ML20238C375

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Connecticut Yankee 1986 Core XIII - Xiv Refueling Outage ALARA Rept
ML20238C375
Person / Time
Site: Haddam Neck, 05000000
Issue date: 12/31/1986
From: Guzallis E, Powell J
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20238C358 List:
References
NUDOCS 8712300237
Download: ML20238C375 (64)
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK, CONNECTICUT lh' .)('(  ;.._. 2.I'h^$@_ _ _ , _ _ _j

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l 1986 REFUELING OUTAGE ALARA REPORT

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1 CONNECTICUT YANKEE 1986 CORE XIII-XIV REFUELING OUTAGE ALARA REPORT Prepared by:

J. O. Powell ALARA Coordinator and E. C. Guzallis ALARA Technician Reviewed by:

W. F. Nevelos l

Radiation Protection Supervisor Approved by:

H. E. Clow Health Physics Supervisor I

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i TABLE OF CONTENTS Page I. INTRODUCTION 1-2 II. RADIATION EXPOSURE CONTROL A. - MANREM Totals Sumary 2-4 B. Major Job ALARA Review Sumary . 16' C. Shielding and Exposure Reduction Techniques. 54-55 III. RADIOACTIVE CONTAMINATION CONTROL A. Personnel External Contamination 56-B. Personnel Internal Contamination 57 IV. RECOMMENDATIONS AND CONCLUSIONS 58-59 1

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LIST OF ILLUSTRATIONS TITLE PAGE FIGURE 1 Daily MANREM and MANHOUR Expenditures 5-6 2 Daily Cumulative MANREM and MANHOUR Totals 7-8 i 3 Exposure' Distribution and Average Exposure per 9

Individual 21 4 Steam Generator #1 - Pre and Post Chemical Decon-TH Steam Generator #1 Pre-and Post Chemical.Decon-Tc 22 5

3' 6 Steam Generator #3 Pre and Post Chemical'Decon-TH 7 Steam Generator #3 Pre and Post Chemical Decon-Tc 24 8 Steam Generator #1, Th and Tc. Skirt Area 29 Steam Generator #2, Th and Tc, Skirt Area 30 9

10 Steam Generator #3, Th and Tc, Skirt Area 31 11 Steam Generator #4, Th and Tc, Skirt Area 32 12 Reactor Cavity Pre and Post Shielding 35-13 Transfer Canal Pre and Post Decon 36 s 14 Steam Generators #1 - #4 Handhole Survey (Composite) 45 15 Reactor Coolant Pumps (Composite) 48 4

l 11 1

I LIST OF TABLES TITLE PAGE TABLE 1 MANREM Expenditures by Selected Work Groups 10 2 CY 1986 Refueling Outage Major Job Man-hour and MANREM Summary 11-13 l 3 Connecticut Yankee's Repetitive Job Exposure Comparison 14-15 l

l 1

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1. INTRODUCTION The subject of this report is the thirteenth Connecticut Yankee Refueling and Maintenance Outage. The Connecticut Yankee plant is located in the town of Haddam, on the east bank of the Connecticut River, fifteen miles south, southeast of Hartford. The reactor is a Westinghouse design, pressurized light water system presently rated at 1825 MW thermal and 600 MW electric. Since achieving initial criticality on July 24, 1967, the plant has generated over 74 billion kilowatt-hours of electricity. The purpose of this report is to document the major radiological precautions and the ALARA techniques which were utilized during the outage, evaluate their effectiveness and recommend improvements for future use.

The summary of data adds to the previous Connecticut Yankee (CY) ALARA Outage Reports data base from 1979, 1980, 1981, 1983 and 1984. (Note:

1982 and 1985 were non-refueling years and are documented in their respective Annual ALARA Reports.) The benefit of this data is that it will aid in MANREM estimates, document the application of ALARA techniques, provide a MANREM reference to quantify the effectiveness of ALARA techniques, assist job / task leaders in job planning, provide a medium for comparison to past performance and corporate goal attainment.

This report is generated in accordance with the Northeast Utilities' (NU) Corporate Management Program for Maintaining Occupational Exposure As Low As Reasonably Achievable manual.

The report covers the period from January 4, 1986 to May 10, 1986.

Topics to be discussed include:

1. Radiation Exposure Control--MANREM Totals Summary; Major Job ALARA Review Summary.
2. Radioactive Contamination Control--Personnel External Contamination; Personnel Internal Contamination.

The Health Physics staff handled all major radiological events without any major problems and without violating any federal radiation protection regulations. All managerial positions in the 1986 Health Physics Outage organization were staffed with permanent CY HP personnel. The use of dedicated CY HP Technicians as Containment, Steam Generator and RCA leadmen which had proved very successful during the 1984 Outage was expanded. The containment area was broken down into 3 zones, with the Primary Auxiliary Building, Main Control Point and the RCA Yprd area comprising 3 additional zones. The Radwaste group was also divided into similar zones. This allowed for workers to become familiar with the personnel responsible for specific areas and was very beneficial in resolving problems that would have led to numerous delays and additional expotures. This system also led to increased attention to detail (i.e. surveys and air samples) and reduced confusion and overcrowding conditions at the main containment control point.

Page 1 of 59

II.A Manrem Totals Summary A total plant dose equivalent of 1506 MANREM was expended during the period January 4, 1986 to May 10, 1986. This total'is based on Radiation Work Permits (RWP) - Pocket Ion Chamber (PIC) readings which were entered into the HELPORE II program.

The 1986 outage MANREM total (1506 MANREM) overran out 1986 outage MANREM projection of 911 MANREM. The overrun was caused in part by the-following:

RCS Loop Temperature Element project which was originally estimated at 91 MANREM was re-estimated to 161 MANREM after mockup training. Overrun 65.6 MANREM.

The SG Chemical Decontamination project expended 50 MANREM more than anticipated. The major problem which caused the Manrem overrun was nozzle dam fit-up problems.

Safety Related Piping originally estimated at 25 MANREM expended 111.6 MANREM, mainly due to work scope increases. Overrun 86.6 HANREM.

Primary SG Inspection and Maintenance repetitive tasks overran the estimated exposure by 15 MANREM. Mechanical tube plugging of 61 tubes expended 71.5 MANREM and the tube pull overran it's estimate of 9.4 MANREM by 31.MANREM.

Refueling operations overran the estimated exposure by 22 MANREM.

Major factor causing overrun: The reactor head having to be detentioned and retentioned a second time during installation.

The Cavity Pool Seal Replacement project overran it's initial estimate by 27 MANREM mainly due to fit up problems caused by seal warping during manufacturing.

Appendix R Modifications, which were not included in the outage estimate expended 28 MANREM.

Approximately 200 valves were repaired during the outage.

Original estimated work scope called for 100 valves to be worked.

Exposure overrun 27 MANREM.

Additional goal overruns were observed in the support organizations due to the extended outage period.

1-2 of.59 l

The following tabulation compares the MANREM and MANHOURS from previous refuelings.

Refueling MAN WKLY MAN WKLY Weeks REM AVG. HOURS AVG. *EDR Outage Detes 6 528 88 35,700 5,950 0.0148 1979 1/26/79-3/12/79 11,775 0.0071 1980 5/31/80-8/8/80 12 1005 83 141,304 878 125 73,383 10,483 0.0120 1981 9/26/81-11/16/81 7 6,055 0.0173 1983 1/22/83-4/15/83 12 1260 105 72,665 i 14 1108 79 46,067 3,290 0.0240 1984 8/1/84-11/10/84 5,898 0.0142 18 1506 84 106,262 1986 1/4/86-5/10/86 Figure 1 depicts the " Daily MANREM and MANHOUR expenditures for the 1986 Refueling Outage".

The graph indicates that during the peak period, daily MANREM ranged from 5 to 38 MANREM per day with an average daily MANREM of l approximately 12 MANREM.

Figure 2, the " Daily Cumulative MANREM and MANHOUR totals for the 1986 Refueling Outage," shows that over the eighteen week 1986 outage we expended approximately 1506 MANREM. By compari.on, s the fourteen week 1984 outage total was 1108 MANREM.  ;

3

= Effective Dose Rate (EDR)

The breakdown of the station MANREM expenditures by work groups is j shown in Table 1. In general,147 MANREM or 11.7 percent of the total l

station dose equivalent was received by permanent CY employees, 1053 MANREM or 83.7 percent by contractors and 58 MANREM or 4.6 percent by offsite utility personnel. No individual exceeded the federal quarterly or annual occupational external exposure limits. In addition, no individual exceeded the 5 REM per year Administrative External Exposure Limit.  ;

t should be noted here that there was a 37.7 percent increase in the number of personnel employed compared to 1984. The average exposure per individual decreased from 679.8 MREM in 1984 to 619 MREM in 1986.

Figure 3 indicates the exposure distribution by dose range of the work force and gives the average of all TLD badged individuals as 619 MREM.

A listing of the CY 1986 Refueling Outage Major Job MANREM and MANHOUR Summary is in Table 2. This listing accounts for approximately 81 percent of the plants outage MANREM. (92 percent is accounted for using the grand totals listed for the asterisked jobs in Table 2.1. -

see respective ALARA Review Job Summary in Section 118.) j l

. 3 of 59

A compilation of the personnel radiation exposure trends for repetitive jobs conducted during CY's 1979, 1980, 1981, 1983, 1984 and 1986 outages are shown in Table 3. In eight of the categories listed exposures have continued to trend downwards. The most significant of these being the ECT/ PROF-REM / Tube, which was reduced by 50 percent.

This decrease in exposure was directly attributed to the use of the SM-10 robotic arm. Most of the remaining categories are effected by outage length and the work being performed, since they are support functions. Due to the extended outage length and the large amount of high radiation and contaminated work performed these activities trended upwards.

4 of 59

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e TABLE I MANREM EXPENDITURES BY SELECTED WORK GROUPS JANUARY 4, 1986 TO MAY 10, 1986

1. ADMINISTRATIVE STAFF 5. OPERATIONS DEPARTMENT Total MANREM - 3.248 Total MANREM -'56.296 Plant Personnel - 2.579 Plant Personnel - 20.536 Contract Personnel - 0.135 Contract Personnel - 35.760 Utility Personnel - 0.534
2. ENGINEERING DEPARTMENT 6. MAINTENANCE DEPARTMENT Total MANREM - 91.488 Total MANREM - 840.194 Plant Personnel - 7.070 Plant Personnel - 66.440 Contract Personnel - 64.959 Contract Personnel - 747.335 Utility Personnel - 19.459 Utility Personnel - 26.419
3. CHEMISTRY DEPARTMENT 7. QC/0A. DEPARTMENT Total MANREM - 2.548 Total MANREM - 34.473 Plant Personnel - 0.887 Plant Personnel - 1.500- {

Contract Personnel - 1.661 Contract Personnel - 31.853 /

Utility Personnel .1.120

4. HEALTH PHYSICS DEPARTMENT 8. I&C DEPARTMENT Total MANREM - 173.349 Total MANREM - 56.952 Plant Personnel - 32.063 Plant Personnel - 16.116 i i

Contract Personnel - 135.861 Contract Personnel - 35.656 Utility Personnel - 5.425 Utility Personnel - 5.180 l I

The MANREM values are based on RWPs--PIC readings which were enteredlinto the HELPORE program, t

I 10 of 59

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CY 1986 REFUELING OUTAGE MAJOR J,0B Sb,iMARY .

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JANUARY 4,1986-M/M/.0,lh - o I. GREATERTHAN10MANREM;]JS, g  ; j ESTIMATED ACTUAL GdTMATEM ACTUAL MANREM Y )'

JOB TITLE MANH0llR MANHOUR MPisktM \. .P 4801.72 161.5 160.620

1. RCS RTD Replacement 4252 p f
2. Primary Steam Generator .

Chemical Decontamination 234J 10.,094 a8 64.8 115.495 ,

3. Safety Related Piping 4350 7699.44 40.5 , 111.631

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Inspection & Maintenance 1837 . 1851.84 A'/ . 9 ' , 99.935 )

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  • 5. Refueling Operatiori, 2835[ 2635.69 y :i8.h / 80.808 3505.97 P,7.0/ 51. P,07
6. Cavity Seal keplacenent 1382 Valve Motor Operator ,'

7.

Replacement' 1212 1202.11 102.4 54.215 [

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8. Inservice Inspection 2946 1868.89 113 38.370 s
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9. Secondary Steam Generator , ,

Inspection / Maintenance 850s 1064.68 1 24.6 32,949 o i

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  1. 1,2,4 Seal Repairs 1080 1262.56 20.6 31/;MAj .

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11. Inadequate Core Cooling (, x Modification (HJTC) 1654 2996.33 31.4 (1,/ . ';l'Q e \' s
12. Appendix R Modifications 1200 1888.75 34.8 , 7 t ki7 ' u s

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13. Cavity Drain Line Replacement 639 686.83 40.0s,. t ly 14 RTD Study 2080 417.64 54!J s;1.476 /

Q' l INCLUDTS ONLY THOSE TMV.S ?>HICH HAD EC/qMATED MAm 00Ps L

  • SUBTOTALS ONLY. s < p AND MANREM. SEE SECTION 118 FOR GRAND '0~ C .

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TABLE 2 CY 1986 REFUELING OUTAGE MAJOR JOB

SUMMARY

e JANUARY 4, 1986 - MAY 10, 1986 II. MISCELLANE0US JOBS JOB TITLE 4,CTUAL MANREM i

1.* Health Physics: (78.742 Total) 71.809 Containment HP Blanket RCA HP Blanket 6.933' l 2. Radwaste: (68.489 Total) 51.767 h

Containment RW Blanket l , ' '

Laundry' Blanket 5.312.

Compe:t LSA and Ship 4.398 .

x RCA'AW Blanket

' 3.517 s l

l Resi ' f ner Movements 3.505 -

1

3. Valve Repair / Maintenance 52.940 s 4 Insulation Handling 51.565
5. Operations: (46.948 Total)

CPS Blanket 4.464 Fill / Vent / Valve 42.484

6. Administration Blanket 15.548
7. Area Set-ups (Shielding / Ventilation) 9.775
8. Transfer Cart Overhaul e 5.180
9. Tool Control 5.162
10. Flux Thimble Cleaning s 4.900 4.100
11. ' etdown Orifice Replacement
12. SG Qtr-turn Fastener Inst. 2.205 ,

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TABLE 2

' CY 1986 REFUELING OUTAGE MAJOR J08

SUMMARY

JANUARY 4, 1986 - MAY 10, 1986

! 11. MISCE'.1ANE0VS JOBS ACTUAL MANREM JOB TITLE

13. Security 1.398
  • 14. Seal Water Return Filter 1.281
15. IXFiherChanges 1.280

,. 3 1

  • Flea [thPhysicsRWPsonly. Job code sort (0051) 112.580, additional 33.838 MANREM expended on specific job / task RWPs.

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TABLE 3 CONNECTICUT YANKEE'S REPETITIVE JOB EXPOSURE COMPARISON 1979 - 1986 JOB DESCRIPTION MANREM 1979 1980 1981 1983 1984 1986 l

1. Refueling (Disassembly /

Fuel Shuffle Reassembly) 117 124 132 62 72 81 l

l l 2. S/G Primary Side Inspection ECT/ Prof. REM Tube 0.058 0.035 0.025 0.025 0.012 0.006

3. S/G Primary Side Repair Plugging REM Plug 2.600 2.044 0.770 0.402 0.645 0.587
4. S/G Primary Manway Removal /

Replacement REM 3/E 11.755 9.060 5.865 4.699 5.977 5.039

5. S/G Secondary Sludge Lance ,

l (4 S/G Total excluding equipment setup) 14.700 10.192 12.571 8.253 7.865 9.790 l

6. Reactor Coolant Pump Repair REM RfF 10.830 10.609 9.536 8.855 10.480 10.422 l 7. Inservice Inspection 12.681 22.869 41.582 76.903 38.920 38.370
8. Valve Repair 25.706 8.132 16.438 41.379 55.832 52.940
9. Cavity Filter Replace-ment 9.703 5.797 5.322 1.435 1.535 0.590
10. Cavity Decon --- 6.880 16.460 7.217 3.785 2.928 14 of 59

TABLE 3 CONNECTICUT YANKEE'S REPETITIVE JOB EXPOSURE COMPARISON CONTINUED 1979 - 1986 MANREM JOB DESCRIPTION 1980 1981 1983 1984 1986 1979

11. Radiation Control Area Decon and Trash (81ankets Only) 48.952 52.589 38.870 57.006 29.302 55.274
12. Health Physics (Dept. Total) 42.083 189.377 222.395 216.580 156.786 173.349
13. Operations (Dept. Total) 11.212 31.296 37.656 40.223 45.452 56.296 I

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o- .

IIR. Major Job ALARA Review Summary Attached are the major ALARA review summaries. These summaries identify the job, list the tasks and their respective estimated / actual MANHOURS and MANREM, list the ALARA controls utilized, describe the effectiveness of the controls, shows survey data and enumerate suggested improvements. It is anticipated that these summaries will be of great aid in future job planning. It is recommended that efforts begin immediately to evaluate and implement, where feasible, the suggested improvements so that they can be utilized during future outages.

Please note that the MANREM difference listed for the tasks is based on MANREM values (Act.-Est./Est.)(100). A negative value indicates that actual MANREM was less than estimated.

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E _ ___. _ _ _ _ _ . _ _ _ _ - - - _ _ _ _ _ _ . . _ _ - - _ _ _ _ _ _ - . - - - J

ALARA REVIEW JOB

SUMMARY

1. Job

Title:

RCS Loop Temperature Elements Estimated Actual Estimated Actual Diff.

Manhour Manhour Manrem Manrem  %

Task Title Instc11/ Remove Staging 900 439.57 43.000 23.479 -45 Remove / Install Insulation 182 260.66 14.014 12.175 -13 Drill / Weld / Install RTDs 1440 3758.33 43.960 110.745 152 Reroute Electrical 1380 280.76 55.200 11.200. -80 Install / Remove Shielding 50 41.74 3.850 2.391 -38 Inspections /Walkdowns 300 12.83 1.500 0.155' -90 TOTALS 4252 4801.72 161.524 160.620 .6 ALARA CONTROLS UTILIZED Automated drilling and welding equipment utilized; Mockup training performed for automated equipment; equipment operator station located in-low dose area; shielded stop valve bypass lines for drilling / welding and RTD installation; shielded cold leg fill lines for junction box electrical reroute; prefabrication performed outside of RCA; laydown areas located in low dose areas; access to staging located in low dose area; CCTV used for HP surveillance.

EFFECTIVENESS OF ALARA CONTROLS Drilling and welding of the RTD bosses expended 67 Manrem more than was anticipated. This' overrun was due to problems encountered.with the automated welding and numerous adjustments that had to be made in the work area. One boss was also ground-out improperly and had to be reworked. The overrun was offset by the Manhour over estimation for staging and electrical rerouting tasks. Several staging modifications were also needed prior to starting work. No problems were encountered with contamination controls. Shielding cost 2.4 Manrem to install and remove and saved an estimated 137 Manrem (DRF 2). Based on_ DRF 2 and assuming additional time for welding and repairs in the area. CCTV monitoring for HP coverage was used extensively and saved an estimated 21 Manrem.

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SURVEY DdTA NA-SUGGESTED IMPROVEMENTS Goal of 95 Manrem'was established prior to mockup training. Project was' re-estimated after mockup training as 161.5 Manrem. Goal setting process should allow for goal modification. Problems-with automated welding were identified during mockup training.. An' effort'should have been made to determine if a manual welding process would have been more efficient.

Staging on all loops was completed prior to identifying the need for modifications'to be made. Coordination between the personnel installing staging and those performing the work could have avoided additional exposure expended to modify staging.

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J ALARA REVIEW JOB

SUMMARY

11. Job

Title:

Steam Generator Chemical Decontamination Estimated Actual Estimated Actual Diff.

Manhour Manhour Manrem Manrem  %

Task Title Setup / Remove Equipment 1335 6246.44 31.520 37.610 19 ,

Install / Remove Nozzle Dams 8 1030.44 13.300 49.375 271 Run process / Slurry resins 1000 2489.23 20.000 23.925 20 Install / Remove Decon Manways - 202.22 -- 2.642 -

Material exclusion Custodian - 104.95 -- 1.075 -

HP surveys post decon - 692.00 -- 0.850 -

2343 10080.20 64.820 115.454 80 Totals ALARA CONTROLS UTILIZED l Shielded drum for diaphragm storage; SG ventilation system; SG jumper pens; jumpers to be mockup trained; audio and visual communications on jumpers; CCTV monitoring utilized for HP coverage and equipment inventory; sleeved all hoses and cables entering skirt; all flanged connections bagged; system leak tested prior to operation; hoses in traffic areas shielded; ion

, exchange columns shielded; shielded cask for resin slurry operation.

EFFECTIVENESS OF ALARA CONTROLS Problems encountered with channel head camera and nozzle dam installation and accounted for 36 Manrem of the overrun. Cancellation of the decon ]

effort on SG 1 and 2 compounded the estimate error.since nominal exposure had been assumed for nozzle dam removal. During the decor. process a faulty air fitting caused a leak of approximately 1000 gallons of process solution into the loop area. Shielding of the Ion exchange columns and the process skid shield wall were effective in preventing doserate increases in the RCA yard end adjacent buildings.

SURVEY DATA See Figures 4,5,6 and 7 for decontamination factors.  :

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a e SUGGESTED IMPROVEMENTS Note: All decon nozzle dams were modified and fit up completed. These dams have been marked and stored for future use.

Camera equipment should be less bulky and lightweight. Mockup training should be considered for installation of cameras. Mockup training for specific tasks should be reevaluated. Workers should be selected on a performance basis or trained until a predetermined amount of work can be done within the given staytime. Workers that can not meet the channel head mockup criteria should be trained for support activities outside the channel head area. Hose runs should be planned to avoid traffic areas.

Housekeeping in the work area should be emphasized.

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y SG CHEMICAL DECONTAMINATION RESULTS STEAM CENERATOR'I d

PRE- POST- POST- DECON SURVEY LOCATION DECON DECON WASH FACTOR HOT LEG ACCESS MANWAY 2.0 0.3 0.25 8.0 TWO FT. FROM MAW. AY ONE FT. FROM MANWAY 3.0 0.5 0.4 7.5 FLUSH WITH OUTSIDE EDGE 5.0 1.25 1.5 3.3 FLUSH WITH INSIDE EDGE 15.0 2.0 2.5 6.0 BOWL REGION ONE FT. INSIDE 20.0 2.0 4.0 5.0 TWO FT. INSIDE 20.0 3.0 5.0 4.0 THREE FT INSIDE 20.0 3.0 6.0 3.3 APPROXIMATE CENTER 20.0 5.0 5.0 4.0 DIVIDER PLATE TOP (NEAR TUBESHEET) 30.0 8.0 5.0 6.0 MIDDLE CONTACT 30.0 5.0 4.0 7.5 28.0 3.0 20.0 1.4 l BOTTOM CONTACT TUBE SH'ET TUBESHEET/ DIVIDER PLATE 30.0 8.0 6.0 5.0 30.0 8.0 7.0 4.3 HIGHEST TUBESHFET READING AVERAGE DECON FACTOR 5.0 l

All readings in R/Hr.

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SG CHEMICAL DECONTAMINATION RESULTS STEAM CENERATOR 1

. SURVEY LOCATION PRE- POST- POST- DECON COLD LEG DECON DECON WASH FACTOR ACCESS MANWAY TWO FT. FROM MANWAY 3.0 0.5 0.3 10.0 6.0 0.7 0.5 12.0 ONE FT. FROM MANWAY FLUSH WITH OUTSIDE EDGE 8.0 1.25 1.2 6.7 FLUSil WITH INSIDE EDGE 20.0 2.0 2.0 10.0 BOWL REGION ONE FT. INSIDE 25.0 2,5 3.0 8.3 TWO FT. INSIDE 25.0 3.0 4.0 6.3 THREE FT. INSIDE 25.0 3.0 4.5 5.6 APPROXIMATE CENTER 35.0 5.0 6.0 5.8 DIVIDER PLATE TOP (NEAR TUBESHEET) 30.0 8.0 6.0 5.0 MIDDLE CONTACT 30.0 8.0 4.0 7.5 BOTTOM CONTACT 25.0 3.0 3.5 7.1 TUBE SHEET TUBESHEET/ DIVIDER PLATE 40.0 8.0 6.0 6.7 i

HIGHEST TUBESHEET READING 40.0 8.0 12.0 3.3 AVERAGE DECON FACTOR 7.3 All readings in R/Hr.

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l SG CHEMICAL DECONTAMINATION RESULTS STEAM GENERATOR 3 PRE- POST- POST- DECON SURVEY LOCATION DECON DECON WASH FACTOR HOT LEG ACCESS MANWAY TWO FT. FROM MANWAY 1.5 0.7 0.5 3.0 ONE FT. FROM MANWAY 3.0 1.25 1.0 3.0 FLUSH WITH OUTSIDE EDGE 7.0 3.0 2.0 3.5 FLUSH WITH INSIDE EDGE 16.0- 5.0 3.5 4.6 BOWL REGION-ONE FT. INSIDE 20.0 6.0 4.0 5.0 TWO FT. INSIDE 22.0 6.0 4.5 4.9 THRi1E FT. INSIDE 22.0 6.0 5.0 4.4 APPROXIMATE CENTER 22.0 8.0 6.5 3.4 DIVIDER PLATE TOP (NEAR TUBESHEET) 30.0 10.0 7.0 4.3 MIDDLE CONTACT 35.0 10.0 5.0 7.0 BOTTOM CONTACT 33.0 8.0 5.0 6.6

)

TUBE SH2ET TUBESHEET/ DIVIDER PLATE 33.0 10.0 8.0 4.1 HIGHEST TUBESHEET READING 30.0 12.0 12.0 2.5 AVERAGE DECON FACTOR 4.3 All readings in R/Hr.

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SG CHEMICAL DECONTAMINATION RESULTS STEAM GENERATOR 3 SURVEY LOCATION PRE- POST- POST- DECON COLD LEG DECON DECON WASH FACIOR ACCESS MANWAY TWO FT. FROM MANWAY 2.0 0.8 0.9 2.2 ONE FT. FROM MANWAY 3.0 1.25 1.25 2.4 FLUSH WITH OUTSIDE EDGE '9.0 2.0 2.0 4.5 TLUSH WITH INSIDE EDGE 20.0 3.0 2.5 8.0 BOWL REGION ONE FT. INSIDE 28.0 4.0 4.0 7.0 TWO FT. INSIDE 28.0 4.0 4.5 6.2 THREE FT. INSIDE .28.0 5.0 7.0 4.0 APPROXIMATE CENTER 30.0 7.0 8.0 3.8 DIVIDER PLAIE

. TOP (NEAR TUBESHEET) 45.0 10.0 9.0 5.0 MIDDLE CONTACT 40.0 7.0 7.0 5.7 i BOTTOM CONTACT 35.0 40.0 4.0 8.8 TUBE SHEET TUBESHEET/ DIVIDER PLATE 45.0 10.0 10.0 4.5

' HIGHEST TUBESHEET READING 45.0 12.0 13.0 3.5 AVERAGE DECON FACTOR 5.1 All readings in R/Hr.

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ALARA REVIEW JOB

SUMMARY

-111. Job

Title:

SafetyRelatedPiping(HangerModificationsl Estimated Actual Estimated Actual Diff._

Manhour Manhour Manrem Manrem  %

Task Title 2900 3678.22 33.500 65.546 96 Outer Annulus Lower Level 338.87 - 2.145 -

Outer Annulus Middle Level -

444.33 - 20.660 -

Loop Areas -

123.28 - 0.935 -

Charging Floor -

460 1075.13 7.312 11.791 61 RHR Pit 5.071 399 Charging / Metering Pumps 235 452.00 1.016 Boric Acid Pump Area 385 428.94 1.575 1.345 -15 Pipe Trenches 170 130.83 6.212 3.260 -48 700.80 - 0.858 -

Misc. Work -

4350 7699.44 49.615 111.631 12.5 Totals Note: Second estimate listed above. Original estimate perfnrmed 12-9-85, goal for 1st estimate 25.289 Manrem.

1 ALARA CONTROLS UTILIZED Project rollback or completion of work in progress at 25 Manrem; shield charging line in immediate work vicinities (LLOA OVHD): low doserate waiting areas to be identified by HP, especially for fire watch; supports to be wiped down prior to cutting; welding; grinding; supports to be prefabricated to the maximum extent possible outside of RCA; temporary lighting to be installed as necessary; additional areas to be evaluated for shielding after initial walkdown; laydown area to be established for PAR shield blocks; access control to pipe trench to be maintained by installing wood hatch door.

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EFFECTIVENESS OF ALARA CONTROLS Project rollback / work completion was not enforced-due to evaluation of exposure used in installing staging (12 manrem had already been spent to install staging in LLOA, 31.4 Manrem was used total), shielding cost 6.3 Manrem to install and remove and saved an estimated 30 Manrem. Almost all areas worked required additional support work which was not estimated at the time of the review and could not be defined until after detailed walkdowns were performed.

SURVEY DATA NA SUGGESTED IMPROVEMENTS All areas to be worked must be defined well in advance of the outage start.

Additional work resulting from inspections and walkdowns should be reviewed on a case by case basis. Scaffolding should be erected in such a manner as to facilitate access to specific work areas (LLOA scaffolding required access from one end and it was a time consuming process to reach the work area).

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ALARA REVIEW JOB

SUMMARY

IV. Job

Title:

Primary Steam Generator Inspection and Maintenance SG #'s 1-4 Estimated Actual Estimated Actual Diff.

Task Title Manhour Manhour Manrem Manrein  %

General Preparations 67 148.45 3.500 3.095 -12 Remove / Replace Manways 306 368.02 19.000 20.155 6 Setup / Remove ECT Equipment 356 255.56 11.200 14.540 -30 ECT/ Profilometry 1108 825.99 51.200 60.385 18 (ECT 14,813/ Prof.700)

Mechanical Tube Plugging (61) - 1827.38 - 71.551 -

543 444.68 9.600 40.496 322 Tube Pull (1) tubes)

Foreign Exclusion Custodian - 263.82 - 1.7.0 6 -

Subtotals 1837 1861.84 84.900 99.935 18 Grand-Totals 4133.90 211.982 Note: Subtotal excludes manhours and manrem from task #5 tube plugging and task #6 tube pull. This subtotal is used in the Repetitive Job Exposure comparison for ECT/ Prof.

ALARA CONTROLS UTILIZED Diaphragms in skirt area shielded; SG ventilation system; jumper pens used for contamination control outside of SG skirt; oil canvas used in SG skirt area for contamination control; all hoses and cables entering skirt area sleeved; hoses and cables routed through cold leg opening; all SG jumpers mock-up trained; stay-times established for all channel head entries; tied off and inventoried all equipment going in and out of area; located eddy current readout in low dose area; used automated ECT and Profilometry equipment (SM-10); utilized mechanical tube plugging and audio ,

communications on jumpers and attendants. CCTV monitors used for Health Physics coverage of work evolutions; tube pull evolutions were scheduled in a decontaminated SG. l

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EFFECTIVENESS OF ALARA CONTROLS The ALARA controls are adequate. The redesigned steam generator ventilation system was easily installed and no airborne radiation incidents occurred. The jumper pens were also redesigned and were easy to decontaminate and maintain. The size of these pens was increased during the outage, generally the expanded pens were still considered too small.

CCTV monitoring was used for HP coverage and saved an estimated 32 Manrem.

The use of the Zetec SM-10 robotic arm resulted in an exposure reduction of 46 percent (86 Manrem) in comparison with previous ECT equipment (SM-4).

Performing the tube pull in a decontaminated steam generator did not save as much exposure as anticipated. This was due in part to a larger scope of work being performed outside of the channel head and numerous problems associated with removal of the tube section from the channel head. Tube plugging Rem / Tube showed a decrease from 1984 levels, due to the decontamination of SG's 1 and 3.

SURVEY DATA See Figures 8, 9, 10 and 11.

SUGGESTED IMPROVEMENTS Investigate the feasibility of using remote fixtures for tube plugging that do not require entry into the SG channel head space. (Tube pull or sleeving evolutions should require the same technology). Mock-up training for personnel entering the channel head should be task specific and a minimum performance criteria established for each task. Workers that can not meet the mock-up criteria should be trained for support tasks outside the channel head. Continue to stress housekeeping in the jumper pens, evaluate running service leads to skirt through pipe penetrations.

Evaluate reph cing SG stairs with ladders to maximize space utilization in the jumper pens. Evaluate the possibility of purchasing a CY communications system for SG work. Each group had their own system and a large amount of time and exposure was used to install, repair, replace and remove this equipment.

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i I COMPOSITE SURVEY j OP3??1 REV 483 STEAM GENERATOR g RWhNO CONTROL NO DATE TsuE SMIRT AREA ONE d

RE ASON 7OR SUHvf v T E CHNICIAN REACTOR POWE R ROUTINE (D. W. M) PR E. JOB POST. JOB  % .

RADIATION CONTAMINATION )

d er TELETECTOR ln I#7 le  !

INST TYPE INST TYPE INST TYPE INST . TYPE )

SERIAL NO SER6AL NO SERIAL NO SERIAL NO f PROBE TYPE PROBE TYPE PROBE TYPE PROBE TYPE CAL. DUE DATE CAL DUE DATE CAL. DUE DATE CAL DUE OATE DOSE RATE READINGS ARE IN MREM /HR AT WAIST LEVEL UNLESS OTHERwtSE SPECIFIED .

CIRCLED NUMBERS h INOICATE SMEAR LOCATIONS j CIRCLED SMEAR LOCATION $ AND NUMBER ((4) 5000) INDICATE CONTAMINATION LEVELS IN DPM/100CM'

. RE ADiNGs iNSiDE TRIANGLEhlNDICATE NEUTRON R ADIATION IN MREM'HR AT WAIST LEVEL ALL READINGS IN REM /Hr.

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ALL SME ARS LESS TH AN 1000 OPun00 CM' n 75% OF ALL SME ARS LESS THAN 20 DPM/?00 CM's HEAL,TH PHYSICS $UPERylSOR/DESaGNEE 29 of 59 .

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. o,, , ,,, ,.c RWPNO CONTROL NO DATE TIME

- STEAM GENERATOR 3

$KIPT AREA WO T E CHNICIAN REACTOR POWt R R ASON FOR SURVEY.

L_l ROuviNE iO w. ul 0,RE.;OO 0,OST.;Os  %

RADIATION CONTAMINATION X)fSY TELETECTOR b l87 la INST TYPE INST TYPE INST. TYPE INST. TYPE SERIAL NO SERIAL NO SERI A'. NO SERI AL NO PROBE TYPE PROBE TYPE PROBE TYPE PROBE TYPE CAL DUE DATE - CAL DUE DATE CAL OtJE DATE CAL DUE DATE DOSE RATE REAOLNGS ARE IN MRiM/HR AT WAIST LEVEL UNLESS OTHERWISE SPECIFICO.

CIRCLEO NUMBERS h INOtCATE SMEAR LOCATIONS CIRCLEO SMEAR LOCAflONS AND NUMBER @ 'M100) INDICATE CONTAMINATION LEVELS IN OPM/100CM'

  • READINGS IN$10E TRIANGLEbiNOICATE NLUTRON RA04ATION IN MREM /HR AT WAtST LEVEL ALL READINGS IN REM /Hr.

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COMPOSITE SURVEY g,,, ny m STEAM GENERATOR 3 RwPNO CONTROL NO DATE TIME SKIRT AREA THREE RE ASON FOR SURvEv_ T ECHNICI AN REACTOR POWE R ROUTINE (D W M)

PRE JOB POST. JOB  %

RADIATION CONTAMINATION XMST TELETECTOR ln l87 la INST TYPE INST TYPE INST TYPE INST TYPE SERIAL NO SERIAL NO SERIAL NO SERIAL NO PROBE TYPE PROBE TYPE PAOBE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE CAL DUE DATE DOSE RATE READINGS ARE IN MREM /HR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED CIRCLED NUMBERS h^ ;NDICATE SMEAR LOCAflONS CIRCLED SMEAR LOCATIONS AND NUMBER INDICATE CONTAMINATION LEVELS IN DPM/100CM'

+ READINGS INSIDE TRIANGLE INDICATE NEUTRON RADIATION IN MAEM/HR AT WAIST LEVEL ALL READINGS IN REM /Hr.

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COMPOSITE SURVEY OPmi REv e43 STEAM GENERATOR g HWPNO CONTROL NO DATE TIME SKIRT AREA FOUR Rf A50N FOR SURVEY T E CHNICIAN REACT OR POWE R

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ROUTINE (D w M) PRE JOB POST.JOO  %

RADIATION CONTAMINATION XMBT TELETECTOR ln l87 la INST TYPE INST TYPE INST TYPE INST TYPE SERIAL NO SERI AL NO SERIAL NO SERIAL NO PROBE TYPE PROBE TYPE PROBE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE CAL DUE DATE DOSE RATE READINGS ARE IN MREM /HR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED CIRCLED NUMBERS h INDICATE SMEAR LOCATIONS CIRCLED SMEAR LOCATIONS AND NUMBER ((4) 5000) INDICATE CONT AMINATION LEVELS N DPM/100 Cur

  • READINGS INSIDE TRIANGLEbtNDICATE NEUTRON RADIATION IN MREM /HR AT WAIST LEVEL ALL READINGS IN REM /Hr.

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32 of 59 a

ALARA REVIEW JOB

SUMMARY

V. Job

Title:

Refueling Operations Core XIII-XIV Estimated Actual Estimated Actual Diff.

Manhour Manhour Manrem Manrem  %

Task Title RX Had Disassembly 140 400.83 7.4 12.175 64 Remove / Install Transfer 0.695 -71 Tube Blind Flange 27 26.92 2.4 233 374.68 8.5 8.868 4 RX Stud Detension 173 106.58 4.3 1.780 -58 Cavity Decontamination i 197 258.50 1.0 2.655 165 Internals Remove / Install 1260 704.95 3.9 4.495 15 Fuel Shuffle RX Stud Tensioning and Reassemble RX Head 603 673.73 23.8 44.285 86 759.10 - 3.490 -19 Miscellaneous -

l l

Sub-Totals 2835 2635.69 58.5 80.808 38 2835 3394.79 58.5 84.298 44 TOTALS NOTE: Subtotal excludes manhours and manrem for task Miscellaneous, which includes retrieval of dropped fuel element and RX Head Shield.

ALARA CONTROLS UTILIZED Temporary reactor vessel head shield; personnel shields; water to railing in transfer canal (Blind flange replacement only). Shielded rails of manipulator crane bridge; permanent plexiglass shield on manipulator mast; shielded seal plate af ter cavity drain down; portable ventilation in cavity; charging floor modular enclosure; stud cleaning machines and associated ventilation; herculited around stud racks; underwater cavity filtration and vacuum system.

33 of 59

EFFECTIVENESS OF ALARA CONTROLS RX Head disassembly was 4.8 Manrem higher than expected due to electrical disassembly being performed out of the refueling sequence and having to be reconnected for the Class A test. Transfer tube removal and replacement was 1.7 Manrem lower than expected due to decon of the canal for transfer cart overhaul. Decontamination cost 1.5 Manrem. Cavity decontamination was lower than expected since post drain down decontamination was a flush and wipe down due to time restraints. Although smear levels were higher than normal no airborne radioactivity incidents occurred. Stud tensioning and RX head reassembly was cause for the biggest exposure overrun. This was due to stud tensioning being out of sequence. In order to comply with procedure the RX head had to be detensioned and re-tensioned. Had this not occurred the total job would have had an overrun of only 9 percent.

SURVEY DATA .

See Figures 12 and 13.

SUGGESTED IMPROVEMENTS Remove seal deck plates prior to flood up so that the seal plate can be easily decontaminated after drain down. Greater emphasis should be placed on following the outage schedule and task procedures. Improve worker pre-job briefings. Continue the use of portable ventilation in the cavity.

Develop an attachment for ventilation on the stud hole cleaning machine.

Pursue the purchase and installation of the Baich QD Stud Tensioner System.

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r- ------. _ _ . _ - _ _ _ _ _ _ _ . __ ___.__ __

OP3221 REV 9-83 " " ' " '

REACTOR CAVITY 1/15/86 CON-22 enE.;Oe 8 POST sos Rx Head Shield "O' ROU11~e<o .M, RADIATION CONT AMIN ATION l tlY l117 ln INST TYPE INST TYPE INST TYPE SERIAL NO SEHIAL NO SERIAL NO PROBE TYPE PRODE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE DOSE RATE READINGS ARE IN MREM /HR AT W AIST LEVEL (JNLESS OTHE9 WISE SPECIFIED CIRCLEO NUMBERS h iNO1CATE SMEAR LOCATIONS CIRCLEO SMEAR LOCATIONS AND NUMBER INDICATE CONT AMINATION LEVELS IN DPM'100CM'

  • READtNGS INSIDE TRIANGLE INDICATE NEUTRON RADIATION IN MREM /HR AT WAIST LEVEL MAXIMUM RADIATION MAxlMUM CONT AMIN ATION

~

Krv MEAD CONT.

'IV '""GE PERSowmELSMitLO V~

r e AIST 100 -

_ 10 80 _

160 11 50 _

120 60 'oi$

400 -

_ 200 _ 1 160 _

18 00 o _

400 A O C

240 220 20C --. i .-- 1 50 C

E 0C] )_3 50 O

- v _

240

?SO _

0 o -

290 40 250 Pre-shield general area

-- doserates around Rx head

- 260 at waist level 0.5-0.7 R/hr 240 600

~

MAX RADIATtON _ . -

~

max CONT AMINATION MAX BET A RADI ATION-ALL SME ARS LESS THAN 1000 DPM/100 CM'It? 25% OF ALL SME ARS LESS THAN 20 DPM/100 CM' a HEALTH PHYttCS SUPERVISOR / DESIGNEE 35 of 59

oPmi REv o-u COMPOSITE SURVEY

"*"" 0" " ' "U "#"

FUEL TRANSFER CANAL CON-14

" ^* "' " ""# ' " " ' ' "

Decontamination ROUTINE (O. W. M) PRE JOB POST-JOB RAOIATION CONTAMitfATION lar lar I .,

INST TYPE INST TYPE INST TYPE SERIAL NO SERI AL NO SERIAL NO PROBE TYPE PROBE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE OOSE RATE READINGS ARE IN MREM'HR AT WAtST LEvFL UNLESS OTHERWtSE SPECIFIED CIRCLEO NUMBERS h lNDICATE SMEAR LOCATIONS CIRCLED SMEAR LOCATIONS AND NUMBER ((4) $000) INDICATE CONTAMINATION L EVELS IN DPM/,00CM"

  • READ 4NGS WSIDE TRIANGLE INDICATE NEUTRON RADIATION IN MREM /HR, AT WAIST <EVEL MAXIMUM RADIATION MAxlMUM CONT AMINATION - 4N ALL READINGS IN REM /Hr.

Fre-decontamination Post decontamination 6

Contact 18 inches _ Contact 18 inches

1. 1.5 0.5 1. 0.5 0.2
2. 10.0 2.0 2. 1.2 0.6
3. 30.0 5.0 - - 3. 1.0 0.6 5 4, i,o o,4
4. 2.5 --
5. 5.0 2.0 5. 1.0 0.4
6. 1.0 0.5 6. 1.0 0.7 4

3 2 _

Survey location # 1 at Blind Flange OAttSMEARStESS1NA~,oooOPM,,ooCM,,r 0 2,s O, .<t SME ARS LE SS TNA~ ,o OPM,,oo CM, .

~~

HEALTH PHYSICS SUPERvlSOR/DE$1GNEE 36 of 59

ALARA REVIEW JOB

SUMMARY

VI. Job

Title:

Cavity Pool Seal Replacement Estimated Actual Estimated Actual Diff.

Manhour Manhour Manrem Manrem  %

Task Title Setup / Remove work area /

install observation 1.620 -73 platform 750 376.57 6.000 291.01 2.550 1.730 32 Cut-up and remove old seal 150 Cut out old pool seal alignment pins 52 182.50 1.990 4.655 134 430 1318.69 16.470 24.603 31 Weld / inspect new pool seal

  • Modify new pool seal 172 1337.20 21.619 -

1382 2168.77 27.010 32.608 21 Subtotals 1382 3505.97 27.010 54.227 130 TOTALS

  • Additions to the work scope for which no estimate was performed.

ALARA CONTROLS UTILIZED HEPA ventilator / hood enclosure for plasma arc cutting and disposal of old pool sea; Herculite laydown for old pool seal; Strippable paint utilized for decontamination of old seal; HEPA ventilated enclosure for alignment pin removal in cavity; Personnel shields and RX Head shield in place for cavity work; RX flange decontaminated to lower doserates in support of seal welding.

EFFECTIVENESS OF ALARA CONTROLS The use of the RX Head shield (DRF 3) saved an estimated 48 Manrem. HEPA ventilation and enclosures were effective in controlling airborne radioactivity. Welding of the new seal was more labor intensive than anticipated. The exposure overrun in this area was also compounded by not estimating for fire watch responsibilities. The major exposure overrun (32.6 Manrem) was due to modifications that were required on the new seal sections to correct fit-up problems. This was due to manufacturing problems wnich caused seal section warping. Removal of crud from the RX flange was also helpful in reducing doserates for seal welding.

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l SURVEY DATA NA.

SUGGESTED IMPROVEMENTS Future estimates will include fire watch responsibilities for any welding operations. The plasma arc cutter for the old pool seal disposal was inoperable and had to be replaced. This could have been avoided had the plasma arc cutter been tested prior to moving the equipment into containment. Warping of the seal sections was not identified until the component was moved into containment, although the component was inspected prior to shipment. Additional emphasis should be placed on the inspection of close tolerance components to eliminate fit-up and modification problems.

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'f $ (.i

( /

. . ) '

_" j _ ]j";

1 1]'

ALARA REVIEW JOB

SUMMARY

i

+ ,

l VII. Job

Title:

Crane /Teledyne Motor Cperitor Repiqt gen,t. [L \

A jl ylz Estimated Actual Estira'tal Ac'O.31 Diff. \' / }

Task Title Manhod Manhou_* Manre.nC Manrem  % , /,

Install / Remove Shielding 154.8 157.84 D.970 l'11.!!B > -33 , .

, \y , c x 21.6 246.42 I.110 '10.0E0 806 v>

Install / Remove Rigging s n

Remove / Install Operators 560.8 600.R5 W. 530 2R J40 -47 '

et 1(

Replace Valve Stems 79.2 51.83 0.790 0.665 J16 1

]' .

t l

  • I Remove / Install Inter- '

ferences  :-165.2 69.08 8.530 2.695 N8 j t

I l Cleanup / Test Operators 230.6 76.09 21.420 6.240 -f 1 i/' s.

I j~

TOTALS 1212.2 1202.11 102.350 54.215' 7 ,

?

ALARA CONTROLS UTILIZED ,

Shielding installed on MOVs 200, 780, 781, 804, 861A-D; shielding installed on loop bypass lines and adjacent railings; secondary side steam generators ,

in wet lay-up for all mid level icop replace,ments; low dose rate area motor operators replaced first for learr%g curve Yffect; masline wipe down of flange for contamination contal; herculite,1Ypown required over grating i areas; glovebags to be utilized on PZR valves 'and MOV 298 (stem replacements); surgical gioves allowed for electrical work. ,

EFFECTIVENESS OF ALARA COMTROLS /

,( u The ALARA controls were adequate. General area shielding was installed \s prior to any job specific shielding being performed. Shielding evolutions were also preplanned well in advance and overall cost 18 Manrem les/ thh3 anticipated for installation and removal. Valve installation, testbg aWd '

, s cleantp cost approximately 30 Panrem less than anticipated. This was dtr >--

i to effective shielding in the loop areas, the learnirq curve approac'ft s jT Average DRF for'all I utilized and the use of very experienced personnel.

job specific shielding 1.7. Shieldingsavedanestimated18.9Manrem[",/,',,t .

Glovebags were not utilized on P7.R M0 replacements due to work area >

restrictions.

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SURVEY DATA ,

r.

NA s. -j.

SUGGESTED IMFf.)VEMENTS Continue to stress the need to use experienced personneh on similar projects. Perform work of a similar nature "In low dose rate areas first for learning curve effect. Continue L! o. perform job specific shielding evolutions only after general area stiieiding has been installed. Perform work in mid level loops when secondary steam generators are in wet hy up, t

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-~7_-

ALARA REVIEW JOB

SUMMARY

$111. Job

Title:

Inservice Inspection Estimated Actual Estimated Actual Diff.

Task Title Manhour Manhour Manrem Manrem  %

NDE Class I & II 2314 1372.92 87.930 29.536 -66 Piping /Supp. Inspec.

Snubber Inspecticn 174.5 314.07 6.644 7.424 12 FG 4 Weld Inspection 60 159.17 2.040 0.820 60 PTP Flywheel Inspection 110 7.40 2.080 0.250 88 l

SG 7-Feedwater Nozzle Inspection 298 15.33 14.100 0.340 -98 TOTALS 2946.5 1868.89 112.794 38.370 -66

( ALAR 3_CONTROLSUTILIZED t Utilice experienced workers for job efficiency; welds, valves, snubbers and pirting marked, tagged fc.r easy . identification; setup and calibrate test eq;iom6nt in low dose rate area; HP to survey prior to start of work; RCP flycheel to be removed to charging floor for inspection; snubbers to be l ramoved to low dose rate area for testing; ALARA to evaluate shielding on a case by case basis; all test equigaent to be wrapped in plastic; worklist te be forwarded to ALARA prior tr.7 the start of outage; Maintenance to erect all staging; weld preparations to be performed as per ISI procedures; radiography for nozzle inspectios1 to be performed during off peak hours (0300-0600 normally); area to be evacuated, roped off and posted when source is exposed; radiographer to wait in low dose area during shoot.

EFFECTIVENESS OF XLARA CONTROLS I

ALARA contro1r were adequate. The feedwater nozzle inspection was l coapleted with the secondary SG filled, doserate 10 percent of expected.

Staging was.kept to a minimum and area access was much better than expecten tiDI manhours were over.: estimated, effective doserate was the same as 1984. Loop 3 cold leg inspection was delayed until the loop was refilled, 5 mattrem saved.' Shie1<..iing. hot spots on loop 2 charging line saved 2 manrem. Hot spot shielding OR top of the pressurizer lowered doserates from 450 to 150 Mr/Hr and suved an additional 3 Manrem.

41 of 59 Y

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SURVEY DATA NA SUGGESTED IMPROVEMENTS Continued emphasis on area decontamination to keep respirator and protective clothing requirements to a minimum. Having dedicated personnel coordinate staging installations and removals resulted in efficient use of

/

staging. NDE worklist should be reviewed for shielding appifcations well in advance of the outage. Investigate increased use of automated weld inspection equipment. Coordinate with Outage Planning and ISI to schedule the majority of loop work when the loops are filled in order to take advantage of more favorable doserates.

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l 1

ALARA REVIEW JOB

SUMMARY

i i

IX. Job

Title:

Secondary Steam Generator Inspection / Maintenance Actual Estimated Actual Diff, i Estimated Manhour Manhour Manrem Manrem  %

Task Title Remove / Replace Handhole 80 186.92 6.480 6.433 -1 Covers / Upper Manways Sludge Lancing Operations 450 533.84 8.550 9.790 15 1

Setup / Breakdown Equipment /

Upper Buadle Washdown 340 162.84 2.500 3.726 14 Photo Flowslot/ Fiberoptics 80 200.75 7.040 13.760 95 Inspection 850 1064.68 24.570 32.949 34 TOTALS ALARA CONTROLS UTILIZED Communication required between work platform and trailer at all times; shirld local hot spots as required by ALARA; sleeve all hoses and cables entering loop area; sludge lance equipment to be leak tested at operational pressure and all leaks repaired; filter bagged and placed in drum; remote operator controls set up in low dose area; replace handhole covers and flood secondary SG as soon as possible following inspection; handhole covers to be loosely attached for shielding when work is not in progress; workers to avoid handhole area as much as possible; HP coverage to be provided using CCTV system as much as possible.

EFFECTIVENESS OF ALARA CONTROLS j

The ALARA controls were adequate. The major overrun was caused by foreign object retrieval during fiberotpics inspection. Local hot spots were shielded as part of the. general area shielding program and included the bypass lines and valves. Although this shielding is provided for other work in the area, it is not considered as dose savings for this work.

(Note: Highest whole body exposure is received by upper arm due to work inside handhole). CCTV monitoring for Hp coverage worked very well and saved an estimated 10 Manrem.

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SURVEY DATA See Figure 14.

SUGGESTED IMPROVEMENTS 3 Continue the use of CCTV monitoring for HP coverage. Investigate robotics for use in foreign object retrieval and video inspection of tube sheet area.

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CO!90STTF 9f f RVi?Y iWPNO CONTROL NO. 'DATE TIME (

Steam Generator Secondary Side llandholes T ECHNICI AN REACTOR POWER R ASON FOR SURVEY.

LJ ROUTINE (D. W M) . PRE-JOD POST-JOB RADIATION CONTAMINATION b l#7 la lar INST TYPE INST. TYPE tNST. TYPE Teletector INST. T YPE SERIAL NO SERIAL NO SERIAL NO SERIAL NO PROBE TYPE PRO 8E TYPE PROBE TYPE PROGE TYPE CA: DUE DATE CAL. DUE DATE CAL DUE DATE CAL. DUE DATE DOSE RATE READINGS ARE IN MREM /HR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED CIRCLED NUMBERS h INDICATE SMEAR LOCATIONS.

CIRCLED SMEAR LOCATIONS ANO NUMBER INDICATE CONTAMINATION LEVELS IN DPM/100CM2

+ READINGS INSIDE TRIANGLEbtNDICATE NEUTRON RADIATION IN MAEM/HR AT WAIST LEVEL ALL READINGS IN REM /lir Survey location SG1 -SC2 SG3 SG4 At plane of handhole 2-2.5 2-3 2 5 12 inches inside generator 25 40-65 8-10 40-45 24 inches inside generator 60 70-75 70 80-90 l

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ALL SMEARS LESS THAN 1000 DPM/100 CM' #7 75% OF ALL SMEARS LESS THAN 20 DP6A/100 CM's HEALTH PHYSICS SUPLRvlSOR/ DESIGNEE i

45 of 59 {

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j

ALARA REVIEW JOB

SUMMARY

X. Job

Title:

Reactor Coolant Pump Seal Repair (1,3,4)

Estimated Actual Estimated Actual Diff.

Manhour Manhour Manrem Manrem  %

Task Title 175 102.41 2.380 1.225 -49 Motor Removal and Decon Piping / Electrical Remove 15 20.58 0.435 1.255 186 and Replace RCP Seal Remove & Replace 458 624.73 15.572 20.120 29 Seal Repair 80 3.17 1.440 0.070 -95 Motor Replace & Align 262 265.78 4.690 5.797 24

  • Motor Inspection - 40.00 - 0.990 -

Miscellaneous 90 205.89 1.629 1.811 11

  • Insulation RCP Bowls -

92.99 - 6.240 -

Subtotal 1080 1262.56 26.146 31.268 20 TOTALS 1080 1355.55 26.146 37.508

  • Unplanned tasks for which no estimate was performed.

ALARA CONTROLS UTILIZED Piping in area will be surveyed by HP to identify hot spots; ALARA to install / remove shielding; herculite laydown area set up around pump; step off pad will be utilized for access / egress from the pump area; doghouse will be set up for decon of small parts as needed; doghouse to be ventilated using a HEPA equipped vacuum cleaner; work on RCPs will be performed when the nearest SG is in wet lay up; ensure shims are marked; tools will be organized in a low dose rate area to be established by HP; restrict traffic in work area; workers to be briefed or trained by an individual with experience at performing this job (video tape of previous seal replacement should be used).

46 of 59

EFFECTIVENESS OF ALARA CONTROLS ALARA controls were adequate. No hot spots were identified that warranted shielding. CCTV monitoring was used for routine area HP coverage and saved an estimated 10 Manrem. Shielding of the loop bypass lines was performed as part of the general area shielding program and saved an estimated 6.3 Manrem (EFDR 1984-0.030 R/hr, EFDR 1986-0.025 R/hr). The major contributor to the overrun was the additional manhours spent on the seal rebuilds.

SURVEY DATA See Figure 15.

I SUGGESTED IMPROVEMENTS Emphasize use of the RCP mockup. Continue the shielding of the loop bypass lines. Install shielding on the rails of one RCP platform to evaluate general area dose reduction potential. Continue to work RCP only when the nearest SG is in wet lay-up.

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COMPOSITE SUP.VEY-m,,, em RwpNO CONT ROL NO, DATE ifME l REACTOR COOLANT PUMP COM 12 .

TECHNICIAN REACTOH POWER R AlK)N FOR SURVEY; POST-JOS ROUTINF (D W. M) PRE JOB RADIATION CONTAMINATION Iar b ier f.

INST TYPE INST. TYPE INST TYPE INST. TYPE SERIAL NO SERIAL NO SERIAL NO. SERI AL NO PRODE TYPE PROBE TYPE PROSE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE CAL DOE DATE DOSE RATE READINGS ARE IN MREM /HR AT WAlST LEVEL UNLESS OTHERWISE SPECIFIED.

CIRCLED NUMBERS h INDICATE SMEAR LOCATIONS-CIRCLED SMEAR LOCATIONS AND NUMBER INOtCATE CONTAMINATION LEVELS IN OPM/100CM8 e READINGS INSIDE TRIANGLE INDICATE NEUTRON RADIATlON IN MAEM/HR. AT WAIST LEVEL ,

Flywheel level 10 - 50

/

\_

O Pn _

T k< Seal Water Return 100 150 50 c- ne i i i i_

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l ) 50 General Area 150 Ceneral Area i

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4 02s,0,AltSMEARSLESSTNAN,oDPM,,ooCM..  !

0.Lt SME ARS i ESS T AN ,ooo DPM,,oo CM. rr  !

HEALTH PHYSICS SUPERVISOR / DESIGNEE 4Ei of 59 I

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4 h I

I ALARA REVIEW JOB

SUMMARY

XI. Job

Title:

Inadequate Core Cooling Modifications (HJTC) {

Estimated Actual Estimated Actual Diff.

Task Title Manhour- Manhour Manrem Manrem  %

Staging 355 764.87 5.075 3.623 -29 .

1 Transport Materials 372 470.95 4.680 0.755 -84 Hanger Installation for 747 shielded canister 140 592.83 1.300 11.015 ICC Head & Internals Mods 787 1064.09 20.360 13.305 -35

  • Install Electrical Cable - 95.42 - 0.400 -
  • Apply Fire Retardant Foam - 8.17 - 0.185 -

TOTALS 1654 2996.33 31.415 29.283 -7

  • Unplanned tasks for which no estimate was performed.

ALARA CONTROLS UTILIZED Work performed on upper guide structure with cavity at refuel level from auxiliary crane bridge; all equipment and materials used in refuel pool hosed down, wiped and bagged prior to removal from area; material removed from cavity (chips, material removed from UGS) will be monitored by HP; shielding to be available; work on RX head in laydown area will be <

performed with the head shield in place; core deluge piping shielded; shielding to be evaluated for use on the catwalk and on top of the coil stacks; HEPA ventilation will be used to control contamination during cutting and welding evolutions on head; HJTC canisters will be assembled in the containment foyer.

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EFFECTIVENESS OF ALARA CONTROLS Shielding of the core deluge lines resulted in a DRF of 2. This shielding was necessary to do work at the shroud level and to protect access to the upper platform. No exposure savings can be estimated due to the way RWPs f 1

were written (Note: MOVs 871 A and B were also changed out at this time).

Problems were encountered with the automated yelding used on the head and required entries into the coil stack area. The upper work platform was installed approximately 5 feet above the catwalk. Therefore, due to lower doserates at this distance shielding was not required. The exposure.

overrun on hanger installation was due to hitting rebar and difficulties experienced with initially installing the canisters.

SURVEY DATA NA SUGGESTED IMPROVEMENTS None i

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__ _______________ _ ___ _ _ _ ____J

ALARA REVIEW JOB

SUMMARY

XII Job

Title:

Appendix R Modifications Estimated Actual Estimated Actual Diff.

Manhour Manhour Manrem Manrem  %

Task Title 255 32.75 6.250 0.920 -85 Transfer Material 405 999.25 17.010 16.457 -3 Install Fire Shields 330 444.94 11.490 10.385 -10 Install MI Cable l

  • Charging Pump Area Fire Damper - 411.81 - 0.495 -

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990 1888.75 34.750 28.257 -19 TOTALS l ALARA CONTROLS UTILIZED l

Prefabrication of materials outside of radiation areas as much as possible; coordinate work in areas with other groups to take advantage of existing shielding and staging; cable pull points to be chosen in as low dose area as possible.

EFFECTIVENESS OF ALARA CONTROLS The ALARA controls were adeqsate. Shield rack was installed in PT 404 area to reduce exposure from the ;30p bypass line (DRF 2). Estimated savings 10 Manrem.

SURVEY DATA NA SUGGESTED IMPROVEMENTS ALARA review was performed when it became apparent that exposures were going to exceed 5 Manrem. This was due to pre-PDCR approved work in progress and the work scope not being completely defined at the time of the initial ALARA review. The work scope should be well defined prior.to the start of work so that all shielding reviews and ALARA considerations can be evaluated.

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. a ALARA REVIEW JOB

SUMMARY

XIII. Job

Title:

Cavity Drain Line Replacement Estimated Actual Estimated Actual Diff.

Manhour Manhour Manrem Manrem  %

Task Title Remove / Install Piping, Valves and Hangers 404 526.18 28.280 15.315 -46 Install / Remove Staging 215 160.65 10.300 5.880 -43 619 686.83 38.580 21.195 -45 TOTALS ALARA CONTROLS UTILIZED Additional shielding required on stored CRDs in sump area; ventilator (1000 CFM) to be used during cutting operation of old drain line; shielding on drain line should remain in place until that section of line is removed; removed section of drain line to be cut into 3 ft. lengths for disposal; removed section of drain line will be bagged or wrapped; catch bag to be used under drain line during cutting operation to contain any remaining water in the line; extra portaband saws will be available at work site; pre-fab supports for new line as much as possible outside of RCA; supports to be wiped down prior to cutting, welding, grinding; temporary lighting required in sump.

EFFECTIVENESS OF ALARA CONTROLS The ALARA controls were adequate. 100 R/hr spot was identified on the drain line after decontamination of the transfer canal. Flushing of the drain line reduced this hot spot to 5 R/hr. Adding additional shielding to the stored CRDs reduced general area doserates in the sump area and ad,iacent loop area (DRF 2).

SURVEY DATA NA SUGGESTED IMPROVEMENTS Continue to emphasize good communications between all involved groups. The successful flushing of the cavity drain line took three attempts and involved the Contractor, Engineering, Operations and Health Physics.

Perform a cost benefit analysis on purchasing new CRDs and the eventual disposal of the CRDs stored in the sump area.

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. o ALARA REVIEW JOB

SUMMARY

XIV: Job

Title:

RTO Study Estimated Actual Estimated Actual -Diff.

Manhour Manhour Manrem Manrem  %

l Task Title Install Multiplexer -64 280 89.85 2.800 1.005 and Cable Install Thermocouple -79 1700 276.08 51.000 10.461 and Cable 51.71 0.500 0.010 -98 Install Cables in RCA 100 417.64 54.300 11.476 -79 TOTALS 2080 ALARA CONTROLS UTILIZED Staging from RCS Loop Temp. Elements to be utilized; modifications to this-staging to be kept as minimal as possible; prefabrication of temperature elements on support band will be performed outside of RCA; delay project start until manways have been reinstalled on steam generators; skirts to be deconned prior to start of job; ventilation will be running in the immediate area of flapper wheeling for tack weld preparations; firewatch to be located in a low dose area.

EFFECTIVENESS OF ALARA CONTROLS l The ALARA controls were adequate. It was determined prior to the start of work that the support band design would be adequate to support the thermocouple. This eliminated the need for tack welding.and firewatch.

Staging did not require modification.

SURVEY DATA NA SUGGESTED IMPROVEMENTS Continue to question the need for some tasks and reduce work scope where 4 j

possible. Good communications between all involved groups resulted in work l scope reduction and allowed for the use of staging which had been installed I for another project.

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l IIC. Shielding and Exposure Reduction Techniques Job Specific Applications:

Installed shielding on the loop bypass lines for RCS Loop Temperature Elementinstallation(DRF2). Estimated savings approximately 137 Manrem.

Shielded the SG chemical decon ion exchanges and process skid.

Adjacent areas showed no increase in background radiation levels.

Shielding installed in support of hanger modifications cost 6.3 Manrem to install and saved an estimated 30 Manrem.

Installed temporary Rx Head shield (DRF 2), utilized. personnel shields in cavity (DRF 3) for refueling and cavity seal installation. Total exposure savings approximately 30 Manrem (15.24 respectively)

Shielding of loop bypass lines for RCP seal rebuild saved an estimated 6.3 Manrem.

Shielding of the core deluge lines in support of ICC modifications and MOV replacement resulted in DRF of 2.

Shielding hot spots on the loop 2 charging line and pressurizer saved an estimated 5 Manrem during ISI inspections.

Installing a shield rack for work on PT 404 resulted in a DRF of 2 and saved an estimated 10 Manrem.

Shielding of M0Vs 200, 780, 781, 804, 861A-D in support of MOV replacements resulted in an average DRF of 1.7 and saved an estimated 18.9 Manrem.

General Area Applications:

Pressurizer spray lines in middle level loops (DRF 4).

All loop bypass valves in middle level loops (DRF 2).

Pressurizer spray valves in middle level outer annulus (DRF 4).

Charging lines MOV 292 B&C (DRF 4).

Drains cooler and MOV 310 (DRF 3)

All Manway diaphragms in SG skirt areas (DRF 3).

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l Other Exposure Reduction Techniques Utilized:

Closed circuit TV for Health Physics coverage saved an estimated 73 .;

j Manrem.

Use of the SM-10 robotic arm for ECT/ Prof, examination resulted in a 50 percent reduction in exposure per tube, thereby saving an estimated 86 Manrem.

Transfer canal decontamination cost 1.5 Manrem to decon and saved 0.2 Manrem on blind flange removal and replacement. An additional 12 Manrem was saved on the Transfer Cart rebuild (General DRF of 3, hot spot of 30 R/hr reduced to 1 R/hr).

Replacement of the transfer cart home switch cost .03 Manrem since this task was performed by a diver. It is estimated that this task could have cost in excess of 1 Manrem had it been done with the canal drained.

Added additional shielding to stored CRDs in sump area.

Flushed cavity drain line to eliminate hot spot of 100 R/hr. Hot spot reduced to 5 R/hr.

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III. Radioactive Contamination Control IIIA. Personnel External Contamination A total of 159 Personnel Contamination Forms were completed on individuals having external radioactive surface contamination in excess of 100 ccpm Beta / Gamma. Considering the total number of s manhours spent in the Radiation Control Area this outage (106,262 manhours), 159 contamination occurrences represents a significant decrease in incidence rate, i.e., one personnel external contamination in 668 manhours. The personnel external contamination incidence for trending purposes are as follows:

Year Incidents Manhours Manhours / Incident 1980 400 141,304 353 1981 137 73,383 535 1983 160 72,665 454 1984 238 46,067 194 1986 159 106,262 668 The personnel external contamination incidence per manhour was 71 percent less this outage than in the 1984 outage and represents the lowest incident rate in the unit's history. This decrease can be attributed to corrective actions being taken from the issuance of radiation work permit non-compliance and the aggressive action taken to decontaminate and maintain major areas.

of the plant at low contamination levels.

The table below list the body regions which received the largest percentage of external contamination. 1984 data is also listed for comparison purposes.

Percent of Total General Body Area 1984 1986 Head, Throat 54 53 Arm, Wrist, Hand 15 24 Trunk, Crotch 16 9 Thighs, Knees, Ankles 14 14 l

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i r 'n Again, the head, neck, face and hair were the regions having the highest contamination incidence. The major causes being rubbing or touching of the face with contaminated gloves and improper respirator and hood removal.

For the first two months of the refueling, the site Health Physicist conducted a study to determine the effect of respiratory protection devices on skin contamination incidents.

The table below lists the general body areas contaminated depending on whether or not they occurred on radiation work permits specifying respiratory protection. The work "with" in the table denotes those contaminations that occurred on RWPs specifying respirator protection and "without" denotes those contaminations that occurred on RWPs not specifying respiratory protection.

Number General Body Area With Without Wrist, Hand, Fingers 10 11 Arm, Elbow 5 3 Shoulder, Chest, Back 4 0 Throat, head 46 24 Stomach, Crotch, Buttocks 8 1 Legs (thighs, knees, ankles) 12 4 As expected, work performed on RWPs using respiratory protection had a higher occurrence rate than those not using respiratory protection. Again, this demonstrates the need to maintain areas to as low a contamination level as possible. Thereby avoiding the use of respirators and additional contamination events.

IIIB. Personnel Internal Contamination Approximately 2909 Whole Body Counts (WBC) were performed during the 1986 refueling outage. Out of these 2909 counts, no individuals had a bonafide internal radioactive body burden which exceeded the action points requiring internal dose calculations and, no individual exceeded the Nuclear Regulatory Commission's (NRC) internal exposure limits. This is based on the amount of personnel internal contamination determined by measurement of radioactive concentrations in air together with the individual's stay time. Subsequent assessment by WBC verified that no individual exceeded any NRC internal exposure limits.

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IV. Recommendations and Conclusions  !

IVA. Recommendations 4

Based on the ALARA group's observations and the job / task leaders post job reviews of the work performed during the 1986 Refueling Outage, the following recommendations are made. These suggested improvements should be evaluated with respect to their feasibility and implemented, if determined to be reasonably achievable. It should be noted that the recommendations represent the authcr's opinion of the most beneficial recommendations to be evaluated for implementation during future Refueling Outages.

-Mockup training should be mandatory on all automated equipment to be used in high radiation fields. For processes like automated welding which may need frequent adjustments an evaluation should be made to determine if a manual method would be more efficient.

-Staging installation should be coordinated with the work party in order to avoid modifications to staging. Control of staging should be assigned to specific individuals for all installations, similar to the maintenance staging ~ coordinators.

-Channel head camera equipment should be lightweight and less bulky than that used this outage for nozzle dam installations.

Mockup training should be considered for any' channel head installations. Cameras and audio equipment should be supplied by the site to avoid having several installations and removal of equipment by different contractors.

-Investigate the feasibility of using remote fixtures for tube plugging that do not require entry into the SG channel head space.

-Mockup training for perscnnel entering the channel head should be task specific and a minimum performance criteria established for each task. Workers that can not meet the.mnckup criteria should be trained for support tasks outside the channel head.

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-Develop an attachment for ventilation on the RX stud hole l cleaning machine.

-Investigate the feasibility of using a robotic device to perform secondary SG fiberoptics inspection and foreign object retrieval.

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-Increase the use of automated weld inspection equipment for ISI inspections. Attempt to coordinate ISI in loop inspections with Outage Planning in order to schedule the majority of loop work when the loops are filled in order to take advantage of more favorable doserates.

IVB. Conclusion A total plant dose equivalent of 1506 Manrem was expended during the eighteen week outage. Nineteen projects received pre-job planning by the ALARA group and their respective job / task leaders. This report documents the radiological improvements that were implemented, describes their effectiveness and details the lessons learned. It is intended that this report will be of great aid in planning and implementing of ALARA techniques for the 1987 Refueling Outage, l

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