ML20097F323
| ML20097F323 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 09/11/1984 |
| From: | Reynolds N BISHOP, COOK, PURCELL & REYNOLDS, TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Bloch P, Jordan W, Mccollom K Atomic Safety and Licensing Board Panel |
| References | |
| OL, NUDOCS 8409180484 | |
| Download: ML20097F323 (12) | |
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LAW OFFICES OF BISHOP, LIBERMAN, COOK, PURCELL & REYNOLDS NEW YORK e2OO S EVENTE E N TH STR E ET, N. W.
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WASHINGTON, D. C. 20036 BISHOP, LIBER MAN & COOK 26 BROADWAY (202) 857-9800 8,
,,,,N EW YO R K NEW YORK 10004 TELcx 44os74 #NTLAw ui
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TELEX 3227e7 M
September 11, 1984 Peter B.
Bloch, Esq.
Dr. Walter H. Jordon Chairman Atomic Safety 881 West Outer Drive and Licensing Board Oak Ridge, Tennessee 37830 U.
S. Nuclear Regulatory Commission Washington, D. C.
20036 Dr. Kenneth A. McCollom Dean, Division of Engineering Architecture and Technology Oklahoma State University Stillwater, Oklahoma 74074 Gentlemen:
Enclosed is our ninth bi-weekly update on the status of important schedule related issues for Comanche Peak fuel load.
Since e y, Nichola S. 'leynolds Counsel foq Applicants h
Enclosure a
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TEXAS UTILITIES GENERATLNG COMPANY
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- 100 NortTH OLIVE >TITEET, L.H. pel * !aALLAM. TEXA> 73201
'54. SEP 12 All:10 Jo E. e. G EO..RG, E
.... w September 10, 1984 Mr. Darrell G. Eisenhut, Director Mr. John T. Collins, Division of Licensing Regional Administrator Office of Nuclear Reactor Regulation Region IV U. S. Nuclear Regulatory Commission U. S. Nuclear Reg,ulatory Washington, D. C.
20555 Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 Gentlemen:
Tha following information represents our ninth biweekly update on the status
.of important schedule related issues for Comanche Peak fuel load in late September 1984.
Information contained in the attachments is the status through September 1, 1984.
Critical Path Currently our major critical paths are associated with final calibration and preoperational testing of the radiation monitoring system, preoperational testing of the reactor protection system and completion of HVAC fire damper modifications.
Each of these critical paths indicate approximately three weeks impact to a fuel load of Septe=ber 25, 1984.
Other Issues Fire Protection Work on fire dampers continues.
We are meeting with NRR staff at the site beginning today to resolve all issues with regard to fire protection and believe that resolution will be accomplished.
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A risvrwrOx or rexAs t rrr,tries rr.rcrate co.strAxi-
Mr. Darrell G. Eisenhut Mr. John T. Collins September 10, 1984 Page 2 2.
Present Craft Ucrk Effort for Unit 1:
Mcnpower Unit 1 Euilding/ Labor / Rigging 165 Paint 150 Pipe 98 Insulation 30 Millwright 23 Fab / Hangers 40 Electrical 235 Instrumentation 14 4
755 Attachments Startup/ Testing Appendix A - D Master Data Base Status Appendix E Paint Completion Schedule Appendix F In conclusion, we continue to make progress.
Essentially, all schedule related issues on which we originally had agreed to report in this letter have been cocpleted or are nearing co=pletion. Our next report with regard to these issues should be the final report.
We are still forecasting approximately three weeks delay in our scheduled fuel load date.
Very t y yours',
cf l' ~ T
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QQ JBC/jb Enclosure (s) cc:
T. Ippolito N. Reynolds
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STARTUP Status Week Ending: September 1, 1984 TURNOVERS:
Last Report This Report Total Accented Total Accepted Subsystems 331 326 331 328 REMAINING TURNOVERS:
Date Accepted Fire Detection Panel, Detectors and Cables S.G. Building Tornado Dampers and Blowout Panels Containment Elevator N-16 Cables and Detectors 08/31/84 Containment Access Rotating Platform 08/30/84 4
3 i
Appendix A
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Aopendix B L
TESTING SD'MAPT (Last Report: AUGUST 18, 1984) z FIELD TESTING RESULTS TOTAL IN-PROGRESS COMPLETE APPROVED PREOPERATIONAL:
ORIGINAL 149 13 125 104 RETEST 31 1
30 20 REFERFORM 22 0
21 15 ACCEPTANCE:
ORIGINAL 50 0
48 47 RETEST 7
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6 REPERFORM 16 0
16 14 TOTALS 275 14 246 206 TESTING
SUMMARY
^
(This Report: SEPTEMBER 1, 1984)
FIELD TESTING RESULTS TOTAL IN-PROGRESS COMPLETE APPROVED PREOPERATIONAL:
ORIGINAL 149 12 128 109 RETEST 31 0
31 23 REPERFORM 22 0
22 17 ACCEPTANCE:
ORIGINAL 50 0
48 47 RETEST 7
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6 REFERFORM 16 0
16 14 TOTALS
'275 12 252 216 Appendix C
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k M!. STER DATA BASE STATUS:
Last Report This Report Unit 1 and Commor. Total 3970 3543
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The above tcbulatica includes Unit 1 and Unit 2 vork items remaining within the security boundary est;_blished for Unit 1 operation.
The following tabulation provides an overview of remaining Master Data Base items:
No. of Itecs To Be Completed Last Report This Report A.
Pre-Fuel Lcad 1989 1693 B.
Under Review 664 142 C.
Post-Fuel Load 1327 1708 TOTAL 3970 3543 Item A above, Pre-Fuel Load - the item count 1693 is the. summation of the DO IT, SU-REL, OP-NEED and PRE-FL items as identified in Appendix E-1.
Item B above, Under Review - the item count 142 is the summation of the PRO POST and D: CEPT Items as identified in Appendix E-1.
.The following attachments are used by the site and should provide a better feel for the remaining work as tracked in the Master Data Base:
1)
By Systen, Appendix E-1 2)
By Building, Appendix E-2 3)
Glossary of Abbreviations, Appendix E-3 I
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GLOSSA 2T OF A33EE7IATICNS' DO-IT' Items required to be-co=pleted to uppcrt. compic. ion of Startup Prerequisite and Preoperational tesring activities.
SU-REL Items required to be completed to supper: Startup release and Operations acceptance of systems per CP-SAP-3.
OP-NEED Ita=s required to be completed to support Operations fuel load preparation activities.
PRE-FL Items not assigned to the above categories that are re' quired to be complete prior to fuel load.
PRO POST Items not assigned to the above categories that n3v, be completed after fuel load.
POST-FL Items that will be completed af ter fuel load as agreed by Operations, construction and Startup.
EXCEPT Items that are under review for identification in the above six (6) categories.
TNE TUGC0 Naclear Engineering CPPE Comanche Peak Project Engineering CONST Construction disciplines, including' pipe, electrical, millwright and hanger.
QC Quality Assurance, Quality Control Quality Engineering ASME, Non-ASME SUB Subcontract TF Cocpletions Group STE System Test Engineer (Startup) i TUGC0 TUGCO Operations SP/IP Special Projects (Startup)
PMG Purchasing / Procurement i
MISC Responsibilities that do not fall in the above categories i
l 4
Appendix E-3
- y Paint Completica Schedule Reactor Containrent Euildinc 91 Shown below are the completion and projected completion dates for the remaining work areas in Reactor Containment Building #1, which includes final inspections and touchup.
Projected Actual I.ocation Comnletion Completion Steam Gen. Comp. 2 & 3 July 27 Steam Gen. Comp. 1&4 August 10 Elevation 808 August 27 1
Elevation 832 August 27 Document review and associated NCR's are all that remain with regard to protective coatings in Containment Building #1.
Document review will be co=pleted by September 14, 1984 N
Appendix F
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