ML20214E970
| ML20214E970 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/15/1987 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| LIC-87-295, NUDOCS 8705220347 | |
| Download: ML20214E970 (24) | |
Text
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9 Omaha Pubile Power District 1623 Harney Omaha. Nebraska 68102-2247 402/536-4000 May 15, 1987 LIC-87-295 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
References:
1.
Docket No. 50-285 2.
Application for Amendment of Operating License dated July 17, 1986.
3.
Letter NRC (W. A. Paulson) to OPPD (R. L. Andrews) dated March 3, 1987.
4.
Letter OPPD (R. L. Andrews) to NRC dated April 30, 1987 (LIC-87-276)
Gentlemen:
SUBJECT:
Response to Request for Additional Information on Five Year License Extension for Fort Calhoun Station Reference 3 included three questions regarding the information submitted by OPPD in Reference 2.
In the process of preparing the responses, several clarifications of the questions were required. On April 30, 1987, as a result of a conference call between OPPD and the NRC, the following clarifications were made:
1.
The first question should reference five additional years of service.
2.
Question 2(a) asked for man-rem exposure data for years 1978 through 1985, organized by plant system.
OPPD has historical exposure data based on job function and not by plant system.
The NRC said that this data would be acceptable.
3.
Question 2(b) requests projections of man-rem exposure for the years 2008 to 2013. A clarification of the duration was made.
The applicable time frame is from 2009 through 2013.
8705220347 870515 eDR ADOCK 05000285 e
eDs c I
, -, =. _
D-When transporting radioactive material, the primary reliance for safety is placed on the packaging. Regulatory requirements (10 CFR 71 and 49 CFR 173 and 178) establish the guidelines that pack-aging must meet. Regulatory limits are established according to the type and form of material for heat dissipation, shielding, con-tainment and nuclear criticality safety.
Because packaging is in accordance with the provided standards, the following items shall be met:
(a)
Shielding efficiency shall be retained.
-(b)
Loss or dispersal of the radioactive contents shall be pre-vented.
-(c)
Nuclear criticality safety shall be assured.
(d)
Adequate heat dissipation under normal conditions of trans-port shall be provided.
(Also includes transport under spec-ified accident damage test conditions).
There are limitations on contents of packages not designed to with-stand accidents.
Therefore, in case of an accident, the risk from possible release would be limited.
Package contents must be limit-ed so that regulations regarding external radiation levels, pres-sure, containment and temperature are met. I
'U. S.-Nuclear Regulatory Commission-LIC-87-295 Page 2 OPPD respectfully submits the attached response to your questions. -If you require any additional information, please contact us.
Sincerely, R. L. Andrews-Division Manager Nuclear Production RLA/me Attachment l
cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.
Washington, DC 20036 W. A. Paulson, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector a
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' REQUEST FOR ADDITIONAL INFORMATION LICENSE EXTENSION FOR FORT CALHOUN STATION,. UNIT NO. 1 4
.1.?
M/RA MEASURES
' Discuss specific'ALARA measures which will be utilized during the 7 addi-tional years of service.
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RESPONSE
/
- As discussed in the cover letter, this question should address only 5~
additional. years of service.
.This response is based on specific ALARA measures currently in place, and the existence of management goals that support the continued in-provement of an effective ALARA program. As goals are achieved, they i
are reevaluated and new goals set. Because of this strategy, OPPD's ALARA programs are continually growing and changing.
Omaha Public Power District (OPPD) is committed to evaluating and imple-l menting-(as appropriate) new ALARA measures as they are developed. The:
company can only speculate o1 specific future ALARA measures that may be utilized during the five additional years of service. Robotics, remote surveillance, remote tooling and improved decontamination could be major factors in achieving ALARA doses.
The company is staying abreast of emerging ALARA concepts through its membership in INPO, EPRI, NUMARC and other organizations. Management at tention has been focused on ALARA by the Fort Calhoun Station ALARA Committae and the Radiation Protection Program Coordinating Committee. An ALARA Radiation Exposure Program has been' implemented and audited by the NRC. The program focuses on in-creased management attention on ALARA and includes OPPD's plant, offsite l
support, design and construction personnel. The program establishes a
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Corporate ALARA Committee, ar.d defines responsibilities and authority for developing, implementing and maintaining the company wide "ALARA Radiation Exposure Program."
Soecific Neasures in Proaress i
1.
Six corporate ALARA goals have been established for 1987. These goals are being tracked throughout this year. These goals are reevaluated annually. Examples of specific corporate. goals are:
a goal for total man-rem exposure, a goal for total curies in gaseous effluent releases and a goal for total radioactive waste materials shipped.
2.
Nine goals s)ecific to Fort Calhoun Station have been established for 1987. T1ese goals are being tracked during the year and like the corporate goals, are reevaluated annually.
Examples of spe-cific plant goals are: a goal for increasing the percentage of the auxiliary building classified as clean controlled areas, a goal for reducing the percentage of the auxiliary building classi-fled as requiring a respirator, a goal for reducing plant depart-mental exposures during a refueling year, and several reduced ex-posure goals for specific high radiation jobs.
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3.
Pre-job ALARA planning and post-job interviews are being done to reduce future doses, j
'4.
A Fuel Integrity Program has been established. Testing of all fuel going back into the core for Cycle 11 was performed. No leak-f ing fuel was reloaded. Offloaded fuel was also tested and inspect-ed so that failure modes can be identified and, if possible,.cor-rected in the future. Chemical sampling during power changes mea-
'sures reactor coolant activity. Reactor coolant activity levels have been established to require specific corrective actions if fuel leakage is suspected.
5.
Containment purge techniques were reviewed'and revised to.emove radioactivity as rapidly as allowed to reduce outage exposure and still stay within 10 CFR 20 and 10 CFR 50 requirements.
l 6.
Radwaste volume reduction is being aggressively pursued by a com-mittee composed of plant, engineering and technical support groups. A new building is under design to allow the company to use state of the art volume reduction (VR) techniques. Various VR processes are being tested presently at the plant.
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7.
A decontamination crew has been added to the plant staff.
8.
A steam generator mock-up has been used to reduce high dose gen-erator work. More mock-ups are planned to be used in the new training building.
9.
At the plant, a formal ALARA suggestion program is in place, l
i 10.
Adoption of EPRI primary chemistry guidelines is under evaluation.
I Use of coordinated lithium-borate chemical control is being con-sidered to prevent radiation buildup in the reactor coolant sys-1 i
tem.
Continuation of existing ALARA measures coupled with an improving ALARA program should lower the dose received during future refueling and nor-mal operations.
2.
DOSE _ ASSESSMENT a)
Provide a table showing Fort Calhoun personnel exposure experi-ences for the years 1978 thru 1985 indicating the man-rem expo-sures by olant system, regardless of how these exposures were i
obtained (e.g., during normal operations, maintenance, repair or refueling activities) and by whom (e.g., by plant operations per-sonnel, plant maintenance personnel, contractor / vendor personnel, etc.).
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RESPONSE
l-As discussed in the cover letter, OPPD does not accumulate man-rem exposures by plant system, therefore, the following tables show the whole body (TLD) man rem exposures of Fort Calhoun Station personnel according to job function at the plant.
Fort Calhoun 2
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Station radiation exposure is tracked in this manner. This infor-mation is further broken down into three subcategories denoting an OPPD employee who is permanently stationed at the )lant, an OPPD utility employee who is temporarily stationed at tie plant or a non-0 PPD employee who is classified as a contractor.
The data for the tables was taken from the compilation of the monthly OPPD Personnel Radiation Exposure Reports. Table 2.a.1 shows by job category the total annuni man-rem exposures to Fort Calhoun Station personnel for the years 1978 through 1985. The yearly plant totals are given along with totals according to job function. Table 2.a.2 shows the total yearly and average whole body plant ex)osures according to job function.
Tables 2.a.3 thru 2.a.10 show tie yearly exposures which are subdivided into the three employee categories mentioned previously.
It should be noted that the data differs from results published in the OPPD Annual Reports for Technical Specification 5.9.1.b.
That section is an Annual Occupational Exposure Report whose dose assignments to the various job functions at Fort Calhoun Station may be based on pocket dosimeter, TLD, or film badge measurements.
It also only reports personnel with an exposure greater than 100 mrem. The data utilized for this submittal is strictly whole body (TLD) exposure and includes all personnel exposed, not just those
>100 mrem. Because of the difference in data used for compilation purposes, the results will vary.
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r Table 2.a.1 AC'IUAL AIGCAL 1RN-REM EXPOSURE FGtr CRIMIN SDLTICN - JOB IUSTICN CNIBG3E 1978-1985 (Sheet 1 of 2)
WEMISHtY GENISDE mr*mIchL GBERAL 1ERI2H IMBDE.
EBB E8VIIG8ENULL MKIERR CIERICAL VINXR BEGDER ISLINIDENT MhBGGW82 F1THR HRSIG
& GMBEL 1978 0.045 1.620 0.325 113.093 18.830 11.458 46.069 28.536 26.948 14.229 1979A 0.030 0.443 0.139 37.326 6.594 1.613 8.078 7.944 10.762 3.662 1980 0.003 0.498 0.049 185.191 28.495 19.997 69.827
~ 114.482 39.790 14.360 l
l 1981 0.059 0.058 0.363 77.764 21.352 12.759 52.444 95.938 27.243 14.510 1982A 0.007 0.083 0.053 39.134 4.898 3.128 15.699 12.734 21.252 2.706-1983 0.195 0.507 0.124 114.532 25.299 18.432 54.556 47.723 48.044 11.384 1984 0.012
- 4.057 0.224 237.919 31.175 12.272 43.554 28.052 55.820 9.778 l
1985 0.009
- 3.782 0.214 93.807 5.348 43.202 23.829 65.378 62.884 13.509 i
NDE: 'Ihe VEMXR - :- ;-f originally irr-1triarl all nort-CE9D employees =ririg at Rrt mlhramt Station. It has W=11y harv== a a*m for vendar sagacyees to may not fit a paz+iailme job function t-la==-
4 fie>& 4e=1.
- '2he sicpifir=* increase in ann-remt espasurut for the mammistry NLaclear - :- ; f in 1984 and 1985 is dLan to a job functicut 1---l---ifi tir=1 of a rumber of people frtat Hamith MtygCis.
A: 'Ihis notes a year not containing a r=D=lig cutage.
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Table 2.a.1 ACIUAL AIGERL MMHEM EXIGURE:
roar cmurxar smTIm - aos runcrim ownrutr 1978-1985 (Sheet 2 of 2)
EBB MKHDrIST OEUUGOR SBCWITY SENS SUMtVISCItY 1BC29EICAL QVOC**
WML 1978 34.918 27.658 R*
0.047 4.640 M*
R 327.663 1979A 5.969 10.255 0.056 0.038 1.183 3.237 R
97.329 1980 62.198 14.629 0.521 0.004 3.897 7.276 R
561.217 1981 35.305 8.901 0.590 0.026 1.790 19.304 R
368.406 1982A 3.771 4.768 0.312 0.004 0.478 3.205 R
112.232 1983 29.354 12.815 0.518 0.022 3.669 27.954 R
395.128 1984 24.209 21.722 1.207 0.040 4.083 23.888 R
498.012 1985 26.585 22.772 0.836 0.097 4.753 8.960 17.048 393.013 Jcb function catWa= fcr Security armi Tecimiral areas were initiated in June 1979.
QA/QC job ftmetions were previrumly included under Technical but since 1985 they are listed in one catarywy.
A: 'Ihis notes a year not ev=* mining a ImA=lig cutage.
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Tabla 2.a.2-(Sheet 1 of 3) 1978 Tot:als 1979 Tot:als 1980 Tbt:als Tot:al Does # People Ave. Does Total Does # People Ave. Does Tot:al Does # People Ave. Does OIDE-DWIIDGENDLL 0.045 14 0.003
.0.030 8
0.004
.0.003 8
'0; OIDHIUCU2R 1.620 8
0.203 0.443
.7 0.063-0.498.
9 0.055 CURIOLL 0.325 16 0.020 0.D9 11 0.0D 0.049 12 0.004 VDOCR 1D.093 323 0.350 37.326 262 0.142 185.191.
430 0.431'-
DEDIEER 18.830 92 0.205 6.594 90 0.073 28.495.
103 0.277 EU!C. MAINE.
11.458 18 0.637 1.6D 21 0.077 19.997 47-0.425 GEN. MkINr.
46.069 56 0.823 8.078 36 0.224 69.827-72 0.970 FlTH R 28.536 23 1.241 7.944 24
.0.331 114.482 123 G.931..
HEAL 1H RfYSIG 26.948 24 1.123 10.762 16 0.673 39.790 44 0.904-INSIM. & CINIRDL 14.229 14 1.016 3.662 10 0.366-14.360 14 1.026 MAQUNIST 34.918 35 0.998 5.969 16 0.373
~ 62.198..
53 1.174 OPHULTCR 27.658 47 0.588 10.255 37 0.277
.14.629 42 0.348 SECURTW NA NA NA 0.056 31 0.002 0.521
'30 0.017 SREES 0.047 4
0.012 0.038 3
0.0D 0.004-3 0.001 SUPHNISGE 4.640 23 0.202 1.183 25 0.047 3.897 31 0.126
'H!GNICAL NA NA NA 3.237 28 0.116 7.276 34 0.214 AIL PERSGtlEL AT FCS 327.663 697 0.470 97.329 625 0.158 561.217 1055 0.532
- All h are in man resa ard Avaa. the penannent (TID) Wmle body exposure at the Fort Calhoun Station...
Tablo 2.a.2 (Sheet 2 of 3)-
1981 Totals 1982 Tot:als 1983 Totals 2ttal Dose # People Ave. Does Total Does # People Ave. Dose Total Dose.4 People Ave. Dome OEM-ENVIR0ftENmL 0.059 9
0.007 0.007 3
0.002-0.195 5
0.039 QEM-NUCIEAR 0.058 5
0.012 0.083 5'
O.017 0.507 6
0.085 CI2RICAL 0.363 22 0.017 0.053 21 0.003 0.124 30 0.004 1
VENDGt 77.764 299 0.260 39.134 275 0.142 114.532 289 0.396 ENGINEER
.21.352 127 0.168-4.898 94 0.052.
25.299 147 0.172 EIEC. MAINE.
12.759 43 0.297 3.128 23 0.136 18.432 54 0.341 i
GEN. MAINE.
52.444 65 0.807 15.699 93 0.169 54.556 92 0.593 i
l FITITR 95.938 103 0.931 12.734 39 0.327 47.723 44 1.085' HEAIHH PHYSICS 27.243 39 0.699 21.252 59 0.360 48.044 61 0.788 INS'IM. & CCNIBOL 14.510 26 0.558 2.706 17 0.159 11.384 18 0.632 MAOIINIST 35.305 39 0.905 3.771 28 0.135 29.354 33 0.890 I
i OPERA'lTR 8.901 37 0.241 4.768 39 0.122 12.815 42 0.305 j
N 1RITY 0.590 38 0.016 0.312 34 0.009 0.518 37 0.014 i
l SICRES 0.026-3 0.006 0.004 4
0.001.
0.022 5
0.004-j SUPERVISCRY 1.790 24 0.075 0.478 28 0.017 3.669-35-0.105-TEG NICAL 19.304
-71 0.272 3.205-70 0.046 27.954 90 0.311 1
1 ALL PERSC2iNEL I
AT ITS 368.406 950 0.388 112.232 832 0.135-395.128 988 0.400 i
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All h are in man run arx1,_e. the perunnent (TID) idole body awIv=nu at the Fort Calhoun Statia:m.
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- Tabla 2.c.2 (Sheet 3 of 3);
1984 Totals 1985 Tot:als Total Dose i Pecole Ave. Dose Total Dose # Naple Ave. Doea 3
i OGM-DIVIR2MENIRL 0.012 3
0.004-
-0.009 1
0.009 OEM-NUCEEAR 4.057 16 0.254 3.782 22 0.172-CEERICAL 0.224 -
37 0.006 0.214-46 0.005'
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VENDOR 237.919 441 0.539 93.807 281
'O.334 ENGINEER 31.175 96 0.325 5.348 16 0.334 ELEC. MAINT.
12.272 22 0.558 43.202 97 0.445-i l
GEN. MAINP.
43.554 54 0.807 23.829 50 0.477 i
FTITER 28.052 28
'1.002 65.378 133 0.492 HEALTH PHYSICS 55.820 36 1.551 62.884 69
~0.911 i
INS'IM. & CONIBOL 9.778 12 0.815 13.509 22 0.614 MAOIINIST 24.209 28 0.865 26.585 44 0.604-t OPERATOR 21.722 39 0.557 22.772 61 0.373 SECURITY 1.207 38 0.032 0.836 36 0.023 SIGRES 0.040 4
0.010 0.097 5
0.019 SUPERVISORY 4.083 35-0.117 4.753 37 0.128 TECHNICAL 23.888 84 0.284 8.960 218 0.041 QA/QC*
NA NA NA 17.048 39 0.437 ALL PERSCHNEL AT FG 498.012 973 0.512 393.013 1177-0.334 j
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- QA/QC job function classification N in 1985 i
All doses are in man rem and represent the pi:u-cu==d. (TID) whole body exposure at the Ebrt Calhoun Station.
NorE: Part of the marked change in the rumhar of people in the engineer and. technical groups fran 1984 to.1985 is due to a job function reclassification of many people in Engineering and Technical Services..,
i Tabla 2.n.3.
Whole Body Dose (Yearly Subtotals)
No. of People ( W )
Average Dose 197H Staticn Utility Contract Station Utility Contract Station Utility Contract 7
QIEM-DWIRONMENIAL 0.039 0.006 10 4
0.004 0.002 OIEM-NUCIEAR 1.588 0.032 5
3 0.318 0.011 CIERICAL 0.292 0.024 0.009 12 3
1-0.024 0.008 0.009 VENDG1 113.093 323 0.350 D EINEER 4.588 12.998 1.244 11 66 15 0.417 0.197 0.083 EIEC. MAINE.
8.713 2.745 9
9 0.968 0.305 GEN. MAINE.
26.461 19.554 0.054 15 39 2
1.764 0.501 0.027 FITTER 18.494 10.042 10 13 1.849 0.772 HEALTH HIYSICS 15.852 11.096 11 13 1.441 0.854 INS 7M. & OWIBOL 13.068 1.161 10 4
1.307 0.290 MAOIINIST 27.381 7.537 13 22 2.106 0.343 OPERATOR 25.487 2.171 33 12 2
0.772 0.181 0
SEC RITY*
NA NA NA NA NA NA NA-NA NA STORES 0.017 0.008 0.022 2
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0.009 0.008 0.022 SUPERVISORY 3.560 0.404 0.676 16 6
1 0.223 0.067 0.676 4
TEQiNICAL*
NA NA
'NA NA NA NA NA NA NA i
1hese job functions nonexistent for Radiation W ire Report until June 1979.
j All doses are in man-rea and represent the permanent (TID) whole body avpn=1re at the Fort Calhoun Station.
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Tabla 2.n.4-Whole Body Dose
.(Yearly Subtotals)
No. of People ( W )
Average Dose 1919 Station Utility Contract Station Utility Contract
' Station-Utility. Contract 9
QEM-ENVIlOMENIAL 0.030 8
0.004 i
QEM-NUCTAR 0.443 4
3
.0.111 0-0 CEERICAL 0.139 10 1
0.014 0.142 VENDOR 37.326 262 1
DGINEER 2.675 3.689 0.230 10 76 4
0.268 0.049.
0.058
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ELEC. MAINT.
1.564 0.049 0.196 0.004-8 13 11 25 0.627 0.047 GEN. MAINT.
6.900 1.178 0.936 0.107 FITTER 6.552 1.392 7
17 HEAIHH PHYSICS 9.861 0.423 0.478 9
1 6
1.096 0.423 0.080 t
0.457 0.005 INS'IM. & CNIBOL 3.652 0.010 8
2 MAQIINIST 5.309 0.660 0.664 0.083 8
8 OPERA'IOR 10.230 0.014 0.011 33 3
1 0.310 0.005 0.011 0.
SECURITY
- 0.055 0.001 28 3
0.002 l
SIORES 0.038 3
0.013 l
15 10 0.072 0.010 SUPERVISORY 1.086 0.097-7 17 4
0.201 0.108 0
TEQiNICAL*
1.408 1.829
- Job functions aMad to Radiation Pww=mt Report in June 1979.
- All h are in man-ren and ivasant the permanent (TID)' whole body exposure at the Fort Calhoun Station.
Tablo 2.0.5 Whole Body Dose (Yearly Subtotals)
No. of People (W)
Average Dose 1980 Station Utility Contract Station-Utility Contract Station Utility Contract QEM-DNIR0ttENIAL 0.003 8
0 QEM-NUCIEAR 0.475 0.023 4
5 0.119 0.005 CIERICAL 0.028 0.006 0.015 7
3.
2 0.004 0.002 0.008 VENDOR 185.191 430 0.431 ENGINEER 12.821 15.664 0.010 10 92 1
1.282 0.170.
0.010 ELEC. MAINT.
7.173 6.464 6.360 8'
14 25 0.897 0.462 0.254 GEN. MAINT.
24.460 23.342 22.025 10 33 29 2.446 0.707 0.759 FITIER 23.388 16.752 74.342 8
24 91 2.924 0.698 0.817 HEAI M PHYSICS 17.734 0.279 21.777 14 1
29 1.267 0.279 0.751 INSIM. & CONIBOL 12.580 0.030 1.750 8
3 3
1.573 0.010 0.583 HAGINIST 15.146 16.549 30.503 9
21 23 1.683 0.788 1.326 OPERATOR 14.392 0.237 33 9
0.436 0.026 btLUKlTi 0.521 30 0.017 STORES 0.004 3
0.001 SUPERVISORY 3.665 0.232 13 18 0.282 0.013 TEQiNICAL 4.199 2.760 0.317 9
24 1
0.467 0.115 0.317 All doses are in man-reet and twtai==d. the p=u-r==d. (TID) whole body Pre at the Fort Calhoun Station.
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-Tabla 2.a.6-1 W ole Body Dose (Yearly Subt:otals)
No. of. People ( W )
- Average Dose 1911 Station Utility. Contract Station Utility Contract; Station Utility' Contzact i
OEM-ENVIRCt8ENDL 0.057 0.002-8, 1
0.007'
'O.002 QEM-NUCIEAR 0.023 0.035 1-4 0.023 0.009 CIERICAL '
O.110 0.253 10 '
12' 0.011 0.021
'-c WNDOR 0.008 77.756 1
298 0.008 0.261 ENGINEER 3.533 6.608 11.211 16
'80 31 0.221
'O.083 0.362 EIEC. MAINE.
3.800 2.700 6.259 8
10 25 0.475-0.270 0.250 GEN. MAINT.
20.078 26.926 5.440 25 35 5
0.803
.0.769
'1.088 FITTER 13.779 23.024 59.135 8
20 75 1.722 1.151-0.788
{
HEAIHH PHYSICS 8.332 0.248 18.663 12 1
26 0.694 0.248 0.718 j
INS'IM. & CCNIROL 10.132 3.413 0.965 10 10 6
1.013 0.341 0.161 MAQiINISP 8.312 16.166 10.827 8
24
-7 1.039 0.674 1.547 f
OPERAICR 8.887 0.014 34-3 0.261 0.005 i
SEXIRITY 0.536 0.054 33 5
0.016 0.011' i
- I SICRES 0.026 3
0.009 1
l SUPERVISCRY 1.512 0.278
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1 0.089 0.046 0
i TE0INICAL 2.624 3.616 13.064 13 25 33 0.202 0.145 0.396 All doses are in man-rem and i=p.=iad. the permanent (TID) 2 ole body avgvwrwe at the Fort Calhoun Station.
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Tablo 2.a.7:
.Whole Body Dose j
(Yearly Subtotals)
No. of People -(W) -
Average Dose 1932 Station Utility Contract Station Utility Contract Station Utility Contract i
QEM-ENVIR0t#ENIRL
'O.005' O.002'
'1 2
.0.005 0.001 i
QEM-NUCTAR
.0.040 0.043 1
4 0.040 0.011 CERICAL 0.053 14 3
4 0.004-0-
l0 VENDOR O'
-0.143-39.134 l'
.274 l
ENGINEER 1.754 3.144 8
86 0.219 0.037~
EIEC. MAINT.
2.725 0.277 0.126 9
13 1
0.303 0.021-0.126 GEN. MAINT.
7.779 7.208 0.712 11 64 18' O.707 0.113 1.040 FTITER 5.180 5.375 2.179 8
20 11 0.648 0.269 0.198' HEALTH PHYSICS 11.669 0.019 9.564 15 6
28 0.467 0.003 0.342-l INSIM. & CNI3OL 2.338 0.368 11 6
0.213 0.061
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MAQiINIST 2.037 1.734 7
21.
0.291 0.083 l
OPERATOR 4.768 39 0.122 SEXURITY 0.291 0.021 32 2
0.009.
-0.011 STORES
'O.004 3
1 0.001 0-SUPERVISORY 0.467 0.011 21 7
0.022 0.002 4
TEQiNICAL 2.037 0.515 0.653 23 32 15 -
0.089 0.016-0.044 All h are in man-run and represent the pernenent (TID) whole body exposure at the Pbrt QLlhoun Station.
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Tablo 2.a.8 L
Whole Body Dose (Yearly Subtotals)
No. of People (W)
Average Dose 1983 Station Utility Contract Station Utility Contract Station Utility Contract ODf-DNIBCNME2ffAL 0.012 0.012 0.171 1
3 1
0.012 0.004
'O.171' CHEM-NUCEEAR 0.067 0.009 0.431 1
2
'3 0.067 0.005 0.144 CIERICAL 0.061 0.047 0.016 14 12 4
0.004 0.004 0.004 VENDCII 0.002 114.S30 2
287 0.001 0.399 ENGINEER 6.426 8.885 9.988 12 102 33 0.536 0.087 0.303 EIEC. MAINr.
4.852 4.136 9.444 10 13 31 0.485 0.318' O.305 GEN. MAINT.
13.257 33.418 7.881 12 59 21 1.105 0.566 0.375 FTITER 16.668 16.182 14.873 10
'20 14 1 A67 0.809 1.062 I
HEAIHH PHYSICS 30.462 2.156 15.426 23 7
31 1.324 0.308 0.498 INSIM. & CONIROL 8.168 1.919 1.297 12 3
3 0.681 0.640 0.432 MACHINIST 10.351 16.100 2.903 8
23 2
1.294 0.700 1.452 OPERATOR 12.697 0.118 40 2
0.317 0.059 SELUN.tri 0.490 0.028 32 5
0.015 0.006 STORES 0.018 0.004 3
2 0.006 0.002 SUPERVISORY 3.482 0.187 20 14 1
0.174 0.013 0
TECHNICAL 12.561 1.893 13.500 29 30 31 0.433-0.063 0.435 C*
All doses are in man-rem and Aq.u.asaut. the pm.mg=:ui. (TID) whole body avranwe at the Fort Calhoun Station.
e
Tablo 2.n.9, t
- mole Body Dose (Yearly Subtotals)
No. of 1%cple (Badges)
Average Dosa t
1984 Station Utility' Contract Station Utility Contract Station Utility contract i
]
QEM-ENVIR35ENIAL 0.009 0.003 1
2 0.009 0.002 QEM-NUCIEAR 2.661 0,
1.396 10 1
5 0.266-0~
0.279l CIERICAL 0.130 0.060
~0.034 10 12 15 0.013 0.005 0.002-VENDCR 237.919 441 0.539 ENGINEER 11.657 15.244 4.274 11-73 12 1.060 20.209 0.356 i
EIEC. MAINE.
6.930 5.342 10 12 0.593-0.445 j
GEN. MAINE.
12.287 31.267 11 43 1.117 0.727 F1 TIER 12.159 15.893 l'.351 0.836 9
19 HEALTH IHYSICS 31.964 23.856 14 22 2.283 j
~1.084 INSIM. & 03 m OL 9.487 0.291 11 1
0.862 0.291 i
i MAOIINIST 11.190 13.013 0.006 7
20 1
1.599 0.651 0.006 OPERAE R 21.090 0.632 37 2
0.570 0.316 1
}
SEXIRITY 1.146 0.061 36 2
0.032 0.031-I STCRES 0.040 4
O.010 1
I i
j SUPERVISORY 3.231 0.810 0.042 17 17 1-0.190 0.048 0.042
}
TECHNICAL 10.914 0.519 12.455 33 24.
27 0.331 0.022 0.461 i
l All doses are in man-nua and represent the permanent (TID) Wole body exposure at the Fort Calhoun Station.
i j -
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1 4
Tabla 2.n.10 4
W1 ole Body Dose (Yearly Subtotals)
No. of INKple (Rarir==)
Average Dose 1
R5
- Statim Utility Contract Station Utility Contract Station-Utility Contract QEM-DWIRCHENIAL 0.009 1'
~ 0.009 i
QEM-NUCEAR 2.291 0.003 1.488 11 3
8 0.208 0.001 0.186 C ERICAL 0.154 0.009 0.051 18 5
23 0.009 0.002 0.002 VENDOR 93.807 281 0.334-INGINEER 5.168 0.180 14 2
0.369 0.090 EEC. MAINT.
6.424 5.228 31.550 12 25 60 0.535 0.209 0.526 GEN. MAINT.
8.507 7.211 8.111 12 16 22 0.709 0.451-0.369 FITTER 7.949 15.783 41.646 9
23 101 0.883 0.686 0.412 HEAL'IH PHYSICS 22.014 40.870 16 53 1.376 0.771 4
INSIM. & C NIBOL 8.851 2.449 2.209 14 2
6 0.632 1.225 0.368 l
MACHINIST 6.667 12.796 7.122 8
21 15 0.833 0.609 0.475 OPERA'IOR 22.080 0.692 54 7
0.409 0.099 SEQRITY 0.813 0.023 35 1
0.023 0.023 SIORES 0.095 0.002 3
2 0.032 0.001 SUPERVISORY 4.654 0.023 0.076 23 10 4
0.202 0.002 0.019 1
TECHNICAL 1.067 6.058 1.835 21 123 74 0.051 0.049 0.025 QA/QC*
2.510 0.018 14.520 9
6 24
-0.279 0.003 0.605 i
New job function classification for Pariiation Rw-Lm Report.
All doses are in man-rem and rep 1.ar:=mt the per==ra: nit (TID) whole body Pire at the Fort alMm Statim.
- i I
b)
Provide a similar table for the years 2008 to 2013.
Include doses from expected decontamination, decommissioning, additional mainten--
ance and related doses.
RESPONSE
As discussed in the cover letter, the requested information.is -
being provided for the five additional years of service..The man-rem exposure to Fort Calhoun Station personnel for the years 2009 - 2013 are projections based on factual data obtained from whole body (TLD) readings documented from 1978 - 1985_according to job function. These projections da not include estimations for-plant decommissioning since decommissioning is a one-time source of exposure.
Exposures for decommissioning are expected to be identical. for a 2008 and 2013 plant shutdown.
Estimates for ex-tensive decontamination and special maintenance are also not in-cluded. ToLdate, the Fort Calhoun Station has not needed to utilize special or extensive decontamination methods.. Improve-ments in the ALARA prograa at Fort Calhoun Station along with tech-nological advancements in robotics, chemistry control,and decontam-ination processes should help to keep these exposures to a mini-mum.
.The projections for exposure are also based on estimated refueling outage schedules assuming eighteen-month fuel cycles.
For the five additional years, 2009'- 2013, it is estimated that there-will be three additional refueling cycle years and two non-refuel-ing cycle years. Table 2.b.1 shows the remaining and projected refueling outages.
Table 2.b.2 shows estimated exposures to personnel based on aver-age exposures received in outage years 1978,_1980, 1981, 1983, 1984, 1985, and non-outage years 1979 and 1982. These predictions are being treated as upper values. since dose savings from a con-tinually improving ALARA program should offset dose allowance for crud buildup. The predicted value is 106.3 man-rem for a non-out-age year and 443.7 man-rem for a refueling outage year. There-fore, for the five additional years, 2009 - 2013, the predicted total dose is 1543.2 man-rem.
l l,
Table 2.b.1 Remaining and Projected Refueling Outages Fort Calhoun Station Approximate Outages Start Dates Refuelina #
September 1988 11
-March 1990 12 September 1991 13 March 1993 14 September 1994-15 March 1996 16 September 1997 17 March 1999.
18 September 2000 19 March 2002 20 September 2003 21 March 2005 22 September 2006 23 March 2008 24 End of Current License
- September 2009 25
- March 2011 26
- September 2012 27 Projected additional refueling outages.
Table 2.b.2 PinTECIED ANNUAL MAN-REM EXESURE:
POEE CAIHXN SIRTICN - JOB MDKTION CPGEGGE 2009-2013 4
(Sheet 1 of 2) 1 QEMISITE CHEMISIRY ELECIRIchL GENERAL HEhI2H IN9Bt.
i D WIR0tMENIAL NUCIEAR CIERICAL VliNDGt DUINEER MAINI1l NANCE MhIN1DIAN 3 FIITER HlYSICS & 03MOL Yearly Ave.
< 0.1 0.3 0.1 38.2
' 5.7 2.4 11.9 10.3 16.0
=3.2 for narMx1tage years 2010 and 2013 i
i Yearly Ave.
0.1
- 3.9 0.2 137.1 21.8 19.7 48.4 63.4 43.5
'13.0 for outage years 2009, 2011, and 2012 4
Totals for 0.3 12.3 0.8 487.7 76.8 63.9 169.0 210.8 162.5 45.4 years 2009 -
2013
)
i 4
- 'Ihis man-rem a=-e is haw solely on 1984 and 1985 data due to a job function reclassification of a -
j number of people into the Owmistry Nuclear category frtan Health Ihysics.
i i
l i
'o :
Table 2.b.2 PR1TECTED ANNUAL MAN-REM EXPOSURE FIRP CAIBOUN STATIN - JOB FUNCI'IN CATEGGE 1
2009-2013 (Sheet 2 of 2)
MAGINIST OPERA 7tR SBaRITY FIORES SUPERVISORY TEGINICAL Oh/OC**
TUIRL Yearly Ave. for 4.9 7.5 0.2
< 0.1 0.8 3.2 1.4 106.3 m W years 2010 arxi 2013
.I l
Yearly Ave. for 35.4 18.1 0.7
< 0.1 3.8 17.5 17.0 443.7 outage years 2009, 2011, arti 1
2012 Totals for years 116.0 69.3 2.5
< 0.2 13.0 58.9 53.8 1543.2 2009 - 2013
- QA/QC projections are based solely on 1985 outage year arxi 1986 non-outage year.
1 _ _ _ _ _ _ _ _ _ _
3.
'10 CFR PART 51.52 a)
' Provide information concerning the requirements set forth in:10 CFR 51.52,.." Environmental Effects of Transportation of Fuel and Waste: - Table S-4" regarding transportation of fuel and radio-active wastes to and from the site.
Include a statement or a.
commitment which confirms that you will meet the transportation
. conditions 'of either Paragraph (a)lor _(b) of 10 CFR 51.52.
RESPONSE
The following statements meet the six transportation conditions of Para-
-graph (a) of 10 CFR 51.52.
(1)
.The reactor core thermal power level for Fort Calhoun_ Station is-1500 megawatts.
'(2)..The _ initial enrichment of Uranium-235 for the Fort Calhoun fuel assemblies does not exceed 3.8% by weight.: The current fuel man--
agement scheme for Fort Calhoun is a low radial leakage design with a core reload every 18 months. The possibility exists for Fort Calhoun to increase its fuel-cycle length to 24 months while maintaining the current fuel management scheme.
If this possibil-
- ity is implemented, the initial enrichment of Uranium-235 for Fort Calhoun fuel will most likely exceed 4% by weight.
.(3)
Presently, OPPD has no plans to transport Fort Calhoun nuclear fuel assemblies from the reactor site.
If fuel assemblies were to be transported, the District would meet the two criteria as men-tioned in the third condition of 10 CFR 51.52, part (a).
- (4)
The radioactive waste shipped from the reactor is reduced to a
- solid form and packaged.
(5)
Unirradiated fuel is shipped to the Fort Calhoun reactor by truck.
Presently, OPPD does not have plans to ship irradiated fuel off-site. However, if needed, irradiated fuel assemblies would be shipped by truck, rail, or barge. Radioactive waste is transport-ed from the plant by truck.
(6)
The Department of Transportation and the Nuclear Regulatory Commis-sion regulate the transportation of radioactive material. The pub-lic, along with transport workers, are protected from excessive radiation exposure by adherence to these regulations. ' A combina-tion of standards and requirements which are applicable to packag-ing help achieve this protection. There are limitations on radia-tion levels from packages and on their contents. Also, persons
.under normal and accident conditions have procedures which limit their exposures.
The Fort Calhoun Station Radiation Protection Manual, Section 11, covers the procedures governing process control, mixing, shipping, l
determination of curie content, waste form classifications, out-side storage and movement requirements, inventory control, collec-l tion and disposal practices, and packaging of radioactive waste.
m e
{ ~ ~'