ML20238C349
| ML20238C349 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/30/1987 |
| From: | Cargill E, Fantacci C GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20238C320 | List: |
| References | |
| NUDOCS 8709100051 | |
| Download: ML20238C349 (93) | |
Text
_ - - - - - - - _
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RIVER BEND STATION, UNIT 1
~
SEMIAMUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i
1 REPORT PERIOD: January 1,1987 Through Jur.e 30, 1987 l
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)
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REVIEWED BY
_ -sh 1.
~ ' ~~ blli/87 j
C.~L. Fantacci, Radiological Engineering Supervisor j
l APPROVED BY d
7 E. M. Car ~ gill, Director - Radiological Programs 1
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8709100051 070831' PDR ADDCK 05000450 R
PDR J
i:
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TABLE.0F CONTENTS'
.PAGE INTR' DUCTION 1
I.-
0
.II.
SUPPLEMENTAL INFORMATION 2
A.. REGULATORY LIMITS 2
B.
MAXIMUM PERMISSIBLE CONCENTRATIONS
-6 f(
C.
AVERAGE ENERGY.;
6 D.
MEASUREMENTS AND APPR0XIMATIONS OF TOTAL RADIOACTIVITY.
6
'E.
BATCH RELEASES 8
F.
ABNORMALLRELEASES 9
G.
ESTIMATE OF TOTAL ERROR 9-III.
GASEOUS EFFLUENTS
SUMMARY
INFORMATION 10
.IV.
~ LIQUID EFFLUENTS
SUMMARY
INFORMATION 10 l
'V.
SOLID WASTE-.
10 VI.
RADIOLOGICAL lMPACT ON MAN i10 w
,'VII.
METEOROLOGICAL DATA' 10-t
- VIII.
RADI0 ACTIVE LIQUID EFFLUEHT MONITORING INSTRUMENTATION OPERABILITY 10 IX.
.RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION OPERABILITY 11-X.
LIQUID HOLD UP TANKS 11 XI.
RADIOLOGICAL ENVIRONMENTAL MONITORING 11
.XII.
-LAND USE CENSUS 11 XIII.
OFFSITE DOSE CALCULATION MANUAL (0DCM) 11 XIV.
MAJOR CHANGES TO RADI0 ACTIVE LIQUID, f
GASE0US AND SOLID WASTE TREATMENT SYSTEMS 11 l
XV.
'lle 1
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s
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PAGE XVI.
-TABLES 1ABLEl1 RAD:0 ACTIVE GASEOUS WASTE l
SAMPLING AND ANALYSIS PROGRAM 12-l TABLE 2. RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 13 l
l TABLE 3 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES 14 l
-TABLE 4 GASEOUS EFFLUENTS - CONDITIONALLY
-l ELEVATED RELEASES 16-H TABLE 5 GASE0US EFFLUENTS - GROUND LEVEL RELEASES' 19 i
TABLE 6 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 22-
[
TABLE 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 26 i ODCM Changes 29 i
l ii
l FEMIAIMUAL RADIOACTIVE EFT 11]ENT REWASE REFORT FNmTY: River Bend Station, Iklit 1 LICENSER; Gulf States Utilities REPORP PERIOD: January 1, 1987 to June 30,'1987 I.
INTRODUCTION Enclcsed is the Semiannual Radioactive Effluent Release Import for
.the. period of January 1, 1987 through June 30, 1987. This report is subnitted in accortlance with Technical Specification 0.9.1.8 of Appendix A to River Bend Station (RBS) License Number NPF-47.
1 of 29
.\\ t {
A t
- II.- ~ SUPPLEMENTAL INFORMATION_
'A.
Regulatory Limits
- 1.. 10CFR20 Limits a.
Fission and Activation Gases In accordance wittt Technical Specification 3.11.2.1,.
the
. dose rate due. to noble gases released in~
~
gaseous effluents from the site to areas'at and beyond the SITE BOUNDARY shall. be limited to less than or equal to 500 mrems/yr to the total body and less than or equal to 3000; mrems/yr;to the skin:
DR
=
D se rate to the total body-in mrems/yr TB n
_[K 3.15 x 10 (X/Q) Q S 500 mrems/yr
=
g g
i=1 and DR
=
Dose rate to the skin in mrems/yr skin
-n 7 { (L
= 3.15 x 10
~
g + 1.1M )(X/Q) Qg $ 3000 mrems/yr g
i=1 (above terms defined in RBS ODCM).
b.
Radiolodines and Particulate In accorftnce with Technical Specification 3.11.2 1, the dose rate due to iodine-131, lodine-133, tritium,'and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents from the site 8
to areas at and beyond the SITE BOUNDARY shall be limited to less than or equal to 1500 mrems/yr to any organ:
DR Dose rate to the organ t for the age
)
I&BDPt group of interest from fodines, tritium, 3
and 8 day particulate via the inhalation j
pathway in mrems/yr n
{Pg (X/Q)p Qg 5 1500 mrems/yr
=
i=1 l
ll-(above terms defined in RBS ODCM)
J l
lL l'
2 of 29 LL_
c.
Liquid Effluents In accordance with Technical Specification 3'.11.1.1, the' L'.
concentration of radioactive material released in_ liquid
/.
effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20,' Appendix B,
Table-
~
II, Column 2 for radionuclides other than dissolved'and entrained noble gases. For dissolved or entrained noble gases, the con.:entration shall be limited.to 2 x 10 microcuries/ml total activity.-
2.
10CFRSO, Appendix I Limits a.
Fission and Activation Gases In accordance with Technical Specification 3.11.2.2, the air dose due.to noble, gases released in gaseous effluents to areas lat or beyond the SITE BOUNDARY-shall be limited.
to:
D
=
e gamma air. dose from radioactive noble Gamma-Air gases in mrad
=
Mg (X/Q) Qj 5 5 mrads/qtr 5 10 mrads/yr i=1 D
=
eta air dose from radioactive. noble Beta-Air gases in mrad n
.Ng(X[Q)Q $ 10 mrads/qtr 1
=
i=1 I
"#8 "!Y#
(above terms defined in RBS ODCM) b.
Radioiodines and Particulate In accordance with Technical Specification 3.11.2.3, the dose to a MEMBER OF THE PUBLIC from-iodine-131, i
iodine-133, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents i
releases to areas at and beyond the SITE B0UNDARY shall I
be limited to:
D
=
Dose in mrem to the organ (t) of a I68DPt specified age group from radiciodines, tritium, and 8 day particulate via the pathway of interest 3 of 29 h___m____m___.____._____
n
~0 })) R (X/Q)D O
=
3.17 x 10 i
i=1 and/or n
-8 ) ' R (D/Q) Q
=
3,17 x 10 f
g i=1 and D
=
Dose in mrem to the organ (t) of a specified age group from radioiodines, tritium, and 8 day particulate from all pathways t
n
}{} D 5 7.5 mrems/qtr
=
I&8DPt z=1
$ 15 mrems/yr (above terms defined RBS ODCM) c' Liquid Effluents In accordance with Technical Specification 3.11.1.2, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive mate rials in liquid effluents released to UNRESTRICTED AREAS shall be limited to:
D Total dose commitment to the organ (t)
=
TOTALt due to all releases during the desired time interval in mrem n
= { (Dta)i where:
DT0TALt i=1 4
i n
n A at Q D,=}'D f and ft y fy = g i=1 i=1 (DF)y D l i i i 1 l l l l l 4 of 29
_ = _ _ _ (if m and -D
- 1.5 mrems/qtr-TOTAL Total Body 3 mrems/yr D
5 mrems/qtr-TOTAL. ANY ORGAN ? 10 mrems/yr (above terms defined in RBS ODCM) 3. 40CFR190 Limits In accordance with Technical Specification 3.11.4, the annual (calendar year)fdose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and =to radiation from uranium fuel cycle sources, shall be limited to: 5 25' mrems to the total. body or any organ (except the thyroid) 5 75 mrems to the thyroid' 4. Miscellaneous Limits a. Ventilation Exhaust Treatment System in accordance with Technical Specification 3.11.2.5, the .ENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31 day
- period, b.
Liquid Radwaste Treatment System In accord
- ce with Technical Specification 3.11.1.3, the liquid raosaste treatment system ahall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the. projected doses, due to the liquid effluent, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.
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B. Maximum Permissible Concentrations 1. Gaseous Releases The RBS Radiological 'Sffluents Technical Specifications (RETS) for' gaseous -releases are based on the dose rate restrictions of 10CFR20, rather than the Maximum Permissible Concentrations (MPC)' listed in 10CFR20 Appendix B Table II, Column'1. 2. Liquid Releases The Maximum Permissible. Concentration of radioactive materials in'11guid effluents'is limited by 10CFR20, Appendix B,. Table-II, Column 2. The MPC chosen is the most conservative value (i.e., the lowest) of either the soluble or insoluble MPC for each radionuclides. C. Average Energy Not applicable to RBS RETS D. Measurements and Approximations of Total Radioactivity 1. Gaseous Effluents a. Fission and Activation Gases Periodic grab samples are obtained from the Main Plant Exhaust Duct, Fuel Building LExhaust Vent and Radwaste Building Exhaust Vent. These samples are analyzed utilizing high resolution germanium detectors coupled to computerized pulse height analyzers. The sampling and analysis frequencies are described in Table 1. Sampling and analysis of these effluent streams provide noble gas radionuclides relative abundances which can then be I applied to the ' noble gas gross activity and gross activity release rate to obtain nuclide specific activities and release rates. The noble gas gross activity released within a specific time period is determined by integrating the stack monitor release rate over the considered time period. An average correction factor of 0.227 has been utilized for this report period due to the infrequent. detection of noble gas radionuclides in the effluent stream. If no activity was detected between stack grab samples and significant increase in hourly averages were recorded, the nuclide relative abundances of the last sample which indicated the presence of activity was utilized to obtain nuclide specific activities. I 1 6 of 29 l i
U J7 q 'b.-' Particulate and Iodines g' -Particulate and iodines are continuously sampled ~from each of the three release points utilizing a' particulate filter 'and charcoal cartridge in line with'a sample pump. ~ -(stack monitor' pump). .These filters and charcoal. cartridges are removed and analyzed in accordance with .the -Frequencies. specified. in Table 1. Analysis is performed to identify and. quantify radionuclides. utilizing high resolutionLgermanium detectors coupled to computerized pulse -height analyzers. 'Given the nuclide-specific-activity concentrations, process flowLrate,. and time which the sample covered;- the nuclide specific activity-released to the environment-~ can -be obtained.
- Due to the continuous sampling process, it is' assumed
'that the radioactive matsrial.is released to-the environment at a ' constant _ rate;-within.the : sampling period. Sr-89-and Sr-90 are quantitatively analyzed by-counting the digestea filter precipitate with a gas' flow proportional' counter. Gross alpha analysis is performed using a zinc' sulfide scintillation counter. c. Tritium-Tritium grab. samples are obtained from.the three release points at.the specified frequencies. listed in Table l' utilizing an ice ' bath condensation collection method. The collected sample is then analyzed. utilizing a: Liquid Scintillation Counter. Given the' tritium concentration, process flow rate, and time period for which: the sample-is
- obtained, the tritium ' activity released to the environment can be determined. Due to the. frequency of sampling,- it is assumed that the tritium is released to
~the environment at a constant rate within the time period for which the sample is obtained. 2. Liquid Effluents Representative grab samples are obtained from the appropriate sample recovery tank and analyzed prior to release of the tank in accordance with the frequencies listed in Table 2. Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed utilizing a high resolution germanium detector coupled to a computerized pulse height analyzer. Tritium concentration is determined utilizing a Liquid Scintillation Counter. Sr-89 and Sr-90 are quantitatively analyzed by counting the precipitate with a gas flow proportional counter. Fe-55 is counted with a Liquid scintillation Counter after digestion of the iron. Gross alpha analysis is performed using a zine sulfide scintillation counter. Civen the nuclide specific activity concentration and total volume of the tank that was released, the activity of each ~ nuclide released to the environmer+. can be determined. I' l - 7 of 29 l l =., Y__-_.___-______-_____--_=__-_
E. Batch Releases ] 1. Liqcid / { 1st Quarter 1987 a. Number of batch releases
- 58 b.
Total time period for batch releases
- 298.27 hr c.
Maxiuum time period for batch releases 8.67 hr d. Average time period for batch releases 5.14 hr e. Minimum time period for a batch release .30 hr f. Average stream flot during periods of 3 release of effluent into a flowing stream : 616,900 ft /sec 2nd Quarter 1987 a. Number of batch releases
- 125 b.
Total time period for batch releases
- 668.99 hr c.
Maximum time period for batch releases 7.62 hr d. Average time period for batch releasea 5.35 hr e. Minimum time period for a batch release 2.38 hr f. Average stream flow during periods of release of effluent into a flowing stream : 505,000 ft /sec 2. Gaseous Primary Containment /Drywell purges are considered gaseous batch releases. Purges are directed through the Main Plant Exhaust Duct prior to release to the er.vironment and are therefore monitored by the Main Plant Exhaust Duct stack monitor. For purposes of this report, a purge is in effect only when purge inlet valves *A0V-128 and *A0V-166, and purge I outlet valves *A0V-165 and *A0V-123 are open. Containment venting (i.e., for pressure reduction) is not considered a release due to the short time duration of each venting period and limited motive force of the release. Due to logistical considerations, all releases through the Main Plant Exhaust Duct for the duration of the purge are considered as part of { the batch. 1st Quarter 1987 l a. Number of batch releases
- 38 l
b. Total time period for batch releases
- 191.7 hr i
c. Maximum time period for a batch release : 48.30 hr i d. Average time period for batch releases 4.79 hr e. Minimum time period for a batch releases : 0.07 hr j 2nd Quartet 1987 3 a. Number of batch rtleases
- 41 J
b. Total time p3riod for batch releases
- 283.07 hr 59.28 hr i
c. Maximum time perdod for a batch release ] d. Average time period for batch releases 6.58 hr l 0.05 hr 5 e. Minic.u. time period for a batch releases l a of 29
F. Abnormal Releases There were no abnormal releases during this eeporting period. / G. Estimate of Total Error 1. Liquid The maximum error associated with sample collection, laboratory analysis, and discharg3 volume are collectively l estimated to be: Fission and Activation Products : 1 14.2% Tritium - 1 14.2% Dissolved and Entrained Noble Gases : 1 14.2% Gross Alpha Radioactivity : 1 14.2% 2. Gaieous The maximum errors (not including sample line loss) associated with sar le flow, process flow, sample collection, monitor accuracy and laboratory analysis are collectively estimated to be: Fission and Activation Gases : 1 37.0% Iodines : 1 18.6% Particulate : 1 18.6% Tritium : 1 18 2% 3. Determination of Total Error The total error (i.e., collective error due to sample collection, laboratory analysis, sample flow, process flow, j monitor accuracy, etc.) is calculated using the following equation: (E )2 (E ) + (E ) +... E = T y 2 where: .i
- U"1 ***
- T E,E2... E individual errors due to sample
= 3 collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc. l l l 9 of 29
k Y: 7: -III. GASEOUS EFFLUENTS
SUMMARY
INFORMATION ~ ' L Refer to Tables 3, 4 and 3 for Summation of All Releases and Nuclides l L . Released,: 'respectively. It should be noted that an entry of l "0.00E+00" Ci or uC1/see sin this section does not indicate the absence. of ; - a. radionuclides;.but,. rather, -indicates that the concentration of.the particular radionuclides ~ below' the Lower was l~ . Limit of Detection (LLD) as listed in Table 1. l-IV. LIQUID EFFLUENTS'
SUMMARY
INFORMATION 1 Refer to Table 6 for Summation of All Releases and Nuclides Released. ItLchould be noted that an entry of "0.00E+00" Ci or uCi/ml in this section does'not-indicate the absence of a radionuclides; but, rather, 1 indicates that the, concentration of the particular radionuclides was below the Lower Limit of Detection (LLD) as. listed in Table 2. V. SOLID WASTE. Refer to Table 7 L VI. RADIOLOGICAL IMPACT ON MAN This information. will be provided in. the end-of-year report as described'in Technical Specification 6.9,1.8. VII. METEOROLOGICAL DATA This information will be provided in the end-of-year report as described in Technical Specification 6.9.1.8. .VIII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY The minimum number of channels required to be OPERABLE as described in Table 3.3.7.10-1 of Technical Specification 3.3.7.10 were, if inoperable at any time.in the period 1/1/87 through 6/30/87, restored to operable status within the required time. Reporting of these inoperable channels in this report is, therefore, not required. 10 of 29
c IX. RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERABILITY t F The. minimum number of channels required to be OPERABLE'as described ' n Table:3.3.7.11-1 of--Technical' Specification 3.3.7.11 were,. Ifl i inoperable-at any time in the period 1/1/87 through 6/30/87, restored to operable: status within the required time. Reporting of these inoperable channels in this report is, therefore, not required. X. . LIQUID HOLD UP TANKS The -maximum quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any unprotected. outdoor tank during the ' period of,1/1/87 through 6/30/87.was less than or equal to.the 10 curie limit as required by_ Technical Specification-3.11.1.4. XI. - RADIOLOGICAL ENVIRONMENTAL MONITORING-There were no chinges in sampling locations for the Radiological Environmental Monitiring Program (REMP) during the reporting period 1/1/87 through'6/30'87. XII. LAND USE CENSUS-This. information will be presented in the end-of-year report. The Land Use Census results will be'available in September 1987. XIII.10FFSITE DOSE CALCULATION MANUAL (ODCM) j Attachment #1 includes those changes along with a description of the I changes made to the RBS ODCM for the period 1/1/87 through 6/30/87. l l i XIV. HAJOR CHANGCS TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems for the period of 1/1/87 through 6/30/87. XV. PROCESS CONTROL PROGRAM (PCP) i No changes were made to the RBS Process Control Program (PCP) for the period 1/1/87 through 6/.30/87. 1 l l 11 of 29
t ) i(l 2 0 I 1 1 m m 4 6 4 6 4 1 1 I 1 1 i n/ L oi 0 0 0 0 0 0 0 0 0 0 - it 1 1 1 1 1 1 1 1 1 1 rtu x x x x x x x x x x ec( 1 1 1 1 1 1 1 1 1 1 we ot l eD s s s s r r r r e e e e t t t t t t t t i i i i M m m m m A s E E E E R i ~ G s a a a a) m m ms O y m R l m m mr P f a a a a ae 0 on G G G Gh a 9 S A t h 'e l l l l O p R I S py a a a a l S Y yt p p p p, A L Ti i i i i 1 A v c c c 1 3 c3 s 9 N i n n n 3 3 n1 s 8 A t i 3 i 3 i 1 1 i - o c r r r rI r R D A P H P H P 1 I P( G S N A ~ G N I 1 LP 'E M L A e e e B S t t t A y a ea ea T. E sc l l tl tl T min a u. iu iu S J se oe ce sce sce myu A l M M M Wcl Wil Moil Qoil W il q rp tp pt p pt p nae am rm mrm mrm S i nr h a aa oaa oaa U MAF CS PS CPS CPS O ESAG EV I TCA e e e 0 l l l s s s s I y p p p u u u u D gc m m m o o o o A nn a a a u u u u R ie S S S n n n n l u M M M i i i i pq b b b t t t t me a a a n n n n ar r r r o o o o SF G G G C C C C g s, e n e B, p i p y d yA T g l T t n t i t n e c i nc unc ei s tu d ou B ou s a nD l iD iD ad e a i t et ee. l l t uat t at l t e e Ps Bl s sl s esv R u i u aiu Rio na l t a wt a l b s ih enh d nh l a u ax uex aex l s o ME FVE RVE AaC esa G A B C D
~ TABLE 2 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Miniinum. of Detection Liquid Release Sampling Analysis Type of A:tivity (LLD) Type Frequency Frequency Analysis (uC1/ml) A. Batch Waste P P Principal Gamma 5x10~7 Release Each Batch Each Batch Emitters; except (Liquid for Ce-144 5x10-6 Radwaste-Recovery Sampie I-131 1x10-6 Tanks P M Dissolved and 1x10-5 One Batch /M Entrained Gases (GammaEmitters) P M H 1x10-5 Each Batch Composite Gross Alpha 1x10-7 P Q Sr-89, Sr-90 5x10-8 Each Batch Composite Fe-55 1x10-0 P = Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days 13 of 29
1 .1 TABLE 3 ) Effluent and Waste Disposal Semi-Annual Report 1987 Year j Gaseous Effluents.- Summation of All Releases ' 1/2 Quarters 4 8 Est. Unit Quarter Quarter Total 1 2 Error, % 1 A. Noble Gases i! 1. Total release Ci 0.00E+00 1.86E-01 3.70E+01-2. Average release rate uCi/sec 0.00E+00 '2.36E-02 1 for period 3. Percent of technical O.00E+00 7.52E-04 specification limit (1) B. Iodines I-131 1. Total I-131 and I-133 Ci 5.86E-05 1.50E-05 1.86E+01 I-133 C1 1.24E-04 2.11E-04 1.86E+01 I-131 2. Average release rate uCi 7.44E-06 1.90E-06 for period sec I-133 1.57E-05 2.68E-05 3. 1-131 + I-133 contribu-tion percent of techni-3.07E+00 8.51E-01 cal specification limit (2) { C. Particulate 1. Particulate with half-Ci lives of > 8 days 1.84E-04 (2) 1.86E+01 2. Average release rate uCi/sec i } for period 2.34E-05 (2) 3. Percent of technical specification limit (2) 8.73E-01 (2) I 4. Gross alpha Ci radioactivity 0.00E+00 (2) i
I ) 1 l i-l- Est. I Unit Quarter Quarter Total 1 2 Error, % D. Tritium 1. Total release Ci 1.10E+00 2.05E+00 1.82E+01 2. Average release rate uCi/sec 1.40E-01 2.60E-01 for period' 3. Percent of technical 4.03E-03 7.52E-03f specification limit (2) (1) Gama airdose limit of 5 mrads/qtr (T.S.3.11.2.2.a). (2) Not available for subasission at this time, supplemental report to follow. i f 15 of 29
L. L 4 l TABLE 4 Effluent and Waste Disposal Semi-Annual Report 1987 Year u. i Gaseous Effluents - Conditionally Elevated Releases 1/2 Quarters Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Ouarter 1 Quarter 2 j 1. Fission Gases i i Argon-41 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Krypton-85m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Krypton-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E4 00 Krypton-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Krypton-88 Ci' O.00E+00 0.00E+00 0.00E+00 0.00E+00 Xenon-133m Ci 0.00E+00 0.00E400 0.00E+00 0.00E+00 Xenon-133 Ci 0.00E+60 0.00E+00 0.00E+00 0.00E+00 Xenon-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 " non-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xenon-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xenon-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 unidentified Ci N/A N/A N/A N/A Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2. Gaseous Iodines Iodine-131 Ci 5.16E-06 1.41E-05 6.14E-07 8.CSE-07 Iodine-132 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 { ) l l ~ Iodine-133 Ci 1.06E-04 1.52E-04 1.85E-05 5.88E-05 f Iod_ine-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodine-135 Ci 0 00E+00 0.00E+00 0.00F+00 0.00E+00 f l l ) 16 of :.9 a
Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 3. Particulate Strontium-89 Ci 7.00E-07 (1) 1.24E-07 (1) Strontium-90 Ci 0.00E+00 (1) 0.00E+00 (1) ) Cesium-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Barium-ianthanum-140 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 q Cobalt-60 Ci 7.13E-06 0.00E+00 1.53E-05 0.00E+00 Chromium-51 Ci 3.83E-05 0.00E+00 4.54E-07 0.00E+00 Zirconium-niobium-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Zinc-65 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iron-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Manganese-54 Ci 8.48E-06 0,00E+00 1.91E-05 0.00E+00 ) _ Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Cerium-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f Cerium-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+0_0 Cobalt-58 Ci 8.46E-06 0.00E+00 1.87E-05 0.00E+00 Silver-110m Ci 0.00E+00 0.00Et00 0.00E+00 0.00E+00 Molybdenum-99 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 unidentified Ci N/A N/A _,, N/A. N/A Total for period Ci 6.31E-05 (1) 5.37E-06 I (1) t l i 17 of 29 o
Continuous Mode-Batch Mode Nuclides Heleased Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 4.C Tritium Hydrogen-3 Ci 8.88E-01 1.22E-01 1.64E+00 3.16E-01 (1) Not available for submission at this time, supplemental report to follow. Main Plant Exhaust Duct is consioered a conditionally elevated release point. l l 18 of 29 i. o
L l TABLE 5 l Effluent and Waste Disposal Semi-Annual Report 1987 Year Gaseous Effluents - Ground Level Releases 1/2 Quarters Continuous Mode Batch Mode Nuclides Released Unit ' Quarter 1 Quarter 2 Quarter 1 Quarter 2 '1. Fission Gases 1 l Argon-41 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Krypton-85n. Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Krypton-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Krypton-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Krypton-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xenon-133m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xenon-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xenon-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xenon-135 Ci 0.00E+00 1.86E-01 0.00E+00 0.00E+00 Xenon-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ Xenon-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 unidentified Ci N/A N/A N/A N/A Total for period Ci 0.00E+00 1.86E-01 0.00E+00 0.00E+00 -2. Gaseous Iodines Iodine-131 Ci 5.28E-05 0.00E+00 0.00E+00 0.00E+00 Iodine-132 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Iodine-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodine-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodine-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l 19 of 29
Continuous Mode Batch Mode P".lides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 3. Particulate 1 Strontium-89 Ci 0.00E+00 (1) 0.00E+00 (1) ] 4 Strontium-90 Ci 0.00E+00 (1) 0.00E+00 (1) I Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cesium-134 Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Bariurn-l anthanum-140 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cobalt-60 Ci 1.46E-0E 0.00E+00_ 0.00E+00 0.00E+00 Chromium-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zirconium-niobium-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zinc-65 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iron-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Manganese-54 Ci 3.25E-05 0.00E+00 0.00E+00 0.00E+00 Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodine-132 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 lodine-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cerium-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cerium-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cobalt-58 Ci 2.06E-05 0.00E+00 0.00E+00 0.00E+00 I 0.00E+00 Silver-110m Ci 0.00E+00 0.00E+00 0.00E+00 l Molybdenum-99 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 unidentified Ci N/A N/A N/A N/A Total for period Ci 6.77E-05 (1) 0.00E+00 (1) 20 of 29
l l Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 4.0 Tritium Hydrogen-3 Ci 8.78E-02 9.29E-02 0.00E+00 0.00E+00 (1) Not available for submission at this time, supplemental report to follow. Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent are considered ground level release points. 4 i 21 of 29 1 1
1 A TABLE 6 Effluent and Waste Disposal Semi-Annual Report _ 1987-Year Liquid Effluents - Summation of All Releases Est. Unit Quarter Quarter Total 1 2 Error, % A. Fission and activation products 1. Total release.(not in-Ci 1.82E-02 3.06E-02 1.42E+01-cluding tritium, gases, lpha a 2. Average diluted concen-uCi/mi 8.14E-08 6.42E-08 tration during period 3. Percent of applicable 1.46E+00 2.45E+00 limit (1)- . B. Tritium 1. Total release Ci 9.26E-01 2.54E+00 1.42E+01 2. Average diluted concen-uCi/mi 4.14E-06 5.33E-06 tration during period 3. Percent of applicable 1.38E-01 1.78E-01 I limit (2) C. Dissolved and entrained gases i 1. Total release Ci 2.89E-03 4.12E-03 1.42E+01 ~2. Average diluted concen-uCi/ml 1.29E-08 8.64E-09 tration during period 3. Percent of applicable 6.46E-03 4.32E-03 limit (3) 22 of 29 I
1 1 l 4 Est. Unit Quarter Quarter Total 1 2 Error, % D. Gross alpha radioactivity 1. Total release Ci 0.00E+00 0.00E+00 1.42E+01 E. Volume of waste released liters 3.43E+06 7.48E+06 8.73E-01 (prior to dilution) F. Volume of dilution water liters 2.20E+08 4.69E+08 5.70E-01 used during period (1) One quarter of 5 Ci annual limit (1.25 C1) for liquid releases except for tritium and dissolved or entrained nobie gases from 10CFR50 Appendix I. (2) 10CFR20, Appendix B, Table II, Column 2 MPC limit of 3.00E-03 uCi/ml. (3) Technical Specification 3.11.1.1 limit of 2.0E-04 uCi/ml for dissolved or entrained noble gases in liquid effluents. l l l 23 of 29
- )
Effluent and Waste Disposal Semi-Annual Report 1987 Year G. Liquid Effluents 1/2 Quarters Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 i Hydrogen-3 Ci N/A N/A 9.26E-01 2.54E+00 Arsenic-76 Ci N/A N/A 1.80E-04 1.24E-03 Strontium-89 Ci N/A N/A 0.00E+00 (1) Strontium-90 Ci N/A N/A 0.00E+00 (1) Cesium-134 Ci N/A N/A 0.00E+00 0.00E+00 Cesium-137 Ci N/A N/A 0.00Et00 0.00E+00 Iodine-131 Ci N/A N/A 0.00E+00 5,93E-05 Iodiney32 Ci N/A N/A 0.00E+00 0.00E+00 Iodine-133 Ci N/A N/A 0.00E+00 1.16E-04 [ Iodine-134 Ci N/A N/A 0.00E+00 0.00E+00 Iodine-135 Ci N/A N/A 0.00E+00 0.00E+00 t Sodium-24 Ci N/A N/A 0.00E+00 2.58E-04 Cobalt-58 Ci N/A N/A 1.46E-03 2.37E-03 Cobalt-60 Ci N/A N/A 1.17E-03 3.48E-03 l l Iron-55 Ci N/A N/A 0.00E+00 (1) Iron-59 Ci N/A N/A 5.54E-05 2.69E-04 Zine-65 Ci N/A N/A 4.33E-05 1.17E-04 Manganese-54 Ci N/A N/A 4.48E-04 4.05E-03 l 1 Manganere-56 Ci N/A N/A 0.00E+00 0.00E+00 [L Chromium-51 Ci N/A N/A 9.70E-03 1.77E-02 l j Zirconium-Niobium-95 Ci N/A N/A 1.58E-04 0.00E+00 i Molybdenum-99 Ci N/A N/A 5.27E-05 4.05E-05 l { Technicit.m-99m Ci N/A N/A 8.00E-05 4.99E-05 Copper - 64 Ci N/A N/A 4.70E-03 0.00E+00 J 3 Tin - 113 Ci N/A N/A 3.31E-06 3.71E-06 24 of 29
t Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Ouarter 2 Quarter 1 Quarter 2 Barium-lanthanum-140 Ci N/A N/A 0.00E+00 0.00E+00 Cerium-141 Ci N/A N/A 0.00E+00 0.00E+00 Cerium-144-Ci N/A N/A 0.00E+00 0.00E+00 Antimony-122 Ci N/A N/A 0.00E+00 1.32E-04 Antimony-124 Ci N/A N/A 0.00E+00 2.48E-04 Rhodium - 105 .Ci 'N/A N/A 0.00E400 3.59E-04 Bromine - 82 Ci N/A N/A D.00E+00 l 1.04E-04 Neptunium - 239 Ci N/A N/A 0.00E+00 1.88E-07 ' Total for period Ci N/A N/A 9.44E-01 2.57E+00 H. Dissolved and Entrained Gases Continuousfode Batch Mode Nuclides Released Unit Quarter 1 -Qu6rter 2 Quarter 1 Quarter 2 ~ Argon 41-Ci _N/A N/A 0.00E+00 0.00E+00 Krypton-85m___ Ci NLA N/A 0.00E+00 0.00E+00 Krypton-85 Ci N/A N/A 0.00E+00 0.00E+00_ Kryoton-87 Ci N/A N/A 0.00E+00 0.00E+00 Krypton-88 Ci N/A N/A 0.00E+00 0.00E+00 _ Xenon-133m Ci N/A N/A 0.00E+00 0.00E+00 Xenon-133 Ci N/A N/A 1.53E-03 2.18E-03 Xenon-135m Ci N/A N/A 0.00E+00 0.00E+00 Xenon-135 C1 N/A N/A 1.35E-03 1.94E-03 Xenon-137 Ci N/A N/A 0.00E+00 0.00E+00 Xenon-138 Ci N/A N/A 0.00E+00 0.00E+00 unidentified Ci N/A N/A N/A N/A 1. Toti:1 for period Ci N/A N/A 2.89E-03 l4.12E-03 (1) 'Not available at this tirne, supplemental report to follow. p 25 Of 29 3
i y TABLE 7 h 1 Effluent and Waste Disposal-Semiannual Report,19g7_ Year Solid Waste and Irradiated Fuel Shipments . Reporting Period 01/01/87 to 06/30/87 Qtr 1/2 A. Solid Waste Shipped for Burie.1 or Disposal (Not irradiated fuel) l I k l 6-month Waste Est. Total I 1. Type of waste Unit
- Period, Class Error, %
] 3 .a. Spent resins, filter sludges m 1.23E+02 A evaporator bottoms, etc. Ci 2.33E+02 2.24E+01 3
- b. Dry compressible waste, m
0.00E+00 N/A contaminated equip, etc. Ci 0.00E+00 0.00E+00 3
- c. Irradiated components, m
0.00E+00 N/A control rods, etc. Ci 0.00E+00 0.00E+00 3 d.Other(None) m 0.00E+00 N/A Ci 0.00E+00 0.00E+00 l 1 i l l' 26 of 29
l'- l I I l 2. l i l J p TYPE OF Spent Resins, filter Dry compressible Irradiated Components Otherl WASTE sludges, evaporator waste, contaminated control rods, etc. (None) bottoms, etc. equip, etc. I Principle H-3 8.38E-03 N/A N/A N/A I Radionuclides C-14 4.08E-04 I (Identify and Na-24 2.56E-03 % Aoundance) Cr-51 2.34E+01 Mn-54 2.72E4 01 Co-57 1.72E-02 I C0-58 1.27E+01 Fe-59 1.96E+00 Co-60 2.72E+01 Ni-63 5.58E-01 Cu-64 0.00E+00 Zn-65 5.82E+00 As-76 2.44E-05 Nb-95 2.42E-01 Zr-95 2.42E-01 Mo 99 3.27E-03 Ag-110m 0.00E+00 Sn-113 1.88E-02 Sb-122 1.29E-03 Sb-124 6.77E-01 1-131 2.99E-03 I-133 1.57E-07 Te-131m 0.00E+00 Te-132 0.00E+00 Ba-140 4.67E-06 La-140 7.35E-05 Ce-141 0.00E+00 Ce-144 0.00E+00 l W-187 6.62E-06 i Np-239 0.00E+00 l Cm-242 0.00E+00 g Sc-46 3.97E-02 j 1 TRO 0.00E+00 i l l 1 27 of 29
IVEE OF Spent Resins, filter Dry compressible Irradiated Components Other WASTE sludges, evaporator waste, contaminated control rods, etc. (None) bottoms, etc. equip, etc. Above Determined by: A. measurement B. estimation C N/A N/A N/A C. measurement and correlation TYPE OF Strong, Tight Liners N/A N/A N/A CONTAINER SOLIDIFICATION N/A N/A N/A AGENT OR Cement ABSORBANT 3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 21 Truck, Exclusive Use CNSI, Barnwell, South Carolina B. IRRADIATED FUEL SHIPMENTS (Disposition) Number of Shipments Mode of Transportation Destination ~ 0 N/A N/A l 28 of 29 L_ _ -----__-__ _
I ATDONENT (1 OEF SI'IE DOGE CAintrATIN M7D E CHAICES NOTE: The previous ODCM was criginally 112 pages in length. The procedure change forms identify the page number prior to the revision. The attached corrected pages are the current revised pages with change bars in the right hand column indicating the changes and the current wording. 1 l s l l l 29 or 29 l t
I I 1 l g l ATTACHMEST - 1 l ODCM/ PROCEDURE REVISION LOG l 1 l__.- 1 I l l DESCRIBE THE ISTORtfATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, I { l 07ae 2a 4 l{e A 5ee 'i6w 3.3.a.z. /hdodblesv l ETC.) f i l V L& c
- c. &
fl nTf l j i ~ l i I l 0 h %,, o < Tec m yn etwom j l l I i l l 1 I I DESCRIBE (IN DETAIL) THE CHANGE (5) TO BE MADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DES'.:RIPTION OF THE CHANGE (S) MADE TO THE ODCM: I I i N po ovnohe n t Fv ro v l { V 4 l s' 1 I I I 1 l i I { l 1 I I _ _. ' t ~ l_ -l 1_ l I i 1 REFERENCES (AITACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S Ah*D 50.59 l ! REVIEWS): l l l 1 I I I I I I I I I I I VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS pR l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.1.'.)? HS NO V i l I l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l l SPECIFICATION 6.5.2. I 7fL( ~h/7 l REVIEWED, RADIOLOGICAL ENGINEERING SUPERVISOR: l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: _ ) [ dd'"7 l 37< [ /> j ~, I I I l I 11 I I i l ATTACHMEST I PAGE 1 Il l l i i 1 l 0F 1 11 RSP-0008 i REV - 0 l PAGE 112 0F II: I I I ll l e
l 2,.. NOTE The K,gg methodology for determining Q s uld TB be used only if isotopic analyses are not available (i.e. prior to initial criticality) or if the i relative abundances of noble gas nuclides in the i 1 effluent stream are similar to thoi. listed in l Appendix D or similar to the noble gas isotopic mixture described in the previous Se:aiannual 1 Effluent Report. (Reference 1.2.19) j Step 2 ' Determine Q, (the maximum acceptable release rate of all gas radionuclides in the gaseous effluent [uci/sec)) based upon the skin { 4 exposure limit of 3,000 mrem / year for all release points by: ~0 ~0 3,000 = 3.17 x 10 3,000 (0.8) Q, = 3.17 x 10 (57Q){(Lg +1.1M )f ) (X/Q)(L+1.1M),gg g f i l i Lg + 1.1Mg Total skin dose factor due to emission from noble = gas radionuclides (i) mrem /sec/uC1/m from Appendix C. E (L (L+1.1M),gf 1 g + 1,1 M ), f, effective total skin = g f i dose factor (mrem /sec/ pCi/m ) from Appendix C Table C-4 NOTE The (L + 1.1M) methodology for determining ,gg Q, should be used only if isotopic analyses are not available (i.e, prior to initial criticality), or if the relative abundances of noble gas isotopic mixture described in the effluent stream are similar to those listed in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) l l l-RSP-0008 REV. I l' AGE 22 0F 111 1
I [ i l- - l l l ATTACHMEhT - I l ODCM/ PROCEDURE REyISION LOG l l I I 1 I 1 DESCRIBE TE INFORMATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, I ino 0 a ftn y l Aech;m
- 3. 3 'z 't cap 2 3 c5 is2 l
l 4 a 3 te n L y l 6' l annd h 4'n e G< l I I l l he ln us s m ma h sin w ,,o on ua 4 ;m i l Msg: g g v l l l t l I DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE TE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO TE ODCM: l I l l Ti oanronk.cnI ti v < o f I l -- v v g l 1 I I I I I I I I l
- 1 l
.l - I -1 l l l l I REFERENCES (AITACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEWS): l I I I I I I I l i i I I I l WILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS OR l l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)? TES NO / i l I l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l SPECIFICATION 6.5.2. l REVIEWED, RADIOLOGICAL ENGINEERING SUPERVISOR: h /S ' ) / l REVIEWED, SUPERVISOR - RADIOLOGICAL PROGRAMS: / /k 7 l l / / / I I I I I I I II I I I l l ATTACHMENT l PAGE 1 ll l l l l 1 1 0F 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 112 l l l ll I l l l
.'. + '. l L NOTE The K,ff methodology for determining QTB
- he used only if isotopic analyses are not available (i.e. prior to initial criticality) or if the relative abundances of noble gas nuclides in the effluent stream are similar to those IJsted in l
Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) Step 2 Determine Q, (the maximum acceptable release rete of-all gas radionuclides in the gaseous effluent [uci/sec)) based upon the skin exposure limit of 3,000 mrem / year for all release points by: Q, = 3.17 x 10'. 3,000 = 3.17 x 10" 3,000 (0.8) (5[Q){(Lg '1.1M )f ) (5[Q)(L+1.1M),ff 1 f i I Total skin dose factor due to emission from noble Lg + 1.1Mg = gas radionuclides (i) mrem /sec/uC1/m from Appendix C. E(L (L+1.1M),ff g g + 1.1 M ) f, effective total skin = f dose factor (mrem /sec/ 11Ci/m ) from Appendix C Table C-4 NOTE The (L + 1.1M),ff methodology for determining Q should be used only if isotopic analyses s are not available (i.e, prior to initial criticality), or if the relative abundances of noble gas isotopic mixture described in the effluent stream are similar to those listed in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) l RSP-0008 REV. 1 pA;;E 22 0F 111
I I i l 1 i l ATTACHMEhT - I l ODCM/ PROCEDURE REVISION LOG l I ( l l l l l DESCRIBE THE IhT0101ATION TO BE CHANGED (INCLUDE P/GE NUMBERS, EQUATION NUMBERS, I l [ae 2 3 eS 5eef o,3 3 3 2. Z /Mdkodoloa v l A +en _(L l' o l L + L i m l e t t =-- l l ~ Fa adiovd l I I comolek s +n beW : e F4ec+ue +ef 4 / c, k N dose h e+ov i l ( m ve m /sec /o c / # ) 46 Acae. dix cm j l % hle C-4. l 1 l l l l DESCRIBE (IN DETAIL) TE CHANGE (S) TO SE MADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO THE ODCM: l l 1 L l Thocavankie<ti E vvo v l l /d U l l' l ll l 1 l I l i I I I i I l 1 - 1 I I I I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEWS): i i l l 1 l __ l l I I I i __ l I l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS OR l l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.la)? TES NO 1/ l l l TESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l SPECIFICATION 6.S.2. i l REVIEWED, RADIOLOGICAL E!jGINEERING SUPERVISOR:b h 01 h0D b,.9fI7 REVIEWED, SUPERVISOR - RADIOLOGICAL PROGRAMS: 1 / I l l I i ll l l l ATTACHMENT l PAGE 1 ll l l l l 1 1 0F 1 li RSP-0008 l REV - O l PAGE 112 0F 11 I I I II I I i
. = l 1 i NOTE The K,ff methodology for determining Q should TB be used only if isotopic analyses are not available (i.e. prior to initial criticality) or if the relative abundances of noble gas nuclides in tiae effluent stream are similar to those listed in l Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) Step 2 Determine Q, (the maximum acceptable release rate of all gas radionuclides in the gaseous effluent [vCi/sec]) based upon the skin exposure limit of 3,000 mrem / year for atl release points by: -8 Q, = 3.17 x 10". 3,000 = 3.17 x 10 ,,,3 000 (0.8) (X/Q) (Lg +1.1M )f ). (X/Q)(L+1.1M),ff f f i l Tota) skin dose factor due to emission from noble L1 + 1.1Mg = ges radionuclides (i) mrem /sec/uC1/m from Appendix C. E(Lf + 1.1 M ). f, effective total skin (L+1.1M),ff 1 = f f dose factor (mrem /sec/ pCi/m ) from Appendix C Table C-4 NOTE The (L + 1.1M),ff methodology for determining Q should be used only if isotopic analyses s are not available (i.e, prior to initial criticality), or if the relative abundances of noble gas isotopic mixture described in the effluent stream are similar to those listed in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) RSP-UCOS REV. 1 PAGE 22 0F 111
I i*;a. l l ' ATTACHMENT - 1 l ODCM/ PROCEDURE rey!SION LOG { 1 l l l = 1 l DESCRIBE THE IbT0RMATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, l l Oa A > y G) 'fiz N 6 ec k-im 3 L 2. ? Jhikclcfens/ l v J rs th d a dnie od Go, /he.,,4<a (P+c % A cia m t, A ) l l* l $ 4.> n 7- ] I I I i l C Fau e r (Cfm) -fu lo uev cace c (cJ.nT { l l I _.l l I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l l 1 i T1 m er vo t% ico i A no v i l u< J v l l 1 I I l i I I I._ l I i l l I I l l 1 l l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FCRMS, TCN'S AND 50.59 l l REVIEWS): l l I l I I I l l l l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCUIATICNS CR l SETPOINT DEERMINATICNS (TECHNICAL SPEC.IFICATICS e.it.)? iTS NO V' l l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUAST TO ~ICHNICAL i SPECIFICATION 6.5.2. l REVIEVED, RADIOLOGICAL E!jGINEERING SUPERVISCR: N -A REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: / [ d 'M/b f l 1 l I ll i l l A'I~ACHMENT l PAGE 1 II I I i 1 i 0F 1 II RSP-0008 i REV - 0 l PAGE 110 0F 1:I l-I 11 I I
~ where: 2.12 x.10 = Unit conversion factor to convert uCi/sec/cfm to uCi/cc. Q = lower of the two Q values, Q
- O*
TB s F = The maximum acceptable effluent flow rate at the point of release based on desitm flow rates (cfm) l Step 3 Multiply the C,value determine in Step 2 by 0.33. By multiplying the C,value by a factor of 0.33, the allowable operating setpoints will be administrative 1y controlled to allocate one-third (1/3) of the total allowable release to each of the release points. The resultant product will be the actual ODCM activity concentration HIGH ALARM setpont for the appropriate PSG monitor gas channel. Step 4 f l Multiply the actual ODCM activity concentration HIGH ALARM setpoint obtained in Step 3 by the applicable monitor's loop accuracy plus a conservatism factor (if desired). j l Step 5 Subtract the product obtained in Step 4 from the actual ODCM activity concentration HIGH ALARM setpoint. This remainder is the setpoint to be entered into the applicable monitor's RM-80. b. Alert Setpoint determination (Reference 1.2.12) 1. Wide Range Gas Monitor (WRGM) 1 Step 1 l U* * *i"* O -A (raaximum acceptable total release rate of all noble gas G radionuclides in the gaseous effluent [uci/sec] based upon the quarterly (92 days) gamma air dose limit of 5 mrads at the SITE BOUNDARY for all release points: Q -A = 1.26 x 10~7 (5)(0.8) 1.26 x 10~7 (5) 3.3.2.2-4 = G (X/Q) (M,ff) (X/Q) {M f g f i i I I RSP-0008 REV. 1 PAGE 21 OF 111 ) .]
j =, I l I i (' ~ l l l ATTACHMEST - 1 l ODCM/ PROCEDURE REyISION LOG l 1 l i I I l DESCRIBE THE INTOEt!ATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, l l op n -dl
- SufiN,
>> 5. 7. 7 'Ak (ba V l l r b, Nm+ P> df o,r/ ric h,y,.oi;n, v> l V U l ^ i V) l($ f 0 $ ru p Gn< /) % ele.1 ( W PG % % l l / l l .< fP O l (?A<?n4:cs >. 43. ?, 7. 'f l l l l h na k bi r*m in P'1ach ~ l l l l I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND I 1 A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l J l 1 j l Yv4>o u D hiec I Fr y e v" l 'I v s l l l i i i l l i 1 I I I I l .l ' l - I I I l I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE TCRMS, TCN'S Aht 50.59 l l RE'cIEWS): 1 I _. I I _.. I_ I l-i i I l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS OR l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)? iTS NO / l l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO 2 CHNICAL l SPECIFICATION 6.5.2. n l REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISOR: [ // i /?[P '> REVIEVID, SUPERVISOR - RADIOLOGICAL PROGRAMS: [u cA i l / l 1 I I 11 I I l ATTACHMENT l PAGE 1 ll l l l 1 l 0F 1 Il RSP-0008 i REV - 0 i PAGE ll: OF '.:: I I ll I i l o
e, where: 2.12 x 10' = Unit conversion factor to convert uCi/sec/cfm to uCi/cc. Q = lower of the two Q values, Q
- O' TB s
F = The maximum acceptable effluent flow rate at the point l of release based on design flow rates (cfm) l Step 3 Multiply the C,value determine in Step 2 by 0.33. By multiplying the C,value by a factor of 0.33, the allowable operating setpoints will be administrative 1y controlled to allocate one-third (1/3) of the tctal allowabis release to each of the release points. The resultant product will be the actua? ODCM activity concentration HIGH ALARM setpont for the appropriate P&G monitor gas channel. Step 4 Multiply the actual ODCM activity concentration HIGH ALARM setpoint obtained in Step 3 by the applicable monitor's loop accuracy plus a conservatism factor (if desired). l Step 5 Subtract the product obtained in Step 4 from the actual ODCM activity concentration HIGH ALARM setpoint. This remainder is the setpoint to be entered into the applicable monitor's RM-80. b. Alert Setpoint determination (Reference 1.2.12) 1. Wide Range Gas Monitor (WRGM) Step 1 I O -A (rnaximum acceptable total release rate of all noble gas G radionuclides in the gaseous effluent [uci/sec) based upon the quarterly (92 days) gamma air dose limit of 5 mrads at the SITE BOUNDARY for all release points: I Q _g = 1.26 x 10'l (5)(0.Sl 1.26 x 10' (5) 3.3.2.2-4 = g (X/Q) (Meff} ( !Q) M i i i I l l l l 4 RSP-0008 RE\\' 1 PAGE 24 0F 11l ) l l
y $,1 1 I I i l ATTAC10fENT - I l ODCM/ PROCEDURE REyISION LOG l 1._, l-- I l 1 l DESCRIBE TE INF0F#ATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, l m} Hi-Sof0s1 % 3-Q2. 1]w Gktfon. V l ,o v v h A l+ < -t So1/ N.,f de %,, ~ 4 e.n '/ l lJ ~ ) ,J.4+ Kn n%p (L a c. n 7a, ; +<> < f vt er rn \\ l l [ < 4 < <:) J [ j e y n %/ .d e m ;4t m, j l l l /p ry,' r. (ev.n h %u) n4b+v- / 76 y /n-/ l l l \\ I I l DESCRIBE (IN DETAIL) TE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND 1 l A COMPLETE DESCRIPTION OF THE CHANGS(S) MADE TO TE ODCM: l I-1 l 7 9 0 o a ra o h ir a I F<w< l )v v u l l 1 1 I I l i I l l I I I j l l l 1 l~ l -I I l l I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FDRMS, TCN'S AND 50.59 l l REVIEWS): I l I I l i i I l l l l I WILL THIS CHANGE REDUCE TKE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS QR l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.la)? HS NO V l i l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, Pl~4 SCANT TO TECHNICAL i 1 SPECIFICATION 6.S.2. REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISOR: {- d /5 h / l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: 6 2 /9,4r i l I l I 11 I i l ATTACHMENT I PAGE 1 ll l l l 1 1 0F 1 ll RSP-0008 l REV - 0 l PAGE !!2 0F 11: 1 I II t
g .E. s i 1 'The highest calculated annual' average relative I Where: (X/Q) = dispersion factor for an area at or beyond the SITE ) BOUNDARY for all sectors (sec/m ). See Appendix F l 1 for (X/Q) for the considered release point. 3 Effective gamma air dose _ factor (mrad-m /uCi-sec). M = gf See Appendix C, Table C-5 for applicable values. 5 = 5 mrads/ quarter (92 days) gamma air dose limit at the SITE BOUNDARY. The gamma air dose factor for radioactive noble H = g gas nuclide (i) in mrad-m /uCi-sec (Appendix C) 1 The fractional abundance of noble gas radionuclides l f = g -1 ~ 1.26 x 10 Inverse of number of seconds per quarter in l = quarters /second 0.8 = Conservatism factor to account for changing isotopic inventory i NOTE ( odology for determining Q,g should The M,fg met g be used only if isotopic analyses are not available (i.e., prior to initial criticality), or if the relative abundances of noble gas nuclides in the effluent stream'are similar to those listed in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) Step 2 Determine Q -A (maximum acceptable total release rate of all noble gas B radionuclides in the gaseous effluents (uci/sec) based upon the quarterly (92 days) beta air dose limit of 10 mrads at the SITE BOUNDARY for all release points.
- 1. 6 x 10 (10) (0.8)
Q 1.26 x 10 (10) = = B-A (X/Q) (N fg) (X/Q) {N f 3.3.2.2-5 j i t { RSP-0008 E' I I
s l l l. 1 I j l ATTACHMEhT - I l ODCM/ PROCEDURE REyISION LOG l l l l l l l DESCRIBE THE INF0F@ATION TO BE CHANGED (INCLUDE PAGE SU!BERS EQUATION NUMBERS, l p & d'{l7 6Wbw ~'> ~$ 2. Z. '/}lDYnffrtlcn y' l l a b 4/vi 6eicerf </ o M,.. e i i r.s '/ l J ]V ) Is t t ef # // n ructo Aos r//~.4 v ( M cG m 3 l ~ l l opo 7 _l { l Ea #,~ s L z. z -s- ] I l l /ww e tc/ou S. <.4..c h sica
- ~
.w u n 4 : n, 1 v I I I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l I l Fern v l 4 s l ~/ v a a v nO h ir, i s* V v l l l l l i i l I. I l - 1 I_ I I i i 1 I - I l l i l i l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE PORMS, TCN'S AND 50.59 l l REVIEWS): I I l l l I 1 l l 1 l 3 I l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS yR I SETPOINT DETERMINATIONS (TICHNICAL SPECIFICATION 6.it.)? HS NO / 1 l THESE CHANGES HAVE BEEN REVIEWED AND FOUND ACCEPTABLE, PURSUANT TO ~ECHNICAL l l SPECIFICATION 6.5.2. l REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISCR: 77 kb i REVIEVED, SUPERVISOR RADIOLOGICAL PROGRAMS: / l / '/ j l l I i ll l I l ATTACH.EST l PAGE 1 ll l l 1 1 1 l OF 1 ll RSP-0008 i REV - 0 l PAGE 112 0F 11: I l Il u-
y K D' e Where: (57Q) The highest calculated annual average relative l = l. dispersion factor for an area at or beyond the SITE li 3 BOUNDARY for all sectors (sec/m ). See Appendix F f ( fot (X/Q) for the considered release point. M,ff Effective gamma air dose factor (mrad-m /uCi-sec). = See Appendix C, Table C-5 for applicable values. l 5 5 mrads/ quarter (92 days) gamma air dose limit = at the SITE BOUNDARY. H = The gamma air dose factor for radioactive noble l g gas nuclide (1) in mrad-m /uCi-sec (Appendix C) f The fractional abundance of noble gas radionuclides = f i i -7 1.26 x 10 Inverse of number of seconds per quarter in l = quarters /second 1 0.8 = Conservatism factor to account for changing isotopic inventory NOTE The M,ff methodology for determining Q g shcuM g be used only if isotopic analyses are not available (i.e., prior to initial criticality), or if the relative abundances of noble gas nuclides in the effluent stream are similar to those listed in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) Step 2 Determine Q -A (maximum acceptable total release rate of all noble gas B radionuclides in the gaseous effluents luCi/sec] based upon the quarterly (92 days) beta air dose limit of 10 mrads at the SITE BOUNDARY for all release points. 1.26 x 10~7 (10) (0.8) ~7 (10,), Q 1.26 x 10 = = g,g ) eff) ) 3.3.2.2-5 i i I i RSP COOS N-I
l
- *a-l A'ITACHMENT - I l
ODCM/ PROCEDURE REyISION LOG l l I l-l DESCRIBE 1~tE IhT04t!ATION TO BE CHANGED (INCLUDE PAGE NUMBERS l' l o 32 c,$ tli 60ehien ~& 'l. l. 2 0MYtocln[cc,v l h. ^ j eAn t (%e v <m d < k;>a he,s o V l l 6c e md e g lin 4 to w l u l 1 l I l-l (* h o mo.o En ue % (J r '. k r em ~%Hl 7'-Z 'to '>< +. I. ? h - 1 I I i l I I I l DESCRIBE (IN DETAIL) TE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND 1 l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO THE ODCM: l ~ ~ ~T4 cn a voOk v sl h=Wnv - u o i l i I l i I i i l i 1 i I _t I l I I l 1 l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S ANT 50,39 l l REVIEWS): l 1 I I I I I I I i .f I 1 I l VILL THIS CHANGE REDUCE TE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS 0 ' i l SETPOIST DETERMINATIONS (TECHNICAL SPECIFICATION 6.11.)? YES NO l l TESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL 1 SPECIFICATION 6.S.2. N i 'W" l I'III7 i REVIEWED, RADIOLOGICAL ENGINEERING SUPERVISOR: /// / [gysby.n/9/cf 7 yr7, l l REVIEVID, SUPERVISOR - RADIOLOGICAL PROGRAMS: // / l I l l 1 11 1 I ) AITACHMEST l PAGE 1 (( l l 1 1 1 0F 1 ll RSP-0008 I REV - 0 1 PAGE 110 0F 11: I l Il l e
1 The following equations provide. for total body and skin dose ; i calculations based on actual noble gas releases during a spec;.f:.c time i ' interval for radioactive gaseous release sources at the site boundary: n bKi*( 0)
- Q 3.4.1.2b.-1 D
"3 Total B %r F i i=1 n b (Li + 1.1M ) x (T/Q) x Q 3.4.1.2b.-2 D
- 8 Skh F
1 1 i=1 Where: D = The total body dose from radioactive noble gases in mrem. K = The total whole body dose factor due to gamma emmissions from 1 noble gas radionuclides (i) (mrem /sec per uCi/m ) from Appendix C, Table C-1. (X7Q)=Thelong-termatmosphericdispersionfactorforgroundicvel (annual average) for the year of interest for the maximum receptor. Actual meterological data and sector wind frequency j distributions will be used to dntermine annual X/Q for the year of interest in sec/m (Appendix E). NOTE i For purposes of calculating D and Total Body DSkin ' # Release Report, X/Q values based on meteorological i data for the actual considered time period should beusedratherthanhistorical(T[Q) values. If at all possible, these real time X/Q values should i also be used when determining 40CFR190 compliance when Technical Specification limits have been exceeded by a factor of two (2.0). 1 l l Q = The number of uCi of noble gas nuclide (1) released during the 1 period of interest. l i l D = The skin dose from radioactive noble gases in mrem. Skin I M = The gamma air dose factor due to gamma emissions from each noble gas radionuclides (1) released. i RSP-0008 REV. 1 PACE 31 F 111
I i o.1 1 I l l ATTACHMEhT - 1 l ODCM/ PROCEDURE REyISION IDG j l-l.- 1 I l l DESCRIBE 'IEE IhTORt1ATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, [ l $I gd N7-6AcS A 5 6. 3 M tedpJ Miway ~] i o / g v )~ l l l V M+ao :
- Iman i y y' e
-tv s lin a>r>/y c l l G l t ___ 1 I 1 I I I I i INCLUDE THE RATIONALE FOR AND 1 l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l 1 1 l TNpaavnOhicd 2Evvc f i l U,_ 0 l v* l l 1 ._. I i _l I ~l 1 I { i i 1 __ t I ._. I I l I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE F0FMS, TCN'S AND 30.39 ) I l REVIEVS): I i l I I l { l I I l l WILL THIS CHANGE REDUCE TEE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS pR 'S NO < 1 SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATICS 6.14)? l l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PUESUANT TO TECHNICAL 1 j l SPECIFICATION 6.5.2. N i l \\ l REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISOR: J ol dC[_,,.. /f/./ 2 d M/lF7 REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS:. / t 3 l I l I ll l l l ATTACHMENT l PAGE 1 ll l l l 1 1 0F 1 ll RSF-0008 i REV - 0 l PAGE 11 OF 11; I I lI I l 1 )
H The dose from other fuel cycle sources will be treated as < 1 mrem /yr. 5.6 Skin Dose The dose to the skin will be calculated for the limiting sector as the sum of: 5.6.1 Direct Radiation (frem storage tanks, N-16 sources, etc.) 3 l The component of dose to the skin due to direct radiation will be determined by thermoluminescent dosimeters (TLDs). 5.6.2 Inhalation Dose The inhalation dose to the skin (only tritium is considered) will be ) determinedatthecalculationallocationsforeachagegrhupaccording to the methods outlined in Sections 2.0 and 3.0 of this manual. 5.6.3 Ingestion Pathway (cew milk, goat milk, racat, vegbtation) The dose to the skin via the ingestion pathway (only tritiuq and C-14 considered) will be calculated at thn consumer locations forg the consumern at risk. If no milk pathway exists in a sector, t,be dose \\ via this pathway will be treated as < 1 mrem /yr. l 5.6.4 Skin Noble Gas Immersjon Dose l l This dose will be calculated in accordance with Section 3.4.1.'g.b for I the maximally exposed MEMBER OF THE PUBLIC in the limiting sect r(s). l l l 5.6.5 Ground Plane Deposition 1 5.6.6 Other Uranium Fuel Cycle Sources This dose from other fuel cycle sources will be t reat ed as < 1 ra rem /yr. \\ l 1 6.0 INTF.RLABORATORY COMPARISON STUDIES l 6.1 Recluirement Technical Specificat. ion 3.12.3 states " Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory i l Comparison Program that has been approved by the Commission." l l 6.2 Pn gram l 1. 1 l l Rse-ucos Rrx. t eact . or n : l l l
1 l j l l I { l ATTACHENT - I l ODCM/ PROCEDURE REFISION LOG l 1 I I i i l DESCRIBE TE ISTOR!'!ATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, i h TCe$ lT7- 'k k itv) TA. Y Shiel No Nlc 0.$~iinnwe&n &c ji g s o i l l ( 6a nc c ! n r o 1. t in n II V +n /ncuy ; m o_ v1 y l l i l l I l l -1 i l l DESCRIBE (IN DETAIL) TE CHANGE (S) TO BE MADE. INCLUDE TE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO TE ODCM: 1 I I l Ty r*,0 ro pl..e c I F r m y-l l
- V J
l l 1 I I I I I I I I I I I 4 l - 1 I I I I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FCRMS, TCN'S AND 30.59 l l REVIEWS): 1 I I I i i l I_ l I l I I l WILL THIS CHANGE REDUCE TE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS CR 'IS NO / l SETPOINT DETEPdINATIONS (TECHNICAL SPECIFICATION 6.11.)? l l TESE CHANGES HAVE BEEN REVIEWED AND FOUND ACCEPTABLE, PCESUANT TO *ECHNICAL l SPECIFICATION 6.5.2. 1 REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISCR: .,b h l REVIEWED, SUPERVISOR - RADIOLOGICAL PROGRAMS: FY7 l / y i j l l 11 I I l AT*ACHMENT l PAGE 1 ll l l l l 1 1 0F 1 ll RSP-0008 l REV - O l PAGE 112 0F... I ll l I
j,... j The dose from other fuel' cycle sources will be treated as < 1 mrem /yr.. 5.6 Skin Dose .,~ 'The dose to tho' skin will be calculated for the limiting sector as the sum of: 5.6.1 Direct Radiation (from storage tanks, N-16 sources, etc.) The component of dose to the skin due to direct radiation will be-determined by thermoluminescent dosimeters (TLDs). 5.6.2 Inhalation Dose-The inhalation dose to the skin (only tritium is considered) will be i determined at the calculational locations for each age group according to the methods outlined in Sections 2.0 and 3.0 of this manual. 5.6.3 Ingestion Pathway (cow milk, goat milk, meat, vegetation) -The dose to the skin via the ingestion pathway (only tritium and C-14 considered) will be calculated at the consumer locations for the consumers at risk'. If no milk pathway exists in a sector, the dose vie this pathway will be treated as < 1 mrem /yr. l 5.6.4' Skin Noble Gas Immersion Dose This dose will be calculated in accordance with Section 3.4.1.2b for the maximally exposed ME!!BER OF T!IE PUBLIC in the limiting sector (s). l 5.6.5 Ground Plane Deposition 5.6.6 Other Uranium Fuel Cycle Sources This dose from other fuel cycle sources will be treated as < 1 mrem /yr. 6.0 INTERLABORATORY C0!! PARIS 0N STUDIES 6.1 Requirement Technical Specification 3.12.3 states " Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission." 6.2 Program l RSP-0005 REY. 1 PAGE 54 0F 111
A I ~ i I I i l ATTACHMEST - 1 l ODCM/ PROCEDURE REyISION LOG l l i l l I l DESCRIBE THE IhT04tlATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, I c 9 b 4 cl]l2 Ta f (~ N l s a s l l I l rn ri v e n_ _ j i 4e s h-w iot on4, +. m l l l 1 _. I I I I I l l l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE TE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: 1 l I t F v < o v' l l T yun a n ol..<n d~ I l I i l i l i I ~l l I I i l 1 I -1 I I I I l l REFERENCES (AITACH COPIES OF COMPLETED PROCEDURE CHANGE P:RMS, TCN'S AND 50.59 l l REVIEWS): i i l I I l 1 I l 1 i I VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS C,R l l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.11.)? iTS NO / l l l TEESE CHANGES RAVE BEEN REVIDiED AND FOUND ACCEPTABLE, PURSUANT TO ~ICHNICAL l SPECIFICATION 6.5.2. , ( I IIEVIEVED, RADIOLOGICAL ENGINEERING SUPERVISCR: L ddC' kN ) l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: $N f'AM ~ / g l 1 l l ll 1 l l A'ITACHMENT I PAGE 1 ll l l l 1 1 0F I II RSP-0008 l REV - 0 l PAGE 11; OT '.;; I l I( t ) I,
.. y, 1;i a TABLE C-1 1 DOSE TRANSTER FACTORS FOR EXPOSURE TO A SE5il-INTINITE CLOUD OF RADI0 ACTIVE NOBLE GASES DOSE TRANSFER FACTORS Gamma Beta ' Beta and Gamma K I.g (L+1. lt!) j g mrem mrem mrem Nuclide uC1 sec/m3 uCi sec/ n3 _uci sec/m3 Kr-63m 2.'4E-9 6.7E-7 Kr-85m 3.7E-5 4.6E-5 8.9E-5 Kr-85 5.1E-7 4.2E-5. 4.3E-5 Kr-87 1.9E-4 3.1E-4 5.3E-4 Kr-88 4.7E-4 7.5E-5 6.0E-4 Kr-89 5.3E-4 3.2E-4 9.3E-4 Kr-90 4.9E-4 2.3E-4 8.0E-4 Xe-131m 2.9E-6. 1.5E 2.0E-5 Xe-133m S.0E-6 3.1E-3 4.2E-5 Xe-133 9.3E-6 9.7E-6 2.2E-5 Xe-135m 9.9E-5 2.3E-5 1.4E-4 Xe-135 5.7E-5' 5 9E-5 1.3E-4 o-9 Xo-137 4.5E-5 3.9E-4 4.4E-4 Xc-138 2.SE-4 1.3E-4 4.5E-4 At-41 2.8E 8.5E-5 4.0E-4 AIR DOSE TRANSTER FACTORS Gamma Beta t1 N 3 g mrad-mrad Nuct(de uC1 sec/m3 uCi sec/m3 Kr-83m 6.1E-7 9.1E-6 Tr-85m 3.9E-5 6.2E-5 Kr-85 5.4E-7 6.2E-5 Kred? 2.0E-4 3.30-4 Kr-88 4.SE-4 9.3C-5 Kr-89 5,5E-4 3.4E-4 Kr-90 5.2E-4 2.5E-4 Xc-133m 4 ME-6 3.5E-5 Xe-133m 1.0E-5 4.7E-5 Xe-133 1.1E-5 3.3E-5 Xn-135m 1.1E-4 2.3E-5 Xc 135 6.1E-5 7.6E-5 Xe-137 4.8E-5 4.0E-4 Xc-138 2.9E-4 1.5E-4 Ar-41 2.9E-4 1.0E-4 Ref. Regulatory Guide 1.109, Revision 1, Table B-1. RSP-0008 REY. 1 PAGE o3 0F 111
c ) I i i l-l l ATTACHNEST 1 l ODCM/ PROCEDURE REyISION LOG l j J J l__ I l l l DESCRILE TE ISTOSATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION t;UMEEES, j i ETC.) 5' l i l O3 M { C hil[N TO e ( ~ 2-l ]_ ~ j w Lh v., ws l a ~' l J.. y
- lo V l
J i l I l ~~~ ~ l e ir <.-A' ,chgbis '. A l t c._ o h__a < d _l l ~ ~ " l /M A : ) l__ l i i _I J l _ __ 1 I ( I DESCRIBE (IN DETAIL) THE CHANGE (S) TO EE MADE. INCLCVE THE RATIONALE FOR AND l ?m j A COMPLETE DESCRIPTION OF TP.E CHANGE (S) MADE TO THE ODCH: l J I __ _l I I _. I T vg a vwM.m l rfvvp < _I I u,,, v ,,, l i_ 1 i I l a1 l. 1 1 l l ,i __ 1 { l -l l 1 l REFERENCES (ATTACH COPIES OF COMPIITED PROCEDURE CIIANGE TCRMS, TUN'S AND 50.59 1 j l PIVIEWS): i j l 'I I l I _._. i 1 1 l 1 l _.. i l . I WILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS C!R l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.16)? YIS SO / I i l THESE CHANGES HAVE BEIN REVIEVED AND FOUND ACCEPTABII, PUR$UA'T.TO TECHNICAL l i SPECIFh 5 TION 6.$.2. 1 ( REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISCR: C k/ [ [ REVIEVED, SUPERVISOK - RADIOLOGICAL PROGRAMS: / 1 I l 1 i 11 i i l 1 ATTACHMENT l PAGE 1 ll l l 1 l 1 1 0F 1 1( RSP-0008 l TdV - 0 l PAGE 11% OF in l l l- __ I _ II i l 1 i
r TABLE C-2 s TEC\\lNICAL BASE 3 FOR EFFECTIVE DOSE FACTORS j The evaluation of dos 2s due to t eleases of redioact3ve material to the atmosphere can te simplified by the use of ef fective dose transfer l i . f acte t s.instead of using dose f actors which are radionuclides specific. l Th.ne ef fectivo factors, which are based on the typical radionuclides distribution in the releases, can be applied to the total radioactivity released to approximate the dose in the environmer,t, i c., instead of hr.ving to sum "cbc isotopic distribution multiplied by the isotope specific dose factor only a single multiplication (K ff, (L + 1 l?Oeff' Hef f, or Ndf titres t.he total quantity of radioactive material released) would be needed. This approach provides a l reasonabic ortimate of the actual dose while climinc:ing the need for a detailed calculational technique.. Use of effectivo dose factors should only be used if isotopic analyses are not available (i.e., prior to initial criticality), if the relative abundances of the noble gas isotopic mixture are similer to those listed in Appendix D or if the relative abundances of tle noble gas isotopic mixture are similar to those listed in the previous Seminannual Radioactive Effluant Release Peport. (Reference 1.2.19) Determi. nation of Ef fer tive Dose Factors The ef fective done transfer factors should be based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations: {K EQUATION C 1 K i{ = ggf i Vhere* K = The ef fective total body dose fact or due to gamma gg l EMISSIONS frOQ all noble g3SPS releaCed. K. = The total body do.se factor due to gamma emissions from l 1 each noble gas radionuclides "i" released. 1 The f ractional abundance of noble J;as radionuclides "i" f. = 1 of t.he total nobic gas radionuclides. ESP-0XS REV. 1 PAGE e4 0F 111 / i
l ATTACHMEST.1 l ODCM/ PROCEDURE REyISION LOG l l I l 1 l I DESCRI3E TE IST0lWATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, I l ETC.) / l C)a o O b75.lB7
- Th h)lf
(~3 l V u v l l l 1 l pM: a n _e,,, u.n -4 w&h mamma l l __ _ l I l 1 l I I I I DESCRIGE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE TE RATIONALE FOR AND l l A CO.9 LITE DESCRIPTION OF THE CHANGE (S) MADE TO TE ODCM: l ~~ l Tw% vn>% en i F v ic v- /* u v l l 1 1 I l l l I I l_ I i_ l 1_ 1 -1 I I l I 1 ) REFERENCES (ATTACH COPIES OF COMPIITID PROCEDUF2 CHANGE FORMS, TCN'S AND S0.59 l i l REVIEVS): I I l f 1 I-l l i I l 1 I._ _. I l WILL THIS CHANGE REDUCE TE ACCURACY OR RELIABILITY OF DCSE CALCULAT;CNS CR 1 SETPO?iT DETERMINATIONS (TECHNICAL SPECIFICATION 6.la)? YIS NO / i l l THESE CHANGES HAVE BEEN REVIEVED AST FOUND ACCEPTABLE, PtJRSUANT TO ECHNICAL l SPECIFICATION 6.S.2. N RE'JIEVED, RADIOLOGICAL E!jGINEERING SUPERVISOR: ____ ('I 2-==s' l w. / 1 REVIEVED, SUPERVISOR RADIOLOGICAL PROGRAMS: N'4b8 / /9/N[ g l / I l l f I I ll l l l ATTACHMENT l PAGP. 1 ll l l l 1 l OF 1 ll RSP-0008 l RIV - 0 I PAGE 112 0F '.;I l l _, !I I 4 l
F. =~ TABLE C-3 EFFECTIVE DOSE FACTORS FOR NOBLE GASES TOTAL BODY EFFECTIVE DOSE - K ff Main Plant Radwaste Building Exhaust Duct
- Exhaust Duct
) Year K ff (mrem-m /uCi-sec) K ff (mrem-m /uCi-se.c) Projected ** 5.56E (-5)** 8,05E (-5) l Main Plant exhaust duct contains contributions from Fuel Buil din.g. Projected values from RBS FSAR. When RBS becomes operational, actual release rates reported in semi-annual effluent report should be used to generate effective dose factors. -5 5.56E (-5) = 5.56 x 10 l l l [ RSP-0008 KEY. 1 PAGE 66 Of' 111
t 1 I l l I l ATTACHMEhT - I l ODCM/ PROCEDURE REVISION LOG l l I I I I 1 DESCRIBE TE INF04t!ATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, j l l5'-) 4 AAb l l l o,,, e n t n ~ w In.nu 21
- V a(J u Mne (L / y (
l l l I l l l h b ', 4. he Aca oU /unm beve 1 l l 1 i l l I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND 1 l A COMPLETE DESCRIPTION OF TE CHANCE (S) MADE TO TE ODCM: l 1 I l ~T40cc m phirnl R < rn < l l "- u l I I I I l l l ) l ,f I.. I I I l. I 1 - i I I I I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEWS): l I I 1 i 1 l 1 I l 1 1 I I l VILL THIS CHANGE REDUCE TE ACCURACY OR RELI ABILITY OF DOSE CALCULATIONS pR I l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6,1!.)? YES NO V l l l l TESE CHANGES HAVE BEEN REVIEv~ED ANT) FOUND ACCEPTABLE, ?URSUANT TO TECHNICAL l 1 SPECIFICATION 6.5.2. l l REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISOR: h bbh E l M7 i u' l C L/,Q 4 [/ 9/'/'7 l l l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: 74/MA/ l f r i l I l 1 I I Ii 1 l l l ATTACHMEST l PAGE 1 ll l l 1 I 1 1 0F I ll RSP-0008 l REV - 0 l PAGE 112 0F 112 l f l. I ll t l l {
EXPECTED RELEASE OF RADIOACTIVE NOBLl' GASES IN GASE01.'S EFFLUENTS FROM RIVER BEND STN' ION FSAR* Containment Building ** Radw.tste Building Nuclide Ci/yr Fraction C1/..'r Fraction Kr-83m 4.7E (-2) 1.07E'(-5) <1 Kr-85m 218 0.050 <1 Kr-85 210 0.048 <1 Kr-87 14.2 0.003 <1 Kr-88 47.2 0.011 <1 Kr-89 118 0.027 29 .03 Xe-131m 21 0.005 <1 Xe-133m 6.6E (-2) 1.504E (-5) <1 Xe-133 2,340 0.533 220 . I '> Xe-135 693 -0.158 280 .24 Xc-135m 140 0.032 530 .46 Xe-137 380 0.087 85 .07 Xe-138 208 0.047 2 1.75E (~.3) l 4,389. 1.0000 1,144' .99 RBS FSAR Table 11.3-1
- Containment Building contains releases from Fuel ! u iIding
) l 1 i 1 -? I l i l 1 I i i 1 RSP-0008 EEV. 1 PAGE 70 0F 111 a
f 1 l l-.. l l l ATTACHMENT - 1 l ODCM/ PROCEDURE REyISION LOG l l l I i l l DESCRIBE TE IhTOEt!ATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, l L l l ETC.) / l On AD 7/ od//ZM MDDrdi D l I ~ l v v <v l l l jut (i ! E p m,a h o. ~ % uAucD gn >rk,. % v l l l l 1 1 I I I i l l DESCRIBE (IN DETAIL) THE CHANGE (S) TO 3E MADE. INCLUDE TE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l l 1 l T Q,n vat % v o V 2 vec r l l J' u v l l l I I I I I I I I I i 1 T ' [ .l - I - I t i I I l I l REFERENCES ( ATTACH COPIES OF COMPLETED PROCEDURE CHANGE PCRMS, TCN'S AND 50.59 l l REVIEWS): l l 1 l l l 1 l 1 1 l l I I ( VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS OR l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATI0S e.14.)? TIS NO / l l TESE CHANGES HAVE BEEN REVIEVED ANT FOUND ACCEPTABLE, PURSUANT TO TECHNICAL
- l. SPECIFICATION 6.5.2.
b[ -A -D l REVIEVED, RADIOLOGICAL E!jGINEERING SUPERVISCR: l REVIEVED, SUPEhVISOR - RADIOLOGICAL PROGRAMS: 4 ^ f/ 7 1 I I I i ll l l l I l ATTACHMENT l PAGE 1 ll l l I 1 l OF 1 ll RSP-0008 i REV - 0 l PAGE ll: OF '.*.: I ll t I l l
__-----____._m___
EXPECTED REISASE OF RADI0 ACTIVE NOBLE GASES IN GASEOUS EFFLUENT 3 FRON RIVER BEND STATION FSAR* Containment Building ** Radwaste Building Nuclide Ci/yr Fraction Ci/yr Fraction Kr-83m 4.7E (-2) 1.07E (-5) <1 Kr-85m 218 0.050 <1 Kr-85 210 0.048 <1 l Kr-87 14.2 0.003 <1 Kr-88 47.2 0,011 <1 Kr-89 118 0.027 29 .03 Xe-131m 21 0.005 <1 Xe 133m 6.6E (-2) 1.504E (-5) <1 Xe-!33 2,340 0.533 220 .19 Xc-135 693 0.158 280 .24 Xe-135m 140 0.032 530 .46 Xc-137 380 0.087 83 ,07 Xc-138 208 0.047 2 1.75E (-3) l 4,289. 1.0000 1,144 .99 RBS FSAR Table 11.3-1
- Containment Building contains releases from Fuel Building
? ) l l RSP-UDCS HEY. 1 PAGE 70 GT 111
l l ~ i ,( l l ATTACHMENT - 1 l ODCM/ PROCEDURE REyISION LOG l l l I l .l DESCRIBE THE INFORMATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, I I on p - 73 eM // Acgwdtx E i ce %,mc + s i i iv a
- e. 2 =
l No mcm e /o be l l u,T u-l l mnve - (bee Meus : /2 /r ~' 70 (2/7y' l l I I I I I I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE TE RATIONALE FOR AND i l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO TE CDCM: ( l I l
- Twoornok ocni E vvo v l
\\ e U V l l I._._ l l l I I I - I I I [ l i j g l - 1 l l 1 l l REFERENCES (ATTACH COPIES OF COMPLETID PROCEDURE CHANGE FORMS, TCN'S AND S0.59 l l REVIEWS): I I I I I I I I I l._ l l I 1 i l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS JO I l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.11.)? YES NO V i l I I THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUAST TO TECHNICAL i i SPECIFICATION 6.5.2. I REVIEVED, RADIOLOGICAL E!jGINEERING SUPERVISOR: k ON As J N'#0 ' l l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: (( 9 4 I g/ i l 1 l l I II I I I ATTACHMEST l PAGE 1 ll l l l l 1 1 0F 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 112 I I I Il i I _l
o1 Long Term Diffusion Estimates E.1 Objective-if Annual average CHI /Q and D/Q estimates for continuous and intermittent releases were calculated for each of the sixteen 22.5-dog sectors at receptor locations used to determine the maximum individual and popu-lation dose receptors. The methodology described in Regulatory Guide 1.111, Rev. 1 provided . guidance for the aforementioned analysis. The resultant CHI /Q and D/Q values for the maximum individual dose receptors are displayed in Appendix F. E.2 Calculation Techniques-Nomenclature (2/w)II (2m/16)~ 2.032 = (dimensionless) 3.14159... m = (dimensionless) = 2.71828... (dimensionless) exp E = Entrainment coefficient (dimensionless) T Q Terrain recirculation factor = T (dimensionless) Downwind receptor distance (m) x = Vertical dispersion o = (plume spread) coefficient (m) j i 1 5 30-ft average wind speed = 30 corresponding to a given hour of onsite meteoro-logical data (m sec"I) 5 150-ft average wind speed j = 150 corresponding to a given l hour of onsite meteoro-logical data (m sec'I) i (CH1/Q) Average concentration I = normalized by soutcc st r e ngtl. (see m~ ) l RSP-0008 REV. 1 PAGE 72 0F 111
o 1 l i1," l l l
- ATTACHMEST - I l
ODCM/ PROCEDURE REyISION LOG l I l I l l l DESCRIBE TE IhT0lWATION TO BE CHANGED (INCLUDE PAGE NL*MBERS, EQUATION NUMBERS, l hctwiquL l A0 75k'))7 'Of$ra 53 0 0 lllcl > rn o s v i l l0 l l /Jtt r4 ; f= + o o 4 ) ca /U r. F.3-I l l l l %ve-F,r u n h m No F.a-7 o t-bel 4m M atoc l ~ a l j 6 l l l l l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE TE RATIONALE FOR AND j l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO TE ODCM: l l l l ( l i ^y o n n ya c> h,c o l FueV l f' ' o y l l l l f I I l I l I l l ) I i -l 1
- I 1 __
- l l I.--. I 1 j l l ) l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEWS): l I I I I i I I l l l l l l l l l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS 0~ t l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.la)? iTS NO l l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l SPECIFICATION 6.5.2. I ) l REVIEVED, RADIOLOGICAL E!jGINEERING SUPERVISCR: O' Of If ' [ / ,// / l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: I l I I ll I i t j l ATTACHMENT l PAGE 1 ll l l l l 1 1 0F 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 1*.: I l Il I
l E.3 CHI /Q Modeling Technique Annual average values of relative concentration were calculated for continuous gaseous releases of activity from the containment building vent and the radwaste building vent according to the straight-line airflow (Gaussian) model described in Regulatory Guide 1.111, Rev. 1. An adjustment was made to the model to characterize the regional airflow pattern. The equation of this model is as follows:
- b 'bi
.$=.%4A (!). .. (.., s,, .y )g s..,,, E 3-1 l e I Since the River Bend Station site is located in relatively open terrain, the terrain recirculation factor (Q)g (presented in Figure 2 of Regulatory Guide 1.111) was applied. The entrainment coefficient (E ) is a function of the ratio of efflux T velocity (u,) to elevated wind speed (u150) f r the conditionally elevated release points. For vent releases occuring below the level of a nearby structure, 100 percent downwash (total entrainment)-is conservatively assumed (E T 1). For vent releases occuring between 1 and 2 times the height of a nearby structure, a conditionally elevated release is assumed, and the entrainment coefficient is defined as follows: 0.0 when u,/U E 5.0 (totally elevated) = T. 150 i T 0.30-0.06 (u,/u150) E = u,/U 5 5.0 (partially entrained) when 1.5 < 150 1 2.58-1.58 (u,/U150) E = T I when 1.0 < u,/u150 1.5 (partially entrained) ET 1.0 when u,/u150 5 1.0 (totally entrained) = RSP-0008 REV. 1 P!sGE + OF 111 )
I i .1 l' ' l l l ATTACHMENT - 1 l ODCM/ PROCEDURE REyISION LOG l I l l_ I ] l l DESCRIBE THE INFORMATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, l ho7(,01/2 Y .61tY
- f. 3 Cbil0()1erlebra. Ticlutaml
.l l j lu o v l l J l l A A A '. F,, u n 4 : u No. fr. 3 - 2 ao 4,w,+ r,, W, m j l c het i<if e F4..niam Mn F, 2. W l l -fo V. P 4 ( h nr /7) l 4 l u i l l r h ua_o F< uo% Nr. F. M +o E. 8 3 1m mnv Rons t n l l l l l l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: 1 1 I j I { l l .t. wn o mole ea \\ (=< vr. / l ~ O () V l l l 1 I I i i I I I I l l 1 \\ -I l l I I l REFERENCES (AITACH COPIES OF COMPLETED PROCEDURE CHANGE PCRMS, TCN'S AND 50.59 l l REVIEWS): l l l l I i i l l I l l ! VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS OR i l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.13.)? HS NO V I l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TICENICAL i i l SPECIFICATION 6.5.2. l ~ l REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISOR: N i l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: E [//'TI g y I I l l ll l l l ATTACHMEST l PAGE 1 ll l l l 1 l OF 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 1;; I l !l t
Within 5 km in each downwind sector,. Equation E.3-1 was evaluated by sector at the property.and restricted area boundaries and nearest resident, vegetabic garden, milk cow, and meat animal. There were no goats whose milk is consumed in the area of interest. This evaluation -was performed for each continuously emitting release point and the intermittent release from the mechanical vacuum pump with onsite data collected during the period of March 17, 1977 th*ough March 16, 1979. The effective release height was computed frem the following equation: h = h - (h )k + h E.3-2 e r t-pr Where the downwash correction factor (as defined by Equation (5) in Regulatory Guide 1.111, Rev. 1) is included in the equation for h pr (see Equation E.3-4). g Values of topographic heights were conservatively assessed as the maximum height within a particular annulus-sector (annsect). An annsect is an area bounded by a 22.5-deg sector and any two radial distances from the release roint. For A-D stability conditions, plume rise for nonbuoyant sources was calculated by the following algorithm: when: u,/u150 I* u, 2/3 x 1/3 1.44 d E.3-3 h = Pr f d 150 i I l l i i I l RSP-0008 REV. 1 P.\\GE 75 0F ; ', I l i j
I em .m j A'ITACHMEST - 1 l ODCM/ PROCEDURE REyISION LOG l l l. I l. l l DESCRIBE THE INT 0kMATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, l l Ae 7?e>&lla $D90AlK 6 l Q c+; o d
- 6. '$ - C NZ/G (hode lloa Tec kra t a ne s l
{ lV ~ h e n odl Eq u A 4 t e>o l l l l l l (knage Eq ua.4t em No. E. 3 ^/ Tb 6 S~ l l l l Re.nn c Ea ua%, See lh tfac h mem+ l 1 I i l I DESCRIBE (IN DETAIL) TE CHANGE (S) TO BE MADE. INCLUDE TE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO THE ODCM: l l __. I l l T~y Ce> G yw h i ca l Evrov l se U u l l l I I I I I 1 l 1 1. I I l l l l I -1 I i l I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.39 l l REVIEWS): 1 1 I I I I I I I I I I I I I l WILL THIS CHANGE REDUCE TE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS OR I l SETPOIST DETERMINATIONS (TECHNICAL SPECIFICATION 6.1.'.)? TES NO t/ l l l TESE CHANGES HAVE BEEN REVIEVED AST FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l i SPECIFICATION 6.5.2. l b' 'ClO l REVIEWED, RADIOLOGICAL E!jGINEERING SUPERVISOR:IL- __ M l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: N h / l / j l l l I I i ll l I l l ATTACHMEST l PAGE 1 ll l l l l l 1 1 0F 1 Il RSP-0008 i REV - 0 l PAGE 112 0F 112 i l l ll l
.-e' when: u,/u_ 150 l u, 2/3 x 1/3 u, l pr d E.3-4 1,44 (d-3) 1.5-h = 1 d u "150 150 and L h 3 d E.3-5 l pr i { "150 / ) \\ The result from Equation E.3-3 or E.3-4 (whichever condition exists) is then compared to Equation E.3-5 and the smaller value of h is Pr used. 1 For E-G stability conditions, Equations E.3-3, E.3-4, and E.3-5 are l compared with: h =4 F,/s
- and, j
I 1/3 - 1/6 F,/"150 h = 1.5 3 pr ) where: (uf9 2 e d / F = m 4 and the smallest value was chosen. l I l l I I RSP-0008 REV. 1 PAGE 76 0F 111
d l_ l-p -.. ~ l ) ATTACHMEhT - 1 l ODCM/ PROCEDURE REVISION LOG l -l l 1 l~ I l DESCRIBE THE INF04llATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, l k($Yo77)7/2 $ don lc F.3 0hlN M Nebe k bnkas l v 6 l lV O V l l' h em n o i Fa flo - F. 'A % P. ?> " 5'* l v l .l l (' > n e n o.' Ga., dr us hk. 's is, J M !!>vlso Dn an Mn Olus l . ml a-h L PM+MA wnJ1 Dnt s%LA d 0 l l l R.) l V l I l 1 I I J DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND l ~l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l l 1 4 l 6 -l l T gcr; & rMM i cak Wye v l l c>v v V l } l 1 t l-I i 1 I l l I i 1 l I I I I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEWS): i l I I l i l I I I l l l ! VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS - i SETPOIST DETERMINATIONS (TECHNICAL SPECIFICATION 6.1/.)? YES NO i l l THESE CHANGES HAVE BEEN REVIEWED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL i 1 l SPECIFICATION 6.5.2. l REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISOR: /2 #C# lb I l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: /f 7 1 j i l l 1 I I ll l l l ATIACHMEST I PAGE 1 ll l l l 1 1 0F 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 1.2 I l ll l e
j o. when: 1 u /5 150 u 2/3 x 1/3 u, h = 1,44 (d-3) 1.5-d E.3-4 8 pr l \\150 d u ( 150 and I; "e - h 3 d E.3-5 l pr I u 150 i The result from Equation E.3-3 or E.3-4 (whichever condition exists) is then compared to Equation E.3-5 and the smaller value of h is pr used. For E-G stability conditions, Equations E.3-3, E.3-4, and E.3-5 are l compared with: =4[F/s/ h \\m pr
- and, 1/3 - 1/6 h
= 1.5 F,/ 150 S l where: (ufd e / F = m 4 1 and the smallest value was chosen. I I i 1 l l l RSP-0008 REV. 1 PAGE To OF 111 s 4
I 1 l I I l ATTACHMENT - 1 l ODCM/ PROCEDURE REyISION LOG l - I l l 1 I 1 DESCRIBE THE INFOR2iATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, i ~ l l ETC.) Y /]DPeolix E l l Daae 79 04 3IL C HI /n o,,4 6/G Adol % TFels:%I j l lv v 3 ec%e E. 4 0 I l l I l N b b: Wako N o. E.4-l l l l I I l l l I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l 1 l T 0ca n phigal F<ver l l
- 9 U
V l l l l l 1 I I l 1 I I l 1 1 ,i l -l l -1 I I I I I REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEVS): l l l l l l 1 I I I I I I I l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS JO l l SETPOIST DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)? TES No V I l l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l l SPECIFICATION 6.5.2. I REVIEVED, RADIOLOGICAL ENGINEERING SUPERVISOR: N2 h 4 AIY I l REVIEWED, SUPERVISOR - RADIOLOGICAL PROGRAMS: h F/f7 l / 1 I I I I I ll l l i l ATTACHMENT l PAGE 1 ll l l 1 l 1 1 0F 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 112 I l l ll l 1 1 -._m
.1 .e -In' the growd hvel portion of Equation E.3-1, the vertical dispersion term: i z + 0.5h /* b i,k ) was constrained to be les's than or equal to 1.732cg ik E.4 (CHI /Q) and D/Q Modeling Techniques ~ Annual average depleted relative concentration values were conservatively. assumed to be equal to annual average relative concentration values;(CHI /Q = (CHI /Q)D). Therefore, no credit was taken for attendant plume depletion of radiciodines and particulate. Annual average relative deposition values were calculated using Regulatory Guide 1.111., Rev. I with the following equation: 1 a I k k Uk n=1 ik. For the conditionally elevated release points, Figures 6 through 9 of Regulatory Guide 1.111, Rev. I were used to calculate the (6/Q)g and (6/Q)g values, while for the ground level release points, Figure 6 was utilized to calculate the (6/Q)G V"1"*' E.5 Methodology Employed for Intermittent Release j The methodology employed in the calculation of intermittent release CHI /Qs and D/Qs was as follows: 1. Two-hour sector-averaged CHI /Q values were calculated without terrain recirculation factors. ) t 2. The 15 percent, 1 hour value was plotted at 2 hours on log-log coordinates, while the annual average value was plotted at 8,760 hr. A straight line connecting the two points was drawn. 3. Log-log interpolation based on total ground intermittent release hours versus annual hours yielded a CHI /Q multiplier. 4. The multiplier was applied to annual average CHI /Q and D/Q values to obtain intermittent CHI /Q and D/Q values. For River Bend Station, a 320 hr/yr intermittent release through the
- containment building vent from the mechanical vacuum pump was evaluated.
RSP-0008 REV. 1 PAGE 77 0F 111
e., m , 5, 4 - r4 . I l l~ ATTACHMENT - 1. l ODCM/ PROCEDURE REyISION LOG j i i _I I I l DESCRIBE THE INFORMATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, I ste E-l ) E-2. : onut 80 F 79 o OW. CilE/() l l>lO 1aa.a. I aoha - s ee a mda ' sa+ s - I i l I l l l 1 l 1 1 I l l l l l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND I l A COMPLETI DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l l OnT /Q 4 blo wa o M 4>cobef044i GA;--+.s cdc M e.74r l I u I I I I I-l l 1 l 1 1 I l l l I I I l I l l l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEWS): 95AP O L.-dL Lb& (ba b+ 3 5 -4 / srmr / Gulu4c MJM l l 9.9. ton w Mer 0 ~ 1 \\ l l 4 I l i l I l l I i I WILL THIS CHANGE REDUCE T1tE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS OR ( l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)? YES NO[ l l \\ l THESE CHANGES MAVE BEEN REVIEWED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l l SPECIFICATION 6.5.2. i l REVIEWED, RADIGI48ICAL ENGINEERING SUPERVISOR: N l REVIEWED, SUPERVISdf - RA' DIOLOGICAL PROGRAMS: I /I2f 7 i e I l l I l ll I I l ATTACHMENT l PAGE 1 ll l l l 1 1 0F 1 ll RSP-0008 l REV - 0 I PAGE 112 0F 112 I I ll l 1 0 I
I TABLE E-1 ANNUAL AVERAGE CHI /Q VALUES x 10-7 (sec/m~) 9 FOR RESTRICTED AREA BOUNDARY Main Plant Exhaust Radwaste Building Sector Duct (Continuous) Exhaust Duct (Continuous) S 11.4 105 { SSW 19.7 186 SW 16.4 215 WSW 19.5 326 l W 23.6 654 WNW 33.1 421 hV 15.7 262 NNV 14.8 138 N 18.8 180 NNE 24.9 211 NE 16.6 150 ENE 12.2 146 ) E 9.07 168 ESE 10.4 154 SE 8.19 93.1 SSE 7.69 45.6 i 1 i i RSP-0008 REV. 1 PAGE IS OF lli I .-____-_______________-_____a
1 1 0 l TABLE E-2 i ANNUAL AVERAGE D/Q. VALUES x 10 9 (m.,"" ) l FOR RESTRICTED AREA BOUNDARY j j Main Plant Exhaust Padwaste Building { Sector Duct (Cont inuous') Exhaust Duct (Continuou,Q { .S 7.61 21.4 4 4 SSW 11.3 39.6 l SW 10.4 36.1 WSW 9.79 38.5 -l W 13.8 68.8 J WNW 18.0 50.3 NW 8 68 40.8 NNW 10.5 24.7 i N 11.8 28.6 I NNE 11.2 27.1 ) NE 8.26 22.3 ) ENE 9.73 22.7 E 7.75 23.0 i ESE 7.76 24.6 1 SE 6.60 17.2 ) SSE 5.34 11.8 j i I i I i i I I I l i ) P.SP-0008 REV 1 PAGE 79 0F 111 l
i 4 a I-I I I J ATTACHMEW - 1 l 'ODCM/ PROCEDURE REyISION LOG l i i i i I l DESCRIBE THE INFORMATION TO BE CHANGED (INCLUDE PAGE NUMBERS EQUATION NUMBERS, l l ETC.) l
- l. % ' 82. - he F-l DLL cifr/ 0 i b/9 R, ' wh 1
wn l Aun w tm a r a uurt 4.d,.id - l l si.t am&d y l 1 I I i I I I I I I i 1 l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND l l A' COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l l See AAtlud 9 rA -0.r Cha - % dm'i-ws4 besd a ESM C Ls. o.s l l% &4w e A he unt4 es Rss. una aawus i carlo *bk) esJJJ l l ud Rmamt %uer%to. "h Lule uddes (2u.rmt -h r Thd m.d cauud dak l l N ~I l hue. h baud a 19 % L aud d ut Co. sus. b a ttd % <% Ac R wa l l d44%f 1.a bhm in e<.r as u A tis h C A - o i 3 3. N 7# ostA no - l l bitl4d Eds L + C 4 4 &sa Q 2 600 m Wu) as t' L w 4 'h %.s ' ~ l l 1 1 l 1 l I l I i l l l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND $0.59 1 i REVIEWS): udEG om ? Isad ah tc; 86 L*t s w cai 123-4 1.M i a6Le F A,.L h R.2.itn adB i,ler. ~ C L.- o Ro, M l ~ 0 I l i I 1 l 1 I I l 1 l 1 l VILL THIS CHANGE REDUCE '1HE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS l l SETPOIE DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)? YES NO l l l l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUAE TO TECHNICAL l l SPECIFICATION 6.5.2. l REVIEWED, RADICI4GICAL ENGINEERING SUPERVISOR: ^S 0/2#)l7 l l REVIEVED, SUPERVISdn~- R' RADIOLOGICAL PROGRAMS: -[ [ V!rf-7 l l / / 1 I I I ) l I I I II i 1 1 1 ATTACHMENT l PAGE 1 ll l l l l l 1 l OF 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 112 1 l-l ll I .{ l O
O S 1 O t 9 3 11 1 N 1 5 02 1 5 72 38 I c 3 3 31 F T tu 3 1 8 O A nD 7 L a U l t n 1 C Ps 2 2 2 2 o 8 L u Q Q Q 4 i A na / / 2 /2 /2 t C ih I l Q l Q 1 Q a E ax H H / H/ H/ c G E ME C C D CD CD o A S l P O s D i .h L ) A d rt U e o D i tr I p co V u ef I c s D c e
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- n E
( W N f wuy R D W f4 f4 W y ia n) N tndw D os W m m m roah N i r eirt A te m 0 0 4 pt a at 9 eeee 0 9 oasp mmmm 9 rce N ce 4 2, 0, aaaa pol n I L [m O o 9 9 1 SSSS 7 8 (lio S 1 mi R ne t 3 otSa 2 E m ii t P S 1 / tsne I c a f'ig D d e cfhe n s2oot v C a l i 7m dwr I ) 4 6 - ee o R ) ( 1 09til t E H 3e ) ) 1 - ipap P ( s r 5 6 0st me s S o o ( ( 2 reic 1 rcne O eD t 1 Q=ooar M s s p l l n T i or e a a e e /l Qmmk m A s di c mn m d c l / t t l u e e y A e t i o i r n iCDmmim l r f enas a g r iimi n ni n a e l a i a n at m de r e l i xx x A e u idte k e r AAt MfiM l l baoa aB m sram t t e s. md x teaem i i P e )))))) m i an a f GM1 M s t. 1 ?3?4 '6 n o. Ca M O
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l j l 1 l ~ l ATTACHMENT - 1 1 ODCM/ PROCEDURE REyISION LOG l 1 I I l I 1 DESCRIBE TE IST04t!ATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, I l ~ -c l ETC') E. ~Th ble $-/ l l l vn e v ue.1 m. (' e, t a,,,,s ? 7 (wk l i l Fo 4 Ik n u,,a n l l l l
- Mvoy
, 7 e G r: n ? +n . ? v9 E + o 7 l l I l i I 1 i I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE TE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO THE ODCM: l l I I l Tv O, a yook:n I Fnw I J" V V l l l 1 l 1 1 I I I -1 I I I I I l I I i l l I I i j REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEWS): l 1 I l 1 I I I I I I l l l l l WILL THIS CHANGE REDUCE TE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS Cf I l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)? YES NO V i l I l TESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL i l l SPECIFICATION 6.5.2. I REVIR2D, RADIOLOGICAL ENGINEERING SUPERVISOR: N_ A g. - 6hh l [ V[/7 l l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: f l g I I i l l l ll l l I l ATTACHMENT l PAGE 1 ll l l l 1 i 0F 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 112 l I _l. Il I I I
-= N O C + 06000000000.W x h M J.c to N O N O N+ 0 N CM C+00W +0 0 C OWO+NCOWO + 3 0CCWecc4c L.J e W TOcMNcN7c N C w Cb & d O 7ece O e-Os 4 c N w" N N r A O O2 a W c O W M O O M a og 4 0 D O V W M NcN O O ~ O 000 Q L +++ 4 A WJW s M E NwN gg
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i I I l j l l A'ITACHMENT - 1 1. ODCM/ PROCEDURE REyISION LOG l l 1 I l l l DESCRIBE THE INFO %t!ATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, I ETC.) _g l ;wv Gtal t!7 S ec ~d rn lo wi T obodv l { r ~ f, e a pa.py l l I I l (;_ ha %e / mi t= 0 ) Yn 2n9F4n? a. I U i l l I I I I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND 1 l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l 1 l l ~i g u a rn o t,ir a l E r ro / l ~" va a l ~ l l l i i l l I I l l l i. l 1 If I l i l I I REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S Aht 50.$9 l l REVIEVS): i I l I l i I I l I I I . _ _ ___ l I l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS Oy/ l l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.1!.)? ?ES No i/ l l l l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSCAST TO ~ECHNICAL l l SPECIFICATION 6.5.2. ( l REVIEVED, RADIOLOGICAL E!jGINEERING SUPERVISOR ~I73.- (T ' I' l l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: / 7 l 6- / l l j l l l l I ll t i l I ATTACHMENT l PAGE 1 ll l l l l 1 i 0F 1 ll RSP 0008 l REV - 0 l PAGE 112 0F 112 l l __l ll I l e
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. = - - yi ; %p ( h $5.,.. 1 'I l-I- l l AITACHMEhT - I l ODCM/ PROCEDURE REyISION LOG l .I' l' l' I l . l DESCRIBE THE IhTOIWATION TO BE CHANGED (INCLUDE PAGE NUMBERS EQUATION NUMBERS, l' 1 ETC )- V 1 l Orb e 4'1 # ns%. 7hNe 1~ -l 2-1 v u _lV $r R o Ve I 1. _. 1 l l 1, _(! ka w e . I91'L R 7 7 + Iz. To .19 2 43 7 E + I b l ~ ^ / I _l I I I I I 1 INCLUDE THE RATIONALE FOR AND I J DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l l 1 ~ ~ l. ~7% o n BMatl E no v' l l 5 V
- _l 1_
I I i I I I l, -1 { l l j l' l l .) l -1 I I I I l REFERENCES (NITACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 5f).59 l l REVIEWS): i I I I i I 1 l' I I 1 1' I I l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS JR i i SETPOIST DETIR.MINATIONS (7ECIUTICAL SPECIFICATION 6.it.)?
- ES NO 1/
I l i THESE CHMGES RAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PCitSUAST TO TECHNICAL i ( SPECIFICATION 6 5.'.I. I REVIEVED, RADIOLOGICAL F.!jGINEERING SUPERVISOR:k - hf 1 l p - e> (4 7 REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: 7 t i I I~ li I I I ATTACIDiEhT l PAGE 1 ll l l 1 l 1 l OF 1 lJ RSP-0008 I REV - O l PAGE 112 0F l',2 i I. -- l Ii_ l 4
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l I I I-I I I l - A'ITACHMEST - 1 l ODCM/ PROCEDURE REVISION LOG l l l_ I l l 1 l l DESCRIBE THE IhTORMATION TO BE CHANGED (INCLUDE PAGE hu!BERS, EQUATION NUMBERS, I l ETC.) l l 19aQP lol 5:9 li5'A e DIk l l O Sv-@9, % B ocht l j l. I I I l fl ha wm e : 7 3 2. t o 7 _J 732 E+07 l l l I.__ l I._ l i I l DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE 'tADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l 1 l l T' won v a phi ca l G nov' I l l su v i l l l l l 1 1 l l l l t l l l l 1 I - I I I I I l REFERENCES (A'ITACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND S0.59 l l REVIEWS): 1 I I I I I I I I I I I I I l l VILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS 03 l l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)? YES NO t/ l l l THESE CHANGES HAVE BEEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l l SPECIFICATION 6.5.2. I I REVIEVED, RADIOLOGICAL E.jGINEERING SUPERVIl0R: Yb pf l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: . M. /, /d#((7 l / c I i I l I 11 1 I t i A'ITA",HMENT l PAGE 1 ll l l l l 1 1 0F 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 112 1 I I ll i I o
8 li 284 n 00 i ++ k 00000000000.1 EE S 2 07 26 99 00 + + 9 E06 24 n g 28 00 i 1 n 69 + + t 1 u f4 1 6f4 EE n a 1 L 176 1 2 o l 309 07 i u F 0000011 1 000.26 i f 0 t c E s a 0 G o c 0 R p 1 A e n H d e d h E i 9 24 e w G i o 01 00 v A D r + 0++ i d P y E+ EE t e S h 6E1 2 a s U T 0000000009507 l u O e E 926 r o S 14 t A ) 9 a r d G n e c 79 R e 00 09 a O s + + +0 Q F /y EE E+ 63 / s ie 98 6E 1 24 X e ) Cn 22 788 .7 00 i t i ud 28 08650 + + r t ( i 5f4 5365+ EE o a R rK 1 7 921 EE212 f 'f e 02600331361 07 S p 0 Q R 2126 / 1 O r 1 X T y C / f V f4 A m 870 09 o e. E 1 F e 001 1 0 R r +++ ++ e i t N m EEE EE6.371 2 u O t Tfs1 92 24 l E I 2e 039 639. 0000 a ) L S mv fs28 01 1 0+ - + + v 3 B R (i 930 2fs 30EEEE m A E L 820 25f431 01 2 a / T V s 571 001 9 3 8 5.f.07 i s N r d C O o 1 626 n u C t a c r E a ) e 8 S f 991 998 i p 0 O 001 000 ( 0 D e + + + +++ r 0 s I F EEt e a oe 31 92fs 1 5. / 1 5 d e P On 0fi a251 301 0 i y S Y o 1 0P0627+ 0 + l / R A nB 7523?32E - E c m w a 1501 9726f 6 u e fi g 00321 5621 0803 n r T r h (m A O 13 3 P ca e L e r A 9898888 a 080000000 f f'o T4 t 1 0+++++++ 3 E c + +EFEEEEE M a EE7921 91 7 1 2f4 e H. N r 2615329726000 t ts 0 T 1550566330 - + + a d1 s 27+ f EE r n-te 01 5953f861 F o1 2 aC l l 1 23091 f'L G .2 6. f.221 s 5 3 0.c.0 7 e 1 s !:d E is526 a 1 n e a l C e 1 7970997 r r-y 90001 000961 2f4 oH d 0+++++++fs 0000 c f T o + EEEEEEE. + - + + e m TL B E 8621 8591: 8ot P / t o AU 33535927 f t i L s sr ED 1 1 s729611 s / i if MA T ..i. . 9 6. o. f. C n 82/6 u ue
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I i 1 l I I l ATTACHMEb7 - I l ODCM/ PROCEDURE REyISION LOG l l - l. I l l l DESCRIBE TE IbTORMATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, l l ETC.) ~ j l Cas e lor d ilz TG e T-l b~ ) U c-l't Th re r d l l y l il C home : 5.67 Eve 5 75 4 6 7 Ev o# l 1 l I I I I i 1 DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND 1 l A COMPLETE DESCRIPTION OF TE CHANGE (S) MADE TO TE ODCM: l I i l 79900 vackice l E r v o v-l sv V y l l l l I I I l' l l h l l 1 I l -i i i l l l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE PCRMS, TCN'S AND 50.59 l l REVIEWS): l l I ___ l l ~ 1 l l ~ l l WILL THIS CHANGE REDUCE TE ACCURACY OR RELIABILITY OF DCSE CALCULATIONS OR i l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.1!.)? YIS N0 t/ I l f l TESE CHANGES HAVE BTEN REVIEVED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL i 1 l SPECIFICATION 6.5.2. \\x j l l REVIEWED, RADIOLOGICAL E!jGINEERING SUPERVISOR: 7b - I// I l REVIEVED, SUPERVISOR - RADIOLOGICAL PROGRAMS: ed [,29A Y i j i /' l l j l l 1 l ll 1 i i j l ATTACHMENT l PAGE 1 ll l l l 1 l OF 1 ll RSP-0008 l REV - 0 l PAGE 112 0F 112 ! l I i i _, l I i
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I a ..f. 1 i l. ATTACHMENT - 1 l ODCM/ PROCEDURE REVISION LOG l I I I I I l DESCRIBE TlfE INFORMATION TO BE CHANGED (INCLUDE PAGE SUMBERS, EQUATION NUMBERS, I i l ETC.)~ l I I l 1 I I I I I I I I I I I I I l DESCRIBE (IN DET!.IL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l 1 I I I I i 1. i i i l I I 1 1 l 1 1 I I I I I 1 l i l I I l REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND 50.59 l l REVIEWS): l I I I I i WILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS OR l l SET?OINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)? YES NO l l I j WILL TH,IS CHANGE REQUIRED REVIf?ON TO LOWER TIER IMPLEMENTING PROCEDURES OR l ] COMPUTER PROGRAMS. YES NO l o l I l THESE CHANGES HAVE BEEN REVIEWED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l 1 l SPECIFICATION 6.S.2. l l 1 l REVIEWED, RADIOLOGICAL ENGINEERING SUPERVISOR: l l 1 l l REVIEWED, SUPERVISOR - RADIOLOGICAL PROGRAMS: l l l l 1 I I I I 11 I I I l ATTACHMENT l PAGE 1 ll l l l l 1 1 0F 1 ll RSP-0008 l REV - 1 l PAGE 111 0F 111 l l l. Il I I l}}