ML17325A923
| ML17325A923 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/16/1988 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| AEP:NRC:0980P, AEP:NRC:980P, NUDOCS 8809260251 | |
| Download: ML17325A923 (14) | |
Text
ACCESSION NBR:8809260251 DOC.DATE: 88/09/16 NOTARIZED:
NO DOCKET FACIL:50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana 6
05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.'NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Forwards steam generator repair project radiation protection 90 day interim Rept 2.
DISTRIBUTION CODE:
AOOZD COPIES RECEIVED:LTR I ENCL 2 SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA STANGsJ COPIES LTTR ENCL 1
0 1
1 RECIPIENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 5
5 INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DOEA/TSB 11 NU3)QC -ABSTRACT G F~
01 EXTERNAL: LPDR NSIC 1
0 1
1 1
1 1
1 1
1 1
1 1
1 1
1 NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 OGC/HDS1 RES/DSIR/EIB NRC PDR 1
1 1
1 1
1 1
1 1
0 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 19
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:0980P Donald C.
Cook Nuclear Plant Unit 2 Docket No. 50-316 License No.
DPR-74 STEAM GENERATOR REPAIR PROJECT RADIATION PROTECTION 90-DAY INTERIM REPORT NO.
2 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 ATTN:
T.
E. Murley September l6, l988
Dear Dr. Murley:
As required by section 7.3 of the Safety Evaluation by the Office of Nuclear Reactor Regulation related to Amendment No.
100 to Facility License No. DPR-74, enclosed is one copy of the Steam Generator Repair Project Radiation Protection 90-Day Interim Report No. 2.
This report summarizes the activities of the Project Radiation Protection/ALARA Group (PRPAG) for the period May 17,
- 1988, to August 18, 1988.
Attachment 1 to this letter provides details of activities for each group; ALARA, PRISM, Radiation Protection Operations, Training, Radwaste, Support Services and Dosimetry.
Based on actual operational experience, the collective occupational exposure estimate for the Steam Generator Repair Project has been decreased from the original 1733 down to 1032 man-rem.
The revised estimates have incorporated actual numbers where appropriate.
Details of the revised estimate are contained in Attachment 2 to this letter.
The Project ALARA group continues to track exposure on a per shift basis and to report the weekly totals in the Project ALARA Committee and the Project Management weekly meetings.
Attachment 3
to this letter provides a comparison, on a weekly basis, of the actual man-rem expended versus the estimated man-rem expenditure.
The reported weekly estimate is derived by calculating the job percent complete based on actual Radiation Work Permit (RWP) man-hours compared to 323,928 revised total Project RWP man-hours.
88092b025i 8809i6 PDR ADOCN 050003ih R
PNU
I rg
Dr. T.
E. Murley AEP NRC:0980P The estimated man-rem expenditure through August 15,
- 1988, was 432.92 man-rem.
Actual man-rem expenditure for this same period was 395.46 man-rem.
The difference between the actual and estimated accumulative exposure can still be traced to the fact that most of the preparatory work took place in extremely low dose areas.'he Project has completed the removal phase and tasks are now accruing exposure at a rate closer to the estimated average effective dose rate (task exposure/task RWP hours).
The Radiation Protection 90-Day Interim Report No. 3, which will cover the period August 19, 1988, to November 19, 1988, will be provided to you by December 19, 1988.
This document has been prepared following corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M. P. Alexic Vice President edg Attachments cc:
D. H.-Williams, Jr.
W.
G. Smith, Jr.
- Bridgman R.
C. Callen G.
W. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis, NRC Region III
ATTACHMENT 1 TO AEP:NRC:0980P COOK, NUCLEAR PLANT, UNIT 2 STEAM GENERATOR REPAIR PROJECT RADIATION PROTECTION 90-DAY INTERIM REPORT NO.
2 1.0 Introductio~i
" Indiana Michigan Power Companv is repairing the four steam generators at the Cook Nuclear Plant Unit 2 wh'ch suffered secondary side tube degradation due to ntergranula=
attack/stress corrosion cracking at the tube support plate and tube sheet regions.
Since this type of large-scale maintenan'ce has the potential for. individual and collective radiation exposures beyond that of routine maintenance, the NRC received a description of the project's planned radiation protection program as part of the Steam Generator Repair Report submitted November 7,
- 1986, and revised on March 30, July 24, October 30, December 4,
- 1987, and February 18, 1988.
The implementation of the Radiation Protection Program as of August 18, 1988, is provided below.
2.0 Hi hli hts for the Period Project work for the month of May included pre-setup of outside facilities, miscellaneous engineering, containment preparations, and the removal of insulation from all four steam generators.
Project work for the month of June included ongoing insulation removal, installation of lead shielding, containment
- decon, doghouse liner plate removal, concrete
- chipping, the cutting of main steam and reedwater piping, and entries into the steam generators.
Project work for the month of July included steam generator doghouse enclosure concrete cutting and removal, plasma cutting of the reactor coolant pipes, removal of the upper assemblies and transporting of the upper assemblies to the turbine building for refurbishment.
Project work.for August 1 through August 18, 1988, included removal and transport of lower assemblies to the storage facility, machining/welding of the Reactor Coolant lines, installation and fit up of new lower assemblies.
3.0 Pro rams and Procedures The Project Radiation Protection/ALARA Group (PRPAG) completed and issued 94 project-specific procedures and three (3) program documents to control the radiation protection and radwaste aspects of the Repair Project.
The procedures cover seven functional areas:
radiation protection operations, ALARA, dosimetry, training, support services, PRISM and radwaste.
The status of each functional area is identified below.
Attachment to AEP:NRC:0980P Page 2
4.0
~Doaimet PRPAG dosimetry staff continues to support the project and has badged 1090 personnel to date, granted 216 administrative dose limit extensions, completed 103 Radiation Exposure Investiga-
- tions, issued 297 multipacks, performed 1513 whole body
- counts, performed 656 respirator fit tests, and issued 341 termination letters.
During the period there were six positive whole body counts
()1% of maximum permissible body burden),
- however, none were greater than 5S MPBB.
The TLD laboratory has processed 40,989 TLD As part of our interlaboratory comparison program we have successfully passed three mock NVLAP tests conducted by the University of Michigan.
5.0 Training The PRPAG Training Staff continues to provide General Employee Training (GET), Project-Specific Training, Supervisor ALARA Training, Respiratory Training and Radiation Protection Technician Training.
The training of 129 Radiation Protection Personnel has been completed.
A total of 1033 personnel have attended PRPAG GET training sessions'ince the last report 15 training modules have. been developed or revised.
A total of 266 formal training classes have been conducted in support of the Project.
6.0 PRISM S ste PRISM is a computerized radiation work permit and dose tracking system.
At present, PRISM maintains information on 1029 project workers, including personnel information, dose history, training qualifications and access information.
To
- date,
'157 radiation work permits have been written and maintained on the PRISM System.
PRISM currently provides an average of 400 reports per week to the various project groups.
7.0 Radiation
'rotection 0 erations The PRPAG Operational Radiation Protection Group staffing levels during the period grew to 85 technicians to support approximately 108,000 entries in controlled areas.
There have been 79 personnel contaminations and 22 Radiological Occurrence Reports during 135,886.9 RWP-hours of work.
8.0 Su ort Services The Support Services group started decontamination of large tools and equipment used for pipe cutting and machining.
Respirator usage has dropped significantly.
Attachment 1 to AEP:NRC:0980P Page 3
9,0 Radwaste The first shipment of Radioactive Material was made to the off-site contractor for processing on June 21, 1988, using the newly constructed RW handling building.
The computerized waste tracking and manifesting system was used for this and subsequent shipments.
A total of seven shipments, totaling 8775.5 net cubic feet (Project 8149.5, Unit 1 626) and 235,187-net pounds (Pro]ect 222,602, Unit 1 12,585) have been shipped during this period.
10.0 ALA~
The PRPAG ALARA Group completed 110 planning stage work package ALARA reviews, 52 in-progress
- reviews, over 100 prejob briefings and 2 work package closeouts.
Review and approval of Design Change Notifications to already approved work packages is on-going.
Mock-up training was completed for shielding installation, containment construction and channel head entry.
Sixty shielding requests and 11 containment requests were processed for installation.
Six containment requests and 17 shielding requests have been removed and/or closed out.
The ALARA Committee held 14 sessions during the period.
Attachment 2 to AEP:NRC:0980P REPAIR PROJECT MAN-REM REVISION Task Activit, Man-Hour Estimate Man-Rem Estimate 1 ~
2.
3 ~
4
~
5.
6.
Erect refueling cavity cover and supports and aux. building equipment hatch deck*
Ins all temporary containments*
Install and load test aux.
building crane*
Defuel and fuel storage*
Install temporary ventilation system*
Install/Remove CCTV and Gaitronics*
2,200 2,264 5,800 8,800 275 48 4.5 22.6
~ 7 47.2 2.5 1 ~ 3 7 ~
8.
9.
10.
Engineering walkdowns 11.
Service air installation*
12.
Containment Preparation*
13.
Project Supervision Install temporary lighting and power*
General decon and housekeeping Temporary shielding installation*
1/200 31/331 1, 197 4,200 1,650 5,750 10,800 9.8 52.4 44.3 36.2 9 '
32 '
28.3 14'nstall temporary supports and RCS pipe restraints*
206 4.2 15.
Remove S/G concrete doghouse sections*
16.
Decon S/G concrete doghouse sections 17.
Insulation removal (All)*
18.
Interference removal (All)*
19.
Cut main steam and,feedwater pipe*
20.
Cut and remove upper shell*
21.
Cut reactor coolant pipe*
22.
Disassemble S/G supports 15,500 6,300 5,974 2,040 500 2,750 1,250 200 27
~ 1 0.6 25.5 12.2 2.0
- 10. 1 25.4 2.5
Attachment 2 to AEP:
C:0980P Page 2
Task Activit Man-Hour Estimate Man-Rem Estimate 23.
Install S/G cover plates*
24.
Remove S/G lower assembly>>
25.
Refurbish S/G upper shell*
26.
Misc. rigging and handling 27.
Radiation Protection 28.
Install S/G lower shell 29.
Install reactor coolant pipe 30.
Install upper shell, perform S/G girth weld 31.
Install main steam pipe, install feedwater pipe 250 5,903 7,000 28,000 62,663 3,250 10,374 5,890 4,840 5.1 33.4
.5 26.7 104.2 18.4 245.3 2.4 5.4 32.
Perform fiberoptic cleanliness inspection 352 0.7 33.
Install S/G -insulation 34.
Install pipe interferences 35.
Install S/G concrete doghouse sections 36.
Remove R/F cavity cover 37.
Perform hydrostatic tests 38.
Refuel reactor 39.
Remove temporary shielding 40.
Remove temp.
power and lighting 41.
Containment Restoration 42.
Remove service air/breath air 43.
Misc. material handling and Radwaste activities 44.
Remove temp. ventilation 45.
Rigging/handling S/G in storage bldg.
TOTAL 7,500 16,220 17,104 2,308 472 3,150 624 176 18,400 767 18, 016 222 212
'323,928 37.5 24.9 22.5 6.6 5.9 26 '
12.5
'3. 2 29.4 4.8 10.8 3.1 1032
- Contains a significant proportion of actual man-rem.
500 450 400 SGRP REMOVAL PHASE PERSONNEL EXPOSURES ESTIMATE VS. ACTUAL CD CD CD CD Y3 LEGEND ESTIMATE ACTUAL 350 800 UJ 250 200 150 CV cd co QO CO CD LA OO OO OO CD CO CV td O
O O
~,
100 S/So 7/7 7/14 7/21 7/28 DATE 8/1 8/8 8/l 5 NOTE:
ESTlMATE VALUES DERlVED FROM PERCENT COMPLETE 8Y HOURS
200 180 160 SGRP PREPARATION PHASE PERSONNEL EXPOSURES ESTIMATE VS. ACTUAL LEGEND ESTIMATE ACTUAL 140 120 2
100 80 CD CO CD CD CD 0
W R
P)
O 60 CD 20 CD CD CCl CD CD CV CD 4/22 4/28 5/5 5/1 2 5/1 9 5/26 6/2 6/9 6/1 6 6/23 WEEK NOTE:
ESTIMATE VALUES DERIVED FROM PERCENT COMPLETE BY HOURS
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