Text

Connecticut Yankee 1984 Core XII - XIII Refueling Outage ALARA Rept
	ML20238C373
Person / Time
Site:	Haddam Neck, 05000000
Issue date:	12/31/1984
From:	Guzallis E, Powell J; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20238C358	List: B12278, Forwards Response to Questions from 871210 Meeting Re 861124 Application to Extend License DPR-61 to 40 Yrs from Date of Issuance.Including Chronology of ALARA Programs for Haddam Neck & Millstone & Yearly ALARA Repts for Haddam Neck; ML20238C367; ML20238C373; ML20238C375; ML20238C382;
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	NUDOCS 8712300235
	Download: ML20238C373 (48)
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e CONNECTICUT YANKEE 1984 CORE XII - XIII REFUELING OUTAGE j

ALARA REPORT Prepared by:

J. O. Powell l

ALARA Coordinator and E. C. Guzallis ALARA Technician of CONNECTICUT YANKEE ATOMIC POWER COMPANY l

HEALTH PHYSICS DEPARTMENT l

Reviewed and Approved By:

l H. E. Clow, HEALTH FHYSICS SUPERVISOR l

i i

8712300235 071223 PDR ADOCK 05000213 p

PDR

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TABLE OF CONTENTS e

Page I.

INTRODUCTION 1

II.

RADIATION EXPOSURE CONTROL A.

MANFEM Totals Summary 2

B.

Major Job ALARA Review Summary 11 C.

Shielding and Exposure Reduction Techniques 37 III. RADI0 ACTIVE CONTAMINATION CONTROL A.

Personnel External Contamination 38 B.

Personnel Internal Contamination 39 C.

Airborne Contamination 39 TV.

RECOMMENDATIONS AND CONCLUSIONS 42

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l LIST OF TABLES TABLE TITLE PAGE

.1 1

MANREM Expenditures by Selected Work Groups 7

l 2

CY 1984 Refueling Outage Major Job Man-hour 8

and MANREM Summary I

3 Connecticut Yankee's Repetitive Job 10 Exposure Comparison l

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LIST OF ILLUSTRATIONS FIGURE TITLE PAGE I

Daily MANREM and MANHOUR Expenditures 4

2 Daily Cumulative MANREM and MANHOUR Totals 5

q 3

Exposure Distribution and Average Exposute 6

per Individual 4

Steam Generator #1 Th and Tc, Skirt Area 14 5

Steam Generator #2 Th and Tc, Skirt Area 15 6

Steam Generator #3, Th and Tc, Skirt Area 16 7

Steam Generator #4, Th and Tc, Skirt Area 17 l

I 8

Reactor Cavity - No Shielding 20 9

Reactor Cavity - RV Head Shield Installed, 21 Transfer Canal 10 Reactor Cavity - Pre and Post Decontamination 22 11 Steam Generator #1 and #2 Pre and Post Shielding 26 12 Reactor Coolant Pumps #1 - #4 (Composite) 31 13 Steam Generators #1 - #4 Handhole Survey (Composite) 33 14 Transfer Canal Pre and Post Decontamination 35 15 Skin Contaminations by Work Group 41

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l 16 Skin Contaminations by Body Location 42 e

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INTRODUCTION The subject of this report is-the twelfth 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, 1

L southeast of Hartford. The reactor is a Westinghouse design, pressurized l

light water system presently rated at 1825 MW thermal and 600 MW electric.

l Since achieving initial criticality on July 24, 1967, the plant has generated over 69 billion kilowatt-hours of electricity at an average yearly capacity of '3.7 percent (MDC net).

The purpose of this report is to document the majtr 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 Dutage Reports data base from 1979, 1980, 1981 and 1983.

(Note:

1982 was a non-refueling year and is documented in the 1982 Annual ALARA Report).

The benefit of this data lase is that it will cid 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 medius 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 August 1, 1984 to November 10, 1984.

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; and Airborne Contamination.

The_ Health Physics staf f handled all major radiological events without any major problems and without violating any federal radiation protection regulations. The 1984 Outage Health Physics manpower was reduced significantly from previous outages.

This necessitated more efficient manpower utilization and management.

All managerial positions in the 1984 Health Physics Outage organization were staffed with permanent CY HP personnel.

The use of dedicated CY HP Technicians as Containment, Steam Cenerator and RCA leadmen proved very beneficial in resolving problems that would have led to numerous delays and additional exposures.

II.

RADIATION EXPOSURE CONTROL o

IIA. MANREM Totals Summary A total plant dose equivalent of 1108 MAKREM was expended during the period August 1, 1984 to November 10, 1984. This total is based on a

Radiation Work Permits (RWP) - Pocket Ion Chamber (PIC) readings which were entered into the HELPORE II program.

Page 1 of 44 L __ _ _ __ _

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4 The 1984 outage MANREM total _J1 LOB MANREM) overran our 1984 outage MANREM goal _oL6,00_MANREJJ. The overrun was caused in part by the expansion of the Primary Steam Generator Inspection _(ECT 14,885/ Prof.

_660_ tubes) and the extensive tube plugging done in SG #2 (52 tubes)._

These tasks were estimated at 120 and 16 MANREM respectively and totaled 186 and 67 MANREM actual.

The Steam Generator tube null was estimated at 2][ MANREM and expended,48_MANREM.

Unanticipated tasks included RCP_(3. seal rebuild (10.5 MANREM), SG#1 foreign object sear 3h (24 MANREM) and recovery from the cavity _ seal _ failure of August 21st.

This task was broken down as follows:

Cofferdam and seal repair 50.4 MANREM; Transfer Canal Drain Modification 16.5 MANREM/; Cleanup and Insulation replacement 80.5.MANREM. The Flexatallic gasket search and retrieval expended 9.8 MANREM and valve repairs exceeded the hre-outage estimate of 29 MANREM (55.8 actual). The overruns accounted for 461.6 MANREM. Discounting these items the MANREM total would only have exceeded the original outage estimate by 7.7%.

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

Refueling MAN WKLY MAN WKLY Outace Dates Weeks REM AVG. HOURS AVG EDR 1979 1/26/79-3/12/79 6

528 88 35,700 5,950 0.0148 1980 5/31/80-8/8/80 12 1005 83 141,304 11,775 0.0071 1981 9/26/81-11/16/81 7

878 125 73,383 10,483 0.0120 1983 1/22/83-4/15/83 12 1260 105 72,665 6,055 0.0173 1984 8/1/84-11/10/84 14 1108 72 46,067 3,290 0.0240 l

Figure 1 depicts the " Daily MANREM and MANHOUR expenditures for the 1984 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 approximately 11 MANREM.

By comparison, the 1983 values for the peak period ranged from 14 to 64 MANREM per day, with an everage daily i

MANREM of approximately 14 MANREM.

]

Figure 2, the " Daily Cumulative MANREM and MANHOUR totals for the 1984 Refueling Outage," shows that over the fourteen week 1984 outage we

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expended approximately 1108 MANREM. by comparison, the twelve week 1983 outage total was 1260 MANREM.

j The breakdown of the station MANREM expenditures by work groups is shown in Table 1.

In general, 241 MANREM or 22.2 percent of the total station dose equivalent was received'by permanent CY employees, 743 MANREM or 68.4 percent by contractors and 102 MANREM or 9.4 percent by 8

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, i

Page 2 of 44

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i It should be noted here that there was a 10.3% reduction in the number of personnel employed compared to 1983.

The average exposure per individual increased from 626 MREM in 1983 to 679.8 MREM in 1984.

Considering the radiological intensity of the work performed and the insignificant increase in average exposure per individual it is evident that some progress has beer made in the effective utilization of personnel.

Figure 3 indicates the exposure distribution by dose range of the work force and gives the average of all TLD badged individuals as 680 MREM.

A listing of the CY 1984 Refueling Outage Major Job MANREM and MANHOUR Summary is in Table 2.

This listing accounts for approximately 75 7

percent of the plants outage MANREM.

(87 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 IIB.)

A compilation of the personnel radiation exposure trends for repetitive jobs conducted during CY's 1979, 1980, 1981, 1983 and 1984 are shown in Table 3.

For those repetitive jobs that have similar l

vork scope from outage to outage, the MANREM in general is trending downwards.

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TABLE 1 MANREM EXPENDITURES BY SELECTED' WORK GROUPS e
AUGUST 1, 1984 - NOVEMBER 10, 1984 1.
ADMINISTRATIVE STAPF 5.
OPERATIONS DEPARTHENT Total MA!! REM - 4.451 Total MANREM - 45.452 Plant Per. - 1.820 Plant Per. - 45.452 Contract Per. - 1.467 Utility Per. - 1.159 2.
ENGINEERING DEPARTMENT 6.
MAINTENANCE DEPARTMENT Total MANREM - 64.353 Total MANREM - 791.667 Plant Per. - 11.004 Plant Per. - 143.329 Contract Per. - 39.136 Contract Per. - 577.710 Utility Per. - 14.213 Utility Per. - 70.628 3.
CHEMISTRY DEPARTMENT 7.
QC/0A DEPARTMENT Total MANREM - 1.525 Total MANREM - 21.455 Plant Per. - 1.141 Plant Per. - 2.383 Contract Per. - 0.384 Contract Per. - 7.087 Utility Per. - 0.000 Utility Per. - 11.985 4
HEALTH PHYSICS DEPARTMENT Total MANREM - 156.786 Plant Per. - 36.081 Contract Per. - 117.418 Utility Per. - 3.287 The MANREM values are based on RWPs--PIC readings which were entered into the HELPORE program.
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Page 7 of 44
's TABLE 2 CY 1984 REFUELING OUTAGE MAJOR JOB
SUMMARY
e AUGUST 1, 1984 - November 10, 1984
)
I.,
GREATER THAN 10 MANREM JOBS ESTIMATED ACTUAL ESTIMATED ACTUAL JOB TITLE MANHOUR MANHOUR MANREM MANREM
1.
PRIMARY STEAM CENERATOR INSPECTION AND MAINTENANCE 2527 1909.36 119.8 186.636.
2 REFUELING OPERATIONS 3176 2568.87 59.6 72.455 3.
VALVE REPAIR / MAINTENANCE 1524 2185.01 29.0 55.832
4.
STEAM CENERATOR MANWAY HANDLING DEVICE 1300 1323.05 79.6 51.447 5.
C0FFERDAM INSTALLATION /
CAVITY SEAL REPATR 2460 1974.04 65.6 50.396 6.
INSERVICE INSPECTION 2314 1294.86 88.31 38.920 7.
REACTOR COOLANT PUMP
1, 2, 3 SEAL REPAIR 936 1048.55 17.9 31.466 8.
SECONDARY STEAM GENERATOR INSPECTION / MAINTENANCE 789 768.88 18.0 26.407 9.
TRANSFER CANAL DRAIN LINE MODIFICATIONS 50 237.53 4.1 16.493
10. CONTROL ROD DRIVE REPLACEMENT 80 224.36 1.9 13.345
SUBTOTALS ONLY.
INCLUDES ONLY THOSE TASKS WHICH HAD ESTIMATED MANHOURS AND MANREM.
SEE SECTION IIB FOR GRAND TOTALS.
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TABLE 2 (CONT [D)
CY 1984 REFUELING OUTAGE MAJOR JOB
SUMMARY
AUGUST 1, 1984 - November 10, 1984 II.
I to 10 MANREM JOBS ESTIMATED ACTUAL ESTIMATED ACTUAL JOB TITLE MANHOUR MANHOUR MANREM MANREM l
l 1.
FLEXATALLIC GASKET RETRIEVAL 48 158.94 4.8 9.865 2.
LOOP STOP VALVE REPAIR 132 96.07 5.7 6.640
3. PRESSURIZER RELIEF 5.552 618.77 VALVE MODIFICATION 4.
CHARGING PUMP REPAIRS 620 1071.93 5.2 5.744 5.
CORE EXIT THERMOCOUPLE SLEEVE MODIFICATION 16 22.76 6,7 1.825 6.
STEAM GENERATOR DIAPHRAGM QUARTER TURN FASTENERS 10 15.09 3.0 1.605 7.
REACTOR COOLANT PUMP l
INSTRUMENT CALIBRATION 60 63.72 1.8 1.556
Estimated as less than 1 MANREM. Design problems led to additional exposures.
Shielding was used when exposures approached 1 MANREM.
See Section IIC.
III. MISCELLANE0ilS JOBS ACTUAL JOB TITLE MANREM 1.
REPLACE INSULATION-SEAL FAILURE 68.727 2.
RADWASTE PROCESSING 54.802 3.
VENTING AND VALVING 39.448 4.
DECON CONTAINMENT 24.083 5.
SGfl WRENCH RETRIEVAL 24.160 6.
PUMP WATER /DECON-SEAL FAILURE 11.817 7.
HP JOB COVERAGE AND SURVEYS 11.050 8.
OPERATIONS BLANKET 7.284 9.
DECON RCA 5.219 l
10. SECURITY BLANKET 2.103
11. CAVITY FILTRATION 1.535
12. CHEMISTRY BLANKET' l.195
13. TRIS 0DIUM PHOSPHATE BASKETS 0.960
14. ADMINISTRATIVE BLANKET 0.952
15. DECON EAST PIPE TRENCH 0.475
16. MAINTENANCE BLANKET 0.330 Page 9 of 44
i' TABLE 3 Connecticut Yankee's Repetitive Job Exposure Comparison 1979 - 1984 JOB DESCRIPTION MANREM 1979 1980 1981 1983 1984 1.
Refueling (Disassembly / Fuel Shuffle Reassembly) 117 124 132 62 72 2.
S/C Primary Side Inspection ECT/ Prof. REM i
Tube 0.058 0.035 0.025 0.025 0.012 3.
S/G Primary Side Repair Plugging REM Plug 2.600 2.044 0.770 0.402 0.645 4.
S/G Primary Manway Removal /
Replacement REM S/G 11.755 9.060 5.865 4.699 5.977 i
5.
S/G Secondary Sludge Lance (4 S/G Total excluding equipment setup) 14.700 10.192 12.571 8.253 7.865 6.
Reactor Coolant Pump Repair i
REM RCP 10.830 10.609 9.536 8.855 10.480 l
7.
Inservice Inspection 12.681 22.869 41.582 76.903 38.920 8.
Valve Repair 25.706 8.132 16.438 41.379 55.832 9.
Cavity Filter Replacement 9.703 5.797 5.322 1.435 1.535 6.880 16.460 7.217 3.785 10.
Cavity Decon l
l 11.
Radiation Control Area Decon &
Trash 48.952 52.589 38.870 57.006 29.302 l
12.
Health Physics 42.083 189.377 222.395 216.580 156.786 l
l 13.
Operations 11.212 31.296 37.656 40.223 45.452 Page 10 of 44
4
.~
1.,.
IIB. Major Job ALARA Review Summary.
Attached are. the major ' ALARA review summaries. These.summariesi identify the' job, 31st 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 i
suggested improvements.
It'is anticipated that these summaries will be of. great aid 'in future job planning..It.in recommended that efforts begin immediately to evaluate and implement, where feasible,.
the suggested improvements so that they can be utilized during future outages.
l Page 11 of 44
A1. ARA REVIEW.10B
SUMMARY
a 1.
Job Tftle:
Primary Steam Cencrator Inspection and Maintenance SG #/s 1-4 Task Estimated Actual Estimated Actual Manrem No.
Task Title Manhour Manhour Manrem Manrem Diff 1.
General Preparations 223 66.75 4.200 3.445 18%
(4 SG) 2.
Remove / Replace Manways 304 190.64-19.000 23.907 26%
Set-up/ Remove ECT 3.
Equipment 400 354.52 21.600 28.148 30%
ECT/ Profilometry (ECT 4.
14885/ Prof.600T 1600 1107.22 75.000 126.723 69%
Mechanical Tube Plugging 67.059 547.72 5.
(52 Tubes) 6.
Tube Pull (2 Tubes) 150 543.27 20.000 47.755 139%
3.413 74.30 7.
CCT Shielding Sub-Total
2527 1909.36 119.8 185.636 55%
Grand Total 3000.35 300.45
Sub-Total excludes manhours and manrem from task #5 Tube Plugging and task #6 Tube Pull.
i l
)
i Page 12 of 44
o s
ALARA CONTROLS UTILIZED Shielded drum for diaphragm storage; hydrogen peroxide flush of primary piping with fon exchange cleanup; S/G ventilation sytems; skirt herculite shroud; S/G jumper pens; jumpers to have mock-up training; tied of f and inventoried equipment going in and out; located eddy current readout in a low dose rate.
area; used automated ECT and Profilometry equipment; utilized mechanical tube plugging and audio and visual communication on jumpers and attendants.
Shielded manway openings during ECT/ Prof, and probe change evolutions.
EFFECTIVENESS OF ALARA CONTROL _S.
The ALARA controls were adequate. The use of a dedicated HP leadman proved to be very effective.
Skirt shourds and custom made bullpens were not replaced after the cavity seal failure. Bullpens consisted of roped off/herculited area.
No increase in airborne' radiation or surface contamination Icvels in the loop areas were experienced.
Manway shielding was utilized for ECT/ Prof. probe changes after increasing inspection requirements to a 100% inspection of tubes.
Shielding cost 3.445 MANREM to install and remove and lowered platform dose rates by approximately one-half saving an estimated 15 MANREM (Information obtained from platform jump tickets).
SURVEY DATA See Figure 4, 5, 6 and 7 Suggested Improvements Investigate the feasibility of using remote ECT fixtures that do not require entry into the SC channel head space.
Investigate the use of mechanical manway shields for use with present ECT equipment to lower the platform dose rate for probe changes. Redesign the present steam generator ventilation rystem and purchase additional fodine removal units as necessary to eliminate the extensive temporary ducting and common exhaust header now used.
Investigate the feasibility of a hard duct permanent ventilation system.
Investigate the feasibility of semi-permanent contamination control barriers (bullpens).
Improve SG mockup training by making the mockup more realistic: height of manway from jump platform, space limitations on the jump platform and include manway shielding techniques.
Include video tapes of actual SG entries "1984" for jumper training. Improve housekeeping in the jumper pens and skirt areas.
I Page 13 of 44
i o *
?
CCMPOSITE SURVEY oesni REvm gTLAttGENEAATOAe Rwe seO.
CoNTRot NO oAig giug estWIT AREA ONE Cow-e R ASON Fon SURVEY.
TLCHNICIAN ROUTINE (O. W. W)
PRE-JOS POST.JOS AAO(ATION CONTA4flNATION lF lM le WST TYPE Teletector WST TvPE WST TvPE SERIAL NO SERIAL NO SERIAL NO PROSE TYPE PROSE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL 00E DATE DOSE RATE RE ADWGS ARE IN WREMMR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED CIRCLED NUuBERS h WDICATE SWEAR LOCATIONS CIRCLED SWEAR LOCAYtONS AND NUMBER WDICATE CONTAMINATION LEVELS IN DPW100CM'
. ntAoWas of TRaNatE/\\.No.CATE NEutnoN nAoiAviOu W uREwm AT =Aest tevet w waxiuuu RAoiAfioN.
uAxiuuu CONTAMINATION -
All readings in RDf/Hr.
l T
T' C
h t
Contact Channelhead 31 10, h
/
[
g 3
l g
-\\
f' ft
/
18" from
\\
20 25
,/
,/ l,,/
s Channelhead N
s f
's - -i
p. '-
N
\\
l j
1 flush w/ plane of l
manway shielding I
7 0
open manway l
not utilized I
i
/
1 e
i 1
0.6 1.5 18" from manway 1ll l Q H'?
1::
=
l T ; ". ' u inii iiiiin l
i i l ', ', L
/
' U h+,, --,,,
_x__
s s
n ~_
I s
l 0.8
/
0.150-0.300 t Contact
/
u -:
-. u.
=
s,, '
h
=:
.=
s f
Q:l '
3
a

)
M
=
' h..m a o
O alt SotARS tESS T AN,oco o,,oo C,
0,,, OP ALL SuEARS LESS TNAN,o o,.,oo e.,.
HEALTN ewYSiCS $ueERvtsoavoESeoNEE Page 14 of 44
i i
COMPOSITE SURVEY
,,y w STEAAI OtiRRATOR e RwPNo CONTROL No DATE TowE emRT Ansa TWO com-4
$0N POR SURVEV.
TECHNICLAN ROUTINE 80 W. W)
PR E-JOB POST-JOS RADtAT1000 CONTA400MATIOtt l
la in I.
INST TYPE Teletector eNST TvPE INST TvPE
[
SEIIAL NO SERIAL NO SER6AL NO f
PROSE TvPE prose TYPE PROSETvPE
(
CAL DUE DATE CAL. DUE DATE CAL DUE DATE DOSE RATE READINGS ARE IN WREnAum AT WAIST LEVEL UNLESS OTHEAwtSE SPECIFIED.
CIRCLED NUwSERS hlNDICATE SWEAR LOCATIONS CIRCLED SMEAR LOCATIONS AND NUW8ER @ $000) INDeCATE CONT Au NATs0N LEVELS IN DPW/100CM'
. READmos assoc TRtANoLEAmocaTt NeutnoN mADiATion a wREumn. At wast Lavec c
uAxiuuu RADiAT ow -
u Ariuuu CoNTAwiNArtoN.
All readings in REM /Hr.
T T'
C h
l Contact Channelhead 40 25
/
\\
,g g
e' fl
/
18" from 20 20 /
/ l e/
Channelhead
\\
s N
s f
f
'~1 p/
N I
(
flush w/ plane of general area l
l 8
7 e
open aanway post shield on
/
platform i
1.5 0.750 1
18,, from manway 0.500-0.700 l
G ;^,i, I
11 1 J
lll r
m s
,,1 1
I M \\lII1 1 'r lll
\\ \\ \\ \\ \\ \\ \\\\
g 1
/
di' i l l lI $ $ 'u 4*
/
g,
_ i
_. L_
f 0.350 1
0.100-0.200
)
l Contact /
G.
l i
/
a-
~~~~
GL Ef
. i t".
%A
/*
=:.
m
=:
=
s 7!1
..T
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111
'11
)
111,
, =
Y
[
Edmuu W l
1 l
9 ALL SWEARS LESS THAN 1000 DPM/100 CM'M 2% OF ALL SuEARS LESS THAN 20 DPM/100 CW' e MEALTM PMVS4CS SUPERvtSOR/ DES 4GNEE Page 15 of 44
]
l e
COMPOSITE SURVEY m, Rev m STEAM OE80ERATOft e RwP NO CONTROLNo DATE Tast SIEIRT ARaA THREE cose-4 m
w ORSURvEY TECmCm ROUT 8NE (D. W. W)
PRE-JOS POST-JOS
%ADIATION C00tTAasfMATIOtt lM lM le INST TYPE TeleteetOr INST TYPE INST TYPE SER4AL NO SERIAL NO SER1ALaso PROSE TYPE PROBE TYPE PROSE TYPE CAL. DUE DATE CAL DUE DATE CAL. DUE DATE DOSE RATE REA08NGS ARE IN WREM/MR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED CIRCLED NUMBERS h WDICATE SWEAR LOCAftONS CIRCLED SWEAR LOCATIONS AND NUuBER R #NDICATE CONTAMINATION LEVELS IN DPM/100CW'
. nEADeNGs NG8DE TMANGLEb8MDeCATE MEUTMON RADeATION W MRErn AT WAsST L8WEL
:.c.-
uAziuuu Raoi ATION.
uAxiuuu CONTAuiNAfioN.
All readir.gt in REM /Hr.
T T'h
/
Contact Channelhead 34 30 g
d
\\
,g f'
fl
/
18" from
-N y
2_2 g
/ l '/
channelhead
\\
-f
\\
's,~~'i t
,e
/
a y
p d
t flush w/ plane of l
I l 0
8 e
open manway 1
/
\\
general area 2.5 0.700 1.5 18" from manway post shield on f
platform II!!
' 4 ", ",1 f
0.300-0.700 lllI
,.$ il,,
=
a n' g
s s
~-_
T,
l ', ', l ', ', "
/
J.
_ ~
s i
0.300 j
(4 l
,/
0.100-0.250'
,c* '
Contact
{
-c'
. % s $l*%
Ql
'b.
=:-
2
^ ~k 5hllll
,1 5 4
. r_-
TI
.L~
' IdmLu W e
e ALL SWE ARS LESS THAN 1000 DPW/100 CW M 26% OF ALL SMEARS L ESS THAN 20 DPM/100 CW e HE.?.LTM PHYSsCS SUPERVISOR /DEStGNEE Page 16 Of 44
_____.____-________m_
. t I
COMPOSITE SURVEY a,3,,,
.,y STEAtt GENERATOR e RWP eso CONTROL *so oATE TsuE SENITAREA FOUR com-a Al ces 7on SURvEv TECHNsCIAN L
ROUTiteE 10. W. W)
PRE-JOS POST JOS RAOSATION CONTAMINATION lW lW
\\e
NST YvPE Teletector msf TYPE mST Tvet
~
^
SEmiAL No SERIAL No SERIAL No PROSE TYPE FNott TYPE PROSE TYPE CAL DUE DATE CAL DUE DATE CAL. DUE DATE DOSE RATE READINGS ARE IN uREu.tfA AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED.
CIRCLED NUuBERS h INotCATE SuEAR LOCATIONS CRCLED sue AR LOCATIONS AND NUuBER E 5000) INDICATE CoNTAutNATION LEVELS IN cpu /100CW 8
. REAomos assoE TAueoLE/\\meneCATE NEUTRON RA06AftON m uREAMWL AT WAST LEWSLM -
uAxiuuu RAoi AtioN.
uAxiuuu CoNTAviNAfioN
All readings in RDf/Br.
T' C
h Contact Channelhead 35 25 l
I
,y 20 e'
/t
/
18" from h
~30 g
/ l '/
~'
Channelhead
\\
f
\\
/
/
l
'i p_/
N 8
8 l
j flush w/ plane of j
l 5
12 s
open manway l
,1 l
1 general area 2
post shield 0.700 1.5 18" from manway i
M b M__ f
-- 7
. i 1
d.-
m p
m 1
h
,/
0.30c
<4p j
i Contact /
0.200-0.300 g/-
f - 0.
.. *, f ;*m
/,./**
5!
5:
}
=;.
=_
=.
' u d m u u JP n
e ALL SWE ARS LESS THAN 1000 Deu/100 Cw M 25% OF ALL SufARS LESS THAN 20 OPu/100 CW e MEALTH PMySsC$ SUPERytSoR/ DES 8GNEE Page 17 of 44
.. ~
ALARA REVIEW JOB
SUMMARY
II.
Job
Title:
Refueling Operations Core XII-XIII Task Estimated Actual Estimated Actual Manrem No.
Task Title Manbour Manhour Manrem Manrem Diff.
1.
RV Head Dissassemb1v 140 109.33 4.100 6.092
'49%
Remove / Store Trans.
2.
Tube Flange 26 12.68 1.000 1.645 65%
3.
RC Stud Detension 255 233.45 8.500 12.209 44%
4.
Cavity Prep.
162 173.38 4.300 4.384 2%
5.
Internals Removal 77 112.42 0.400 1.365 241%
6.
Fuel Shuffle 1260
_ 972.98 3.900 3.390 137 7.
RV Head Preparation 30 114.53 1.400 5.260 276%
8.
Internals Installation 220 119.25 1.100
.620 44%
9.
Replace RV Head 40 72.80 3.000 3.115 4%
10.
Cavity Decon 125 89.77 4.300 3.785 127 11.
RV Stud Tensioning 554 380.26 10.800 16.740 55%
12.
Remove Cavity Seal Ring 35 31.67 1.000 1.965 97%
Install / Transfer lube 13.
Flange 19 14.67 1.400 1.810 29%
14.
Reassemble Rv Head 233 131.68 14.400 10.075 30%
15.
Miscellaneous 275.86 12.753 SUBTOTAL
3176 2568.87 59.600 72.455 22%
2844.73 85.208 GRAND TOTAL s
SUPTOTAL exc3udes manhours and manrem from task *15 Miscellaneous.
Page 18 of 44 g
ALARA REVIEW JOB
SUMMARY
II. (Cont'd)
ALARA CONTROLS UTILIZED Temporary reactor vessel head shield; personnel shields; water to. railing'in transfer canal; shielded deck and rails of manipulator crane bridge; permanent plexiglass shield on manipulator mast; flushed crud in seal plate crevices; deconned head flange and cavity. seal plate; portable ventilation in cavity; charging floor modular enclosure; stud cleaning machines and associated ventilation; herculited around stud racks; underwater cavity filtration / vacuum system.
EFFECTIVENESS OF ALARA CONTROLS Reactor Vessel Stud Detensioning expended 3.7 MANREM more than expected. This expenditure was due to the improper installation of the Reactor' Head Shield, which was later corrected.
Stud Tensioning was also higher than expected (5.9 MANREM) due to having to perform an extra tensioning pass.
It is estimated that the Reactor Head Shield saved ~12.5 MANREM and cost 1.4 MANREM to install and remove. Shielding was not used on the cavity seal plate and vessel flange drip tray, no elevation in dose rates was observed when compared to 1983. data.
Adding 2 ft. of water to the transfer canal-during blind flange removal and replacement saved ~3 MANREM. -Miscellaneous activities included repair of the Fuel Transfer Cart, which expended 9.3 MANREM.
Cavity ventilation was adequate, an airborne contamination incident occurred on August 18th from aggressive cleaning of cavity seal flange. Work was later completed with the flange wet.
Post drain down cavity decontamination (3.8 MANREM) using the Kelly vacuum system did not lower contamination levels as much as expected.
SURVEY DATA Sec Figures 8, 9 and 10.
SUGGESTED IMPROVEMENTS Cavity seal ring is labor intensive to install due to modifications.
Cavity-seal should be reevaluated for design.
Increase and improve worker briefings for high risk evolutions e.g., blind flange evolutions. Tool list should be required and tools accounted for prior to entry. Transfer cart should have-extensive maintenance performed.
Evaluate method for decon of transfer canal in support of the above.
Instructions as to placement of modified hanger for reactor head shield to be included in ALAP.A controls.
Reevaluate cavity.decon.
methods, Kelly Vacuum System versus strippable paint, lower contamination levels af ter decontamination may justify the higher exposure received using strippable paint.
'l Page 19 of 44' J
.e OP3271 REV9 83 t
REACTOR CAVITY AND RWP NO, CONTROL NO DATE TIME FUEL TRANSFER CANAL CON-s 8/13/85 HEASON FOR SURVEY TECHNICIAN REACTOR POWER g
ROUTINE (D. W. M1 PRE-JOB POST-JOB l
RADIATION CONTAMINATION i
lar In Isr I.
(
INST TYPE INST. TYPE INST. TYPE INST. TYPE
[
SERIAL NO SERIAL NO SERIAL. NO.
SERIAL NO P
PROBE TYPE PROBE TYPE PROBE TYPE PROBE TYPE l
CAL DUE DATE CAL DUE DATE CAL DUE DATE CAL DUE DATE DOCE RATE READINGS ARE IN MREM /HR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED.
CIRCLED NUMBERS h lNDICATE SMEAR LOCATIONS CIRCLED SMEAR LOCATIONS AND NUMBER @ $000) INDICATE CONTAMINATION LEVELS IN DPM/103CM' a
[
RE ADINGS INSIDE TRIANGLEblNDICATE NEUTRON RADIATION IN MREM /HR. AT WAIST LEVEL l
--> N l
NO SHIELDING l
g u w w w 100 100 i
200 200 200 500 1
i 800 300 1R g
REACTOP 300 HEAD l
i 600 l
l l
300 200
\\
\\
150 100
/
"w e
,=
a=a
~
ALL SMEAAS tESS THAN 1000 DPM/100 CM' #7 25% OF ALL SME ARS LESS THAN 20 OPM/100 CM' e HEALTH PHYSICS SUPERVISOR / DESIGNEE Page 20 of 44
}
I 4
OP3221 REV &83 REACTOR CAVITY AND RWPNO.
CONTROL NO.
DATE TIME FUEL TRANSFER CANAL CON-8 8/15/85 REASON FOR SURVEY-TECHNICIAN REACTOR POWER
~
ROUTINE (D. W. M)
PRE-JOB POST JOB RADIATION CONTAMINATION lar la lar 1
INS T. TYPE INST. TYPE INST. TYPE INST. TYPE STRIAL NO SERIAL 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 E
CIRCLED SMEAR LOCATIONS AND NUMBER @ 5000) INDICATE CONTAMINATION LEVELS IN DPM/100CM'
READINGS INSIDE TRIANGLE INDICATE NEUTRON RADIATION IN MREM /HR AT WAIST LEVEL
--> N HEAD SHIELD j
f INSTALLED w w "w
5.0 100 180 NO SHIELDING 300 200 300 1R 300 Note: Readings 100-150 mr/hr general area after REACTop HEAD head Shield installed
'I J
e 1
250
~
l 1
-~
1 120 100 E
\\
s
\\
120
-80
~
Transfer Canal prior
/
800mr/hr -
to f100d-up 1.5 R/hr_
Drain 100 R/hr,
8 R/hr GA Transfer Canal water level at top Of rail for Blind Flange Removal 50 R/hr
- L 2.5 R/hr General Area Contact
-15 R/hr underwater
~
~
-500-700 MR/hr General Area ALL SMEARS LESS THAN 1000 DPM/100 Cue #7 25% OF ALL SME ARS LESS THAN 20 DPM/100 CM' e HEALTH PHYSICS SUPERVISOR / DESIGNEE Page 21 Of 44
.y__.,._.,__
.. _, ~~.,,._.,._,...,.;,, _._.-,..- _.,.., _ m.
OP3271 REV 9-63 lCONTRO.NO Pre DATE AU/14/b 41ME UZUU RWPNO CAVITY WALLS cou_
Post 10/15/84 1515 Af A50N F OR SURVE Y TECHNICIAb ROUTINE (D W. M)
PRE JOB POST JOB RADIATION CONTAMINATION ler ler lo (NST TYPE INST TYPE INST TYPE f
SERI AL NO SERIAL NO SERIAL NO PROBE TYPE PROBE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE j
DOSE RATE READINGS ARE IN MAEM'HR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED I
CIRCLED NUMBERS h INDICATE SME AR LOCATIONS CIRCLED SME AR LOCATIONS AND NUMBER INDICATE CONTAMINATION LEVELS IN DPM/,00CM' s READINGS INSIDE TRIANGLE INDICATE NEUTRON RADIATION 1N MREM'HR AT WAIST LEVEL MAXIMUM R ADI ATION -
M AxiMUM CONT AMINATION -
SOUTH WALL S' FROM CAY. FI,00R 15' F ROM CA V. F LOCR 10' F ROM CA V. F LOOR 5' FROM CAV. FLOOR
)
1r 15' 19h' g
g 23 $h,g O
l 9
WEST WALL 12' h 15' NORTH 2r O M M
v s
v NORTH WALL PRE POST PRE
' POST PRE POST PRE POST 1 613 MRAD 30 K 6
180 MRAD li 176 MRAD 60 K 16 6 RAD 70 K 2_ 11 RAD
.130 K 7 32 RAD 4 RAD 12 20 MRAD 17 14 RAD 20 MRAD 3
286 MRAD 40 K 8
50 K 13 2 MRAD 88 MRAD 18 100 MRAD 4
15 _ RAD 80 MRAD 9
48 MRAD 14 218 MPAD 200 K 19 14 RAD 240 MRAD 5
143 MRAD 100 K 10 2 MRAD 4.8 RAD 15 80 MRAD 20 32 MRAD D Alt SME ARS tESS1 A~,ooo D M,oo CM,,7
,ss o, AtL SME AnS L ESS 1NA~,o o,M,,oo CM,.
HE ALTH PHYSICS SUPE RvtSOR/DE StGNE E Page 22 Of 44
=
4 ALARA REVIEW JOB
SUMMARY
III. Job
Title:
Valve Repair / Maintenance t
Task Estimated
Actual Estimated
Actual Manrem No.
Task Title Manhour Manhour Manrem Manrem Diff.
Inspect and/or 131.83 2.575 1.
Repair PM Valve 0.020 4.43 2.
Operations Remove / Test 152.87 6.020 3.
Reinstall 16.287 324.78 4.
Repack / adjust Replace gasket /.
28.702 1427.18 5.
leak repar Install a new 6.
valve 143.92 2.228 Total 1524 2185.01 29.000 55.832
Because of uncertainties in the number and scope of valves to be worked on, en accurate estimate of manhours and manrem could not be determined by Maintenance.
The estimates used for tracking purposes was therefore obtained by averaging 1981 and 1983 data.
ALARA CONTROLS UTILIZED Maintenance to inform HP at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in advance to allow for proper job planning; one maintenance person to coordinate work; insta]Ied shielding on numerous pipes and valves; maximized use of power tools; flushed lines or removed valves to low dose rate area whenever possible.
EFFECTIVENESS OF ALARA CONTROLS i
ALARA controls were adequate.
More coordination between Maintenance and Health
]
Physics /ALARA for daily work load planning is indicated.
Personnel installing 1
shielding should be instructed as to proper methods of installation to enhance its effectiveness.
Exposures increased in 1984 due to the number of valves worked and areas in which work occurred i.e., Rx Head, Loop Bypass Lines.
SUCCESTED IMPROVEMENTS Mockup training for the insto11ation of shielding for varying configurations; investigate use of PMMS scheduling system for advance notification of valve daily work load to HP/ALARA for planning purposes.
1 Page 23 of 44
ALARA REVIEW JOB
SUMMARY
IV.
Job
Title:
Steam Generator Manway Fandling Device Task Estimated Actual Estimated Actual Manrem No.
Task Title Manhour Manhour Manrem Manrem Diff.
1.
Area Prep.
104 101.89 6.370 4.264 33%
Remove old equip.
2.
modify platform 128 323.79 7.830 8.302 1%
Install new 3.
platform 680 500.79 41.620 19.682 53%
Install Handling 4.
Device 100 233.85 6.120 13.634 123%
Install / Remove 5.
Shielding 100 47.18 6.120 2.670 56%
Decon SG 6.
Skirt Area 72 44.35 4.410 1.525 65%
7.
Area Cleanup 116 71.20 7.090 1.370
- 8Q7 %
Pepair Manways 395.23 5.030 SUB-TOTAL 1300 1323.05 79.560 51.447 353%
GRAND TOTAL 1718.28 56.477
Unplanned task for which no estimate was made.
ALARA CONTROLS UTILIZED Mock-up training-platforms assembled outside of RCA; decontamination of SG skirt area and floor beneath lower grating; bu11 pens outside of skirt area for contamination control; shielding of cold leg piping inside skirt; mechanical manway shields SG 1 and 2 - SG 3 and 4 modifications performed with manways in place; HEPA equipped ventilators utilized during drilling of baseplate holes and cutting torch / welding operations; additional lighting as needed.
I l
l i
1 Pege 24 of 44 1
E I
EFFECTIVENESS OF ALARA CONTROLS L
I Mock-up traininF proved to be of great value not only for assembly of the platforms but' also in resolving alignment problems., Shielding of the cold leg l
. piping proved to be of minimal value, caused interference problems during l'
handling device alignment and was subsequently deleted from' controls for work on SG 1 and 2; mechanical manway shields. worked well and saved an estimated 9 NANREM; bu11 pens proved to be. restrictive for ingress / egress of personnel and material and were replaced'with herculite laydown area; ventilation was l
adequate, no significant airborne contamination incidents occurred during work evolutions.
' SURVEY DATA See Figure 11 SUCCESTED IMPROVEMENTS Controls for similar construction work should consider material transfer access requirements. Construction wntk inside the skirt areas not requiring manway removal should be done with manways in place and the loop piping full; shielding of open manways should be done using mechanical shields which maximize efficiency due to the ease of installation.
t I
l l
I Page 25 of 44
_. ~.
COMPOSITE OP3221 REV 9-83 STEAM GENERATOR 3 RWPNO CONTROtNO DATE TIME 1
SKfRT AREA 1 and 2 cca-s j
i.Chr?iCIAN RE ASON FOR SURVEv lf gggg X
ROUTIME (D W. M)
PRE JOB POST-JOB RADIATION CONTAMINATION
\\er I;r I.
INST TYPE leleteClOr INST TYPE INST TYPE SERIAL NO SERIAL NO SERIAL NO PROBE TYPE PROBE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE DOSE RATE RE ADINGS ARE IN MREM /HR AT WAIST LEVEL UNLESS OTHEPWISE SPECIFIED CIRCLED NUMBERS h INDICATE SMEAR LOCATIONS CIRCLED SME AR LOCATIONS AND NUMBER INDICATE CONTAMINATION LEVELS IN DPM'100CM'
READINGS INSIDE TRIANGLE INDICATE NEUTRON RADIATION IN WHEM/HR. AT WAIST LEVEL M AXIMUM RADI ATION.
MAxlMUM CONTAMINATION =
SG #1 SG #2 All readings in R/hr 1
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ALL SME ARS LESS TH AN 1000 DPM/100 CM' #7 25% OF ALL SME ARS LESS THAN 20 DPM'100 CM'o HEALTH PHYSICS SUPERvtSOR/ DESIGNEE l
Page 26 Of 44 J
l 1
l ALARA REVIEW JOB
SUMMARY
l V.
Job
Title:
Cofferdam / Seal Repair Task Estimated Actual Estimated Actual Manrem No.
Task Title Manhour Manhour Manrem Manrem Diff.
(
Equipment 1.
Setup / Seal Mod.
1120 1411.19 32.000 39.111 22%
Disassemble Old Seal 2.
/ Install New Seal 320 62.93 17.920 1.650 91%
l Inspect 3.
Pool Seal 40 34.84
.320
.420 31%
4.
Decon Seal Ring 80 30.66 4.480
.180 90%
Install / Modify /
5.
Cofferdam 900 434.42 10.830 9.035 17%
TOTAL 2460 1974.04 65.550 50.396-
.23%
ALARA CONTROLS UTILIZED 1.
Cofferdam - Workers experienced in bi-metal welding utilized; water-stop to be welded on cavity side only. Fabrication of waterstop to be performed in low dose rate area on charging floor; HEPA ventilator and tent used in cavity for grinding of weld area.
2.
Cavity Fool Seal Repair - Strippable paint used on seal plate for decontamination; ventilated tent used for insertion of reinforcement pins in rubber seals. Reactor head shield; minimize time spent in cavity.
EFFECTIVENESS OF ALARA CONTROLS ALARA controls were adequate.
Problems were encountered using strippable paint on secondary seal pieces.
Problems also encountered with fit up of secondary seal due to close tolerances required.between secondary seal and cavity floor, which required installation of knife edges.
SUGGESTED IMPROVEMENTS Workers should be made aware of proper appifcation of strippable paint for ease j
of removal and bonding which can take place on newly painted surfaces.
Redesign of the entire cavity seal should be considered due to the close tolerances required, labor intensity of installation and the greatly increased time required for installation in a high radiation area.
9 Page 27 of 44
d 4
ALARA REVIEW JOB
SUMMARY
VI.
Job
Title:
Inservice Inspection Task Estimated Actual Estimated Actual Manrem No.
Task Title Manhour Manhour Manrem Manrem Diff.
NDE Class I & II 1.
piping /supp.inspec.
1450 460.06 55.100 10.700 80%
2.
Snubber inspec.
360 70.31 14.080 2.940 79%
e
?
Cont. Air Recire.
0.175 54.17 3.
Fan Inspection Vibration j.
4.
Measurements 10 43.01 0.220 0.481 119%
l Hydrostatic leak 0.310 1.00
S.
Test SG #2 Reinsulation of 6.
SG #1-4 450 587.86 18.000 23.444 30%
Instrument repair 26.94 0.100
7.
calibration RCP Flywheel 8.
inspection 44 51.51 0.910 0.770 15%
I GRAND TOTAL 2314 1294.86 88.31 38.920 56%
l
Additions to work scope for which no estimate was performed.
l ALARA CONTROLS UTILIZED Utilize experienced workers for job ef ficiency; welds, valves, snubbers and piping marked, tagged for easy identification; setup and calibrate test equipment in low dose rate area; HP to survey prior to start of work; RCP flywheel to be removed to charging floor for inspection; ALARA to evaluate shielding on a case by case basis; all test equirnent to be wrapped in plastic; worklist to be forwarded to ALARA prior to the start of outage; Maintenance to erect all staging; weld preparations to be performed as per ISI procedure.
EFFECTIVENESS OF ALARA CONTROLS ALARA controls fur ISI work were very general in nature. This is due to the numerous locations worked and the generally low amount of manhours spent in one location. The ISI worklist was submitted well in advance of the outage which was very helpful in prejob planning.
Respirator requirements were less restrictive in most areas of containment in comparison with previous outages and helped in reducing exposures especially in snubber inspections.
Exposure estimates were based on 1983 workscope, of.which approximately 25% was performed.
It appears that the ISI workscope will remain constant at this 1
level.
]
I SUGGESTED IMPROVEMENTS j
Review worklist prior to start of outage for veld inspection areas and possible shielding placement. Area decontamination should be performed as in the 1984 j
outage to keep respirator requirements to the least restrictive level possible.
Page 28 of 44
~a
.a.,
ALARA REVIEW-JOB
SUMMARY
VII. Job
Title:
Reactor Coolant Pump Seal Inspection / Replacement Task Estimated Actual Estimated Actual Manrem-No.
Task Title Manhour Manhour Hanrem Manrem Diff.
Seal Inspection /
1.
Replacement 35.8 440.82 8.010 14.918 176%
1.413 78.08 2.
Seal Repair Aux. Piping and 3.
Elec. Conn. Rem /k6p.
52 9.84 1.530
.645 58%
Motor Replacement /
4.
Algn.
162 255.32 2.900 7.785 168%
Motor Removal /
5.
Decon 242 174.57 3.300 3.335 1%
6.
Miscellaneous 122 89.87 2.200 3.370 53%
. Total 936 1048.55 17.940 31.466 75%
ALARA CONTROLS UTILIZED Areas to be surveyed to identify hot spots that warrant shiciding; herculite bullpen to be set up along railing and over grating; HEPA filtered containment to be used to decon small parts; utilize cleaning solution with low volatility characteristics; ensure seal water valves are shut to prevent excessive leakage; divert ventilation air flow fr.3 the work area; restrict traffic in the work area; work to be performed with nearest SG in wet lay-up; video tape training of past RCP rebuild to be utilized.
EFFECTIVENESS OF ALARA CONTROLS Estimate based on seal replacements on RCPs 1 and 2 only. RCP 3 seal was also replaced. REM /RCP showed an 18% increase over 1983 exposure levels. Effective dose rate increased 667. Major cause was increased general area dose rates on the grating level resulting from hydrogen peroxide crud burst and curtailed I
cleanup.during the early stages of the outage.
Although the major hot spot in the pressurizer surge line was flusbrd out, it became evident that much of the material was dispersed throughout the reactor coolant system.
SG when not in wet lay-up increased general area dose rates by a factor of two, t
Page 29 of 44 L
SURVEY DATA See Figure 12 SUCCESTED IMPROVEMENTS Investigate shielding the railings of RCP areas in an attempt to minimize background radiation from other sources.
Minimize time spent deconning parts in immediate area, remove parts to modular unit on charging floor.
Continue to work RCP only when nearest SG is in wet lay-up.
Maintain RCS clean-up for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after hydrogen peroxide addition.
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l Page 30 of 44 i
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COMPOSITE SURVEY I
m REvo-as flACTOR COOLANT PUMP RWP NO.
CONTROL NO DATE TIME CON-12
,. ASON FOR SURVEY' TECHNICIAN REACTOR POWER ROUTINE (D. W. M)
PRE-JOB POST JOB RADIATION CONTAt$1 NATION l
ler la ler I.
INST. TYPE INST. TYPE INST TYPE INST TYPE l
SERIAL NO SERIAL NO SERIAL NO SERIAL NO.
PRO'E TYPE PROBE TYPE PROBE TYPE PROBE TYPE l
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 @ $000) INDICATE CONTAMINATION LEVELS IN DPM/100CM8 e READINGS INSIDE TRIANGLEhlNDICATE NEUTRON RADIATION IN MREM /HR. AT WAIET LEVEL SURVEY TAKEN AFTER MOTOR WAS REMOVED 53 MR/HR M
MM I
I T
75 MR/HR 150 MR/HR 100 MR/HR c, -
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9 ALL SMEARS LESS THAN 1000 OPur100 CM' #7 25% OF ALL SME ARS LESS THAN 20 DPM/100 CM' e HEALTH PHYSICS SUPERVISOR / DESIGNEE Page 31 Of 44
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SUMMARY
'e n
9 V111. Job
Title:
Secondary Steam Ge.u.rator Inspec tion /MMuter ance j 1
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Task Estimated t.c ;ual
, Estimated Agtxal fanrem No.
Task Title Manhour Mnhour Manrem Mar t t4 Offf.
l Rem / Rep.handhole 1..,
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1.
covers /manw.
85 7 0.'94 2.98J 5.702
-9 C !
11. 3 Mf',
'/. 865 '
11%
J /
2.
Sludge Lancing 569 406.27 j,
Set-up/ Breakdown 3.
Equip.each Gen.
100 183.69 2.100 2.420,
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Photo Flowslot of s
4 Fiber-Optic Insp.
35 80.08
.?._. 3 5 0 7.060
-200%
I
3. 3,6_0, 28.50,
S.
Handhole Repairs TOTAL 789 768.8$
18.820 2,6.407
' 40%
Unplanned task for which no estimate var raue.
ALARA CONTROLS UTILIZE.D-g Communications established between work plat ferra and traier; shielded local hc*
,l spots; all hose and cables entering loeps t; be sleeved; s'.ugge lance qu_pment I
to be leak tested at operational pressure: h eculiced area under fi'*.n tra?ler and laydown area for filter Crums; opewtcr centrols 12 be setup.,ir a2'bv dos,9
j, j
rate area; avoid handhole aras as mucN as possible; ei edite hand oh! cover 9
replacement and flooding of secondaiy aide followinp iyipecticos; hardhole covers to be loosely attached for shielding when sc,rk as not 11 prggress.;
EFFECTIVENESS OF ALARA CONTROLS i
The ALARA controls were adequn a Bypass lines were shicided. Handhole cover t
removal and replacement and fibet optica' inspection exposures were higher that expected due to a significant :.ncrease in dose rate levels when compared to l g 1963.
f r
SURVEY DATA 1
.t See Figure 13 f i
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i SUGGESTED IMPROVEMENTS b
u Investigatethepossib.'.11tyofperformingsecondarySGffpultionwhenthe primary side is full.
2PRI RP825-2 interim report O t a t uggests that dosetate l
reduction up to 30% may be possible.
Investigate shielding,M area / surrounding handholes to lower exposure brine, removal and replacement. " Ensaret afterence to j
establish staytimes for foreign object retrieval.
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-l COMPOSITE SURVEY oesni REv s.a3 q
RwrNo CONTROL wo oATE lTiuE' STEAM GENERAT0m cow-e
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(SIDE VIEW)
HANDHOLE S(*#NEY 1
~ ' ~ '
R SONFORSURVEY.
TECHNICIAN ROUTINE (D w. W)
PRE. JOB POST JOB I
RADIATION CONTAttlNATION P
i, i,
i.
1 1._
j 8NST TYPE eNST. TYPE INST. TYPE i
j SERIAL No SERIAL No
_l SEPrAL No
- Y f
,g; J-
'T y pro 8E TYPE pro 8E TVPE '
pro 6E TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE l
')
.I DOSE RATE READINGS ARE IN WREM/HR AT wAtST LEVEL UNLESS OTHERwlSE SPECIFIED i
CIRCLED NUWSERS h INDICATE SMEAR LOCATIONS cimetED $utAR LocA iowS AND NUusER CM INDICATE coNTAuiNAvioN LEVELS iN DPwioocw l
. nEADeNos wesioE TmANotEAmscucATs NEutMN RADeATION M WREWHR. ATWAST LEVEL.
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us t wruu cont AMINATION,
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18" - 4 R/Hf }'RESilIE1J.)
INSIDE CENERATOR 18" 500,mr/Ilr POSTSilIELD l
91 R/Hr @ 3 ft.
]
ERAR*" ole 2 - 7R/Hr 67 R/Ilr @ 2 ft.
i 36 R/Hr @ 3 in.
amo ttytL
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,i. y ALL SWEARS L ESS TH AN 1000 DPM/100 CW'M ~
25% OF ALL SMEARS L ESS THAN 20 OPM/100 CW e MEALTM PHYSICS SUPERv4SOR/DEstoNEL
~~~
j Page 33 of 44 L________t____________._
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4 3)..
ALARA REVIEW JOB
SUMMARY
IX.
Job
Title:
Transfer Canal Drain Line Modifications i
Task Estimated Actual Estimated Actual Manrem No.
Task Title Panhour Manhour Manrem Manrem Diff.
Int.pect/Heasure 1.
Urain Line 10 37.92 0.750 3.745 399%
~~
Wash /Decon/ Trash 2.
Pielcuy 30
_ 60.31 1.100 2.178 98%
3._,Filt b Change
.185 5.00 4.
Install Canal Drain 10 48.04 2.200 7.290 231%
1.905 39.42
i '. Aojust Drain 1
.295
6.
Leak Tert 21.42
~
I,
.895 25.42
7.
Weld Pipe In Sump TOTAL 50 237.53 4.050 16.493 307%
10.
t 1
Additions to work scope for which no estimate was made.
l A11.EA C0fj7ROLS UTILIZED l
Teleme*.ric dosimetry for personnel entering transfer canal for removal of trash; transler canal flooded and cavity filter / vacuum system used for decontamination.
Lay /own area established, HEPA ventilation and shielding provided for removal and replacement of piping in sump area.
EFFECTIVENESS OF ALARA CCNTROLS Transfer canal decon was ineffective using underwater vacuum system. Later, j
l wash down ef. canal after good canal drainage was established was more effective in reducing. dose rates. The drain valve required multiple entries and numerous l
redesigns to meet required leak rate.
SURVEY DATA See Figure 14 i
SUCCESTED IMPROVEMENTS Investigate decontamination methods for transfer canal, possible hydrolaze or power wash Irjrove valve design fer ease of installation or seismically I
qualify drain line thereby making valve installation unnecessary.
l l
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Page 34 of 44 L _ _.
j
FOR DRAIN MOD WORK l
i OP3271 REV 9-63 FUEL. TRANSFER CANAL RWPNO CONTHOL NO DATE TIME CON-14 Rf ASON FOR SUHvEY T E CHNICIAN ROUTINE (D W M',
PRE-JOB POST. JOB RADIATION CONTAMINATION ler ist la l
INST TYPE INST TYPE INST TYPE SERIAL NO SERIAL NO SERIAL NO
ROBE TYPE PROBE TYPE PROBE TYPE CAL DUE DATE CAL DUE DATE CAL DUE DATE DOSE RATE RE ADINGS ARE IN MREM'HR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED CIRCLED NUMBERS h INDICATE SME AR LOCATIONS CiRCtED Sut AR tOCATiONS AND NUMBER INDICATE CONT AMIN ATION LEVFLS IN DPM'100CM' 1
l e READINGS INSIDE TRI ANCLE INDICATE NEUTRON RADIATION IN MREM /HR AT WAIST LEVEL 1
l uAxiMUM RADIATION '
MAXIMUM CONTAMINATION -
4N l
l PRE-DECON POST DECON 3 R/hr i
1. 5 R/hr 4 R/hr 15 R/hr Contact drain 0
100 R/hr Contact drain 10 R/hr Contact floor 2 R/hr Contact floor 1
ALL SMF ARS t ESS THAN 1000 DPM'100 CM'ft 25% OF ALL SMEARS EESS THAN 20 DPM/100 CM' n HEALTH PHYSsCS SUPERvlSOR/ DESIGNEE Page 35 Of 44
[
ALARA REVIEW JOB
SUMMARY
~
X.
Job
Title:
Control Rod Drive Replacement Task Estimated Actual Estimated Actual Manrem No.
Task Title Manhour Manhour Manrem Manrem Diff.
Remove old CRDs 1.
Cut-up and Drum 70 131.62 1.680 7.315 335%
1.610 34.16
2.
rack in sump area Store 12 CRDs in 3.
sump area 10 16.92 0.240 0.920 283%
l 2.915 29.58
4.
Remove Drums 0.060 4.00
S.
Area cleanup Store 2 0.525 8.08
6.
CRDs in SFB Total 80 224.36 1,900 13.345 595%
Additions to work scope for which no estimate was made.
No estimate was made for removal since shielded drums were to be used which would have resulted in an insignificant exposure.
ALARA CONTROLS UTILIZED Work area to be herculited; rebar cutter equipped with PVC. shielded alignment-device to be used; HEPA ventilator to be used at shear assembly; CRDs to be rinsed during removal from cavity pool; CRDs to be cut to 30" lengths and placed in stovepipe drums; cutting operation will be scheduled at times of minimum containment occupancy (normally 0300-0700 am)
J EFFECTIVENESS OF ALARA CONTROLS Ventilated tent substituted for laydown area due to airborne contamination incident during initial CRD cuts when HEPA ventilator was not energized.
Stop work authority was exercised.
Estimated manhours for cutting operation was low by 53%. Stovepipe drums were unavailable and problems with the containment elevator delayed drum removal. Shear alignment device could not be shielded as intended. Job scope was increased due to sump area storage rack construction.
Shield rack surrounding cutter was utilized to reduce operator exposure.
SUGGESTED IMPROVEMENTS
'Similar operations should be planned with the use of a ventilated tent.
Availability of special equipment must be verified and equipment checked as operational prior te the start of work.
9 i
Page 36 of 44 I
t D
4 -
IIC. Shiciding and Exposure Reduction Techniques
'o Installed ' temporary Reactor Head Shield. Dose, reduction factor.
of approximately 2, utilized personnel shields in cavity (DRF~3),
maintained water level'in reactor vessel as high as possible
~
during Reactor Head Disconnect and Core Exit Thermocouple Sleeve Modifications.
Estimated savings 15 MANREM.~
. Shielded RHR and core deluge piping in lower level outer. annulus o
near fl.SG-loop entrance using two' mobile; shield racks and lead blankets.- (DRF ~2 to 10)
Increased wat;er level in the transfer canal during blind flange o
removal / replacement (estimated savings. 5 MANREM). -
Shielded loop bypass lines in the middle level. loop area'during.
o RCP seal work secondary steam generator work.and valve packing (DRF~2).
Shielded steam generator manways with 4 layers of (~ 2 inches) o lead blankets during ECT/ prof. inspections.
(DRF~2 on jump platform).
Shielded open manways on SG $1 and.#2 with mechanical manway.
o shields during the manway handling' device installation and quarter turn diaphragm f astener -installation.- '(DRF-7 at.
manway-DRF~3 on jump platform). Saved an estimated 9 MANREM.
Expedited flooding of the secondary side of the steam generators o
following inspection.
o Shielded safety injection line - loop 1 during welding of check valve #305 on seal water line to.RCP #1.
Shielded MOV 292C and bypass valve on RHR line for valve vork.
o Shicided pressurizer spray line for work associated with PORV o
modifications.
Shielded pressurizer spray valves with portable shield racks in o
order to lower general area doserates for work on CRDM cooling fans.
Sbielded horizontal crossconnect with 4 layers (~ 2' inches) of lead blankets for pressurizer spray valve work.
Posted-no loftering cigns in the penetrations area lower level o
outer annulus and routed traffic to steam generators and generel.
loop access away from area.
e 9
l I-Page 37 of 44
'I I
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III. RADI0 ACTIVE CONTAMINATION CONTROL IIIA.
Personnel External Contamination A total of 238 Personnel Contamination Forms were completed on individuals having external _ radioactive surface contamination in excess of 100 ccpm Ey. Considering the total number of man-hours spent in the Radiation Control Area this outage (46,067 man-hours), 238 contamination occurrences represents a significant increase in incidence rate, i.e., one personnel external contamination in 194 man-hours. =1he personnel external contamination incidence for trending purposes are as follows:
Year Incidents Man-hours Man-hours / Incident 1980 400 141,304-353 1981 137 73,383
'535 1983 160 72,665 454 1984 238 46,067 194 The personnel external contamination incidence per man-hour'was 57 percent greater this outage than the 1983' outage and represents the highest incident rate'in the unit's history.
A review of personnel contaminations was performed to identify recurring problems and methods to reduce future external contamination.
Figure 15 shows the percentage of personnel receiving external radioactive contamination for the various work groups. As expected, the work groups having the largest number of workers contaminated were those performing high risk radiological operations i.e., maintenance' laborers, decon and radwaste technicians, and steam generator jumpers.
Figure 16 shows the regions of the body which received the largest percentage of external contamination. 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. Two work groups were studied in detail.
In the first group, two. individuals accounted for all seven skin contamination incidents.
In the.second group, there were 62 skin contamination incidents.
Of the'62 incidents 53%
were repeat offenses. Three individuals were responsible for 19%
of the 62 incidents.
The number of repeat incidents and the major body location contaminated indicate a 3ack of worker awareness or disregard for correct radiological protection practices. Actions to correct j
this situation should include identification of repeat offenders j
and notification of supervision for worker counseling and/or j
disciplinary action.
Page 38 of'44 c
J
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Contamination of the trunk and legs showed a marked increase f
compared to 1983. This is partially attributable to problems encountered with the dry cleaning facility which was later corrected.
i l
It should be noted that containment lower level work areas experienced increased contamination levels due to the cavity seal failure.
Also, extensive work was performed in high risk radiological areas.
(e.g., cavity seal modification, transfer cart repair, 100% ECT inspection of steam generators, trarsfer canal drain line modification and cofferdam installation).
IIIB.
Personnel Internal Contamination Approximately 2254 Whole Body Counts (WBC) were performed during the period of August 1, 1984 to November' 10, 1984.
Out of these 2254 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 l
Regulatory Commission's (NRC) internal exposure limits. This is l
based on the amount of personnel internal contamination
[
determined by measurement of radioactive concentrations in air l
together with the individual's stay time.
Subsequent assessment l
by WBC verified that no individual exceeded any NRC internal exposure limits.
IIIC.
Airborne Contamination In general, the number of airborne contamination occurrences was about the same this outage as in the 1983 outage. None of the airborne occurrences resulted in personnel internal exposures above the NRC limits.
The major airborne contamination occurrences are described below:
1.
August 2 ti. rough August 9,1984, the containment building exhibited elevated iodine Icvels requiring the use of respirators j
with iodine canisters. MPC fractions ranged from 0.5-1.65.
The cause was found to be reactor coolant Icakage from RCP #1.
Containment access was also restricted during this period.
I 2.
Au gust 18, 1984, elevated airborne contamination levels on the charging floor required the use of respirators for approximately two hours. The cause of this incident was the cleaning of the cavity seal seating surface with scotch brite pads and wire l
brushing the flange dry.
3.
Au gust 24, 1984, Primary Auxiliary Building access was restricted l
and iodine respirators required due to high fodine levels from the RCP seal water filter change.
Page 39 of 44 J
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4 4.
October 1, 1984,' respirators were required on the charging floor.
for approximately four hours. MPC fraction 0.8, due to Reactor Head lift.
q 5.
October 2, 1984, AMS alarm on charging' floor.
Charging' floor initially evacuated. Respirators required for approximate 1y'two j
hours in containment.
Cause was determined to be wire brushing; of SG #4 manway' diaphragm without ventilation.
6.
October 2, 1984, 1945-0200 hours.
Respirators required on charging floor. Cutting of control rod drives for' disposal, f
ventilation was not energized.
Area decontaminated and j
ventilated tent installed for cutting operation.
i 7.
October 14. 1984, 0315-1400 hours. Respirators required charging floor, increased respirator requirements to all of containment.
Dec9ntamination of cavity in progress. Air sample in cavity.2 x 10 uCf/cc.
8.
October'16, 1984, 2000-0300 hours.
Respirators requ' ired on charging floor during modification of' cavity deck plates.
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'IV.
RECOMMENDATIONS AND CONCLUSIONS IVA.' Recommendations Based on the ALARA group's-observations and the job / task leaders post job reviews of the' work performed during the:1984 ; Refueling' Outage.-
the followingfrecommendations'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 author's' opinion of the most beneficial recommendations to-be. evaluated for implementation ~during future Refueling Outages.
1.
Perform cost benefit analysis for the following Primary Steam Generator options:
a.
Chemical decontamination of SG channel heads b.
Mechanical manway shields for ECT, inspection Remote ECT fixtures that require no entry.to th'e channel c.
head.
2..
Investigate the feasibility of installing a permanent ventilation system and permanent contamination control barriers:for work associated with the' primary steam generator inspection.
In lieu of a permanent ventilation. system, redesign the temporary ventilation system and acquire' additional equipment as necessary.'
3._
Improve Steam Generator mockup training by making the mockup more realistic, e.g., height of manway from jump platform, space q
limitations on jump platform.
Also include manway shielding-techniques and video presentation of actual SG entries.
4.
A redesign of the cavity pool seal should be considered.
Modifications during the 1984 outage have made_the cavity pool' seal very labor intensive to install.
-i 5.
Extensive maintenance should be performed on the Fuel Transfer.
I Cart.
6.
Evaluate various decontamination methods for the Fuel Transfer Canal in support of recommendation #5 and blind flange removal and replacement.
7.
Reevaluate decontamination methods for post drain-down cavity decontamination evolution.
j I
s 3
Page <43 of 44-i
_ _ _ _. _ _ _ _ _________________.____,j
.ea, 6
i 8.
Investigate the feasibility of performing the Secondary Steam Generator Inspection when the primary side of the SG is full.
9.
Investigate the use of the Preventive Maintenance Management System as a tool in ALARA planning and scheduling for valve work, etc.
10. Develop a worker and supervisor ALARA training program to further q
enhance ALARA attitudes.
1 IVB, Conclusions f
In conclusion the 1984 Refueling Outage, from a radiological perspective, was a success..The Health Physics Department handled all major radiological events without any major problems and without violating any Federal Radiation Protection Regulations.
Key factore contributing to this success were the use of permanent CY Health Physics Department personnel in the managerial positions of the Health Physics Outage organization, state of the art Health Physics equipment and programs, and strong management support.
A total plant dose equivalent of 1108 MANREM was expended during the fourteen 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 1986 Core XIII-XIV Refueling Outage.
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I Page 44 of 44 k
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