ML20070E218
| ML20070E218 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/31/1990 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20070E213 | List: |
| References | |
| NUDOCS 9103050220 | |
| Download: ML20070E218 (3) | |
Text
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l 3.~ EXPOSURE INFORMATION a,
NUMIER OF PERSONNEL AND l!AN. REM BY VORK /RD JOB FUNCTION REPORT - 2990 2
NUMBER OF FERSONNEL (>A00 MREM)1 TOTAL MAN.REH WORK & JOB FUNOTIOM STAT 10N PTILITY C00 TRACT STATION UTILITY CONTRACT Reactor Operations & Surveillance Mainte. nance & Construction 9
0 20 3.514
.015 7.883 Operations 1
0 0
2.588
.329
.714 L3ealth Physics & Lab 11 0
11 3.333
.100 4.536 Supervisory & Office Staff 4
1 1
1.630
.147
.497
- Engineering Staff 1
0 3
.849
.053 1.085 m....................................................
Routine Plant Maintehance Maintenance & ConstructioT 28 0
76 8.204
.079 19.774 Operations 1
0 1
1.518
.062
.927 Hebith Phytics & Lab 8
0 31 2.328
. 02fi 7.603 Supervircry & Office Sttff 7
0 2
2 720
.013
.674 EnBineoring Staff 2
0 18
.i24
.151 4.300
. Inservice Inspection Maintenanca & Construction 5
0 44 2.470
.067 15.911 Operationc 0
0 1
.328
.018
.715 Wealth Physics & Lab 0
0 7
.407'
.014 3.183
' Supervisory & Office Staff 1
0 0
.712
.000
.274 Engineering Staff 0
0 15
.336
.021 3.901
.......e....................................................................-...................
Special-Plant Maintenance Maintenance & Construction 22 1
43 6.688
.175 13.539 Operations 0
0 1
.502
.051
.846 Health Physics & Lab 5
0 10 1.533
.010 4.165
= Supervisory & Office Staff 0
0 0
1.325
.069 407 i
' Engineering Staff 0
0 9
.464
.026 3,211 JWaate Processing
. Maintenance & Construction 8
0 32
-3.620
.021 11.456 (Operations 0
0 2
.764
.04 9
.7 33 health Physics & Lab 9
0 7
3.218
. 031 4.063 Supervisory & Office Staff 1
0 2.
.982
.028
.370 Engineering Staff 0
0 10
.325
.127 2.452
=......................r...................-.........r................v............................
Refueling Maintenance & Construction 26 0
17 6.277
.000 5.891 10peratic':s 0
0 0
.647 000
.090 3
-Health Physics & Lab 1
0 2
.379
.001
.886 Supervisory & Ofi' ice Staff 0
0 0
.500
.000
.058
-Engineering Staff 0
1 1
.193
.229
.435 Totals M:aintenance & Construczion 60 2
163 30.174
.350 74.434 Operations -
25 1
13 6.348
.319 4.048 Health Physics-& Lab 23 1
P3 11.199
.185 20.435 Supervisor.y & Office Staff 27 1
6 7.8E3
.256 2,180 Engineering Staff
'12 1
46 3.065
.617 15.367 Grand. Totals-155 6
211 11.204 1.733 129.634 1Number of personnel > 100 mrem based on PIC data 2Total man-rem based on ratio of PIC data applied to TLb data 9103050220 910227 l
PDR ADOCK 0500 2
i R
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' Page '2 el 1?
b.
PERSONNEL MONITORING REPCRT 1.
In 1990, 1568 individuals were provided personnel monitoring devices.
This information is provided in accordance with 10 CFR 20.407(a)(2).
This total includes the number of individuals required to be reported under 10 CFR 20.40?*a)(1).
2.
Below is a statistical summary report of the personnel monitoring information recorted for individuals for whom personnel monitoring was provided in 1990 in accordance with the requirements of 10 CFR 20.407(b).
l Number cf 'ndividulJ s Estimated whole body exposure range (rtms) in tesh racise No %3Asurable r.xposure...,,,
...................................... 768 i
.*26 Me a sur a'ot r. exposara lots than c.1.
0,1 to 0.15.....
.................. 216
.s
.............. 157 0.25 to 0.5..
0.5 to 0.75........,...........................................
....... 58 j
0.75to1.0.......................................................s......3-1.0 to 2.0........................................................
.. 13 2.0 to 3.0............................................................... 0 3.0 to 4.0................................................................
0 4.0 to 5.0................................................................
0 m
jl 5.0 to 6.0................................................................
0 8
6.0 to 7.0................................................................
0 7.0 to 8.0..................................................
............. 0 8.0 to 9.0.....................
.......................................... 0 ga 9.0 to 10.0...............................................................
0 j
10.0 to 11.0..............................................................
0 1
11.0 to 12.n..............................................................
0 12 +.................................................................... 0 55 1
h l
I l
Page 13 of 13 c.
SO.G?E OF DATA The information provided in Section 3.a is based on estimated exposures obtained from rocket Ionization Chamber (?IC) readings.
The information provided in Section 3.b.2 is obtained from Thermal Luminescent Detector (TLD) readings which is the offic!al record of exposures.
There is a discrepancy in the total number cf personnel
- h. ring received greater than 100 mrem exposure during 1990 in the two sections.
This discrepancy results from the difference in the ranges used in reporting exposure information.
Regulatory Guide 1.16 requires information for personnel with 2reater than 100 mrem while 10 CFR 20.407 requires information in enges, vita one range beginning at 100 mtem.
Therefore, individualo with 100 mrem are reflected in Sentitt 3.b.2 but not reflected in Section 3.a.
4.
SINGLE RELEASE OF RADIOACTIVITY OR RADIATION EXPOSURE CREATER THAN 10 3
PERCENT OF ALLOWABl.E ANNUAL VALUES For each outage or forced reduction in power during 1990, there were no single releases of radioactivity or single radiation exposures greater than ten percent of allowable annual values.
5.
CHALLENGES TO THE PORVS AND SAFETY VALVES During 1990, there were no challenges to the Pressuriter power operated relief valves (PORVs) or safety valves.
6.
INDICATIONS OF FAILED FUEL During the fourth refueling outage, all 193 fuel assemblies that were loaded during Cycle 4 were ultrasonically inspected.
Of the 193 fuel assemblies inspected, three assemblies with one defective fuel pin in each assembly were identified.
Two of the defective assemblies were discharged and one was reconstituted, substituting stainless steel filler rods for the def'.ive pin.
7, REACTOR COOLANT SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPFCIFICATION 3.4.8 LIMITATION During 1990, there were no instances in which the Reactor Coolant System exceeded the Technical Specification 3.4.8 limit of one microcurie per gram Dose Equivalent I-131 or 100/E microcuries per gram of gross activity.
.