li l 1 i l '.!u! L i i ir ! ! i l , s .i ! ! i it ic f: - - - LEGENO; . s==a mt h.h%*M.. SOURCE: ilTLE: HEW ST CEO APwL Dagg SCHEDULE NO JOS NO. HOPE CREEK GENERATING STATION ' ,.{. C- d'" = SCHEDULED SDRs - -- - -- Ii. 10sss __ ___ s
,unic u m. meia.c . .A. ca. _ _ _ _
- SHLEE or en e eeen
, ... .~..~. .\=.~..-.- W~= - ~ u-
, , 15. OPEN PUNCHLIST ITEMS B. SDR STATUS (Cont.)
Below is a SDR report from the project's computerized program indicating numerically the SDR'S Issued, Closed and Open by system and facility through June 11, 1985. System descriptions
- are available in section 8G.
1 5 lj SYSTEM ISSUED CLOSED OPEN j?j l 41 P.4 AB 232 90 , i 142 !j AC 96 24 72
. AC 393 263 h 130 AE 278 146 132 hi. AF 112 30 82 AK 105 72 33 l
; AM 51 48 l .1 3 j AN 168 76 -
92 1 l p, AP 160 114 1 s 46 l [:l , BB 690 249 1 441 fc] BC ,,758 423 it 335
;; BD . 238 35 154 BE 247 f! 151 96 4
BF 143 61
.; 82 c: BG 219 96 123 N
, ,; BH 117 69 48 I:j BJ 167 82 85 BN 50 38 12 CA 53 24 23 CB 82 39 43 a1 CC 15 4 11 $9
'l CD 4 1 3 Fi CE 18 1 17 CF 31 8 23 .., CG 53 34
- c. 19 k u.
'y T . "4 ->
I.( I[$ e w 15.4
l _ _ ,, . . . - .-.. . .: . ~u ' $ ~ ~.' " s L : ; - . ua:: ' - *:' - 2 ~ ' - '-' " ; - i . h_ "j !, 15. OPEN PUNCHLIST ITEMS B. SDR STATUS (Cont.)
' '. SYSTEM ISSUED CLOSED 0 PEN CH 57 33
, 24 r.
CJ 18 7 11 M. DA
- .8 189 138 51 c, DD 36 25 11
- DE 27 15 12
.; EA 382 207 175
'l EC 171 90 81 ED 144 89 55 EE 325 186 139 fj EG 367 200 167 EP . 1 1 0 EG 35 28 7 FA 163 157 6 FB 17 6 11
, FC 14 6 8 FD 9 5 4 FW 16 11 5 GA 108 89 19 GB 175 63 112 GD 8 6 2 GE 123 71 52 GF 63 51 12 GH 19 7 12 1
1 GJ 10 9 1 GK 62 28 34 GL 22 3 19
- GM 139 12 . 127 g GP 3 2 1 GQ 55 -
46 9
-s
_, GR 58 13 45 5 l 9 ^^" s 15.5
. u .. y. . ,.
*- , c. . . . ..w .a.. ..u..-- . u_ : **L.im ,'..:.:. 2.iL.I.;J: ' . . . . . L. G:.ub,, .
- 15. OPEN PUNCHLIST ITEMS
~
B. SDR STATUS (Cont.)
' . l' SYSTEM ISSUED CLOSED OPEN t
GS 130 28 102 GT 154 85 69 L. ' GU 73 16 57 1 HA 6 1 5 2 HB 98 20 78 4 HC 23 8 15 HG 1 0 'l
'A HH 1 0 1
- 2 HJ 0 0 0 m
JA 76 69 7 l.s i;j JE 108 85 23 KA 135 104 31 KB 85 47 38 KC 560 348 212 KD 80 71 9 {' ' ' KE 54 8 46
. KF 30 6 24
'- KG 4 2 2
+
KH 3 1 2
~
KJ 805 474 331 .; KL 117 33 84 s KP 10 3 7 r' LA 1 0 1 is 'l LE 4 2 2
/ LF 3 2 1 Ti MA 18 12 6 n ^
MC 111 110 1 MD 99 96 3 ME 2 2 0 ,; MF 7 7 0 a-15.6
~
. .: =:c.wa:, . .
- e. .y,
. . x a.. . .. .ax .. < . . _ . , , . - . . . . . zu .u. a. :. . . . . :. ~. a. :. > a. . . -i
- 15. OPEN PUNCHLIST ITEMS
, f:~ ) B. SDR STATUS'(Cont.)
SYSTEM' ISSUED CLOSED OPEN MTE 35 31 4 NA 36 35 1 NB 215 203 12 ,.]1 NF 0 0 0 [c; NG 149 125 24 9 NH 85 84 1 NJ 17 14 3
.j NK 85 74 11 e 'd NL -
8 4 - 4
'.a
',-:: NG 67 50 17 PB 79 77 2
)) '
'! PG 115 100 15
[j PH 36 33 3 PJ 41 29 12 PK 134 117 17 E
, a. -
4 PN 113 66 47 PR 0 0 0 i+ L. QA 8 5 3 9 QF 32 15 17 W j QH 4 0 4 - QK 46 15 31 RC 12 5 7 RG 50 15 35
- e RJ 285 155 130
,; RK 47 34 13 U RL 747 603 144
. SA 13 8 5 SB 99 57 42 SC 11 8 3
- SE 32 20 12 -
T 1 15.7
, ,;;y '.
, 3 % . l. .* = . .:.
- .~ . . , .: . . . . .a
. . .. w.
, ~ ,- h.,:::.a u .: i . a:d w a,. w.v.:2,- a-.... .
j 15. OPEN PUNCHLIST ITEMS
,c
.1 '( . , -
. B. SDR STATUS (Cont.)
SYSTEM , ISSUED CLOSED OPEN SF 27 18 9
.. SG 27 24 3 1
s SH 1 1 0
- j. SK 26 18 8 SM 66 43 23
.f SN 16 12 4 m; SP 6 5 1 S SS 1 1 0 ST 6 1 5 [*j SV 34 9 25 ZA 10 3 7
$ ZB 12 5 7 1 ZC 32 14 18 ZZ 509 344 165
~
4 A077 3 3 0
!! A102 1 1 0
~
A120 1 1 0 . . . D087 1 1 0 c..
'i D102 19 12 7
- 4 D124 47 35 12
- D137 49 40 9
'j-E054 34 21 13 j E137 61 34 27 I' F054 2 0 2
. F146 13 7 6
; F163 16 10 6 3, l Jh i
\%,.
- l 15.8 L
. . , -- . c, .
's 0L- , ,:' .a_.. __. _ w a u x: 2:. ,-ug;i. ,;_xa,._,. :.;, nw. ; z,; y ,_ s w; ,__;., ;_ w,. ,, ;
-29 . . . ,
- L
=
- 15. OPEN PUNCHLIST ITEMS ,
B. SDR STATUS (Cont.) , SYSTEM ISSUED CLOSED OPEN G102 11 5 6 1 1 0
! G120 l G123 1 1 0 H102 2 0 2
-i Il02 15 13 2 0 0 0 Q102
~
Z102 24 9 15 0102 8 5 3
.a TOTAL 13778 8151 5627 q
z I
- si e
b F *%
'i E
'4 1 0 h h . N 4
'e e
F 15.9
- . .. . i .. .
\ I
, l i .
BECHTEL CONSTRUCTION INC. ' i HOPE CREEK GENERAllNG STATION - JOB 10866 f STATUS OF NONCONFORMANCE REPORTS (NCRs vs. TIME) saae - 8850 LEGEND:
^
Is >asas" 9 d[*
,os, s'%1 o._________.o .c ..
I t
.M 1088 l
(1050 C 3 ACTUAL E oss %. , g i= ,,,, -s, o...............O,,,,,,,.... [ *** i sas 'l t $25 a.++ ++ + +++o ctosso men *, e- \ h o \' F AC No. I Fuf L LOAO: DEC. 8. s eeS l b E m- i% - NOTE: 8 9 ctosto Nca s uns wctM lg 725 l bZ yee- i 4 O Ncw nca s Tws witu 689 % jg 4I 640 % g -4 9 Actual reocatsS THtS WEEK rins s
- -E see O
se a > 's , occuitt uen.s mataatto topart. 7808 E It?5 wa.mws cratnatto fonait ' 8'O 5
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)
* % [
447 + 2 _I 400 ,
.,4
& W++ x,,400
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NOTE: g t 70TAL NMS ENERATED To oaTE 8613 j. i
,3,_' ' }(375 ,
y h ' 32, J 3e3 3,'j,~
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\ b95 e.r l JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOW DEC JAN FEB MAR APR l 1985 1986
p_c - x _;,. ., , 3 ,: . z. . u . , G ;. ) ,
- 15. OPEN PUNCHLIST ITEMS
- 0. PROBLEMS / SOLUTIONS DESCRIPTION OF PROBLEM CORRECTIVE ACTION CURRENT STATUS I
SDR Work-Off [ b Timely closeout of SDRs must A detailed SDR computer base has Recognizing that new SDRs will be L continue in order to support been developed that traces the status generated at the rate of 300-400 per the preop testing and system of each open SDR. This interactive week, the project is targeting for s. I turnover to operation schedule. tile identifies the system need date closing approximately 600 per week l These SDRs result from primarily for each SDR, current status, priority to clear up the existing backlog. two causes: exceptions noted for each SDR and other miscellaneous Additional personnel has been added i 3 at the time of system turnover information, to process these, and results to date and deficiencies / modifications indicate that the rate is fully },
,. noted during system checkout. Critical SDRs are reviewed daily by achievable. ['
i yi Construction Management and Startup. -
- Overall work-off curves are continually !,:
published indicating progress accom- [/. plished and near/long term work-off : requirements. The critical path to closing SDRs is h:!
, primarily non-manual intensive. This I includes necessary paperwork packaging, material procurement, and timely buy-offs. '
f Non-manual staffing in this area has !~ been significantly increased and work . [; hours extended. te NRC 5 (8-6) 4 h
.u, e.,:a,m.
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;. 15. OPEN PUNCHLIST ITEMS f .j - f. . ,
i.*.! t; . "r L '
, E.
SUMMARY
e 6' The volume of completion work as identified in the SOR program f.' is progressing well and will support preop requirements leading
- , to fuel load.
- q 6,.
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=:i 4
t 'l'{ . l t -, b 9 p l s 4 f I
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5 NRC 5 (8-7)a 15.12
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J HOPE CREEK GENERATING STATION a.. -
- NRC CASELOAD FORECAST s (Eh.a q
- d. 16. SEISMIC II/I REVIEW
! Question: Status and schedule for Seismic II/I review (IEB 79-14).
G 2 A. INTRODUCTION
..) Specification 10855-G-052(Qs) has been issued to implement the ?; Seismic II/I. Evaluation Program to meet the requirements of Regulatory Guide 1.29, Position C.2. Seismic II/I considerations were included in the design as bulk layout drawings were issued for
, . , construction. Seismic II/I requirements are also indicated on the
, pipe index, hanger drawings and architectural wall drawings.
u 2 Formal wsWdowns are being performed in accordance with Specification
'; G-052 for Seismic II/I Evaluation. The walkdown status and completion schedule are shown below and on the attached curve. The walkdown teams evaluate and document the acceptability of the design. }i B. STATUS AND SCHEDULE 4 ;;.];;
INITIAL INITIAL FINAL FINAL - WALKDOWN WALK 00WN WALKDOWN WALKDOWN AREA % CPT. F/C CPT. F/C CPT. F/C CPT. Control / Diesel Gen. 100 - 50-60 11/08/85 Bul.ldings [i Reactor Building 20 08/30/85 10 11/08/85 Intake Structure 100 - 100 -
.,' C.
SUMMARY
The foregoing discussion demonstrates that the engineering design and review efforts to insure implementation of the Seismic II/I program are consistent with the needs of the overall pro, ject schedule. s n T '. < S.*
* NRC 5 (B-10)b 16.1
9 . . . . . < p r'-
..t x- . .. u .. m.s. = ,..,G.: a .a2:= u h % % k.ah.:..L: . :. . . ....' -
1 HOPE CREEK GENERATING STATION NRC CASELOAD FORECAST ((I}
- 17. POWER ASCENSION AND OPERATIONAL PROCEDURES i
'l ,
Question: Detailed review and current status of power ascension testing
. procedures 'and operational procedures.
A) Power ascension test procedures including safety-related and nonsafety-related.
- 1. Number required
- 2. Number not started
- 3. Number in preparation and approval process
- 4. Number approved B) Operating procedures required for fuel loading: Including station administrative, station operational, surveillance (e.g. technical specification), maintenance and emergency procedures.
- 1. Number required
- 2. Number not started
- 3. Number in preparation and approval process j 4. Number approved i m v r%
l nev A. INTRODUCTION The overall procedure effort is 83.1 percent complete. All procedures are scheduled to be finally approved through September 1985. Procedures are being written to include commitments and industry operating experience. Surveillance procedures are being developed in coordination with startup testing to ensure that tests are accomplished in an effective and complementary manner. n
} 8. POWER ASCENSION TESTING PROCEDURES AND OPERATIONAL PROCEDURES Below is the current status of power ascension testing procedures and operational procedures.
a) Power Ascension Test Procedure Status Number required 125 Number not started 0 Number preparation and approval process 121 Number SORC approved 4
~ ,, NRC 8 (B-11)a 17.1
- m. i.c ...,
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~.1 17. POWER ASCENSION AND OPERATIONAL PROCEDURES N .w g 0 ji -, I,'2, 9 B. POWER ASCENSION TEST PROCEDURES AND OPERATIONAL PROCEDURES Operating Procedure. Status 3.,
Not Prep. and 50RC Required Started Approved . Approved
- _ - . _ .
. ,1 Station Administrative
- 37 (46) 0 (8) (38)
'! Operations 565 35 388 142 Reactor Engineering 50 0 50 0 ?l
- ); Chemistry 214 7 103 104
'1 ',! Radiation Protection 80 0 34 46 3 Maintenance 373 5 233 135 Instrument and Control 1,063 121 817 125 ,) Technical Support 23 0 5 18 R ,- .
7, Total 2,414 168 1,638 608 g $~i)
%+ ,,
L, 3 Technical Specificatloc 1,005 95 873 37 Surveilladce Procedures (Already Included in Above Totals Among Various Departments 3 m H. o a m i..
- Note: Additional procedures have been added to the original if effort of 37 procedures.
k p [; c , 3; v NCR 8 (B-16) p, i 17.2 L
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- PROCEDURE DEVELOPMENT ' "
- sotaua
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j . dj M GENERAnNG SMnON PERCENT COMPLETE
~~~~~
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) 17. POWER ASCENSION AND OPERATIONAL PROCEDURES f: { '; 8. POWER ASCENSION TEST PROCEDURES AND OPERATIONAL PROCEDURES (cont.) Startup Procedures Required for Fuel Load ji Below is a listing by type, total number and status of procedures required for fuel load. f
- Total Number of Procedures for Fuel Load f Not SORC k.
Procedure Type Started Starte.d In Review Apprvd* Total p b Station Procedures e-
-i Administrative Procedures 0 3 5 38 46 i
Station Operating Procedures , :.
~* Admin./ Directives / General 1 0 6 10 17 O *0perating Procedures / Instructions 8 0 133 39 180 [-
k
- Abnormal / Emergency Procedures 0 0 57 33 90 F
- Surveillance / Alarm Responses 26 22 170 60 278 Total 35 22 366 142 565 t
Station Technical Procedures
- Technical Document Control 0 1 1 14 16
- Technical Miscellaneous 0 1 47 4 52
- Fuel Management 0 0 5 0 5
- Power Ascension Tests 0 5 116 4 125 Total 0 7 169 22 198 f
- Procedures are being exercised in the field during preoperational testing and following turnover' to operations (RTO) and required change incorporated.
l 1 NRC 8 (B-17) I t 6
...;..,. . o .i- u: - .z u. '- .: =: . . - ..aca.:~ : 7a :. .i v.u . 2.
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- 17. POWER ASCENSION AND GPERATIONAL PROCEDURES
', [ 3 t_.
- 8. POWER ASCENSION TEST PROCEDURES AND OPERATIONAL PROCEDURES (cont.)
Startup Procedures Required for Fuel Load (cont.)
,s Total Number of Procedures for Fuel Load i Not 50RC L I Procedure Type Started Started in Review Apprvd* Total f}.
4 p Station Maintenance Procedures K
- Qualification Procedures 0 0 2 14 16 F
*Mainistrative Procedures 0 2 2 10 14 .
e
- General Procedures 2 5 23 21 51 i
- Corrective / Prevent. Maint. Proc. 3 15 161 77 256 e "Special Process Procedures 0 0 3 0 3 I
, " Surveillance 0 1 7 11 19
- Calibration 0 0 0 2 2 .
l[
- Fuel Handling 0 0 12 0 12 !
i
*1&C Mainistrative Procedures 0 0 0 11 11
'I&C Tech. Spec Sury. Procedures 94 84 612 0 790
*I&C Device Calibration Procedures 1 5 91 41 138 Total ,
100 112 913 187 1,312 Station Radiation Protection Proc.
*Emer9ency Plan Procedures 0 0 0 19 19
*Mainistrative/ Training 0 0 2 8 10 '
'C al i bra t ion / Surve i l l ance/Abnorma l 0 5 27 18 50
,
- Preventive Maintenance 0 0 1 0 1
- Chemistry Main. Procedures 0 0 2 4 6
- Chemistry Sampilng Procedures 3 4 21 35 63
- Chemistry Miscellaneous 4 1 75 65 145 Total 7 10 128 149 294
!
- Procedures are being exercised in the field during preoperational testing and following turnover to ;
, operations (RTO) and required change incorporated. . ; NRC8(8-18) ,
;;.9. ua g.:.ai . . a. . , t . a.: w ...: w: --.: . . .a .. a .- .
j - ja i j 17. POWER ASCENSION AND OPERATIONAL PROCEDURES (m O .j)
- C. POWER ASCENSION TEST PROGRAM ACCELERATION
- 1) Reduction of shutdowns, unplanned trips, mechanical hold points.
; - Review recent BWR startup scram history 'il j - Review design and installation of critical systems
<:<} } - Review recent BWR startup test history 43 Q - Evaluate recommendations for implementation
.l; 2) Reduction and simplification of tests
- Review program for possible test deletions
.] - Review tests for duplication / extra content
- Evaluate recommendations for implementation ! 3) Technical specification relaxation ', ,, - Review technical specifications 1 ::q w
JJ - Evaluate possible relaxation ! q 1
; 4) Detailed and flexible scheduling l L' - Project target schedule (no contingency / optimum performance) l l
J - Detailed scheduling
- Testing contingency scheduling
- 5) Aggressive performance
- Utilize industry experienced people
- Dedicated integrated test organization
- Commitment to schedule
~
- j - Dedicated engineering for quick declsiors
- Team concept l
; l I ,
, NRC 8 (B-19) i
' n
'Q /
17.6
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. % .%a_
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- 17. POWER ASCESION TESTING p D. PROBLEMS /SQLUTIONS f.
p DESCRIPTION OF PROBLEMS CORRECTIVE ACTION CURRENT STATUS p
, p.
- 1) Technical specification sur- Preop tests provide a baseline for - Evaluation is underway to take veillance testing prior to plant equipment and systems. The credit for surveillance /preops in ,
fuel load. Tech Specs are a reference docu- this category. g ment for the preops, and Opera- t; tions review further assures ; Tech Specs are considered in !; preop development, j t" Surveillance tests generally are To implement this approach, sur-performed independently of the veillance test procedure com- , preop. However, certain preops, pletion has been prioritized to P because of-their natrue, virtually meet preop procedure review dates. h duplicate Tech Spec items. ,, Other surveillance test procedures The balance of surveillance tests j are being performed during the are performed independent of .. preop program; either in concert the preop. If greater than 6 with the actual preop test or months retest cycle, they are utilization of the surveillance scheduled immediately following test to satisfy prerequisite completion of the preop. Sur-to the preop. veillance tests less than a 6-month cycle are performed after The surveillance testing is being preop and scheduled in the final integrated into the Hope Creek quarter to support fuel load and project schedule. early power ascension tests. NRC 8 (8-20)a a
. . . . , t.,-:::.a.:: . . : s a.: -c'.; . :a 2.' a . a :, s . a : % . D --' -
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- 17. POWER ASCESION TESTING ['
L D. PROBLEMS / SOLUTIONS i: P h.i DESCRIPTION OF PROBLEMS CORRECTIVE ACTION CURRENT STATUS ['a
- 2) Inclusion of industry / operating Each industrial experience docu- The "CD" nunber assigned provides ,
experience infonnation into ment (in addition to FSAR, SER tracking assistance and documented ! procedures and Emergency Planning require- associated between the commitment l ments), Wilch is resolved through and the resulting procedure or i incorporation of the requirement procedure steps, i into procedure action for . Hope Creek Operations, is assigned inclusion of the "CD" number [' a "CD" (Closing Document) number. Into the resultant procedure - serves as a means of identifying - the commitment and thus assists in verifying commitment com- ii ' pletion. I C Inclusion also provides Lo assistance to technical weiters : performing rewrites and 2-year reviews. I NRC 8 (8-21)a 0 p
-_ _ - _ _ _ _ - _ . _ _ _ _ _ _ _ _ s
_ b
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^3 D', 17. POWER ASCENSION TESTING a ~. A
- r. 2 ,.-.
- y E.
SUMMARY
-)
i Procedure development constitutes a significant effort and is
,; scheduled to complete in September 1985. Sufficient manpower gj has been applied and management is closely monitoring development
'i progress. This will support NRC operating readiness review in Jd the 4th quarter and provide sufficient time for verification and l1 training as required. F
- .s A
-C
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, , NRC 8 (B-13) 17.9
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HOPE. CREEK GENERATING STATION ; 1 - NRC CASELOAD FORECAST d' R. q.. .
- 18. STAFFING, TRAINING AND OPERATOR LICENSING '
.! I Question: Detailed review and current status of permanent station and j}1 support staffing, training and licensing.
n: j a) Staffing for operation, including presently employed,- projected and authorized for each group reporting to the j Vice President Nuclear. .
.+
fi b) Staffing of Hope Creek station organization ir.cluding presently employed or contracted, projected, and authorized r for each organizational subgroup. c) Training program: Outstanding training courses required y prior to fuel load, identifying job titles, numbers of z.) personnel, and projected completion, h d) Operator and senior operator licenses presently onsite, R contracted, projected, and required for fuel loading. J Uh
;3 j g- A. INTRODUCTION -
< h' B. . , ' Staffing - 390 PSE&G employees are presently authorized for 1985 and
', all are projected to be present to support fuel load. The current PSE&G staff level is 360. To augment station maintenance craft a Plant Betterment and Maintenance (PB&M) contract using The General Presidents Agreement is in place for support during preop and power ascension phase as required. Additional contractor personnel are .
being used to handle the larger than normal workload during startup for procedure development, spare parts ordering and establishment of station programs. Training - All required training courses will be completed to support fuel load. Additionally, operator licensing exams are scheduled for July and October 1985. B. STAFFING, TRAINING, AND LICENSING
.. .i Following are responses to the specific questions outlined above:
a) Vice President Nuclear staffing
,' b) Permanent station and support staffing c) Training program d) Operator and senior operator licenses 1
4 5 t 18.1 NRC 8 (8-15)a
.).
r s :- , .
~. .
l m==-as VICE PRESIDENT - NUCLEAR
- 5. STMFING REPORTING RESPONSIBILITIES VICE PRESIDENT
+
NUCLEAR fulLIC N 04MMION ,. I I I I SALEM OPERATIONS HOPE CREEK OUALITY ,
- i OPERMIONS SUPPORT OPERMIONS ASSURANCE I I i
METHODS & LICENSING & ENGINE EXTERNA 1. SYSTEMS RELIABILITY AFFAIRS p 6 l-I PERSONNEL & PROJECT PRa>ECT PROJECT ADM NSTRATION f ENGINEERING SERvlCES MANAGEMENT I l - SECURITY HUMAN
~
~
& SAFETY RESOURCES TRAINlNG _
ADMINISTRATION RADIATION ORGANIZATION ; SERVICES DEVELOPMENT
, i i DRD ~~
INDUSTRIAL f MAINTENANCE . RELATIONS [', T _ _ ___. _ _s
.. . _ , I
- 18. STAFFING, TRAINING AND OPERATOR LICENSING f
B. STAFFING, TRAINING AND LICENSING a) Vice President Nuclear Staffing PSE&G PROJECTED
. PRESENTLY AT PSE&G PSE&G FUEL LOAD AUTHORIZED
- Safey Review 10 21 21
; Quality Assurance 86 115 115 di Personnel & Administation 41 41 41 Operations Support 353 314 314 Operations Services 305 316 316 Salem Operations 524 530 530 Hope Creek Operations 358 390 390 d:, VP-N and Staff 21 8 8
- 0) Permanent Station and Support Staffing PSE&G c
PRESENTLY EMPLOYED . PROJECTED ,. - PSE&G* CONTRACT AT PSE&G 6/10/85 6/1/85 FUEL LOAD AUTHORIZED .. Management / Admin. 20 11 24 24 Operations 93 20 79 79 Technical 22 26 43 43 Maintenance 116 62 115 115 I&C 44 44 45 45 Rad. Protection 41 2 59 59 Chemistry 24 6 25 25 Totals 360 171 390 390
- PSE&G numbers do not include two transition positions. There are two people in this category; one in Management / Admin. and one in Technical.
NRC 8 (B-22)a 18.3
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i
! HOPE CREEK OPERATIONS .
i GENERAL MANAGER AND STAFF YEAR END 1985 - 390 ' CURRENT - 360 EERAL MANAGER (1) EXECUTIVE ~
- i SECRETARY '
L (1) .; i li l :
- f
't ASSISTANT TECHNICAL OFFICE ADMINIS RATOR R , g (1) s SENIOR 4 STATION SECRETARY gu r- PLANNING , COORDINATOR (1) ! r i i c OPERAll0NS CEMISTRY/RP I MAINTENANCE . l MANAGER MANAGER MANAGER i tu (1) (1) ' i
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HOPE CREEK GENERATING STATION f OPERATIONS DEPARTMENT . i YEAR END 1985 - 79 OPEFATIONS CURRENT - 93 MANAGER til ; ! OPERATING DAY . f
; ENGINEER -
SENIOR (2) . til ;
- I SENIOR SENIOR SHIFT SENIOR '
STAFF NUC. SHIFT TECHNICAL OPS. SUPPORT
- ENGIEER SUPERVISOR ADVISOR SUPERVISOR
? HI (6) (5) in ,
un i i I I E SHlfT SHIFT STAFF SUIVI "I i ENGidER CLERK SUPERVISOR
- SUPERVISOR .
gg (3) 86) (5) I MJC CONTROL ~ OPERATOR , (15) 1 EQUIPMENT EWIPHENT OPERATOR STM (RADWASTES
@8 usi i
UTILITY ' ' OPERATOR ' (3) 7
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Q) i HOPE CREEK PERATIONS TECHN ICAL - YEAR END 1985 - 43 CURRENT - 22 TECHNICAL MANAGER (Il i I I TEO N CAL SYSTEM l ENGINEER ENGINEER lit 111
! I I l l I ELIABILliY LEAD LEAD REACTOR TEO M CAL Apg)
ECHANICAL ELEC/ CONT SAFERVISOR SLFERVISOR PEN ORMANCE SYSTEM SYSTEMS gli lu SLPERVISOR lll Ill lH
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EACTOR TOR ELIABILITY
' TEO N CAL Apg) SYSTEM SYSTEM STAFF GROUP ENGIEERS EpsilEER SIMF PE WORMANCE ENGIEERS StPERVISOR ISI STMF (ISI (8)
(31 (H O ENGINEERING ASSISTANT lli : , i UAIA TOR ENTRY CLERK CLERKS H1' N (Il til
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g ,..,. , qv , HOPE CREEK OPERATIONS CHEMISTRY YEAR END 1985 - 25 CURRENT - 24 CEMISTRY/ RADIATION
- PROTECTION MANAGER !
un t CHEMISTRY , I ENGIEER f (1) ; I > CLERK (1) l SE AFF
- SENIOR CHEMISTRY ,
i 5 SUPERVISOR CHEMISTRY
" UI (1) {.
I I C E MISTRY CE MISTRY CEMISTRY SUPERVISOR SUPERVISOH SUPERVISOR OPERA 110NS LABORATORY INSTRUMENTS (1) (1) (1) l l l l CEMISTRY TECHNICIAN
; (6)
CHEMISTRY ' ASSISTANT
, (12) i
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., ? n, i 1; .3 HOPE CREEK OPERATIONS '
MAINTENANCE . YEAR END 1985 - 160 HAINTENANCE CURRENT - 160 3 MANAGER. I I I i MAINTENANCE I&C ENGIEER ENGIEER (1) (1)
; I I L
! I I I I I e ;
SE ' SENIOR SENIOR g SENIOR SENIOR SENIOR SENIOR SUPERVISOR SUPERVISOR OR SUPERVISOR BOILER SUPERVISOR PLANNING STAFF ; l NECHANICAL ELECTRICAL 1&C I&C SUPERVISOR SUPERVISOR i-REPAIR i (1) H) gn (1) (D (1) (1) ,! i
! i-1 I 5 MAINTENANCE MAINTENANCE MAINTENANCE I&C I&C OUTAGE STAFF ! 6 SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR PLAN ENGINEER j (2) (3) 4 (5) (3) (3) (2) (4)
( .. - - i i DAILY DAILY DAllE ~' ' f DAILY DAILY . PLANER PLANNER PLANNER l PLANNER PLANNER (p (H (H l n) (1) l [- i e ELECTRICIAN BolLER REP HACHINIST ng) (18) I&C I&C . i CLERICAL CLERICAL 11 8 ) TECHNICIAfjS TECHNICIANS gg3 g3) [ SHIFT ELEC. CUSTODIAN (13) 8 31 : (6) (18) L i UTILITY / I&C ASSISTANT : STATION ~ (4) r : M CHANIC ([ . ' .~ 14C WORKER , ; (32) (4) ; , y: ( .- f I,
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c) Training Program Non-Licensing Training Program Status Training common to all departments 3 Reactor engineers Chemistry / radiation protection Maintenance Department Instrument and control Operations All Departments _
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~, NUMBER TO NUMBER BE TRAINED COMPLETED
~
General Employee Training 357 269 Hazardous Waste /Right to 357 101 g Know Training Radiation Worker Training 335 0 Respirator Training Not Avail. 0 9 NRC 8 (B-23) 18.11
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- 18. STAFFING, TRAINING ANO OPERATOR LICENSING I.
- 8. STAFFING, TRAINING AND LICENSING (Cont.) :.
L d) Operator and Senior Operator Licenses i t Senior Reactor Operator * , 6 MONTHS 6 WEEKS t. ~ TOTAL PREVIOUS PREVIOUS BWR NAVY AT OPERATING AT OPERATING NO. BWR LICENSE PWR LICENSE CERT. NUCLEAR BWR BWR i. i Tctal Candidates 29 11 4 16 13 5 10 .
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Operating Shift 16 9 3 6 10 5 5 - Personnel : m e fi; Management 8 2 1 5 3 0 0 f STA 5 0 0 5 0' 0 5 i-
*There are 29 Senior Operator (SRO) candidates to fill 20 SRO positions.
Reactor Operator ** L 2 WEEKS TOTAL BWR NAVY AT OPERATING . NO. CERT. NUCLEAR BWR Tctal Candidates 16 16 10 16 bi, (All Shift Personnel) , e:' . hi i
*There are 16 Reactor Operator (R00 candidates to fill 15 R0 positions.
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e i f-I h HOPE CREEE OPERATIONS , LICENSED OPERATOR TRAINING SCHEDUE.E - SRO Candidates RO Candidates , First NBC Examination 14 R July 1985 Second NRC Esamination pg R October 1985 < i t j Two additional NRC Examinations are scheduled for 1986 - one for cold license and one hot license LICENSE CANDIDATES TRAINING OChilFICATIONS AND OPERATING EXPERIENCE PRFVIOll3 PREVIOUS NAVY 6 MONTH 6 WF.EK [ CD
- RedH PWR RWR NUCLEAR $ OPEN R OPEN 320 CANDIDATE TITLE LICENSE LICENSE CERTIFICATION PROGRAM e RWR RWR
- 3. CONNOR OPERATIONS NANAGER X X C. VONDRA OPERATING ENGINEER X X J. NAGAN OPERATING ENGINEER X X l S. SAUNDERS SR OPERATIONS SUPERVISOR X
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L. AVERSA SR SNIPT SUPERVISOR X l X l L TRUN SR SHIFT SUPERVISOR X i X - s.. L RILEY SR SNIFT SUPERVISOR X X f.
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- J. ADANS SHIFT SUPERVISOR X X ;
R. ESRIGNT SHIFT SUPERVISOR' SHONEMAN X X X e-. to ' to F . IIU CN RS SitIFT SUPERVISOR X X X o L. NEWNAN SHIFT SUPERVISOR X X X D. POWELL SHIFT SUPERVISOR GRAND GilLFX X X [ t T. BUSSELL SHIFT SUPERVISOR X X X ll R. STANATO SHIFT SUPERVISOR X X X , F. NIGGINS SHIFT SUPERVISOR ). X X X '~ f, . S. FUNSTEN I&C EleGINEER X X 7, s R. TIIOMPSON RX E80GINEER ' X X 'i J. MANRVLAN RX RWGINEER X X J. JONNSON SHIFT TECIINICAL ADVISOR X X h N. AIIARO SHIFT TECHNICAL ADVISOR X X [;. j g 5 I' I [' n I
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R. LEWIS 800 CLEAR C000 TROL OPERATOR X X X I h ': J. DEDO 90!NICO NUCLEAR C000 TROL OPERATOR X X - T. KID 00100 000 CLEAR C000Th0L OPERATOR X X X ; W. CMAUSSE 80UCLEAR CONTROL OPERATOR X X X T. EASLICE NUCLEAR COSITROL OPERATOR X X X s Y t k. c.
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.]
- structured plan to assure meeting and coordinating activities i required to support fuel load.
I Objectives . _.. sl
- To have one unique document of all major tasks to be accomplished by Hope Creek Operations to support fuel load.
[ Assess and portray the status of all major tasks. Provide a tool for station management to update major task progress. t Identify support required in order to f acilitate major task completion, a Make visible Hope Creek Operation's efforts to support fuel load. 5 Enhance the development and implementation of sound station management f practices. e Replace the existing department plans. j Technical Department Major Task Identification ___ i
. I.
TE-1 Staf fing TE-2 Training l TE-3 Procedure Development
,< TE-4 Commitment Tracking TE-5 Occument Control Program TE-6 Records Management Program TE-7 Personnel Training Records TE-8 Facilities - Computer Hardware Installation TE-9 Technical Specification Development TE-10 Technical Specification Surveillances TE-11 Regulatory Reporting Program TE-12 Station Operations Review Committee (50RC) Enhancement TE-13 50R/0R Resolution Tracking i
18.23 NRC 8 (8-1)a
* :. . . - . . . ..N. . u .?.5 :a 'T-. . X' HOPE CREEE OPERATIONAL READINESS PLAN
( f RADIATION PROTECTION DEPARTMENT i QATE.L February 8, 1985 E1QR TASK In Hi.L RP-6 i M TASK M&MEL Emergency Plan MAJOR T&gK QESCRIPTIONr i q The objectives of this major task are as follows: e Support development and implementation of the HCGS Emergency P1an in order to satisy the applicable requirements of NUREG-9654/ FEMA-REP-1, Revision 1. I e Per the established Division of Responsibility (DOR), develop selected Emergency Plan Implementing Procedures. o Obtain equipment to support emergency preparedness activities as required. . e Review emergency preparedness facility requirements. y ' e Designate individuals to full those emergency response t positions for which the Radiation Protection Dept. is responsible for manning. - 4
, e Complete Emergency Plan training as required.
e Participate in practice drills and NRC/ FEMA Emergency Plan i full scale exercise as required. l The Nuclear Site Protection Dept. has the overall responsibility for L developing and implementing the HCGS Emergency Plan. The 132' el. l Technical Support center (TSC) must be functional by 6/1/85 to
; support the Emergency Plan Appraisal which is tentatively scheduled for 8/1/85.
H&J.QR TASK SPOMSOR2 E. Karpe
, REQUIREQ INTERFACEfSir Nuclear Site Protection Dept., Procurement & Material Control Dept., Radiation Protection Services, Site Engineering, and other HC0 Departments.
SUPPOM ED MILESTONEfsir Emergency Plan Exercise and Fuel Load PRCDECTED START Q&%E.L N/A - Already in progress. PROJECTED COMPLETION DAZE 1 October 29, 1984 DEPT. MANAGER APPROVAL: - 5 k^^' = 18.24 G . _ . _ _ .__ -. _ . - - . . _ . _ -
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, 18. STAFFING. TRAINIA * ..0 OPERATOR LICENSING a [$1 '
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SUMMARY
2 i s Hope Creek has an adequate staff onboard to support fuel load. Additionally, licensing exams are scheduled in a timely manner to
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have sufficient operators to man the plant at fuel load. Non-licensing training is on schedule to complete initial requirements prior to fuel load. a j . l
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