PY-CEI-NRR-1384, Semiannual Radioactive Effluent Release Rept for 1991: Quarters 1 & 2
| ML20082M316 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/30/1991 |
| From: | Kensicki S, Lyster M, Shatman R CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | |
| References | |
| PY-CEI-NRR-1384, NUDOCS 9109050138 | |
| Download: ML20082M316 (107) | |
Text
. - . _- - . _ - . _ - -- -- - - . -. . < . . - _ . - ..
CENTERIOR ENERGY PERRY NUCLEAR POWER PLANT va A<uw pg nm y Michael D. Lyster 10 CE NTI R ROAD pggn ggg ,ug g pg 7 g g g (g PE NHy OHto 440Pi Augtts t 24, 1401 m M < M 3?37 py_cp]jpyg 13g4 },
U.S. Nucleat Regulatory Commission Document Conttol Desk Washington, D. C. 20555 Perty Nucleat Povet Plant Docket No. 50-440 Semiannual Radioactive f;f f luent Release Repott Gent 1cmen:
Ve are hereby submitting the Semiannual Radioactive Etfluent Release Repott for the Petty Nuclear Povet Plant, Unit 1 fat the perlod of Januaty 1 to June 30, 1991. This repot t meets the tequitements of Regulatory Guide 1.?l, as applicable to the Perry Technical Specification, Section 6.9.1.7. All effluent ieleases vete vithin tl e concentiation and ielease 1imits specifled in the Radiological Effluent Technical Speci!Itations.
At the time this tcpott was generated, the second quartet analysis results for Stiontinm-89/90 and Iten-55 vete not available. An addendum vi11 he genetated when the results become available.
Also, . June 5, 1991, it was deter mined t hat the effluent system flow tate monitor for the Turbine Building /Heatet Bay Building vent radiation monitot had been inopetable duting two tan opetation since the summer of 19R8 (refer to Attachment 4 1icensee Event Repot t 91-012). As a tesult, a revision to the Semiannual Radiological Eftluent Repott will be submitted for the time periods when the flow monitot reading difteted from the acttml flow reading by greatet than ten pettent.
If you have anv questions, please feel tree to rall.
Sintetely,
, \ -
t *'E g Mic hael D. 1-ys t e r MDL: AllL:njc i
Attathment cc NPC Project Managet NRC Renident office NRC Region III S. Focht - ANI l~
(
'~"
b
]l
s Tile CLEVE!,ANI) El,ECTRIC !!.LilMI NATI NG COMI'ANY PERRY Ni1 CLEAR POWFR PLANT IIN I T 1 S E M I A N N tlA I. RADIOACTIVE E F F l.llE N T RELEASE REPORT 1991: Ot1ARTEftn 1 4 ?
e b't? I*'f$r} # D ' )
L gg %
a...
-() Ag'74(? 6 (,( ' i
, ..I(' I Iy I Il I f ' ,1 f ' d I' CDff1000? ill'l t )'? { i 3 I t_ m e- n {
,4 g -
^ ~ ~ ~ *
,- '#, ,A -
, /
n n:, L // O',;,eg/5 v J
,en r t al if/ina ue r , Prriy Nurlent De o! P .1 cr n t l
l m ,m-- - - . . . . , - . - - --_ . _ .
i 1
i
! TABLE OF CONTENTS i
I i
i l
- Page i
j Introduction .......................................... 4 l Radiological Impact on Man . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 f Supplemental Information ............................., 7 s
, Liquid Effluents ...................................... 9 i
l Gaseous Effluents .................................... 11 I
Solid Waste .......................................... 12 i
Meteorological Data .................................. 12 I
l Abnormal Releases .................................... 13
- Applicable Technical Specification Requirements . . . . . . 13 4
e f
i i
l T
l 6 6 2
4 i l
l l ,
u I
i i
i j
l ATTACIIMENTS t
Attachment 1: Radiological In. pact on Man (Dose Summaries)
) Attachment 2: Radiological Impact on Man (Land Based Sectors) t l Attachment 3: Technical Specification Limits Attachment 4: Liquid Effluents Attachment 5: Gaseous Effluents
! Attachment 6: Solid Waste i
j Attachment 7: Meteorological Data
- Attachment 8: Abnormal Gaseous Release i Attachment 9: Gaseous Effluent Monitoring Instrumentation l Attachment 10: Process Control Program (PCP) Changes
! Attachment 11: Offsite Dose Calculation Manual (ODCM) Changes i
i I
l 1
4 i
w i
i 1
a i
)
?
?
i t
i I
INTRODUCTION i
This Semiannual Radioactive Effluent Release Report (SRERR), f covering the period of January 1 through June 30, 1991, is
- submitted in accordance with Section 6.9.1.7 of Appendix "A" (Technical Specifications) to Perry Nuclear Power Plant l i
(PNPP) License No. NPF-58. It is designed to meet the !
requirements of Regulatory Guide 1.21, as applicable to the l PNPP Technical Specifications. Portions of the Technical F Specifications applicable to this report, Sections 3/4.3.7.9, !
3/4.3.7.10, 3/4.11, 3/4.12, 6.13.2, 6.14.2, and 6.15.1, are !
known as the Radiological Effluent Technical Specifications j (RETS).
l
)
During quarters 1 and 2 the plant produced 4,561,638 Megawatt !
Hours Electric Gross. The net reactor capacity averaged 85.9 i percent. The reactor was critical a total of 3927.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
l Liquid and gaseous radioactive effluent releases to the {
environment during this reporting period were samuled and j analyzed in accordance with the requirements of cae Technical l Specifications. All radioactive effluent releases were within the concentration and release limits sp?cified in the I RETS. l 1
Calculations and terms utilized in this report ate those outlined in the PNPP Offsite Dose Calculation Manual (ODCM). !
I The second quarter analysis results for Sr89/90 and Fe55 were !
not available for the generation et this report. An addendum j will be generated when the results become available. i I
i i
t
-l 1
l
_ 1 -
RADIOLOGICAL IMPACT ON MAN Sampling and analysis of liquid and gaseous effluents were performed in accordance with the frequencies, types of analysis, and Lower Limit of Detection (LLD) outlined in the PNPP Unit 1 Technical Specifications.
Radioactive material was detected in some of the liquid and gaseous effluent samples analyzed. Dose calculations, using measured effluent flow and meteorological data, resulted in dose to individuals at levels below 10CFR20 and 10CFR50, Appendix I limits. Direct radiation resulting from plant operation, as measured by environmental thermoluminescent dosimeters located around the plant, did not contribute any measurable dose to members of the public for the reporting period and, as there are no other nearby fuel cycle sources, 40CFR190 limits were not exceeded.
Summaries of maximum individual and population doses resulting from liquid and gaseous radioactive effluent releases are given, in Regulatory Guide 1.21 format, in Attachment 1.
l Technical Specification 6.9.1.7 requires assessment of radiation doses from radioactive liquid and gaseous effluent to members of the public while onsite. These onsite doses are assessed relative to offsite dose values, and are adjusted for appropriate dilution, dispersion, and occupancy factors.
ONSITE DOSE FOR LIQUID EFFLUENTS The onsite liquid effluent pathway of concern for members of the public is shore exposure while fishing along the Lake Erie coast. Occupancy is assumed to be 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year and the dilution factor for the point of exposure is 10.
l Ratioing this exposure pathway to doses calculated for l offsite locations yields the following onsite dose values.
Total Body Organ Quarters 1 & 2 3.9 E-01 mrem 1.5 E-03 mrem (skin)
Quarter 1 3.8 E-01 mrem 1.4 E-03 mrem (skin)
Quarter 2 5.7 E-03 mrem 1.3 E-04 mrem (skin)
~
_ 3_
j
. _ _ _ _ . . _ _ - _ _ _ . . . _ ~ . - . _ . _ __. -- _ --
ONSITE DOSE FOR GASEOUS EFFLUENTb Several cases are considered for onsite gaseous effluent exposure to members of the public including traversing a public road within the site boundary, shoreline fishing, non-plant related training, car pooling, and job interviews.
The onsite activity with the highest dose potential, relative to gaseous effluents, is shoreline fishing. Occupancy is again asaumed to be 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year. Accounting for this and the difference between annual average disgersion values for the onsite point of concern, 6.6 E-05 s/m , the following maximum onsite dose values are generated. The maximum onsite doses for gaseous effluents for the first and second quarter may not be cumulative.
Total Body Organ Quarters 1& 2 2.8 E-03 mrem 5.9 E-02 mrem (thyroid)
Quarter 1 6.3 E-04 mrem 5.1 E-03 mrem (thyroid)
Quarter 2 2.8 E-03 mrem 5.6 E-02 mrem (thyroid)
AVERAGE INDIVIDUAL TOTAL BODY DOSES Average total body dose to individual members of the public is determined for the population that lives within fifty miles of the plant for gaseous effluents (2.42 E+06 persons)
, and the population that receives drinking water from intakes within fifty miles for liquid effluents (1.82 E+06 persons).
These doses are calculated using the total population dose figures found in Attachment 1.
Gases Liquid l
Quarters 1 & 2 1.1 E-06 mrem 1.7 E-03 mrem
! Quarter 1 2.0 E-07 mrem 1.6 E-03 mrem Quarter 2 8.7 E-07 mrem 3.0 E-05 mrem i
Gaseous and Air Dose calculations at the site boundary were performed for two cases. Attachment 1 provides *he calculated maximum site boundary dose values for all sectors including those sectors which are totally over water in which no member of the public resides (These are the W, WNW, NW, NNW, N AND NNE SECTORS). Attachment 2 provides the L calculated maximum site boundary dose values for the land based sectors in which members of the public reside.
l I
W M a
SUPPLEMENTAL INFORMATION Regulatory Limits Technical Specifications 3/4.11.1 and 3/4.11.2 outline requirements for release of radioactive liquid and gaseous effluents, respectively. Concentration of radioactive material in liquid effluents and dose or dose commitment resultant thereof are limited in unrestricted areas. Dose and dose rate due to radioactive materials released in gaseous effluents are limited in areas at or beyond the site boundary. Technical Specification limits are listed in Attachment 3.
Maximum Permissible Concentrations The Maximum Permissible Concentrations (MPCs) in liquids are those outlined in Technical Specification 3.11.1.1 (10CFR20, Appendix B, Table II, Column 2, with the lower of the soluble and insoluble MPC being used; for dissolved and entrained noble gases, concentrations are limited to 2 E-04 vCi/ml).
PNPP Unit 1 Technical Specifications do not contain a concentration requirement for gaseous releases, therefore, MPCs are not used to calculate maximum release rates for radioactive gaseous effluents.
Average Energy Average energy requirements for radioactive effluent mixtures do not apply to PNPP Unit 1 Technical Specifications or Off-site Dose Calculation Manual.
Measurements and Approximations of Total Radioactivity Analyses of specific radionuclides in effluent samples are used with effluent path flow measurements to evaluate the radioactive composition and concentration of effluents.
_ 7 -
. - . .. - -. - ~ - - ~ .-.
Batch Releases i
Liquid effluent releases were considered continuous (runs of Emergency Service Water (ESW) Loops A and B) as well as batch (Liquid Radwaste [LRW] discharges). Although the ESW system is considered to be a continuous release path when in service, it is not run continuously.
All gaseous effluent releases from Perry Nuclear Power Plant were considered continuous.
LIQUID RELEASES January 1 - March 31, 1991 Batch Continuous Number of Releases 41 63 Total Time of Releases (min) 8.3 E+03 5,9 E+04 Minimum Time for a Release (min) 1.7 E+02 2.0 E+00 Average Time for a Release (min) 2.0 E+02 9.4 E+02 Maximum Time for a Release (min) 2.4 E+02 3.6 E+04 Average Effluent Stream Flow 2.0 E+05 3.2 E+04 During Periods of Release (1/ min)
- The total of ESW Loop A (5.2 E+04 min) and ESW Loop B (7.3 E+03 min)
April 1 - June 30, 1991 Batch' Continuous
! Number of Releases 58 62 Total Time of Releases (min) 1.1 E+04 9.4 E+04 Minimum Time for a Release (min) 3.0 E+00 1.4 E+01 Average Time for a Release (min) 1.9 E+02 1.5 E+03 Maximum Time for a Release (min) 2.3 E+02 4.3 E+04 l
Average Effluent Stream Flow 2.8 E+05 4.4 E+04 During Periods of Release (1/ min) l
- The total of ESW Loop A '7 E+04 min) and ESW Loop B (6.8 E+04 min)
I s
. . _ - _ m._. . .._.. _ __ _ .._ _ ._. _ . _ _ _ _ _ _ _ . _ .__..-._ ..= _ . _ . _ _ _ _
t I
LIQUID EFFLUENTS For the first quarter of 1991 there were 41 batch and 63 continuous releases. Batch release total waste volume for
, the first quarter was 4.8 E+06 liters; total continuous release waste volume was 1.9 E+09 liters; total plant discharge during periods of release was 1.2 E+10 liters.
i For the second quarter of 1991 there were 58 batch and 62 continuous releases. Batch release total waste volume for
}
the second quarter was 6.3 E+06 liters; total continuous release waste volume was 4.2 C+09 liters; total plant discharge during periods of release was 2.5 E+10 liters. l I
Summaries of the radionuclide total curie activities, average diluted concentrations, and percentage of MPC (in Regulatory i Guide 1.21 format) are included in Attachment 4. li i
If a radionuclide was not detected, ero activity was used l for that isotope in dose calculations. A zero activity l indicates that the radionuclide was not present at a level r greater than the Lower Level of Detection (LLD) of the instrumentation used. In all cases, these LLDs were less
-than the levels required by Technical Specifications. The i following are typical LLDs. I Radionuclide LLD (vCi.eml)
, Mn-54 2.4 E-08 !
l Fe-59 5.8 E-08 l Co-58 1.9 E-08 {
Co-60 3.4 E-08 j 2n-65 4.6 E-08 [
Mo-99 2.1 E-07 -
I-131 2.3 E-08 !
Cs-134 2.3 E-08 i Cs-137 2.6 E-08 i
, Ce-141 3.2 E-08 l l
Ce-144 1.3 E-07 l l
Sr-89 3.0 E-08 l Sr-90 3.7 E-08 i Fe-55 5.7 E-09 l H-3 4.6 E-06 f Gross Alpha 6.0 E-08 {
t i;
4
-9 -
__ _ . - . . _ _ _ _ _ _ _ _ _ _ . _ . _ - _ .. _. . ._ _ _ . _ _ _ _ _ _ . __ _ _ -.s
l Estimates of error associated with sample analysis, discharge volume, and dilution volume follow. Analytical error terms are based on split sample analysis results, the majority of which are confirmatory measurements, the othets ate inter-labotatory comparison results. Discharge and dilution volume (flow rate instrumentation) error is assessed using loop instrLmentation accuracy terms.
Gamma Analysis 101 11- 3 Analysi c 81 St-89/90 Analysis 10%
re-55 Analysts 211 Gross Alpha Analysis 4 'A Service Water volume 311 (Dilution)
Emergency Service water 251 Volume (Discharge)
Liquid Radwaste Volume 1%
.. t o ..
GASEOUS EFFLUENTS Summaries of the radionuclide total curie activities, average release rates (in Regulatory Guide 1.21 format) are included in Attachment 5.
If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A cero activity indicates that the radionuclide was not present at a level greater than the Lower Level of Detection ( LI.D ) of the instrumentation used. In 311 cases, these LLDs were less than the levels required by Technical Specifications. The following are typical LLDs.
Radionuclide LLD (uCi/ml)
Kr-87 1.7 E-08 Kr-88 2.3 E-08 Xe-133 1.8 E-08 Xe-133m 5.3 E-06 Xe-135 6.4 E-09 Xe-138 1.0 E-07 Mn-54 2.7 E-13 Fe-59 5.6 E-13 Co-58 3.2 E-13 Co-60 4.6 E-13
- n-65 7.7 E-13 Mo-99 2.1 E-12 Cs-134 2.1 E-12 Cs-137 3.1 E-13 Ce-141 3.2 E-ll Ce-144 1.5 E-12 I-131 2.8 E-13 I-133 4.9 E-13 Sr-89 3.8 E-14 Sr-90 6.8 E-14 H-3 3.0 E-10 Gross Alpha 5.4 E-12
f l
Estimates of error associated with sample analysis, sample flow rate, and effluent flow rate follow. Analytical error terms are based on split sample analysis results, the majority of which are confirmatory measurements, the others are interlaboratory comparison results. Flow rate instrumentation error is assessed using loop instrumentation accuracy terms.
Noble Gas Analysis 11%
Particulate Analysis 9%
Iodine Analysis 12%
H-3 Analysis 8%
St-89/90 Analysis 10%
Gross Alpha Analysis 4%
Sample Flow Rate 4%
Effluent flow Rate 4%
T SOLID WASTE There were 19 radioactive waste shipments transported from PNPP for the period covered in this report. Four shipments of dry active waste were sent for compaction prior to burial (8960 cubic feet). There were 15 dewatered liners (2730 cubic feet), which were sent in 15 separate shipments. There was 1 dewatered HIC (136 cubic teet) which was sent in 1 shipment. There was no irradiated fuel transported from site.
There were no liners solidified. See Attachment 6 for volume and activity values. All radioactive-shipments during the ;
reporting period were LSA and shipped in strong type !
packages or NRC certified packages. l METEOROLOGICAL DATA Cumulative joint frequency distribution (JFD) tables of wind speed and direction for each stability class, as well as for ,
, all stability classes combined, are given in Attachment 7 for !
l the annual and semiannual period and for each quarter of the j semiannual period covered by this report. - >
t These JFD-tables are the results obtained from the processing I of hourly average meteorological data collected at the PNPP !
site met tower. It should be noted that the 1-3 mph JFD !
column includes wind speeds down to 0.1 mph and that hours of i 0 wind speed appear only in the totals columns. The separate _i i
tallies of periods of calm include wind speeds from 0.0 to l
<0.7 mph. Differential temperature (ST 60 - 10 meters) is !'
generally used for atmospheric stability classification.
l i
I
?
- . . - - . - . - - - - - _ . _ _ _ - .~. ~ . -. - , - -. - - - _ ~.-.-.. ._,
I i f I
ABNORMAL RELEASES !
l 3
There was one abnormal gaseous release during the reporting j period. The release occurred due to the loss of the Turbine l Building / Heater Bay exhaust fans while the supply fans j l continued to operate. Under these circumstances, the supply ;
flow would exit the turbine building and heater bay through l unmonitored windows, louvers, doorways etc., circumventing i the normal radiation monitor, 1D17K850. This event began at l approximately 2100 on 3-04-9I and was terminated at 0245 on -
3-05-91. l The release is categori:ed as an Abnormal Release, solely due f to the fact that the release was unmonitored. No Technical l Specification doae or dose rate limits were exceeded. In I addition, The Turbine Building / Heater Bay exhaust is an :
unfiltered pathway providing no *reatment to the effluents and would not requ.re reporting per Technical Specification 3.11.1.5.
I Air samples taken in the turbine building and heater bay both "
l verified that any activity present was below the lower limit of detection ( L L.7 ) for our counting equipment. Dose and dose :
rate calculations for this event were based on the results obtained from the weekly filter and charcoal cartridge analysis from the Turbine Building / Heater Bay Ventilation System. The only isotopic value present was I-133 on the charcoal cartridge at a concentration of 5.58 E-12 uCi/ce.
The organ dose for the abnormal release period was 1.60 E-03 mrem constituting 0.11 percent of the annual limit. The dose rate for the abnormal release period was 2.45 mrem / year constituting 0.16 percent of the limit. See Attachment 8.
There were no abnormal liquid effluent releases during the reporting period.
APPLICABLE TECHNICAL SPECIFICATION REQUIREMENTS Per PNPP Technical Specifications, certain noncompliance items, changes, and findings are reportable in the Semiannual Radioactive Effluent Release Report. -
Radioactive Liquid Effluent Monitoring Instrumentation noncompliance ( PNPP Technical Specification 3.3.7.9, Action b.):
i There was one case in which liquid effluent monitoring instrumentation was not restored to an operable condition within the time required by Technical Specifications.
l
During the reporting period, one item met the criteria as reportable per Technical Specification 3.3.7.9.b, for inoperability in excess of 30 days.
On August 12, 1990 the Radwaste to ESW licuid effluent radiation monitor was decin ed inoperable when a High alarm came in isolating a Radwaste discharge which was in progress. The alarm appeated to be due to electrical spiking. The source of the spiking was a grounding problem which was difficult to identify and correct. While attempting to isolate the electrical noise problems, the monitor's sample liner became too contaminated tc be effective for further use and testing was suspended until a modified sample liner was installed. After a new sample liner was installe3, a grounding problem in the preamplifier was feu-d and corrected. The monitor was declared operable an February 5, 1991. During inoperability period, independent samples were taken per Technical Specifications. This evant was also reported in the SRERR for the 3rd and 4th quarters of 1990.
Radioactive Gaseous Effluent Monitoring Instrumentation noncomoliance (PNPP Technical Specification 3.3.7.10, Action b.):
There was one case in which gaseous effluent monitoring instrumentation was not restored to an operable condition within the time required by Technical Specifications.
On May 10, 1991, the Turbine Builcing/ Heater 3 ty ventilation system was changed from one exnaus* fan operation (winter mode) to two exhaust fan operation (summer model The flow monitor indicated a flow of 280,000 cfm while the expected flow was 345,000 cfm. Due to the discrepancy in expected and indicated flow, the monitor was declared inoperable. Upon further nvestigation, it was determined that the flow monitor had been inoperable during summer mode cperations since the summer of 1988.
The pitot tube array, for the Turbine Building Heater Bay ventilation system, will be calibrated during the third refueling outage. Until the calibration is complete, a default value f 345,000 cfm will be utiliced for dose calculations. See Attachment 9.
J
]
Liquid Holdup Tanks noncompliance (PNPP Technical Specification 3.11.1.4, Action a.)-
There were no outside temporary tanks containing radioactiva liquid on the PNPP site during the reporting period.
Radiological Environmental Monitoring Program (REMP) changes (PNPP Technical Spacification 3.12.1, Action c.):
For the reporting period, samples were obtained at their ified respective locations as required by the spec-ollection frequencies.
During the reporting period, water sample location 28, food products location 70 and milk sample location 71 were added. Milk and feed / silage location 30, food products location 50 and milk and feed / silage location 52 were deleted. In addition, the REMP location maps in the ODCM were updated.
The changes to Locations 28, 30, 50, 52, 70 and the location maps were included in the SRERP for the 3rd and 4th quarters of 1990.
Land Use Census findings (PNPP Technical Specification 3.12.2, Actions a and b.)-
During the reporting period there were no changes to the Land Use Census.
Process control Program iPCP) changes (PNPP Technical Specification 6.13.2)
During the reporting. the Process control Program tPCP) was revised to Revision 3 to allow for the use of new radwast? processino vendors and the processing of waste tram decontar T a t i o ri procedures. See Attachment 10.
Offsite Dose Calculation Manual (ODCM) Canges (PNPP Technical Specification n.14.2)
' During the reporting period, a Tru necame affective incorporating the liquid radwaste dilution flow range and the tables and references for the individual dilution factors for the potable water and fish ingestion pathway. The TCN also reflects the changes made to the REMP program. The new REMP milk location 71 will be added to the ODCM during the 3rd or 4th quarter of 1991 See Attachment 11
Major Changes to Radioactive v'a s t e Treatment Systems (PNPP Technical Specification 6.15.1)
There were no changes made to the Radioactive Waste Treatment Systems during the reporting period, m
_ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - J
5 I
t i
t 1
' Attachment 1 !
Radiological Impact on Man (Dose Summaries; j i
h i
I, t
t
?
r h
1 I
t 1
e i
i e
I e
I I
i i
l f
4 r
h I
, - . - . , .. ,,. . - , . . - - . . . . . . . . . . . . - - --. s
i Attachment-1 (Page 1 of 3) nadiological Impact on Man (Dose Summaries) 1991: Quarters 1 r. '2 iu 1
a 3UMMARY OF MAXIMUM INDIVIDUAL DOSES LAET ACCUMULATIONS FOR PERIODS!
l L 00!D 91 1 1 1-91 63024 OASE0VS 91 1 1 1-91 63024 A!R 91 1 1 1-91 63024 3 _
ATTLICAPLC ESTIMATED AGE LOCATION % OF LIMIT l :' .;~"* DLL Att DOSE GROUP DIST DIR APF'L IC A BL E (MREM) (M) (TOWARD)
LIMIT (MREM)
.:2U1: TOTAL EODY 5.40E-02 ADULT RECEPTOR 1 1.0Ef00 3.0EiOO
.:'U:: LIVER 7.77E-02 TEEN RECEPTOR 1 7.8E-01 1.0Ef01 i ...................................
- L: "A! AIR 00$C 3.96E-02 293. WNW 4.0E-01 1 0E401 (GAMMA-MRAD) i l!.: 1A0 AIR 005E 5.38E-02 283. WNW 2 7E-01 2.0Ef01 i (P!TA-NRAD)
- L: ;A; T t0DY 2 56E-02 ALL 203. WNW 5.1E-01 5.0E400
- LE 3At 3 r. ! N 6.77E-02 ALL 203. WNW 4.5E-01 1 5Et01
- !!NE1 *HYROID 4.94E-01 INFANT 203. WNW 3.2E400 1.5Ef01
' ' ' 'I CL'L A T E :
SUMMARY
OF POPULATION DOSES LAST ACCUMULATIONS FOR FERIODSl LIQUID 91 1 1 1-91 63024 GASEOUS 91 1 1 1-91 63024
' ~ ~ 13 0:' AFPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM) l _:7U:t TOTAL 00DY 3.1E400
.!:U!L THYROID 3.70-02
?AT*:U: TOTAL 00DY 2.6E-03
'!":000 THYROID 1 6E 01 l
l l
l J
Attachnent 1 (Continued - Page 2 of 3)
Itadiological I mp~a c t on Man (Dose Summarien) 199T: Quarter 1 l
IUMARY OF iiAx! MUM INDIVIDUAL DOCES
. ;. 51 AECumVLATIONS FOR PERIODS:
. ! .1U I D 71 1 1 1-71 331?4
.-i, ECUS 91 1 1 1-91 3314
.R 71 1 1 1-91 3314 trr ::A: L; E S T I M A T E l. AGE LOCATION % OF L Ilill 27 ;: - 3r " a DDEE GEDUP D131 DIR APPLICADLE MhCM) (ft) (IDWARD) LIMll (MREM)
- .:' *:iAL : :' f 5.::E-0; ADULT EECEfiCF, 1 1.BE600 3.00t00
_. .: - L : ';E F. ' t:E-02 TEEN REEEF10k 1 7.6E-01 1.0EiO1
+ - --
.o. m.r
..:.- . 3..s. E *s3 ~*4
.< 4
. 9 . O E. - O '. 1 'E+01
.:A,~ ; -r Ap;
- .: : ,: , ,.- ,t. :0;E 4 ;.0EE-02 :94 N 5.4L-02 0.0Ef01
- w. .m . r e . ')
os
.: ." :;.2
. 7:E-03 ALL 274 4 1.1E-01 5.0E+00
' :: L E :t.: :L:
1.47E-02 nLL
- 94 N 7.3E-02 1.5Et01
'0:D 3.31E-02 CHILD 20. NHW :. E-01 1.5E+01
'. 1 ,.,
...n.r. -
IUnit AR f 0F F'OPULATION DOSE 2 ,
L ,. 31 ACCU.*ULATIONS F0E rEFIODS:
- 9 L'! ? 01 1 1 1 01 3314
- AEE3UE 31 1 1 ;-;; 331: 4
... ~.. ... .. - ....-.-....--......-- . ... --....--
~~~;_:g+ wrL :AFLE E;T MATED fd A N FGruLAT 0N DOLE siEE50H-REM)
_ . ',' , ,,: : '.D T A L , D 0 D Y J g.n r 1.
, '. .r E+00 w L . ., e
. J. , i) nswri J. Js.
g>t . . 4
. .: . . . 'aYF 0:0 ';. IE-33 E
N N l l
l l
i Attachment 1 (Continued - Page 3 of 3)
Radiological Impact on Man (Done Summaries)
- 1991
- Quarter 2 a
l
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PER10 dst L1001D 91 4 1 1-91 63024 GASEOUS 91 4 1 1-91 63024 AIR 91 4 1 1-91 63024 APPLICABLE ESTIMATED A0E LOCATION % OF LIMIT
- CT"LUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (H) (TOWARD) LIMIT (MREM)
, !]UID TOTAL BODY 7.86E-04 ADULT RECEPTOR 1 2.6E-02 3.0Et00
.I LICUID LIVER 1.49E-03 TEEN RECEPTOR 1 1 5E-02 1.0E401 li;ILE GAS AIR DOSE 3.96E-02 283. WNW 4.0E-01 1 0Et01 (OAMMA-MRAD)
NCILE GAS AIR DOSE 5.3BE-00 283. WNW 2.7E-01 2.0E+01 fBETA-MRAD)
NDILE 3AS T. BODY 0 56E-02 ALL 283. WNW 5.1E-01 5.0Ef00 NC&LE 3AS SEIN 6.77E-02 ALL 203. WNW 4 5E-01 1 5Ef01 l ICDINE1 THYROID 4.50E-01 INFANT 283. WNW 3.1Ef00 1 5Ef01 FARTICULATtt l -..................................
SUMMARY
OF POPULATION DOSES LAST ACCUMULATIONS FOR PER10 dst LIQUID 91 4 1 1-91 63024 UASE005 91 4 1 1 91 63024 t
ETFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PLRSON-REM)
LIQUIL TOTAL BODY 5.4E-02 LIQUID THfROID 7.7E-03 i
CASE 000 T0iAL BODY 2.1E-03 GASEQUS THYROID 1.6E-01 l
l
i Attachment 2
) Hadiological Impact on Man (Land liased Sectors) 1 I
l.
l
~
j .s
l Attachment 2 (Page 1 of 2)
Radiological Impact on Man (Land nased sectors) l Quarters 1 & 2 J
AFPLICAOLE ESTIMATED AGE LOCATION % OF LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)
~
NOLLE GAS AIR DOSE 7.93E-03 1445.-SSE 7.9E-02 1 0Et01 (OAMMA aRAD)
NOBLE GAS AIR DDSE 6.39E-03 1420. S 3 2C-02 2.0Ef01 (DETA " RAD)
NCILE CAS T.200Y 4.39E-03 ALL 1445. SSE 8.8E-02 5 0E100 NOBLE GAS SKIN 8.14E-03 ALL 1445. SSE 5.4E-02 1.5Ef01 10DINEL THYROI 2.37E-91 INFANT 900. WSW 1.9E400 1.5Ef01 PARTICULATES Quarter 1
...-.....--......--------- .----- ..---.-------.-------- .----~~~~----
APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT rTFLUENT
~ ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)
. ---.........------....... ........----......--------.--------~~~----
NOILE GAS AIR DDSE 2.79E-03 1420. S 2.8E-02 1.0Ef01 (GAMMA-MRAD) 101LE GAS AIR DDSE 4.64E-03 1420. S 2.3E-02 2.0Ef01 (CETA-MRAD)
NOI.LE GAS T. BODY 1.24E-03 ALL 1420. S 2.5E-02 5.0E+00 JO?LE GAS SKIN 3.21E-03 ALL 1420. S 2.1E-02 1.5Et01 10 DINE 1 THYE01D 2.16E-03 CHILD 700. WSW 1 4E-02 1.5E+01 PARI!CULATES i
~
J
Attachment 2 (Page 2 of 2) l Radiological Itapact on Man,,(Land Based Sectors)
Quarter 2 AFFLICABLE ECTIMATED AGE LOCATION % OF LIMIT ETFLUENT ORGAN LCEE SLOUP DIST DIR APPLICAliLE (MREM) (M) (TOWARD) LIMIT (MREM) 1CILE 3AS AIR '05E 7.E7E-03 1445. 3SE 7.9E 02 1.0E+01 (GAMMA ML; NDELE GAS AIR DOSE 3.09E-02 1445. SSE 1.9E-02 2.0E401 i DE T A- 9R.;D )
NCILE GAL i. ECD 1 4.25E-03 ALL 1445. GSE 0.7E-02 5.00400 NCBLE GA1 St;IN 3 04E-03 ALL 1445. SSE 5.4E-02 1.5E+01 IC0lNE1 THYED!0 2 35E-01 INFANT 900. WSW 1.9E+00 1.5E401 FA0i100LATEE
- ~ . _ . . . - . _ - . ._ _ _ _
i 4
l
) ,
Attachment 3
- Technical Specification Limits s
t 4
i l
1 t
i l
i I
~
Attachment 3 (Page 1 of 1)
Technical Specification Limits i
LIQUID EFPLUENTS: 1 t
- Concentration < 10CTR20
- release rate limit :
Appendix,D, Ta51e II, TS 3.11.1.1 Column 2 l
1.5 mrem total body + quarterly done limit l
+<~1 5 mrem any organ per TS 3.11.1.2 ;
- 3 3 mrem total body
- annual dose limit !
1 10 miem any organ per TS 3.11.1.2 GASEOUS EFFLUENTS Noble Gases j I
- 3 500 mrem /yr total body 4 dose rate limit i 3 3000 mrem /yr any organ per TS 3.11.2.1 i I
4 $ 5 mrad air gamma + quarterly air dose {
limit per TS :
3 10 mead air beta 3.11.2.2 I i
)
+ 1 10 mrad air gamma + annual air dose j
~< 20 mrad air beta limit per TS l 3.11.2.2 [
t i
L
! I-131, I-133, 11 - 3 , Particulates with 11alflives >8 Days
- 1 1500 mrem /yr any organ
- dose rate limit per ,
- 1 7.5 mrem any organ
- quarterly dose limit per TS 3.11.2.3 l
. t
- 1 15 mrem any organ
- annual dose limit !
j per TS 3.11.2.3 ;
~
I
[
- Dissolved or entrained noble gas concentration is limited to 1 E-4 uCi/m'..
I i
i l t
h
Attachment 4 Liquid Effluents
~
_ _ _ . _ _ _ _ _ _ _ _ - - --- -- ' ~ ~ ~ ~
_. . m . - - _ . _ _ _ . - . _-
e i
i l
.I t
i t
i i
e I
i i
f a
1
' * * *"1 5 1 ..f1 4 .. e* ...4 .... a .. e f3 , .... * .... -...
g ...4 . .. . s . . t M 7 t rt
- 5 . t *
- 1 i .
I 1 . : 9 .
8 ' 9 + **
l t t ** (4 i +
- t
- f fJt S. r (4 a f3*6 '
a t-J t t) * ** *T 7+"
i
! Cd: t ? - *: 1 e . n . t . t . e -= . . t . t . 4 f . * . * . t ~T t -
t
-* +
f tM3* I 70 t t M 4 *e t t t ***
t t t t * ** --*a j f t'1 f * * *
..-*r- # s 4 . O 1 ys -** tt13 9 -4 e t3 3 3. --* t f y 3, e 4 t e-4 , p w'9 f mya e
4-4* st r.
et e tv t
" Uf! ' '**t0A 1 1. 3 . 11 I "*f't t O e; 9 Ot 4
'.1 6 ? O:Y. 1 w'""' t Z f'".
- t. y 4 *? f'1 4 ()<! t O t 3 ~*1 M
- Ot1 3 !*' f f ' fl D *
- -4 ' sD .
f .ti O 8 *' 79 t Z M l .-4 ee4 : '"*7 t Zt*T* w-t* **
- O f'1 i T 7 t "? ! t > i i1 *
- tf7 I ( 1 *'t t yt f* 1 f f 't n ( 1 *7 1 7. t C +r*()t OT' t -4 3* ? O '1 *'e 8 C t 1 t f- 3 : ..f7 4 pafa # .- e e 4f+1 e . 7 I f- t ;g i
i XS
- 1 1 *
-r-i u f'1 t . J. 4 r~ e Z t *1 p j ? w>4 8 1
t nZt f) t . M tM-t cy e ef1Z* O+= t t t- , , , .-
? O J. t t 7a "9 t 3.-448*9f'1 e "vp p e? 9 p-4 9 t?f*1 t --? 1 **? 8 7 t =ri
- ot i M! : + m SC e 3. -4 t *?f-l e * *. .*
j IMt 95 t t: 9Mi 4 -+ 'C TOM: Z t et o.4 tQCe f U.4 : I fe y. t r O t M t? 8 f*
- b tr Mt"'7P?8F t I r* O 8 W 9 P f*
- P.? ~*
t r
1 1
-4 i t ** f"1 9
- f-t 8 . SC e I M *-18*~ew 9 M 1 Z e f*1'1 e %4 5M t 9 M 711 us-4 Ut **1 9 -* ;. pp 1 ** u t 1 f- a i r. 1 ~) I t Z r* 3
- t *-* $ 8 Z r- t *) f 4 9 Z e"~ f M J* t P S t* t7 "M g
4 1 f7 0 t t C *** I 9 t/l i > 1 f* 4 O C # tet t t F- 3 OC I to t m 1 7Zt # ~4 f"'t t I f'1 t U tM tf*
- OC t (*? (1 8 11 t -4 -*.4 -
9 64 t --4 9 M t M fw a -4 9 M i 4w t .4 0*Mt -4 9 '
f-* fl s 9 t -o r" t t i me t ;g g "9 f*1 9 e Z 8 *r e *"9ftt 3 gE t "9 f"1 9 i w s' *
- ?
9OUS 1 Of*1 i . t t 6 H $ f*1t? f 4 -4 9w a t'Te-p i t t *-4 t MC t 3* < 1 C 77 ecds t Ja' 33 3 1 p O.
2 t4 g ;P9 y eM t 4 6 -9 9 1 g -.4 9 ;r9 0 r"* f'1 e ys 4
- M
? D?
.. -4 a wg
, ! 4( t w t 'l t t 8 O t 09-4 8 9 y 9 4 he 9w
) t-1 0 8 f f 4 t 7 >t t -4 e C to f*** -?
- i f"'t t t 8 -4 9 $O t 9 +4 t tO 9 9 t O e 1;g31 m t :T' -9 #. U 8 Mt t t? I t I w t 3O f e Z t *-?
t m 2 e t t 9 e t t *:* t > T*
- O f !T O* * * * **
( g 9 .. . . t I e....
t t
t t..
1 e .C4 4
9 I
....g....t..t t i
.M, e
t .... g
....f..
I t B 8
..*.t-- i Z . . tt .)t .1 c.
i e f~ t f f~ t t
t**.t t***** t .... I t <4 y. pay y,
- ** 1 1 *4 t t t -4 t Ce t t a Cf 9 e i Ce t "PP t t 4 ** f- J o.4 ea 9 e 1 4 t i f1 P 4 O t t Oi e t t O 9 /) 9 C8 il ***> '#
44 0 4
%.3 f7 t 9 4 0 t oi i t utOg 3 e 4 -fnt I e >-.9t nt O t Z9 .e 2- 7 ~. --
i F1 1 1 *4 8 9
%*9 %9H I
- ft t t*t N 9 e.e 1 1 44 t '. t 4 8 "? wl e f7 " Y 8
78 9 M1 i ' t $ IK 0 t M t E6 e t "I t
- C f
-48 t M '** Ov '.y
- a g
f (J t t t.71 t 9 t g ft e O I 6 e 1 6eO
. t t t ,I t
t r-- t i g i f"* t i i M3 e M O g .c i
t t , e 1 t B I t t t f .1
_ t 9 . -
l 1
t
.. e t....
I 4 t t..
t t
.. . 0 .. t .. I f...9 g ..f.. t t .. t .. t.... I (f) t ....
- t U -4 8 t t t t t t t 8 e e I t t t e f*
] t t t t t r*t* -1 i.*
j t 8-* 9 3 6* 1 t
1 -O 9 t
t Jm #
t
=
t t t a t t t t t t 9 as f' 7x " *'
I 1 9Jt ($ 3** t MS Ut Ot a **
, t - t 4 - t t. i i . t .O t3.ma i t . t . S. i O
8 4 - , . 4 i
ca f --*
?
4 8 OI e *G t 6 PJ l Mi th 4 ma e t %J 4 9 ,
y
' t t Z e F) 9 -O 3 4 % 8 e f *1 t *-*t e I
Ce t t -O 1 e fJV h 8 -J t t wt t-9 99*9 o. e O t s t Jw t f .P t t 6*.v' t t F- *"**?.
37 t (7 4 1 t'l t t t'1 e f*1 8 M i
, f.'1 tI 0 M, t, f71 t e 3p 9 f'1 i Mf f -49 t *** 4 -4 t - 1 t t t I t f.vt 9 t t I t t t t t 9 i e 0 8 I e Mt . . f-r- . , -
t ** 4 't O $ tot O8 t
1 6* *OO t O4 ofOt t t O3 O4 I 7e t to t O3 0 -O 3
- t *t t t O4 +. 8ui t,4 9 9 4 4 t (23 9 O 8 t t 9I f30 i e t #7 M4 4 9 9 I 8 9 8 I , 9 e t t t t I e t.7 * **
t .. .. t . . . 4 .. . . t t
f .. .. O f.... 1 3.. I t . . .. g . . .. f .. I t....g....t..
9 t t g t....t cy(y 9 1 1 i t t 8 4 8 8
- 3 t 0 8 t t t t I t t t I t 1 i t 8 etJ d 4 9 9 e i e f f I LJtJ t PJ e t Jm I e t tJ t L** 0 *-. t t tm e t O. ** f 0 Ne ** 8 Qt n.*
t 6
. 1 t
( 89 9 e
- 1
- 6 4
9 Ot S t
. t . 3 I e . 0 . t u.
t 9 9
I y B . t + t 8
Ct t je j C* t PJ $ u e t O9 tJ f O I a N. -O t
! t tJ f g -O 9 iO4 8 W9 Ch I td 8 f g t 3* I J' Ja 1 I **1 t 8 M t 8 tb 9 OtM t t 3
8 (b t CP 9 0 ? J 4
- f'1 9 9 f*1 i f'1 9 r*1 9 t f*1 8 fvt I fvt t t 9 Mt t*1 8 9 -49 9 +1 1 -*- t 9 -t- t t t 4 9 0 t t t t t I t+e t 8 8 e 9 9 t Me
. # ** t t O t t Ot e O8 a9O+ t O8 OtOI e of e -O f i OB t t ** 1 Ot 1 -ry 9 3 t t t t t t ta i wtut 8 w. ytot 9 9 Oi US 8 e 8 9 d
t .* 9 3.... t t .. t t .. . 1 .. . 98 .. I t
0 t t f .. .. t ..
t 9 .. O e i I ..
t t 1 .. .+ t . . . 4 t t t . . .. t t
I a
4 i
1 l
1
(
a i.
-.J
Attachment 4 (Continued - Page 2 of 2)
Liquid Effluents OUARTER 1 : OTART DATE 91010101 END DATE 91033124 00ARTER 2 : START DATE 91040101 END DATE 91063024 OATE "r REPORT: AUG. 7, 1991 FREPANED BY:
CONTINUQUS MODE
.......................................................CH
- NUCLI.tE; : QUARTER BAT HODE ern cir.asus ww
. UNITO !1 :
. QUAR,TER 1 QUARTER
!.. OUAR,TER I
. 1 .
. ... .....,....................._............. . 1 . t H3 : CI 0 00E400 0.00E+00 1.0
...............................................1E400 CRii
- 1 1
3 07Ef00 t CI : 0.00Ef00 1 0.00Et00 : 8.47
...................___.........__...................E-04 MN!4 1
1.31E-02 1
- 01 : 0.00Ef00 0.00E+00 2 36E-03 i 1.16E-04 !
TEtt CI
...,. ..__................. : 0 00E400 1 0 00Ef
........__ . 00 : 2 79E-03 ! 0.00Ef00 t C050 : C1 ! 0 00E+00 !. 0 00E+00- 0 00Ef00 1 1.66E-04 t
....._...........__..........__........1 ........................
4 COLO : CI : 0 00Ef00 0 00E+00 1 1.
2N05
_.............................. ..... .. 37E-02 .............._.....
2.79E 03 8
- CI : 0.00Cf00 0.00E+00 4.
it??M
........................................ 96E-03....................1 2.58E-03 1
- CI : 0 00Ef00 : 0.00Ef00 : 8.42 0 00E400 t I
.............___._..............................E-06 AG110H : CI
- 0 00E+00 l - 0.00Ef 00
.... ......._........................ ... ____.1. . 2 10E-05 : 7.45E-04 1--
- C0124 : CI : 0 00Ef00 : 0 00Ef00 5 94
- C0107
_.......................................E-03 !
1.55E-05
- CI : 0.00EtVO : 0 00Ef00 : 8 37E- 3 :
.......... .._ ..........__..._...................... 0 1.02E-04 I
,
- Sti 5 : CI : 0.00Ef00 : 0.00Ef00 : 2.42E-04 : 0 00Ef00 l .........................__..__.............................. ........
i TOTAL FOR : : : : 1-
- PERICO l
- CI ! 3.00E100 : 0.00Et00 : 1.05Et00 : 3.0?Ef00 :
(ADOVE) : : :
...............................................:........_..8
~
- iti;; : CI : 0.00Ef00 : 0.00E+00 : 1IO6E-03: ~ 1.20E-03 :
- t YE12: : CI : 0.00Ef00 : 0.00Et00 : 1.01E-04 : 1.31E-04 :
L l
l l
' FJt v
>j ,_)'i
. p/
.., ,. n
- d
_w i ~_M 28 - .
, , _ . _ _ _ _ _ _ _ - _ _ . _ _ _ _ - - - ~ - * - - - - " - - - " - " ' - -
- - - - - - - - - - - - - _m a hawag ess.wA. huh - hem A- -
E I
I i
I I
i d
i t
J I
I Attachment 5 Gaseous Effluents c
4 1
1 I
I 1
l l
l l
l I
. _ ___ _ __ _ . _ _ . m I
i .
l i
1 Attachment 5 (Page 1 of 2) 1 Gasecut Effluents I
5 0UARirq : Sing; DATE 71010P)1 END DATE 91033124
- JUARiff .; . STAh! DATE 71040191 END DATE 91063024 EFFLUENT AND WASif DISP 0 GAL REPORT GAEEOUS CfrLUENTS -- SUMnATION OF ALL RELEASES QUARTER : QUARTER :
- UN113 .:.
. 1
........................ )
i A. F13510H AND ACTIVATION GASE3. . .. .. .... . ........... '
- * . TOTAL RELEA2E CI
- 30E+00 : 1.33E401 :
! : ". AVERAGE FELEASE :UCI/SEC: 4.89E-01 : 1. 6'/E + 00 : :
- RATE r0k FER*0D .
ECHN % : gfA : 0:.
3 . F.E. E C E.9 T. G.r., ,w , ,I
- Cu C, A L : _. . H/A i e
., t . r. . r . w n . .MiT . .
j
.. . ...._ .. _ . ........ . . ... .... ..... . .. i
- c. ,r,...
.u.~t
- 1. !OTAL ICDINC-131
- C : 6.7dE-04 : 3.35E-03 :
. a
. s
. . ~ .
e no e. r_ ue .a.
. . r. %o r e u,, .a.
. . i r 3.og.ne. ta .
4.m.r. 04 a snlr. 4 r ET I9 -
n r.'.4 .... . ................ . .. . .....
' ; : N/A :
- 1. ?."me "X TE ICCH . N/A ,
a m , I ct.,, N v T .O. F , n N . N, I C, AL. :
u.M.T .. . . . . . . . . . . . . . . . . . . . . . . . . . . . ~
. r i v .
I
- e. ni~.u. c , , ,. ~.. a . c.. n.,
r, . , ,6E-0,, .
n, J. .. ..
4 . 8 7 E - 0 c,.,. ..,
...,A.,, , ...,,d
., w.
. r
..,,e.
. n . n, .
. w 1 . . .
.rr. .. . a, n.,.. , . . .r. e . 6 . n a, E . 0 6 . 3.e1L.08 a .
-n. E,.'._n,.,.
. ..sce.. .
vt c r. ... . L- . .
0.00Et00 :
TCO: MICA
. : 0.00E400 1 .
t
~.E' , .::. ..n... '. :. ". . e ,I ,., .41, L ,: .
t
, _ ._. ._. ... . . .............. .......... p
.-.s..
. 4 nv. , b, . .n.y e ,e .
8.96E-06 . 2.62E-05 .
t i .
~.. . . .
n.s.n...>,,.. . . .
.. . m .. ,., .4 u.
0.00Et00 : 0.00Ef00 :
C! l
- 1. *?'l-L ".EL:l.00 :
l ..
n s . v, po t* l ,*s . s . - 0 . 0 p%(
~ t 0, 0 t
.s.
s .> z r* r
- r_ e
. .J r. ,. .e ea e,. p e. .
.m n=.
s- *%*-enr.. %.
- . .n. rr.e...e
. .i . . .
a
_- -..e ,c.or ,. ., . n, rn s.
- r. -
- n N, c,i u nL .
. gfA .
N/A .
-..r
.e o.,.. Lnt .Jiu 64s.6 8 s .w
...,. ... ...,......... . .+....
d I
i i
1 I
i e
b f
r t
--.m.,m_ - . , , . . . . , _ - _ , _ . . _ _ _ ._ _,__,m
___ v,_.. ._ . . _ . . ,.,,,,.r-_,.,,#_,. . - _ . , , _ ,y____,._-,_._7,_,, - , , , , . . . . _ , , . . , ,,.,_..v.
?
f I
I Attachment 5 (continued - Page 2 of 2) {
Gaseous Effluents :
i r
i ie r
00ARTER : : START DATE 71010101 END DATE 91033124 I UUARTER 2 : START DATE 91040101 END DATE 91063024 i DATE OF REPORT: AUG. 7. 1991 4
FREPARED BY: ,
CONTINU0US MODE BATCH NODE l
- NUCEIDES : UNIT 3 : QUARTER : QUARTER : QUARTER : QUARTER l
- RELEASED : : 1 : 2 1 : 2 : !
.._. ..........__....__................................... ____..__... 1
- . II
- CION AND ACT!JATION OASES
- KR00n : CI : 0.00Ef00 : 1.37E-03 : ------ -
I
- fRC7
..............................4..__
- CI : 6.77E-02 l 2.14E-02 : ............._______.............._ - - -- ; -------- :
7.00E-03 : 3.17E-02 :
- LR30 : CI l
--- _. .. 1
- XE133 : CI : 3 93E-01 : 1.20Ef00 -------- ! -------- :
- XE135M : CI : 8 31E-01 5.32Et00 l -------- 1 -------- : i
- XE1:5 : CI : 2.06EiOO : 5.93Ef00 : --~~---- : - ----- ! !
- XE1 7 : CI : 2.57E-01 :
2 59E-01 ----
l !
- XE138 : C1 : 2.41E-01 : 4.37E-01 : ---- ; ----- : !
TOTAL FOR : : : : : :
. PE.RICD : CI : 3.00Ef00 : 1.33Etoi : --------
. On 0 n, .
h
- 2. !0 DINES .
1131 CI 6.74E-04 : 3.3;E-03 l ----- :
l !133 : CI : 1 82E-03 : 6.85E-03 l -------- -------- : .
,0
. T n. m . v TnR .. . . . . .
- PERIOD :
CI :
2.49E-03 : .
1.00E-02 : .
l
. ( s t noo.me 1 . . . . . .
t l
7, .,ca s n m. R.
, T 9. C . t iveni.s ,
- CRO? : CI : 4.77E-05 2.70E-07 : - - - - - - - - -------- : !
. CR90 : CI : 1.06E-06 : 6.00E-09 : -------- ; --------
. .i m . e ,. .,
4 . o,,, E . ,o ,s ... E.0,,
--,u,... s . o. . . . . .
. .l f, t.
n t,e .f f *;
a Mi a . . . .
I a
l I
b L
P r
- t
- - . . .t I,
i t
?
?
- I i
if e
i t
3
$ a i t Attachment 6 :
s I
t Solid Waste -
l i
-t i t i 6 4 h I
I t
i f
l
, s i ?
I
?
I
?
I I
I t
i r
s I !
i i
, i l
l s
l f
.i k
I h
f L
i
?
Attachment 6 (Page 1 of 4)
Solid waste f
}
l Solid Waste Shipped offsite for Disposal During Period from January 1 to June 30 1991 i WASTE STREAM.
Resins, rilters, & Evap. Bottoms !
Waste !
Cu. Cu. Curies i Error C'. ass Peet Meters l Shipped (Ci)
A 2730.0 77.2 9.01 C+02 + 25%
l i
B 136.0 3.8 1.14 E+03 U/A C 0 0 !
0 N/A ALL 2866.0 81.0 2.04 E+03
+ 256 :
WASTE STREAM:
Dry Active Waste P
Waste !
Cu. Cu. Curies % Error '
Class Feet Meters shipped (C1) !
A 8960.0 253.5 1.41 E+00 + 251 B 0 0 l C 0 0 ~ N/A [
0 0 N/A ;
ALL 8960.0 253.5 1.41 E+00 1 254 l t
NOTE: 5120 cubic feet have been shipped for compaction. An 8 to i reduction facte,r is expected. No dry active waste was shipped for direct burial during the reperting period. i l
WASTE STREAM:
Irradiated Fuel Waste Cu. Cu, Curies % Error i Class, Feet Meters Shipped (Ci)
A 0 0 [
3 0 N/A l 0 0 0 N/A !
C 0 0 0 ALL 0
~N/A '
0 0 N/A :
WASTE STREAM.
. Other Waste .
f Waste Cu. Cu. Curies i Class % Error !
Feet Meters Shipped A 0 tC1) , t 0 0 N/A i
B 0 0 C
0 N/A 0 0 0 N/A i ALL 0 0 0 N/A i 1 !
\
l
~ _ _ _ - _.
l Attachment 6 (Continued - Page 2 of 4)
Solid Waste l
Estimates of Major Radionuclides by Waste Type WASTE TYPE: Resins, Filters, & Evap. Bottoms Waste Nuclide Percent Class Name Abundance Curies ;
i A re-55 52.146 4.70 E+02 Co-60 19.194 1.73 E+02 '
i In-65 18.084 1.63 E+02 Mn-54 5.281 4.76 E+01 Cs-134 0.996 8.98 E+00 Co-58 0.997 8.81 E+00 Cr-51 0.953 8.59 E+00 Cs-137 0.641 5.78 E+00 Ni-63 0.458 4.13 C+00 Fe-59 0.416 3.75 E+00 Ce-144 0.336 3.03 E+00 3
H-3 0.258 2.33 E+00 a C-14 0.114 1.03 E+00 Ag-110m 0.099 8.91 E-01 Ni-59 0.022 2.00 E-01 St-90 0.021 1.86 E-01 Pu-241 0.002 1.63 E-02 Pu-239/40 0.000 9.51 E-04 cm-242 0.000 5.72 E-04 Am-241 0.000 3.93 E-04 Pu-238 0.000 1.39 E-04 cm-241 0.000 1.49 E-05 I-129 0.000 0.00 E+00 i Nb-94 0.000 0.00 E+00 Tc-99 0.000 0.00 E+00 1
I l
1 Attachment 6 (Continued - Page 3 of 4) l l Solid Waste l I l j
Estimates of Major Radionuclides by Waste Type i
, NASTE TYPE: Resins, filters, - Evap. Bottoms i
Waste Nuclide Percent
"'30s Name Abundance Curies B Fe-55 63.623 7.25 E+02 i Co-60 19.043 2.17 E+02 :
On-65 9.214 1.05 E+02 !
Mn-54 3.396 3.87 E+01 l Cs-137 1.711 1.95 E+01 !
Cs-134 1.439 1.64 E+01 '
Ag-110m 0.676 7,70 E+00 1 Ni-63 0.315 3.60 E+00 '
Co-58 0.274 3.12 E+00 Sr-90 0.222 2.53 E+00 Ce-144 0.067 7.69 E-01 Fe-59 0.015 1.66 E-01 H-3 0.002 2.33 E-02 Pu-241 0.001 1.29 E-02 C-14 0.001 5.76 E-03 Tc-99 0.000 1.57 E-03 Pu-239/40 0.000 4.07 E-04 Pu-238 0.000 7.42 E-05 Am-241 0.000 2.57 E-05 Cm-242 0.000 0.00 E+00 I-129 0.000 0.00 E+00 Nb-94 0.000 0.00 E+00 Ni-59 0.000 0.00 E+00 I
ww -wawwe----.m-erwve----%-w-weww ,w-e+riw er a w-t w r9 ew"-eamm--w a-wrw'-v-eew w gr-,ewvtr-W-'--*e-ew9--*=-^-W---rep.
-~__
i r
Attachment 6 (continued page 4 of 4) !
SOLID WASTE j WASTE TYPE: Dry Active Waste 3
T l
Waste Nuclide Percent Class Name Abundance Curies l A Fe-55 84.451 1.19 E+00 Co-60 8.587 1.21 E-01 i Mn-54 6.025 8.49 E-02 Co-58 0.295 4.15 E-03 ,
l Fe-59 0.204 2,08 E-03 En-65 0.139 1.96 E-03 j Cr-51 0.076 1.08 E-03 Sb-124 0.061 8.56 E-04 Ag-110m 0.046 6.45 E-04 .
Ni-63 0.044 6.22 E-04 ;
Nb-95 0.023 3.22 E-04 ;
i Cs-137 0.021 3.01 E-04 l Ce-144 0.014 2.01 E-04 Cs-134 0.010 1.34 E-04 ,
Sr-90 0.001 1.61 E-05 l Pu-241 0.000 4.51 E-06 i C-14 0.000 3.57 E-06 ;
Ni-59 0.000 2.88 E-06 i H-3 0.000 2.45 E-06 t Tc-99 0.000 2.54 E-07 Cm-243/44 0.000 1.85 E-07 l Cm-242 0.000 8.68 E-08 l Pu-238 0.000 2.65 E-08 i Pu-239/40 0.000 2.18 E-08 ,
Am-241 0.000 9.16 E-09 l l i Jolid Waste Disposal summary l l
No. of Mode of [
Shipments Transportation Destination, 5 I
! 8 Truck Burnwell [
l 11 Truck Richland l l 0 N/A Beatty ;
l' 0 N/A Other I
t i
I t
5
P Attachment 7 Meteorological Data ;
I s
1 l
h I
i o
t i
l l
_ _ _ - ~ _ _ _ _ . - __- _ . . . _ . . _ . . _ _ . _ _ _ -
i I
I Attachment 7 (Page 1 of 12) l Joint Frequency _ Distribution Tables - 1991: Quarters 1 & 2 ;
HOURS At EACH WIND SPEED AND DIRECTION PERIOD CF RECORD = 91010101-91063024 l STABIL11Y CLASS ALL DT/DZ
, ELEVATION: LPEED:SPD10P DIRECTIONIDIR10P LAPSE!DT50M
' WIND SPEED (MPH)
WIND
- DIRECT 10N 13 4-7 8-12 13-10 19-24 >24 TOTAL t N 14 94 73 18 0 0 199 NNE 19 72 86 1 0 0 179 NE 36 84 111 46 0 0 278 ENE 68 114 129 37 3 0 351 E 99 89 10 0 2 0 208 ESE 99 67 29 1 0 0 196 SE 62 61 35 39 0 o 197 SSE 50 76 51 21 0 0 198 S 49 101 80 18 2 0 250 SSW 36 154 140 45 2 2 379 SW 28 144 170 45 2 0 390 WSW 21 77 205 143 41 2 489 W 14 101 213 101 11 0 440 WNW 15 90 93 26 3 0 227 NW 16 96 79 16 6 0 213 NNW 16 61 67 2 0 0 147 t
TOTAL 642 1481 1579 559 72 4 4341 PERIODS OF CALM (HOURS): 15 VARIABLE DIRECTION 0 HOURS OF MISSING DATA! 3
^
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101 91063024 STABILITY CLASS: A DT/DZ ELEVATION! SPEED 1SPD10P DIRECTION DIR10P LAPSE:Df50M WIND SPEED (MPH)
WIND DIRECTION 13 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 2 0 0 0 2 NNE O O 3 0 0 0 3 NE 1 0 10 16 0 0 27 ENE 1 0 0 1 1 0 3 E 0 1 0 0 0 0 1 i ESE O 2 0 0 0 0 2 SE O 1 0 1 0 0 2 SSE O O O O O O O l S 0 0 0 0 0 0 0 SSW 0 0 1 0 0 0 1
, SW 1 3 0 3 0 0 7 WSW 0 1 1 2 0 0 4
- W 0 0 5 0 1 0 6 WNW 0 0 2 0 0 0 2 HW 1 4 1 0 0 0 6 NNW 1 1 0 0 0 0 2
-' PERIODS OF CALM (NOURS)1 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 m
4 Attachment 7 (Continued - Page 2 of 12)
Joint frequency Distribution Tables - 1991: Quarters 1 * ,2 HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD 91010101-91063024 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SPD10P DIRECT 10N:DIR10P LAPSE DT50M WIND SPEED (MPH)
WIND DIRECTION 13 47 9-12 13 10 19-24 >24 TOTAL N 0 0 0 1 0 0 1 l
NNE O O 21 0 0 0 21 NE 1 1 17 11 0 0 30 ENE 1 2 1 1 1 0 6 E 1 2 1 0 0 0 4 i ESE O 1 0 0 0 0 1 SE O O O 3 0 0 3 SSE 0 1 0 0 0 S 0 0 0 0 0 '3 0 3 0 0 0 4 SSW 1 SW 0 1 6 0 0 0 7 WSW 0 0 4 6 1 0 11 W 0 3 10 16 4 0 33 WNW 1 1 8 2 0 0 12 NW 0 3 0 0 0 0 3 NNW 0 0 0 0 0 0 0 TOTAL 4 18 72 40 6 0 140
~ ~ ~ ~ ~ ~~~~~ ~~~~~~ ~~~~~~~ ~ ~~~~~~
PEkibD5~bFC5LMiHbbkh55 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101-01063024 STABILITY CLASS: C DT/DZ ELEVATIbit SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-10 19 24 >24 TOTAL 0 4 9 1 0 0 14 N
0 6 24 0 0 0 30 NNE 0 35 3 12 16 7 0 NE 0 12 ENE O 2 5 4 1 1 0 1 0 3 E O a 6 0 0 0 7 i ESE o 1 O 1 1 4 0 0 6 3E O 3 2 1 0 0 6 SSE 0 7
, S 0 2 5 0 0 0 4 1 0 0 0 5 SSW 0 0 15 0 2 9 4 SW 0 29 0 3 12 11 3 WSW 0 63 u 0 3 41 18 1 0 2 12 0 0 0 14 WNW 0 21 0 5 15 1 0 NW 0 1 7 0 0 0 0 NNW TOTAL 0 52 166 51 6 0 275 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSINO DATA: 3 N
b i
I Attachment 7 (Continued - Page 3 of 12) {*
, Joint frequency Distribution Tables - 1991: Quarters 1 & 2 f
HOURS AT EACH WIND SPEED AND DIRECTION
, PERIOD OF RECORD = 91010101-91063024 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SPD10P DIRECTION!DIR10P LAPSE!D150M
..................................................__. 4......
< WIND GPEED(MPH)
WIND 1 DIREETION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 1 ......... ... ... .... ..... ..... ___ .....
N 7 79 62 16 0 0 166 NNE 7 54 36 1 0 0 98 [
NE 9 61 66 12 0 0 148 >
i ENE 4 59 108 31 0 0 202 !
E 7 33 14 0 1 0 55 ESE 4 15 10 1 0 0 38 SE 2 16 22 28 0 0 68 SSE 4 16 37 12 0 0 49 S 3 31 40 13 1 0 88 ;
SSW 4 36 79 34 1 1 155 SW 6 31 97 34 2 0 170 k h 6 h 0 WNW 6 77 70 24 3 0 100 NW 4 75 63 15 6 0 163 :
NNW 8 55 59 2 0 0 124 i TOTAL 92 765 1084 403 55 3 2402 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSINO DATA: 3 I
HOURS AT EACH WIND SPEED AND DIRECTION i PERIOD OF RECORD = 91010101-91063024 STABILITY CLASS: E DT/DZ l ELEVATION: SPEED SPD10P DIRECT 10N DIR10P LAPSE D150M ;
,i ...........____.....................__........................ ;
WIND SPEED (MPH) !
l WIND DIRECT!ON 1-3 4-7 8-12 13-18 19-24 >24 TOTAL !
N 2 10 0 0 0 0 12 NNE 8 11 1 0 0 0 20
. NE 4 9 0 0 0 0 13 ENE 14 41 14 0 0 0 69 E 20 37 1 0 0 0 58 ESE 10 32 5 0 0 0 47 SE 7 24 12 3 0 0 46 SSE 11 31 11 8 0 0 61 !
S 16 51 33 5 1 0 106 !
SSW 19 92 58 11 1 1 182 }
SW 11 101 58 4 0 0 174 I WSW 7 19 29 9 1 0 65 [
W 5 18 3 2 0 0 28 i WNW 2 10 1 0 0 0 13 ?
NW 7 8 0 0 0 0 15 l NNW 5 4 1 0 0 0 10 ;
TOTAL 148 498 227 42 3 1 919 i
.............__..______...................__ ................. j PERIODS OF CALM (HOURS): 0 l VARIABLE DIRECTION 0 t
, HOURS OF MISSlHG DATA: 3 :
I I .
f l
a t_.._._.... _ - . . .__,_.. _ .._ , _ ... _. _ _ _ _ ._ _ . ._._.,_ .. _ ____, -,- - . - , _ . .
i I
I I
i 4 r Attachment 7 ( Continu" ' - Page 4 of 12) j i Joint Prequency Distribution Tala as -_1991: Quarters 1 & 2 l d
i 1
l HOURS AT EACH WIND SPEED AND DIRECTION FERIOD OF RECORD = 91010101-91063024 STABILITY CLASS: F DT/DZ l ELEVATION: SPEED SPD10P DIRECT 10N DIR10P LAPSE:DT50M l WIND SFEED(MPH)
WIND
+
DIRE 2T10N 1-3 4-/ 8-12 13-18 19-24
>24 TOTAL N 0 1 0 0 0 0 1 NNE 2 1 1 0 0 0 4 NE 7 1 1 0 0 0 9 i ENE 19 1 0 0 0 2g i E 19 1p ., 0 0 0 0 36
' l ESE 15 15 0 0 0 0 30 .
SE 7 10 0 0 0 0 17 l SSE 10 22 0 0 0 0 32 i d
S ? 10 0 0 0 0 19 SSW 5 17 0 0 0 0 22 SW 9 6 0 0 0 0 14 4 WSW 3 1 0 0 0 0 4 W 2 2 0 0 0 0 4
" *4 3 0 0 0 0 0 3 ,
2 0 0 0 0 0 2 i Nkw 1 0 0 0 0 4 2 j PERIODS OF CALM (HOURS): 1 VARIABLE DIRECTION 0 t' HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101-91063024 ;
STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPD10P DIRECT 10N:DIR10P LAPSE DT50M !
WIND SPEED (NPH) l WIND i DIRECTION 1-3 4-7 B-12 13-18 19-24 >24 TOTAL }
N 3 0 0 0 0 0 3 (
l i NNE 2 0 0 0 0 0 3 I
NE 14 0 1 0 0 0 16 ENE 29 4 0 0 0 0 33 l l
E 52 2 1 0 0 0 55 .
i 70 0 0 0 0 71 ESE 1 SE 46 9 0 0 0 0 55 f:
SSE 25 3 0 0 0 0 28 >
S 21 7 0 0 0 0 28 0 0 10 l SSW 3 2 0 0 3 l SW 2~ 0 0 0 0 0 0 0 0 0 0 1 l WSW 1 3 ;
W 2 1 0 0 0 0 i 0 0 0 0 3 j WNW 3 0 i
0 0 0 3 i NW 2 1 0 i l 0 0 1
' NNW 1 0 0 0 I
..... ............. .....___..................... ......_____. f
- 28) 30 2 0 0 0 316 TOTAL j 14 i PERIODS OF CALM (HOURS): '
VARIABLE DIRECTION 0 3 f HOURS OF MISSING DATA: f
- 41 -
_ _._._ _ ___ _ - ~ _ _ _ _ _ _- - _.. ._._
4 1
Attachment 7 (Continued - Page 5 of 12)
Joint Frequency Distribution Tables - 1991: Quarter 1 i
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101-91033124 3TAFILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10P DIRECTIONDIR10P LAPSE!DT50H l WIND SPEED (MPH)
DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N 3 33 51 18 0 0 105 NNE 5 35 19 1 0 0 60 NE 6 33 41 16 0 0 96 ENE 7 42 51 15 0 0 117 E 17 49 10 0 0 0 76 ESE 23 29 18 0 0 0 70 SE 11 24 22 12 0 0 69 SSE 22 44 40 16 0 0 122 S 17 48 68 16 2 0 151 SSW 16 44 105 41 2 2 210 SW 16 45 112 32 0 0 205 WSW 13 39 131 94 29 1 307 W 6 56 105 58 8 0 233 WNW 4 51 58 25 3 0 141 NW 5 41 54 14 6 0 120 NNW 8 30 40 0 0 0 78 TOTAL 181 443 925 358 50 3 2160 PERIODS OF CALM (HOURS): 2 VARIABLE DIRECTION O l HOUR 3 0F,Ml_SS_ING DATA: 0 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 01010101-91033124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10P DIRECTION DIRIOP LAPSE:DT50M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 9 0 0 0 0 0 0 0 NNE O 0 0 0 0 0 0 NE O O 2 4 0 0 6 ENE O O O O O O O E O 1 0 0 0 0 1 ESE O 1 0 0 0 0 1 SE O O 0 1 0 0 1 SSE O O O O O O O
- S 0 0 0 0 0 0 0 SSW 0 0 1 0 0 0 1 SW 0 3 0 -3 0 0 6 WSW 0 1 0 2 0 0 3 W 0 0 4 0 1 0 5 WNW 0 0 2 0 0 0 2 NW 1 2 0 0 0 0 3 NNW 0 0 0 0 0 0 0
, TOTAL 1 8 9 10 1 0 29 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF,M1SSING. DATA: 0 J
e 1
i !
Attachment 7 (Continued - Page 6 of 12) j l
Joint Frequency Distribution Tablen - 1991: Quarter 1 j i
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101-?1033124 STABILITY CLASS: P DT/DZ ELEVATION: SPEED:SPD10P DIRECTION!DIRIOP LAPSE:DT50M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 >24 TOTAL q ......... ... ... 0-12
.... ___13_ ....._18 19-24 ... .....
4
' H 0 0 0 1 0 0 1 NNE 0 0 3 0 0 0 3 HE O O 3 2 0 0 5
(
i ENE O 1 0 0 0 0 1 E O O O O O O O .
ESE 0 0 0 0 0 0 0 i SE 0 0 0 3 0 0 3 !
SSE O 1 1 0 0 0 2 i 5 0 0 2 '
0 0 0 2 SSW 0 3 1 0 0 0 4 SW 0 0 6 0 0 0 6 WSW 0 0 4 5 1 0 10
. W 0 2 5 1 3 0 11 WNW 0 1 7 2 0 0 10 NW 0 2 0 0 0 0 2 NNW 0 0 0 0 0 0 0 PERIODS OF CALH(HOURS): 0 ;
VARIABLE DIRECTION O '
HOUR S OF MI S_S I...N.G.
D AT A : 0 - _ .
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101-91033124 STABILITY CLASS! C DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAP 9E:DT50M WIND SPEED (MPH)
WIND DIRECTION 1-3 >24 TOTAL
____..... .._ 4_7 8__12
_. _ _ ..... ____. 13-18 19-24 ___ ...__
N 0 0 4 1 0 0 5 NNE O 1 3 0 0 0 4 t NE O 2 3 3 0 0 8 t ENE O 0 3 0 0 0 3 E O O O O O O O ESE O 1 5 0 0 0 6 ,
(
O 2 2 1 0 0 5 S 0 1 5 0 0 0 6 SSW 0 3 1 0 0 0 4 SW 0 1 9 2 0 0 12 WSW 0 2 9 6 3 0 20 W 0 2 10 4 0 o0 16 WNW 0 1 7 0 0 0 8 HW 0 0 0 0 0 0 8 {
NNW 0 0 6 0 0 0 6 TOTAL 0 16 76 19 3 0 114 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION F HOURS OF MISSING DATA: 0 f e
- r E_...._,._...._-.~._..._..-_.._..._._..,_,._._.-.__,.._.._.._..._.___...__..__....-._.__.___--.__._...-._,.__... ,
l l
e Attachment 7 (Continued - Page 7 of 12)
Joint Frequency Distribution Tables - 1991: Quarter 1
! I
' f HOURS AT EACH WIND SPEED AND DIRECTION j PERIOD OF RECORD = 91919101 91033124 l STABILITY CLAES: D Df/DZ ELEVATION: SPEED:SPD10P DIRECTION!DIR10P LAPSE DT50M WIND SPEED (MPH)
DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 31 47 16 0 0 96 NNE 3 32 13 1 0 0 49 NE 2 29 33 7 0 0 71 l ENE 2 24 45 15 0 0 96
' r E 4 19 B 0 0 0 31 !
, ESE 1 10 11 0 0 0 22 SE O 9 14 4 0 0 27 SSE 0 11 29 7 0 0 47 5 1 24 34 11 1 0 71 SSW 2 15 59 31 1 1 109 l SW 6 12 59 24 0 0 101 i WSW 7 31 110 75 24 1 248 !
W 2 44 84 52 4 0 166 i WNW 3 45 42 23 3 0 116 NJ 33 46 l 1 1 14 6 0 100 ;
NNW 7 28 33 0 0 0 ~ 68
, TOTAL 43 397 667 280 39 2 1428 PERIODS 0" CALM (HOURS)! 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 0
?
HOURS AT EACH WlHD SPEED AND DIRECTION PERIOD OF RECORD = 91010101-91033124 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SPD10P DIRECTION: DIRIOP LAPSE:DT50M ,
WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 2 0 0 0 0 3 NNE 1 2 0 0 0 0 3 NE 2 2 0 0 0 0 4 ENE 4 13 2 0 0 0 19 E 5 22 1 0 0 0 28 ;
ESE 6 13 2 0 0 0 21 !
SE 3 7 7 2 0 0 19 i i SSE 9 18 8 8 0 0 43 '
i S 12 20 27 5 1 0 65
- S~W 8 21 43 10 1 1 84 ;
i S. 6 29 38 3 0 0 76 ;
WSW 4 5 8 6 1 0 24 i W 3 7 2 1 0 0 13 !
- WNW 1 4 0 0 0 0 5 i NW 3 3 0 0 0 0 6 :
NNW 1 2 1 0 0 0 4 ;
TOTAL 69 170 139 35 1 417 PERIODS OF CALM (HOURS): 0
, VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 1 4
i t
r
I J
Attachment 7 (Continued . Page 8 of 12) j Joint Frequency,j t stribution Tables - 1991: Quarter 1 j I
1 l
1 HOURS AT EACH WIND SPEED AND DIRECTION !
PERIOD OF RECORD = 91010101-91033124 i STAlt!LITY CLASU: F DT/D2 i,
ELEVATION: SPEED:SPD10P DIRECTION!DIR10P LAPSE DT50M !
WIND SPEED (MPH)
WIND l DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL t
, I N 0 0 0 0 0 0 0 NNE O O O O O O O l NE 2 0 0 0 0 0 2 !
ENE 2 1 1 0 0 0 4 .
E 6 7 0 0 0 0 13 !
ESE 3 4 0 0 0 0 7 SE 3 7 0 0 0 0 10 '
SSE 6 10 0 0 0 0 16 S 2 1 0 0 0 0 3 SSW 1 1 0 0 0 0 2 4 0 0 0 0 0 4 SW WSW 2 0 0 0 0 0 2 ,
W 1 1 0 0 0 0 2 l WNW 0 0 0 0 0 0 0 !
NW 0 0 0 0 0 0 0 !
NNW 0 0 0 0 0 0 0 (
.___.__....___...___................... ___.............-_____ i TOTAL 32 32 1 0 0 0 45 PERIODS OF CALM (HOURS): 0 4
VARIABLE DIRECTION 0 i 0
HOURS OF M.IS.S.ING DATA:
HOURS AT EACH WIND SPEED AND DIRECTION k i
PERIOD OF RECORD = 71010101-91033124 STABILITY CLASSI G DT/DZ ELEVATION: SPEED:SPD10P DIRECTION DIRIOP LAPSE:DT50M i WIND SPEED (MPH) '
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL i __....... __. ___ .... ..... .....
N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 O 0 0 0 0 0 0 i NE 3 0 0 0 0 4 l ENE 1 E 2 0 1 0 0 0 3 l 0 0 0 0 13 (
- ESE 13 0 SE 5 1 0 0 0 0 6 i SSE 7 2 0 0 0 0 9 >
S 2 2 0 0 0 0 4 i SSW 5 1 0 0 0 0 6 l SW 0 0 0 0 0 0 0 i WSW 0 0 0 0 0 0 0 !
W 0 0 0 0 0 0 0- l t
WNW 0 0 0 0 0 0 0 NW 0 1 0 0 0 0 1 [
0 0 0 0 ;
NNW 0 0 0 TOTAL 36 10 1 0 0 0 47 ?
......___.._____..._. __ .____ ._.... _ _ .......__ ._....____ 3 PERIODS OF CALM (HOURS): 2 VARIABLE DIRECTION 0 0 ;
_ H O_ U_ R. . S O. F._11.SS.I NO. . D A T A : ,
i t
i
~ 45 - [
t
Attachment 7 (Continued - Page 9 of 12)
Joint Frequency Distribution Tables - 1991: Qua-ter 2 HOURS A1 EACH WIND SPEED AND DIRECTION FERIOD CF RECORD = 91040101-91063024 STABILI!Y CLASS: ELL DT/D2 ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAISE:DT50M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7
..._ .... _-_ --- B-12 13__18 19-24._.._ >24 TOTAL N 11 61 22 0 0 0 94 NNE 14 37 67 0 0 0 119 NE 30 51 70 30 0 0 182 ENE 59 72 78 22 3 0 234 E 82 40 8 0 2 0 132 ESE 76 38 11 1 0 0 126 SE 51 37 13 ?7 0 0 128 SSE 28 32 li 5 0 0 76 5 32 53 12 2 0 0 99 SSW 20 110 35 4 0 0 169 SW 12 99 58 13 2 0 185 WSW 8 38 74 49 12 1 18' W 8 45 108 43 3 0 207 WNW 11 39 35 1 0 0 86 NW .1 55 25 2 0 0 93 NNW 8 31 27 2 0 0 69 TOTAL 461 838 654 201 22 1 2181 PERIODS OF CALM (HOURS): 13 VARIABLE DIRECTION O HOURS OF MISSING DATA: 3 HOUkS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91040101-91063024 3TABILITY CLASS: A DT/DZ ELEV A110N: SPEED SPD10P DIRECTION;DIR10P LAPSE:DT50M WIND 2 PEED (MPH)
WIND DIR;CTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 2 0 0 0 2 NNE O 0 3 0 0 0 3 NE 1 0 8 12 0 0 21 ENE 1 0 0 1 1 0 3 E 0 0 0 0 0 0 0 ESE O 1 0 0 0 0 1 SE O 1 0 0 0 0 1 SSE 0 0 0 0 0 0 0 5 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 3W i 0 0 0 0 0 1 WSW 0 0 1 0 0 0 1 W 0 0 1 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 2 1 0 0 0 3 NNW 1 1 0 0 0 0 2
___. ----- ---_-_...----__..._ ._-_- -....__~.----..--._-----
PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O
.HOU.RS O.F MISSI.NG DATA:
3 1
~
1 s
Attachment 7 (Continued - Page 10 of 12)
Joint Frequency Distribution Tables - 1991: Quarter 2 HOURS AT EACH WIND SPEED AND DIRECTION 3ERIOD OF RECORD = ?iO40101-91063024 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P w
_....._____________..-__ ..____________........_ LAPSE:DT50M _______.......
WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 r
. . . . . . . _ . ___ ... 8-12
.... __13__18
. .. __ 19_24
>24 TOTAL '
N 3 3 0 0 0 0 0 NNE o 0 18 0 0 0 NE 18 1 1 14 9 0 0 25 ENE 1 1 1 1 1 0 5 E 1 2 1 0 0 0 4 ESE 0 0 0 1 0 0 1 SE O O O O O O O 3SE O o 0 0 0 0 S
0 0 0 0 0 0 0 0 SSW 0 0 0 0 3 0 0 SW 0 1 0 0 0 0 1 WSW 0 0 0 0 W
1 0 1 0 1 5 15 0 WNW 1 22 <
1 0 1 0 0 0 2 NW 0 1 0 0 0 0 1 NNW 0 0 0 0 0 0
______ ______.__________.. _____________________..0 . ......--.
TOTAL 4 8 40 26 2 80
.______________________________ ........-_-____ ___0___ .______
PERIODS OF CALM (HOURS) 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91040101-01063024 STABIL:TY C' LASS: C DT/DZ ELEVATION: SPEED SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)
WIND DIRECTIDH 1-3 4-7 B-12 13-18 19-24 '224 TOTAL N O 4 5 0 0 0 9 NNE 3 5 21 0 0 0 26 NE O 10 13 4 0 0 27 ENE o 2 2 4 1 0 9 E O 1 1 0 1 0 3 ESE O 0 1 3 0 0 i sE 0 1 0 2 0 0 3 SSE 0 1 0 0 0 0 1 5 0 1 0 0 0 0 1 SSW 0 1 0 0 0 0 1 SW 0 1 0 2 0 0 3 WSW 0 1 3 5 0 0 9
_ W 0 1 31 14 1 0 47 WNW 0 1 5 0 0 0 6 NW 0 5 7 1 0 0 13 NNW 0 1 1 0 0 0 2 TOTAL 0 3e 90 32 3 0 161 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3
_ 47 .
Attachment ' (Continued - Page 11 of 12)
Joint Prequency Distribution Tables - 1991: Quarter 2 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD JF RECORD : 91040101-91063024 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SPD10P DIRECTION: DIR10P LAPSE:DT50M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 B-12 13-18 19-24 >24 TOTAL N 7 48 15 0 0 0 70 NNE 4 22 23 0 0 0 49 NE 7 32 33 5 0 0 77 ENE 2 35 63 16 0 0 116 E 3 14 6 3 1 0 24 ESE 3 5 7 1 0 0 16 SE 2 7 3 24 0 0 41 SSE 4 5 9 5 0 0 22 5 2 7 6 2 0 0 17 SSW 2 21 20 3 0 0 46 SW 0 19 38 10 2 0 69 WSW 3 22 49 40 12 1 127 W 3 30 70 13 1 0 117 WNW 3 32 28 1 0 0 64 NW 3 42 17 1 0 0 63 NNW 1 27 26 2 0 0 56 TOTAL 49 368 417 123 16 1 974 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 91040101-91063024 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIRIOP LAPSE DT50M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 B-12 13-18 19-24 >24 TOTAL N 1 S 0 0 0 0 9 NNE 7 9 1 0 0 0 17 NE 2 7 0 0 0 0 9 ENE 10 28 12 0 0 0 50 E 15 15 0 0 0 0 30 ESE 4 19 3 0 0 0 26 SE 4 17 5 1 0 0 27 SSE : 13 3 0 0 0 18 3 4 31 $ 0 0 0 41 SSW 11 71 15 1 0 0 78 SW 5 72 20 1 0 0 98 WSW 3 '4
. 21 3 0 0 41 W 2 11 1 1 0 0 15 WNW 1 6 1 0 0 0 3 NW 4 5 0 0 0 0 9 NNW 4 2 0 0 0 0 6 TOTAL 79 328 38 7 0 0 502 PERIODS OF CALM (HOURS): 0 VAFIABLE DIRECTION 0 HOURS 3F MISSING DATA: 3
I 1
I i
i Attachment 7 (Continued - Page 12 of 12) l Joint Frequency Distribution Tables - 1991: Quarter 2 !
t f
I HOURS AT EACH WIND SPEED AND DIRECTION )
PERIOD OF RECORD = 91040101-91063024 :
ST ABI L I T'. CL ASS: F DT/DZ e ELEVATION: SPEED:SPD10P DIRECTION: DIP.10P LAPSE:DT50M !
WIND SPEED (MPH) l DIRECTION 1-3 4-7 >24 TOTAL
_._ ...._ ... __. 8_12 13__18 19_24 N 0 1 0 0 0 0 1 .-
NNE 2 1 1 0 0 0 4 NE 5 1 1 0 0 0 7 ENE 17 5 0 0 0 0 22 .
E 13 6 0 0 0 0 19 i ESE 12 11 0 0 0 0 23 ;
SE 4 3 0 0 0 0 7 i SSE 4 12 0 0 0 0 16 i S 7 9 0 0 0 0 16 SSW 4 16 0 0 0 0 20 SW 4 6 0 0 0 0 10 WSW 1 1 0 0 0 0 2 W 1 1 0 0 0 0 2 WNW 3 0 0 0 0 0 3 NW 2 0 0 0 0 0 2 i NNW 1 0 0 0 0 0 2 j
....________.___________________________..____________________ j
_I91__.___.._______.b..______________b.____2_____0___$_______ f PERIODS OF CALM (HOURS): 1 i VARIABLE DIRECTION O ;
HOURS OF MISSING DATA: 3 l
r HOURS AT EACH WIND SPEED AND DIRECTION l 91040101-91063024 PERIOD OF RECORD = i STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIRivP LAPSE:DT50n t WIND SPEED (MPH) l WIND DIRECTION 4-7 >24 TOTAL l
.________ 1_3
._ 8-12 13 _18 19-24 N 3 0 0 0 0 0 3 e 0 0 0 0 0 2 i NNE 1 NE 14 0 1 0 0 0 16 !
ENE 28 1 0 0 0 0 29 E 50 2 0 0 0 0 52 l f
ESE 57 1 0 0 0 0 59 SE 41 8 0 0 0 0 49 l 0 0 0 19 i SSE 18 1 0 0 24 I
.S 19 5 0 0 0 0 4 !
SSW 3 1 0 0 0 SW 2 0 0 0 0 0 3 [
WSW 1 0 0 .0 0 0 1 !
! W 2 1 0 0 0 0 3 :
i WNW 3 0 0 0 0 0 3 2 0 0 0 0 0 2 i
! NW 0 0 0 0 0 1 I NNW 1 TOTAL 245 20 1 0 0 0 249 l
+
PERIODS OF CALM (HOURS): 12 VARIABLE DIRECTION 0 l HOURS OF MISSING DATA: 3 i
i
~
?
_, .. _ _ . - - - . . - , _ . , . _ . . _ _ _ . . - __ ,~. . _ . - _ . - . . - . . , __ -
_ . . . ~ . . . _ _ . . . . _ _ .
i l
l
}.
i 1
a i
Attachment 3 Abnormal Gaseous Release Y
I I
" y46' .sa"'
.'~~ 'p..y.y'j,b F
~ .;,c"3b "g'q: g * #f "'* W14.c f Cts +"- - v.;,
7: - -
y -
% .,a.39<..; *l!;; C ,, ,@, 's,9.:, .
m.Vq u
g, - .1 .- -
~; OM12A (CEI-54' Fage 37 45 - LAST
, 4g
&. ".3 O. :/IEev.;,t,y,',L[ ; ,_ >; 6 g n, , - c- -
-4%
Attach; ment 13,
. Form:20M12At CEI-54-11 'D
%' Mj; .f; -'(
I*
Abnormal caseous Ef fluent Release Oats Shee't "' '
v 3. o $ ,): / o i ~.
@I O 3 09 J t oa <1/ 0 306., 2e ie 5 tart /T.nd Dates Meteorological Data / ares (s) of conc rn (Attpch Joint Trequency Distribution Tables): S t. uktA Source of Material (include vent): lm J m d R f6h A 76 e.w J ,
H v &t. U h .M } (lc.,in.h h d p u blw Aw w Ir 1 ' ed eIIb -
i j Remarks U dl *hl E d.,A E. NAC % ,l.e 1 ilid.N,bbk.bl/N,< _
,d,t J- 'sted u.I.,4 i N d
5 ht 4 >- ,_..
- \ ' -
,? -
4-Q
. l.$0C* 3 e n s. , $% Le L 2 :Je V ** y & p.ktj c. , ~$.E 4 : E'py*- ^ggw.swm. - EX~ ~;c
-'~555b:
Y'
- gj'y."d. g gy %'r > ]#
A i B C ' D F. =-B k C I D - - -F .
Flow Rate' Conversion Ralesse Rate Activity Concentration (cfa) Factor (uct/sec) (C1)
- Isotope (uCi/ce) fo, R k L-*H 4. W - 19 19f mn 472 y'36-4 dis 472 .
1 472 4 472 w.
)
1 472 i
472
\ t 472
~~~
( ,
i 472 i
' ,,...3 10CTR20 Compliance (T.S.3.11.2.1) .
- .;.,c W: -
(arts /yr) Dose' Rate' 2 b LkMIT .?% r41 3 _ ~~
Noble cas Total Body (>. 4l 2500 . .
- % -3000,= 2v- r.
Noble cas Sk.in - - - .m Organ I a.WE6 , 1500 .-- , . . . . , .
I 10CFR50 App. T Compliance (T.S.3.11.2.2 I, 3)_.
Otr Ann Q) 1.IMIT Release Otr 1.IMIT Annual (arad or ares) 10.0 HG Air y 9 % 76-3i 5.0 I terc 3 NG Air 5 # / ,o r (. - 2. 10.0 /. , y c - z 10.0 Organ /. God - 3 4.4'7 e - 3 7.5 . Y. y 7 c- 3 15.0 Total Body
- O S 77r- 3 2.5 !
5 7 tt- 3 3.0
- Not a T3 limit; 5ared/yr is 10LFR50, Appesuitx I dose limit 2 4.> > W (3) M ikesI.' A a,. l%R bbw Date 3 ubi Performed By _
R.,- er CRJAlK Dat. swk
_... D=A #- gg ' e/ m L{ Y g %
i SITE: PERRY 03/11/91 14:40 USER: JR
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS:
GASEQUS 913421-91353 AIR 91 3 421-91 3 5 3 APPLICABLE ESTIMATED AGE LOCATION : 0F LIMIT EFFLUENT ORGAN DOSE GROUP DIST D1R APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)
NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 !.0E+01 (GAMMA-MRAD)
HOBLE GAS AIR DOSE 0.00E+00 273. H 0.0E+00 2.0E+01 (BETA-MRAD)
NOBLE GAS T. BODY 0.00E+00 ALL 5. N 0.0E+00 5.0E+00 NOBLE GAS SKIH 0.00E+00 ALL 3. N 0.0E+00 1.;E+01 10 DINE 1 THYROID 1.60E-03 CHILD 233. WNW 1.1E-02 1. E&01 PARTICULATE 3 m_
-_-_----m______m__ _ _ _ _____ m m. _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ , _ _ _ _ _ _ , _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
._.___.m._____., _ . __ _ .._-_ _ -- - . _ _ _ . _ _ _ _ _ _ _ _ . _ - _ _ _ . ._.. _ __.._._ _ ._
SITE: PERRY 03/11/91 15:00 -
(<L ~ USER: JR ~
SUMMARf 0F MAXIh0M INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS:
5ASE005 ..
91 1 1 1-91 31024 AIR
. ....................-.... ..91 1....1.1-91
. . . 31024 APPLICABLE ESTIHATED ADE LOCATION : OF EFFLUENT '~ ORGAN DOSE LIMIT
~ ( MREM) '"~ GROUP DIST DIR APPLICABLE (M) (TOWARD) LIMIT (MREM)
NOBLE GAS AIR DOSE 9.00E-03 294
- (GAMMA-dRAD)
N 9.0E-02 1.0Ef01 NOBLE GAS AIR DOSE 1.08E-02 294
( B E T A-ftR A D )
N 5.4E-02 2.0E+01 NOBLE GAS T.30DY 5.72E-03 ALL 294 N 1 1E-01 5.0E+00 NOBLE GA3 SKIN 1.47E-02 A 294.
. . . . . . . . . . . . . . . . LL.........
N 7.8E-02 1.5Et01 10 DINE 1 THYROIO 4.47E-03 CHILD 290. NNW 3.0E-02 1.!E+01 PARTICULATES l
l l
l l
! \,
v
- J3 C. .f3
- s3nC . 'r? ; E COE: *3D6: 1NC; [Ndn13s: 031W3
- VivG DNIEEIL JD S300F C N 01133'd ! . 314 Y I 8v n 0 .(Ebn0H)W1Y 30 500ld3e 0 ( 0 0 C 0 0 11101 j O C C 0 0 0 0 NNN 0 0 0 0 0 0 0 MN O O C C C C C MHP O O 0 0 0 0 0 P 0 0 0 0 0 0 0 MSE O 0 C C 0 0 0 m5 C C C L 0 C MSS C 0 C C 0 C C E C C C 0 0 0 0 35E 0 0 0 0 0 C C 35 0 C 0 0 0 0 C 353 C ( C 0 0 0 C 3 C C C 0 C C C 3H3 0 C C 0 0 0 0 3h C C 0 0 0 0 0 3NN 0 C C 0 0 0 0 h 1Y1Ci t:-' e:-61 81-t1 21-E i-r E-1 N01133dIC' GNIn (Hdw)G33d5 GNIN WO;1C:3SdV1 d0i31C: H01133310 dO1GdE;G33d5 !N011VA373 20/1C e :55Yl3 A11718vA5 E0;0E016-Itt0E0ie r 03C33b JC 00Id3e HOI 1333IC GNY G33d5 GNim H3Y3 IV S8n0H 0;;ri ic / t ; 'E0 1 11ND :11NG Add 3d :3115
F l
.IY3 C; 73: ' d 3 fi C 2VV15 00E: ' 3Ill;1.NC O ( WdI. 3 s : :331N3
, :rjec DNISSIL JE S'en0W C N01133 DIG 3MVIVVn
- ( S:300H)W1VD 30 50
(
C 0103d ------
C C 0 0 0
...------..-...--------------------------.--...------101---. 1V C
O C 0 0 0 0 0 NNN O C C C C 0 0 MN C 0 0 0 0 0 C NNM 0 0 0 0 0 0 0 F 0 0 0 0 0 0 0 0
MSK 0 0 0 0 0 C MS 0 0 C 0 0 0 0 0
MSS C 0 0 0 C C S C C 0 0 0 0 0 0
355 C C C 0 0 0 35 0 C C 0 0 0 0 C 0 353 0 0 0 C 0 3 C C C 0 0 0 0 3N3 0 C C C 0 0 C 3N
( 0 0 0 C 0 0 3NN C C C 0 0 0 0 N 11101 t:- v -61 81-!! Cl-E 1-r E-1 NOI13381C ONIM (HdW)C33d5 QNIn WO;10:3SdV1 DOI 810: N01133810 dO10dS:G33d5 20/1C
- N011VA373 {
E :SSV70 A1IlI8V15 EOSOE0le-iCr0E016 =
080338 30 00I83d 1.01103010 QNV C33d5 GHIP HJV3 IV Sbn0W OS:t! lo/il/:0 1 11Nn : 11Nn A883d l3115
. .. - , _ , . - - . _ , . . , _ , , . _ _ . . - . . . - . , - . _ - - . , . .-___-_---_..m._ . . - . . , _ - _ _ - . - - _ _ . _ - - - - . - . . _ .
i SI13l d3dbA nN11: .rN11 1 0t/11/61 ir:~0 I H0085 Y1 3V3H ring 5d330 YNli 01333i!0N i d3W!00 03 83308G = e10E0921-610EOSOE 51V811I1A 31VSSl D C1/GZ 373oV110N: 5d330:SdGIOd 01333110N: OIBIOd 1vdS3:01 SOW !
MING sd33u)WdH( '
MINQ 01833110N 1-E r-4 E-IC it-18 16-;t '. ;.. t.....
101V7 t
e N 0 0 0 0 0 0 C '
NN3 0 0 0 0 0 0 0 N3 0 0 0 0 0 0 0 j
- N3 0 0 0 0 0 0 0 '.
0 0 0 0 0 0 0 353 0 0 0 0 0 0 0 53 0 0 0 0 0 0 0 2 SS3 0 0 0 0 0 0 0 -
5 0 0 0 0 0 0 0 SSP 0 0 0 0 0 0 0 SM 0 0- 0 0 0 0 0 i 4
MSM 0 0 0 0 0 0 0 m 0 0 0 0 0 0 0 !
MHM 0 0 0 0 0 0 0 i NM 0 0 0 0 0 0 0 i NNn 0 0 0 0 0 0 0 i j
101el 0 0 0 0 0 0 0 d32I00S 03 DV1W)H0035(l 0 6v8Iv813 013331!0N 0 h003S OJ LISSINO GV2v: 0 3N133: 3831n3NC 3ON1:ND3' 2 SOC 51Y31 0633' 33X; 10 3XII l
l i
1
__ _ _ _ _ , _ _ _ _ _ _ _ _ _ , _ _ _ _ . _ _ _ _ . _ . , _ , _ , _ , , , , _ ~ _ -
4 4
i I
1 5113: d33 A GNI1; ngyl ; ct/II/61 H:;0 fi i
- H003S VI 3W3H n!NG 5d33G VHG CIM331 ION i
- 8100 03 8330d0 =
610E0tti e,10E0002 5'1V6IlI1A 01WSS: G CI/02 c .:
h h V[f"Ni~~~~"h)~33Cik~dCi~0d ~~ "~' i'8k~3[ ION: OI3iod 1VdS3:C1;OW j
'__........... _-...------- i nINO Sd33C)WdH( t nING '
~~~j3[{U t-E r-4 6-t: it-IS 16-2$ <t 10111
___ ... ..._ ..... ----- ~~- -----
3 j $
0 0 0 0 0 0 0 0 0 i o e 0 0 :
3" 0 0 0 0 0 0 C i
0 0 C 353 53 [
0 6
0 0
0 0 0 0
0 0 0 0
j g' 3 p g 0 0 l 0 0 0 i 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 h 0 0 0 0 0 0 0 M 0 0 0 !
0 0 0 0 0 0 0 0 0 !
M 0 0 0
! NM h h h 9 e 101V1
____....___..---------____3_____I__.__I...I_-___b------(-----
0 d30I005 03 DV1W)H0GSS(: 0 ny319813 GIM33110N O H0n35 03 LISSIND G?iti v 3g133: 333;nyut ON11Nn3< 350C SIV31 0633' 33X[ 10 3X!1 l
l l
l 1
5113 d3381 GN11: ONIl 1 0E/it/61 it:SO H003S VI 3V3H PINQ 5d330 VNO 01333110N d3MI00 03 33303C = 610 tot 01-et0EOSOI !
51V81111A 31VSS: 3 01/GZ ;
373oW110N: 5d330:Sd01Od 01333110N:OIBtod 7Vd53: 01;:OW 1
--............--................................................ i MING 5d330)WdH( l MING !
GIB33110N I-E t-l E-lC it-IS 16-tt <Ct 101v7 i i
N 0 0 0 0 0 0 0 !
NN3 0 0 0 0 0 0 0 l N3 0 0 0 0 0 0 0 j 3N3 0 0 0 0 0 0 0 1 3 0 0 0 0 0 0 0 i 353 0 0 0 0 0 0 0 i 53 0 0 0 0 0 0 0 !
533 0 0 0 0 0 0 0 1 5 0 0 0 0 0 0 0 j SSM 0 0 0 0 0 0 0 i SM 0 0 0 0 0 0 0 n$M 0 0 0 0 0 0 0 !
M O 1 0 0 0 0 i j mNM O O O O O O O ;
NM 0 0 0 0 0 0 0 j NNM 1 0 0 0 0 0 1 10111 1 1 0 0 0 O ; i 430I305 03 3v1W)H0035(: 0 irv3I*A13 CI533110N 0 h0035 03 WISSINO OY1Y 0 3N138: 2331n3NE DCN11Nn3' )50; 51y31 air 388 :3XE 10 3XII !
i i
1 4
i 4
i i
I t
I i
4 4
1 4
l
}
4 i
l i
1 4
4 i
f 4
l l
5113l d388A DN11l DN11 T l
4 02/II/61 lrtSI H0085 VI 3yaH MINO 5d330 YNQ c13331 ION d33100 03 833080 = 610tottI-610E000E SIV61111A 31VSS: 3 C1/GZ
' 373oW1IDNl 5d33GlSdG1Od 018331I0H: 013!Od 7vd j ___________...______________________________________S3:01:0W _.___________
MINQ 5d33C)WdH(
l MINO CIM33110N 1-E t-L <;t 101Y7
_________ ___ ___ E___tC 12
_ .__ _18 16-te N O O O O O O O NN3 0 0 0 0 0 0 0
! N3 0 0 0 0 0 0 0 l 3N3 0 0 0 0 0 0 0 I 3 0 0 0 0 0 0 0
! 353 0 0 0 c 0 0 0 53 0 0 0 0 0 0 0 SS3 0 0 0 0 0 0 0 5 0 0 0 0 0 0 0 SSM 0 0 0 0 0 0 0 SM 0 0 0 0 0 0 0 i
i MSM 0 0 0 0 0 0 0 M I 0 0 0 0 0 1 MNM 0 0 0 0 0- O O NR 0 0 0 0 0 0 0 NNM 0 0 0 0 0 0 0 101vl I 0 0 0 0 0 d3810GS 03 ;V7W)H0035(: 0 l 698Iv873 013331 ION 0 l H003S 03 LISSINO CvlY (
l l
'N 33: 333103NC 3ON1:Nn34 :70E E1131 CA358 23XE 10 3X11 l
I I
~- --- ---------------~---'---------------------__...m m_._._. .
-r ~r-- n e ,vawewww".wwr-r~~- ~~--ne-~. .
, .ees ~,,,,n,- ,-ew--m n n.e e~ .,,,- -+,w ,,e n e .-,..,r,,r,n,---,e,>,.v. - , ,--r- -
1 4
1 1
5113: d388A DN11 ON]1 1 0C/11/61 it:SI j t
H008$ VI 3V3H MINQ 5d33C VNQ 013331 ION -
d38I00 03 83308G = 610E0r;I-610E0 0E SIV011I11 07VSSl D C1/GZ '
4 373AV110H: 5d33G:Sd01Od CI830 LION:C18IOd 7VdS3:CISOW MINO 5d33C)WdH( 3 MINQ $
01833110N i-t t-4 6-lC iE-IS 16-Er :tt 101v7
,! N 0 0 0 0 0 0 0 NN3 0 0 0 0 O O O N3 0 0 0 0 0 0 0 3N3 0 0 0 0 0 0 0 3 0 0 C 0 0 0 0 353 C 0 0 0 0 C :
53 1 0 0 0 0 0 T SS3 i 0 0 0 0 0 1 5 0 0 0 0 0 0 0 SSM 0 0 0 0 0 C O l SM 0 0 0 0 0 0 0 :
MSM 0 0 0 0 0 0 0 i M 0 0 0 0 0 0 0 i MNM 0 0 0 0 0 C O }
NM 0 0 0 0 0 0 0 !
HNM 0 0 0 0 0 0 0 !
101V7 t 0 0 0 0 0 r j d381005 03 3V7W)H0035(: 0 j 618IV.A73 01333110N 0 1 F003S Dd LISSINO GelY: 0 _
3N133: 'e31n3NC 3ON11ND3' : SOC 51131 CA33' ]3XC 10 3XII !
1 I
i 4
r i
i I
4
)
1 i
a 4
i e
?
l 4
t
1 51131 d333A nNll: nNII i 0E/li/61 tt;;I H003S VI 3v3H RINQ 5d33C VNG C13331:0N d38100 03 83300G = 610E0r;1-610E0COE s 51V81711A 31VSS: eil 01/CZ 313oW1 ION 5d330:sd01Od 01333110N:CIMIOd iYdS3:01 SOW NINC 5d33C)WdH(
RING C18331 ION !-E t-4 <2V 101V1
._... ... ... ... E-lC 1t _18 16- t N 0 0 0 0 0 0 0 NN3 0 0 C 0 0 0 0 N3 0 0 0 0 0 0 0 3N3 0 0 0 0 0 C 0 3 C 0 0 0 0 0 0 353 t 0 0 0 C 0 C 53 1 0 0 0 0 O i SS3 1 0 0 0 0 0 1 5 0 0 0 0 0 0 0 SSM C 0 C 0 0 0 0 SM 0 0 0 0 0 0 0 RSM 0 0 0 0 0 0 -(
n i i 0 0 0 0 RNM 0 0 0 0 0 O O NM 0 0 0 0 0 0 0 NNM 1 0 0 0 0 0 i 201vl 9 1 0 0 0 C d3M!00S 03 ;11W)H0035(: 0 6v3I?973 CId331 ION C H0n.SS. .J : CT
.C .
_NI'V' "ca WISSIND noNP '" N11Y:
'~i
'ND7' '"- ......
- uvi tua>u. :y.r .e s - .;,ti..
v .
.: h 1.,. ".
- c. ,.r e i w 81, 2 ..e. ., w.a. .7 :. u.
sut S V 811, iA: .1 ; V ei,: e
- er 2 ,. t e
,. .i w
. 917 u r. .i a.
' ?':1:
j !w 1 w,u_ a ..
s a .-
.e. .i w -8 3si, .c i .u.ag.-:i :<- .
- saq:
1
- ..c E. 5.116.
e i w g I1I I ., iA
,1. A..Y.w 6i,l: 7 3_o .
- SC snWWoYA 03 e71 iv873S 6E ibIN1 393H 11973 53dv3V1371 E31naNC 00 6V31 10 db3610nS 0d110N 3N130: :NE 5d33C S3NS08 bnW53E*
- S3108NE 00 693i' 10 db36I0nS Cd110N 3N130 :I; I I :03WVI
- CC b30'b30':' 1* I :03WVI AON IN31nGIND vA3 FING 5d33C
- E3108NC 50 8932 10 eB3610nS 0dlION 3N138; :it ON3 531 CJ CV13S'
- CC W071Id73 S1v81 VMQ 3NG tv135 E3108HC 3XI1S eb09MVW
-. . . . . - . - , - . . - . . - _ . ~ . _ _ . . - _ ~ . . . - . . . . . - . _ _ . - - - . . - . ~ - - - . _ . . .
Attachment 9 Gaseous Effluent Monitoring Instrumentation a
v l
l i
l l
I i
l i
1
_.51 -
_..- -.- - - - = . _ . . . - . --- . . .
i.L guct t.a etGww.roet commstuon av .8*.Ow 4 0 o-e **o 3 'W 4'0* :
i 4C,.7 0.* Jea;
. . ... s . a : !
u , ;
- e. o.r.r...rsoc: .
t n. ,, ,-.,..r e..o, s,.oo.c.om.
r . .o 4 i t.!CENSEE EVENT REPORT (LErN c.o e.n.n o
. a.c.o.u o
. r.o..v.o..
.o
. c .cv. .o.
..c. . ..rn c>... .miim. ovi eco.
e : -oc u .o.
t
..cu.s.a.r.e.a r o.= . ssic.
, -o...c ouc .c= ..w-cre= s o. xw .e io .=o.ics 1 m.s.
ce to
.l
- o. . ..r .o evoco.=oa ..> c..tno= x : mas.
occa ti - .--am a JJ * *c4 . 4 P&Clufv m.ese ist P a rr'r Nuclear Power Plant, Unit 1 10 151310101414 10 1loFD !5 '
- " Program Deficiencies Resulted in an Icoperable Ef fluent Flow Monitor Without the ;
T. A n i a _11 %, 4 3 a v i aa 7 i a l t e ; ~.
R e m i r .d ^ *--w mr e e r.r Acticas ""se,ee Wen. hsu!rin =3 an.e a e ciuns a . myse =
avs.v mars via i u a =v i n . i r o.ri ni i
-o r-6 s, i . . .. ; . . .. t j" tin'.wi _ c, y;;-o n. i s..j.. i
..<~r--.. p e r ~-. .. ;
- 13 i s t o i o i o e i i f l
~~
0 16 015 9!! 91 1 ~Cllb 0 !0 0l 7 l 0j 3 9 !1 a,5,4,3,o, , ,
e as,onT s suom.f*t g sv.su ar .o me esca.,.so.esres se ., g,e g .cn , - ., ., - _ .t u ,
- * * ' ' III i :n.ettima l I re om.s i i Ent.etris l l '171 'w i a *.we . { 6 M*as4.a1Ha na sea.H u l l 3e rzent2Ha l====
l 7111s.s ['
uv e n. j l EJn6.sm a rm=42H=.e l l1mgad . ,,
. s en IiOtO t'===*i2eLeasteet1Het ==== {.-- l .===. m e e f v. .c a YI E73.euhe Jn J I :s.aane.nusma aee j ,i to.72 442m.anas 1 m mm eent ui.e ! tays.eaim } j sayz me.ene, x -n w e I i t.L Mt.eG n.e 1 I ma rzest2ttee f
'1 l 70 ansmis1H i uCIa.sa t 038.r.c7 ena N.s un riti l 'ti.Armone =v e.
- 9
..s. wcs
,ii e: ,ic o i_ni,,,i, we r-r .. uacra-O-- 112 ~= . :~.:--.- re . - s i ~. tm
.wsT1 os.e time .ca t.cM to =1.='ar s.4Lw.s sesensano .= r ws .erner iis
- usa lvsTe-i
- ow o-e-r l **.NP "17""#8[ f c as f rvsti m >a.=r l d? *
,,',,f, l l
t i i 1 , I I I I i ,
t I ! 1 .
1 t liiiiili,il l l:, l I,li,.Ii,iI .
l i
- . . o .mcr o ... 4 i ~, u. ...
a m e-to me masam i L
4.r4 6ito
.==.g
- mn-ro su. -wo- a.rre 1,. i .o r i . i j i s ne r..er - . ,.ao ... _ __ _m n. ,
On June 5, 1991, it was determined that the effluent system ficw rate monitor for the Turbine Building / Heater Say Building (!3/HB) vent radiation monitor had been inoperable during two f an operation since the summer of 1988. During this ti=e,
[
the effluent flow rate was not estimated every four hours in violation of l Technical Specif . tion 3.3.7.10. ;
The causes of this event were program deficiencies. The preoperational testing !
program did not fully test th e accuracy of the vent effluent flow monitors. The '
current program does not verny the accuracy of this flow sensing device, or adequately compensate f or deviations in air temperature. i i
All other vent effluent flow .nonitors were evaluated for similar flow degradation
~
with no problem found. This pitot tube array will be calibrated by capping individual pitot tubes as required and possible degradation will be investigated.
The calibration instructions for the T3/HB vent and similar effluent flow t l monitors will be revised to evaluate the performance of the flow sensing device. ,
Prior to restoring the flow monitor to operable status during two fan operation, '
a mechanism for temperature compensation will be established. This. event will be ;
discussed as part of the licensed operator requalification program. i l
..c ~.,
l G L.?j'/W [~d l0C
- -_ _- - ~ - - __. - - . .- - - __ - - - . - . . - - _ - - - -.- -
W 5 ** I * " " M 'W"*" . pea f :ve %o 3tsc otte
%aC 8C ow 3sa.
(47'e t$ 4. D92 UCENSEE EVENT REPORT (LER) ?,'.;"'.
m . ~'.',M.,. ..:".8.[c.m"." "'O.
- ~. . . = . s'/,s e'(T.'v.i...
TEX CONTINU ATION 6
=,e
. 3 .. c a m,m ..c. ,v im a s %.c .c ogGa ;.v : 3w.it s i0 % Ostl e 0 TO
- ws e p ..sa.m.M 8 ew X :
m e w eaa.A
- a. m.taaaved.'s v .0.s,107 E NC - .co= ac 4
' 340cio.,
- iO :cm os e ?CS
..crer,....n wc= i r w-n a m i i.in w u a .. l ..aa a
,..<w-,
, ,,.. , in u., . ....., % ....;
I l ! l l Perrv Nuclear ?:wer Plant. "ni: '
IO '5'0!3103 414 ! 0i a l ! ! 011 '2 !"O D l' O b P O I S
.. , ~ , - - . ,. w -
- 1. Introduction On June 5, 1991, it was determined that the effluent system flow rate monitor for the Turbine Building / Heater 3ay Building (T3/HB) vent radiation monitor had been inoperable during two fan operation since the summer of 1988. During this time, the effluent flow rate was not estimated every four hours in violation of Technical Specification 3.3.7.10. At tha time of the discovery the plant was in Operational condition 1 (Power Operation) at 100 percent power with the Reactor Pressure Vessel [R?V) at 1025 psi and saturated conditions.
- 11. Even: Description On May 10, 1991, the Turbine Building / Heater Say Building ventilation system was changed from one fan operation (winter mode) to two fan operation (summer mode).
Subsequent Technical Specification channel check taken on the T3/H3 vent effluent flow monitor indicated a flow rate of 230,000 cubic feet per minute (cfm). The difference between the conitor reading and the expected flow of 3e5,000 cfm was considered to be excessive and the : low monitor was declared inoperable.
Extensive troubleshooting of the flow monitor revealed no instrumentation deficiencies. On May 30, '. 9 91, the low flow reading on the T3/HB vent effluent flow monitor was confirmed when a : low seasurement over the stack outlet with a hot-wire anecometer found the actual : low to be 324,000 cfm. On June 5, 1991 further research into the history of this equipment found that during preoperational testing :he vent effluent : low monitor was never verified to indicate the actual effluent flow in the summer mode. A review of operating data shows a degradation in indicated flow beginning in 1986, with the indicator considered to have been inoperable since the summer of 198f Additionally, this data may have contributed :: nonconservative reporting of dose as part of t.he Semiannual Iffluent Report.
III. Cause Analysis The reason hat the T3/HB vent effluent flow monitor indicates 19wer than the actual stack flow in the su=cer mode is due to one or more of the following factors. The pitot tube is located such that excessive turbulence in the duct could cause negative pressure areas in the pitot tube region with both fans running. With only one fan operating in the winter mode, the turbulence region does not extend into the pitot tube array, allowing it to accurately sense stack flow in this mode of operation. Blocked or leaking total pressure port sensing lines in :he pitot tube array could cause an indicated artificially low flow.
The same response would occur if the flow element tubing were partially blocked vtth dirt. Additionally, the flow instrumentation can not automatically compensate f or changing air flow temperature. The exact failure mecnanism is unknown at this time.
The failure to identify the degradation in indicated stack tiow was due to program defictencies. The preoperational :esting program did not fully test ne accuracy of the vent effluent flow monitors. The current survenlance prograc
,c. .a -
~ ,l $ N ~,
..c.a.. n.. v s %c a .. . u . r o. w-wo. , , , , ,y ,
w I u P ra.4 5 .s EL12 0
UCENSEE EVENT REDORT (LcR)
< - '-5.'. o*.*.". no',v"a"a "u" ."". . x". s r'w:o: *".'s" .*c*.*.'.".' >'
' TEXT CONTINU ATION *.o
- . "'m"."n.' "r.^". .*a .* *. ." r ". .' ' ".c'.* *.'u o'. *;"s' ."
. wo. ..s-c m me ac m. 2.once m a
n.
- a. e.* ov .iavcno=
...n.a.. oev3cer ..s~ noecre :,c m
..ma f y ..mt :li wa a r w.St. 43 619 NUh.G G . Si ! ..G4 t!)
v....
..oo... s~..,
.... ;* i ,
s . ., ,
Perrv Nuclear Pcwer Plant, Uni: ! ;0 'S'O'3'O a4 0 911 O il I 010 0 Il cr oj5 Joes not verify the accuracy of this flow sensing device, or adequately compensate for deviations in air temperature. A discussion of each of these factors is provided in the following paragraphs.
During preoperational testing, all af the pitot tube arrays associated with flow monitors included in the plant Heating, Ventilation and Air Condition (HVAC)
Systems were verified to indicate tr.e actual eff'aen; flow rate. In some cases the flow sensing ele-lent was calibrated (selected pitot tubes capped) to assure that the monitor tedicated the actual duct flow rates. Although pitot tubes do not normally require calibration, due to the location of these devices some were modified to obtain the correct : low indication. To confirm the effluent flow rate design crt:eria, TB/HB vent effluent flow was determined to be 345,000 cfm with two fans running. This value, however, was never compared to the T3/HB vent effluent flow monitor indication. Operator readings taken from this flow monitor during the summer af !986 were approximately 330,000 cfm. '4hile a five percent deviation between the flow monitor indication and the testing value is within the expec'.ed accuracy of the pitot tube array, it shows the monitor may never have indicated the actual effluent flow.
Tech Spec 4.3.7.L0 requires a quarterly functional test and an eighteen month calibration of these monitors. Both of these requirements are satisfied by a combined functional and calibration on a quarterly frequency. However, there is currently no method to identif y deviations in pitot tube output to the flow monitor. The current effluent flow, as measured on May 30, l991 with a hot-wire memometer, af 324,000 cfm is a decrease of six percent from the 345,000 cfm : low measured during p: aoperational testing. This decrease could be due :o dir:/ dust in the duct work ur a gradual fan flow degradation. The current reading of 280,000 cfm is a fif:een percent decrease from :he operator log readings of approximately 330,000 cfm taken durind the summer of 1985. The fact that the effluent flow monitor indication has decreased at s greater rate than the actual effluent flow, indicates a possible degradation of the flow sensing element.
- he T3/HB vent effluent flow monitor measures the velocity pressure in inches of water. A conversion scale is placed on the monitor indication to convert this value to a volumetric flow rate ir. cubic feet per minute. The conversion used considers :he air to be at 70 degrees Fahrenheit and 29.92 inches of Mercury.
Actual T3/H3 vent effluent temperatures average approximately 125 degrees Fahrennett in the summer months. This 55 degree difference in temperature can alter the indicated volu=etric flow rate by as much as five percent. Changes in barometric pressure have less of an impac'. on the indicated flow. *his variation can also partially explain why lower than expected flow rates are noted in the summer montas and that indicated : low has degraded over time as the heat rate in the plant has increased.
}
,.c.,._ . -
Q ] W //Wi-IA0 L
. . . .. . . . . .m . ,o. , co ..o.
,;. c,, o.c . , , , , , , , , , , , , , , _ ,
E 4 4t 4 40 M LICENSEE EVENT REPORT (LER) ',$,.'a!,%',,ug,"o c *'.%"jir'J".'.V ,*o'."J"lj TEXT CONTINUATlON 17.,"m*.','.7 "1".^.",,Ni *C,lEc*'/l2 .~;"l ,','l$,N, 10 . ca...mo. ....wo.
- = . wo. a x mu.i 0.o. iC E o.6. ~ .8ci . .a, 4,t.o DU.C?
voc for m..=0;E cro~d oc 5- C.~r N o'm.n O
..cn,a,... ,n poc.er v.... m u . ,o . . . .. j ..c m i*a i P't".i. t 0"J?,T;;
t i !
Perry Nuclear Power ?lant, Unit 1 015l01010i4le!0 91 l l- 0!!! 21-l0l0 015 05 0 13 rm ~ . ,.- ,~.c m.un IV. Corrective Action
- All other vent effluent flow monitors were evaluated f or similar problems. The remaining three effluent pitot tube arrays are installed in long straight ducts; 4 the turbulence region does not extend into the pitot tube arrays to cause inaccurate flow measurements. These effluents are all filtered discharge pathways, in which the particulates which could degrade the pitot tube are removed. Additionally, the air temperature of these effluents does not deviate excessively from the calibrated value and therefore does not affect the accuracy of the indicated t ow races. With all of these factors considered, the TB/HB vent effluent flow monitor is the only one which deviates from the expected flow value.
.4 This pitot tube array will be calibrated before the end of che third refuel outage, by capping individual pitot tubes as required. ~he condition of the pitot tube array will be investigated to determine the cause of any degradation. i The T3/HB ventilation system will be cleaned in an effort to restore system flow.
The calibration instructions for the Turbine Building / Heater Bay Building vent and similar effluent flow monitors will be revised to evaluate the performance of the flow sensing device, by comparing actual flow values to 4 predetermined acceptance criteria. Prior to restoring the flow monitor to operable status during two f an operation, a mechanism for temperature compensation will be established.
Until the pitot tube array can be calibrated, the monitor will remain inoperable during two fan operation, and the default value of 345,000 cfm will be used for I
calculating dose reported in the Semiannual Radiological Ef fluent Release Report.
A revision to the Semiannual Radiological Effluent-Release Report will be submitted for the time periods when the flow monitor reading differed from the actual flow reading by greater than ten percent. This event will be discussed as part of the licensed operator requalification program to stress the value of channel checks in evaluating plant performance.
V. Safety Analysis The radioactive gaseous effluent instrumentation is provided to monitor the release of radioactive materials in gaseous effluents during actual or-potential releases. The operability and use of this instrumentation is consistent-with the requirements of General Design Criteria 60, 63, 64 and 100 of Appendix A to 10 CFR ? art 50. The flow monitor portion of this instrumentation is used in I
l w.C Fee == Jaam m
- L EI djW W 1370'
as ~uc o . .. a .ro. n o...u.o. Asem ov f 0 0u. 40 l'*00104
~,g.C.o..
ggi a.A t amatl 6 3047 o u"o * " *" 'o : " * '5 LICENSEE EVENT REPORT (LER) '". c
- o'*.'.". r io'- :o't t ": io."". . :v e s t so o "- "i . e"..'.'
" *" * " "" ' ' ' ' 3 ' " ' " ' ; 0 " 0 5
"** *" "'C TEXT CONTINU ATION 4=O a't *SM T1 u'nn"ec t u'e g r 'ga nNC Mit % 301 JS NuCasam 3C 9MS a%c TO 4 6 Gu LA ' N*
- C04w &5 Coe WASwe=GTON j iga ci o.S,
- kt s e p t avsop s es pugviou ammtcf O p s ict
'f J Mah AGt wG h ? 440 Ev3G{ f 4 A $mwGTON OC :0901
. ,,....i. j u ar u-. . # ; u . ,, u . . . ., , . .c >
i .,,, , 1..... . . . , , ,..sv..,
- i, l
i i !1 j i Ferry Nuclear ?cwer ?lant. Unit 3 15 io:3io?4;4 0 911 !" 011 ! ! !0 !0 ' 015 ,cF 0i5 w ~ , . - .., .c % - oon calculating the of f site dose. Although the err'. in flow was in the nonconservative direction, the total plant eft en doses during the time this instrument was inoperable were significantly less than Technical Specification limits. Applying appropciate correction f actors to the non-conservative contribution of TB/HB effluents would not result in total effluent doses exceeding the Technical Specification limits. This event is not considered to be safety significant.
Two incidents involving flow estimates not being performed when the vent effluent flow instru ent was inoperable were reportec by LER 36004 and 86011. Both of these events were attributed to personnel error, and the corrective actions of training those personnel involved would not have prevented this event. Another event involving i= proper calibration of liquid ef fluent flow instrumentation due to procedural deficiency was reported by LER 90019. In that event the flow sensing element improperly calibrated is a turbine =eter, was improperly calibrated as a result of inadequate calibration instruction. h corrections made to its calibration instruction would not be applicable to any of the vent effluent flow onitors.
Energy Industry !dentification System Codes are identified in the text as {XX}.
98C*wn 144 A +++P f- ( { l/lYl $ 0
a j
i l
Attachment 10 Process Control Program (PCP) Changes I
a 4
(
l l
1 l
l l
l l
~
1 .
s f
OM12E: PCP Page , i Rev. 5 The Cleveland Electric Illuminating Company PERRY OPERATIONS MANUAL Process Control Program UTI.E : PROCESS Com0L FROGRA14 (PCP)
// b~ -9k e m r n\ 5,.
REVISION: 5 EFFECC VE DATE: G J\ a \ ,ok , VJh-
.--,--...a
'r '
c a .- .;.
9 l
1 m m/
L.J J R FREPARED: James T. Ratchen , rev) 5-9-91
/ Date r
e1 ~
REVIEVED: Q. / ' N '-
[~
/#[Y/
Date
.l l /
vl' PORC REVIEV AND RECOMMENDATION FOR APPROVAL w2ETING NUMBER: QHO30 DATE: 'Ib-9{
m - a f I
/ 4' f/ /
APPROVED: 'N i bi l'
// _- [ } '
y // /' l Date
i l
OM12E: PCP Page : 11 Rev. . -
Table of Contents.
Section Title Py 1.0 T.NTRODUCTION 1 l.1 Definitions 1 2.0 VASTE TYPES 2 2.1 Evaporator Concentrates (Bottoms) 2 2.2 Bead Resins 2 2.3 Filter Demanerali:er Media Sludge 2 2.4 Traveling Belt Filter Cake 3 2.5 Filter Cartridges 3 2.6 Oily Vaste 3 2.7 Dry Active Vaste (DAV) 3 2.8 Other Materials 3 3.0 PROCESS DESCRIPTION 3 3.1 Filling of Ianxs 3 3.2 Sampling / Analysis t.
4 3.3 Preconditioning 4 3.4 Mixing Ratios a 3.5 Devatering 4 3.6 Solidification Processing 5 3.7 Cartridge Filters 11 3.8 Dry Active Vaste 11 4.0 PRODUC"" CONTROL 11 4.1 Test Solidification 12 4.2 Product Quality 12 4.3 Acceptability 12 5.0 7ASTE CLASSIPICATION. CHARACTERIZATION AND 13 MANIFEST REQUIREMENTS 3.1 Vaste Classification 13 S.2 7aste Characteristics and Manifest Requirements 13 6.0 ADMINISTRATIVE CONTR01.5 14 7.0 QUAI.ITT ASSURANCE 14 8.0 RECORDS 16 9.0 ATTACHMEm'S 16
10.0 REFERENCES
16 10.1 Commitments 16
OM12E: PCP Page 111 Rev. : 5 10CFR50. 59 Applicabili ty Check
_Tes No
- 1. Is there a change to the plant as described in the USAR?
, W Reason: R,.c ., , , r. ; . , z/ -y . s r gs,c ! '
R e.
- 2?e. .
- 2. Is there a change to a procedure / instruction as described in ,
the USAR? Reason: n, . . d .f , s hs .t -L-a 2 l
0, _ u l - e ! o ?; i. c . n s.. , hJ - n c u r AQ. C.J . T 3 m s l k w e w. r. .u . u ;hy wT. . . lo d ;ts , g _ , l
- 3. Is there a test er experiment not described in the USAR that .
, . . , j might affect the safe operation of the plant? I ! ^'
Reason: % g s, ~r a ,sr ., - e m, , . ._, j p .a. u
. %% h -
4 Is there a change to the Technical Specifications or Operating J !l
,! ,6 i License? Reason: 77, , .AL_ , t/ ..y .(m . 7,d ,, / ' !
fo r. r_L~<,<ne % .g . _ s ~i <. .
l
- 5. Is there an effect on the environment or change to the Environ-mental Protection Plan? Reason: 1, . . . p. s ,. A ., _ . n %, , I i W' l Am n ,_ w.-c- Tn cL .. - s : pp . % ,_. _ x n l m.a.C 4 M 4 ~M a. 6d A cs.s- Amt m '
, Ansvers to all ques tions are "No", no potential for an Unreviewed l i
Saf ety or Environmental Question exis ts, no further review required. I I
i j 3 Ansvers to Questions 1, 2, or 3 marked "TES", preparation of a safety evaluation is required. Safety Evaluation No.
l l ; Ansver to Question 4 marked "TES", preparation of a license amendment is required. Letter No.
, ; Ansver to Question 5 narked "YES", preparation of an environmental evaluation is required. Environmental Eval. No.
Prepared /Date c_fo.4,l Pavipved/Date r roved /Date/ I
$ /M/4 !,u.(; I 4l/0!?! / ( ?//* I
/- i~
Q SCOPE OF REVISION:
Re". 5- 1. TC's from previous revision that vere evaluated for incorporation - TCN-1 and 2.
- 2. Revised in its entirety, no rev. bars needed.
- 3. The Revision allows for the utilization of new processing vendors and the processing of vaste from c!'emical decontamination.
OH12E: PCP Page : 1 Rev. : $
1.0 INTRODUCTION
The Process Control Program (PCP) is designed to provide adminis-trative control and guidance for the solidification, devatering and other processing of applicable forms of radvaste for ultimate disposal. The PCP contains information pertaining to the current formula (mixing ratio), sampling, analyses, tes ts, and de termina-tions to be nade to ensure that the processing and packaging of radioactive vastes, based on demonstrated processing of actual or simulated vet solid vastes, vill be accomplished in such a vay as to ensure compliance with 10CFR20, 10CFR61, 10CFR71 Federal and State regulations, burial ground requirements and other requirements governing the disposal of radioactive vaste.
The PCP is applicable to the plant installed and Pacific Nuclear Co. , Chem-Nuclear and Scientific Ecology Group (SEG) supplied mobile radvaste systems for solidification and devatering of applicable vaste forms. The PCP is not applicable for intermediary processing at offsite vendors.
l Numerous features have been incorporated into the design of the solid radioactive vaste system and the building housing this system to insure that exposures of operating personnel to radiation vill be kept within ALARA guidelines.
1.1 Definitions The following definitions are applicable to the sections that follov:
ACCEPTABLE ENVELOPE: (of solidification \devatering): specific <
properties of vastes that fall within the limits of the parameters required for solidification. These parameters are established within the test solidification instruction for each applicable vaste type.
EATCH: the volume of isolated vaste cor.tained in a tank that vill be processed for solidification or devatering.
CONTAINER: the physical container in which the final vaste produer is deposited.
EIGH INTEGRITT CONTAINER (BIC): an approved container for burial having an expected life of 300 years. All HIC's must have an approved Certificate of Compliance. '
l l
l-OM12E PCP
{ Page 2 Rev. : 5 SOLIDIFICATION: the conversion of radioactive caterials from liquid and solid systems to a monolithic, immobilized solid with a definite .
volume and shape, bounded by a stable surface of distinct outline on all sides (free standing), with a free water content of less than 0.5% by volume.
2.0 VASTI TTPES There are numerous types of radioactive sacerial expected to be generated at the Perry Plant that vill require processing, including solidification or devatering, prior to their disposal. These radvaste types can be categorized based on their chemical and physical properties. The vaste types expected at PNPP are evaporator concentrates (bottons), bead resins, filter demineralizer media sludge, traveling belt filter cake, filter cartridges, oily vaste, and dry active vaste (DAV).
The following vaste types (other than DAU) may be solidified individually or in combination, with the provision that the chemistry of the vaste falls within the acceptable envelope for solidification.
I 2.1 Evaporator Concentrates (Bottoms)
Evaporator concentraces (bottoms) result from the processing of the chemical vaste tanks which centain condensate deeineralizer regeneration solutions and/or lov concentrations of the following:
trisodium phosphate, minute amounts of other chemicals used for chemistry analyses, or decontamination solutions. They vill normally be in the range of 5% to 25% sodium sulfate by veight.
2.1 Bead Resins Bee.d resins are collected from the condensate, liquid rudvaste, and supprussion pool demineralizers and stored in the spent resin tank.
Bead resins are also collected from chemical decontamination processes.
2,3 Filter Demineralizer Media Sludge Sludge is the vaste product generated by the backvash of the condensate filters, the reactor water cleanup filter /demineralizers,-
and the fuel pool filter /demineralizers. Sludge may consist of powdered ion exchange resin at varying degrees of exhaustion, fibrous filter media, and small concentrations of various solids and corrosion products. The media are decanted prior to l solidification /devatering in the appropriate settling tank.
\;.
s OM12E PCP s
Page : 3 Rev. : 5 2.4 Traveling Belt Filter Cake This is the product remaining on the liquid radvaste tra"eling belt filters used to process vaste vater streams. It consists of one or more of the followings diatomaceous earth oc powdered resin, various solids, dirt, and corrosion products in smal.' concentrations.
2.3 Filter Cartridges Filter cartridges from che oetergent drain tank system, CRD pump suction and discharge filters, and any other disposable-type filter cartridge that may be used in permanent or temporary, plant or vendor systems are included in this cate4ory.
2.6 Oily Vaste oily vaste is that oil collected in liquid radvaste systems as a resulting from leakage and asintenance on various lubriestion and hydraulic systems.
2.7 Dry Active Vaste (DAV)
Contaminated air filters, paper, rags, clothing, tools, equipment
( and parts, that cannot be effectively decontaminated are contained in this category. Also included are laboratory vastes.
2.8 other Materials Various other saterials not specifically identified above, vill be evaluated for solidification or devatoring on a case-by-case basis.
3.0 PROCESS DESCRIPTION The following process descriptions apply to both plant ari vendor supplied systems. Any differences between the two have been noted.
3.1 Filling of Tanks Once it is determined that a liquid radvaste systes batch tank is to be processed, it vill be recirculated to ensure a homogeneous six-ture. Eductors inside the tanks enhance the mixing espabilities.
The tank. vill be isolated using the plant's tagout program to ensure that no additional vaste is added.
+
l
I f
i 5
OM12E PCP !
g ,
Pege 8 4 t " *~ [
Rev. : 5 i 3.2 Sampling / Analysis i t
.s samples vill be obtained and analyzed for each batch of vaste in i accordance with OM12Cs CHI-42, OM12A CHI-70, and OM1A PAP-1102 respectively for the plant system, or vendor procedures and PCP for vendor supplied systems. Prior to sampling. tanks vill undergo i i
sufficient sixing and/or recirculation to ensure representative i sampilng. At a minimum, for solidification, analyses vill be performed for radionuclide content, pH, oil content, and settled l solids (oil and concentrates only). At a minimum, for devatoring, analyses vill be performed for radionuclide and oil content. These ;
analyses are necessary to ensure that the vaste falls within the ;
acceptable envelopes for solidi fication/devatoring.
- t 3.3 Preconditioning _
Vaste preconditioning is the chemical or physical adjustment of the :
vaste to bring it within an established acceptability envelope to ensure solidification. The need for and type of preconditioning -
i shall be determined using sample analysis results and vill be i perfotmed in accordance with OM12A CHI-78 or ver. dor procedures and !
PCP. Upon completion of vaste preconditioning 6 additional samples j shall be obtained, as required, to determine solidification mixing
( ratios. !
Oily vastes may require special preconditioning. Handling of oily I wastes vill be conducted in accordance with burial ground i requirements.
3.4 Mixing Ratios !
Mixing ratios give the respective amounts of vaste and solidifica-tion agents required for acceptable solidification. The determina- I tion of mixing ration shall be performed for each batch of vaste to be solidified. Solidification mixing ratios are dependent upon percent settled solids and sodium sulfate concentration. The vaste ,
i type and ratios of cement, vaste, sodium sulfate (for Class A t vaste), and water are determined in OM12A: CRI-78 or vendor I procedures and PCP. !
3.5 Devatering '
Devatoring is the removal. of water from solid material. to a concen- f tration of less than. 0.5% or 1.0g by volume, as applicable to con- [
tainers used and burial. site limits. Devatoring of radioactive i spent resins, filter sludges and traveling belt filter cake shall be ;
performed in accordance with approved operating procedures which are based upon documented test data demonstrating the ability to achieve {
t t
- Painable veter limits as specified in applicable regulations. !
t i
~
. _. . - - . _ - ~ . . _ _ .. ~ ...- - ----_-,_ - . ,_ ...,.- _ _ . _.--- _ .,.-,-.,. _ -. _
0H12E PCP Page : 5 Rev. : 5 3.6 Solidification Processing 3.6.1 Descript. don of Plant Processing System Solidification and/or devatering of vet solid radioactive vaste vill be processed by Chem-Nuclear's Rapid Devatoring System, NUPAC Services Division's Resin Drying System or by SEG's Mobile System. These systems are discussed in Section 3.6.2.
The following description applies to the plant installed solid radvaste system that vill interf ace with the vendor equipment (See Figure 1).
(
(INTENTIONALLY BLANK)
(
~
in
P
. t I
l l
OM12Et PCP i
. Page i 6 i
- Rev. 5 ;
i Solid Radioactive 7sste Processing Systes l I
X . II f
,_ _ I___3lE _ . _ . ,
- f l f we
-+< . g i g!
-i;
!!gi -
i l
i li . -
L r:
~~
.---- x i f
! II s,
t, I i 1 ! I t L I e e I% 1 i :
i' ,
- l- - - -
l \;
ri-igg" -
3, I :
. i
~
UN j,
. ?
, se fi{l g
t ,
i X 0 !
I
!: <>c % ,
I x ;
X b .
it .
t i . I e
. w
' r,* I in -
t
. I
% rr l t
[ W e ro X I L >4-~ l i
% % 4 I f
e e e f
I la E' ]
pu5
) @e
?i) Figure i J]
? m]
' . l f
i I. '
---e--t-+- r rr m - w-v-r--t ea e *-r+ -~*-? **-'t-"e* * - - +- * " ' " ' ' ' * - - " " * * " " " " ' * * ' " ' " ' " " * ' " * ' * * ' ' ' - ' ' * " " ' ' ' ' ~ ~ * - " " ' ' ' " " -
OM12E PCP e Page : 7 Rev. t 5 Af ter the proper amount of vaste has been accumulated in a settling or vaste tanks or has been transferred to the vasto -
mixing tank, the tank is decanted to remove excess free water (except when the vaste being handled is traveling belt filter cake, in which case a predetermined amount of water or other approved aqueous solution is added to the tank for slurry I
1 transfer of the contents). The vaste slurry is transferred at a preset rate to the vendor's equipment, in accordance with OM13At RVI-G51-(SRV), where i t is either devatored or solidified with cement. The vaste mixing tanks and settling tanks have recirculation capabilities where a representative sample can be drawn. If needed, a devatering connection is available which is routed to the liquid radvaste system. An additional connection has been provided back to the vaste mixing tank for use in the event of a lir.er overfill condition.
Hot vater flush connections are provided ta thoroughly flush the plant and the vendor equipment into the liner used for processing. The vaste transfer line and devatoring return lines are located behind a two foot thick shield vall to reduce exposure to the operator during processing.
3.6.2 Description of the Vendor's Vaste Processing System 3
' The vet solid radioactive vaste vill be transferred to the vendor's equipment to be devatered or solidified in accordance with site approved procedures. Table 1 lists the Topical Reports, proccdures ano any comments for each vendor.
The vendor's equipment is located in the Radvaste Building in the fill aisle, storage area, and truck bay (see Figure 2).
Normal processing of radicactive vaste vill be performed in the fill aisle with only the vandor's cement transfer equipment being located in the cement silo room Periodically, when determined prudant, vaste vill be processed in the truck bay.
Vhen this is performed several restrictions vill be imposed to minimize the potential for radioactive spila and ensure the principles of ALARA are maintained. These includes all processing to be performed in an NRC approved cask, all hosing and associated connections to be placed in hose bags, truck bay access doors to have temporary curbing placed in f ront of thwa, and locking all access areas to the truck bay. The areas where the procassing takes place are specifically designed to handle the movement, storage, and processing of radioactive vaste.
Concrete valls sud floors in these areas have protective coatings and sil dd/ cssk valls are provided betveen the vendors equip %4* I and potantial radioactive sources to keep personnel exposures ALARA. The storage area is large enough to contain 15 liners. This provides adequate storage before it is shipped to a burial site.
m
__ __ , _ _ _ _ _ _ _ _ _ . _ . _ _ - - . - - - + - - - - - - " '
7, . y., % *
- l-- -
n <
i i
l-1 l
Weeder preceduses for sedweste Processing Weedet Topical Sepest opesettag Psecedures commeete f chen-seclear endleective Weste Sewetesieg setup and opeteting Psecedere tot 4. Test entidif8catiees
{ System, tes-23546-St-F-A .the aos-teet Welt, 70-09-432 w114 he see e euk
! batch et the eene weste tree.
sph!!o cement seitdificetles opesettes esecedure tes the settle i'
Systes,(383-3 comeet sealdification unit se. 221,
?
SD-of-430 Pacific- mucises reckagleg Dewetesieg seede Ocying (Dewaterlegl System.
Seclear System. TF-82-F-A est-e l. as Pacific Nucleet Systems oposetion and naistenesce sneeeel tot 1. Test solidaticatione medweste selidification the EUFAC medweste solidification =111 be tua se each Systee, TP-SS Systee,'OM-ite batch of the same weete type.
Systee Descripties et Pacific secteer systee*e tedisective essete valene Beductie Systee 378-888 operaties frecedese tes RWS-484 Liguld Vetense Seducties Systee, ces-4422-es
.cimeu fic . sea ..w -t c. . .e c. ..- ee. c.at... ..o. se f., .ete. e,
.c.ie,,
- i. re.t .eu. facetiene y .g o,eo,
.., e,ecess fe, .ewatene, of ... .eene end rutet
.eed e, ee oewste.sa e.e4 ..sie on.
,etoe ... 2....
ch ..,
wu z .e ..e se eaa .{g 6stc et tuo esee weste ___=
Sludje, 385-443 type.
I San Gn m Sedweste Se1&dificat(en 'StG Se .dificaties systee, $$-484 O
- 2. esente will be empplied 4 System, F5-53-e314 to the sse equipeeet at 28 gpe aseteed et te gee due to pway tientatioes.
Tab e 4
,- y e ,e-....w - . , , - - < - - - ,+ n i.... . . . . .
e 4
OM122 PCP c
f' .
. Page : 9 Rev. : 5 Vendor Mobile Solidification Equipeent Layout l n e I }
? /
/
A h;; .. !. d
/ l9 :!n2
_ =a ym E k 2 = 4 2 N s <
g =
(- s
- 2
~
l / $
1 R
/~c</ ~ .
/ / s
-- / /
I l
k Nt Rw 62.0 1
g
(..
1 Figure 2 !
, ON12E PCP Page : 10 Rev. t S 3.6.3 Radiological Effluant Controls and Monitoring All processing with the vendor's equipment vill be performed in a room with a volume sufficient to contain any postulated spill. A floor drain, routed to the liquid radvasta systee, provides drainage in this area. All liquid radvaste discharges are sampled and monitored prior to their release to the environment.
Caseous discharges from liners are processed througn the vendor's off-gas blower system as described in the vendor's Topical Report. Ventilation from the areas housing the radvaste treatment and processing equipment, including the vendor's of f-gas blover system, is routed through HEPA filters and charcoal beds prior to release to the environment via the Uni t 1 'Nu t . Radiological monitoring is provided for Regulatory Guide 1.21 compliance to meet applicable Federal Code requirements.
3.6.4 Health Physics Support Health Physics personnel vill provide radiological control during the solidification and devatoring process. All vork
(' vill be conducted under a Radiation Vork Permit to keep petsonnel exposures ALARA.
3.6.5 Plant Utility Support
- 1. Fire Protection Fire suppression is provided above the processing and ,
storage area to protect against fires. A fire hose is available in the truck bay for miscellaneous uses. .
- 2. Two-Vay Communication i
. s A two-vey communication system vill be used for L l
' communication between the plant operator and the vendor :
equipment operator. This vill facilitate smooth !
' coordination between the different segments of the vaste !
processing systes.
3 .- Heatingr and Ventilation l l The Radvaste Building Ventilation System vill maintain a !
negative pressure in the processing and storage area. '
Heating is provided by the building heating system vhose !
heat source is the plant auxiliary boiler, j t
e,--. . . . - _ . ,n ..,, , . ., , -. - - - - - . , . . - - - , - . . - - , , -
l OH12E: PCP Page : 11
( Rev. 5
- 4. Overhead Crane An overhead crane vill be used to transfer equipment betveen the storage and processing area and the truck bay.
The crane has a 15 ton capacity which is fully capable of handling devatered and solidified liners.
- 5. Closed Circuit Television Closed Circuit Television vill be used, where applicable, for remote viewing of the processing and storage areas.
The overhead crane has an independent camera for vieving all lifting and placing operations.
3.7 Cartridge Pilters Cartridge filters may be disposed of by encapsulation in a cement matrix in steel drums or liners. The encapsulation of cartridge filters shall be performed using approved procedures that provide reasonable assurance that the final vaste form vill meet the stability criteria of the Branch Technical Position on Vaste Form.
Cartridge filters may also be disposed of by placement in HIC's that are certified by the land disposal facility's State Agency.
I' 3.8 Dry Active Vaste Potentially contaminated dry vastes vill be collected in containers located throughout the radiologically controlled areas within the plant. The vaste vill be periodically collected and transported to a temporary storage area prior to vaste segregation (as per OHlA PAP-1901). Vaste segregation vill be performed to reduce vaste volume and to recover reusable materials.
In order to reduce the vaste volume, compressible vaste vill be compacted into shipping containers in accordance with OH13As R7I-G51-(SRVC). Caution vill be taken to avoid items that vould cause free water formation e.a well as other compressibility hazards.
Noncompressible vaste vill be loaded manually into suitable shipping containers.
4.0 PRODUCT CONTR01.
Devatering/5olidification processes vill be conducted by qualified PNPP or vendor personnel in accordance with approved plant and/or vendor operating instructions and procedures.
PAP-0525 Solid Radvaste Administration vill ensure appropriate documentation and compliance with this program.
i
OH12E PCP Page : 12 Rev. : 5 4.1 Test Solidification Test solidifications are performed on vaste stream samples to verify plant and/or vendor calculated solidification formulae. Test shall be performed to support solidification mixing formulae as follows:
l (1) every batch of the same vaste types (2) when sampling analysis falls outside the normal established envelope and preconditioning is ineffective, (3) following any liner of the same vaste type where solidification has been determined to be unacceptable (4) when it is believed that some unexpected or abnormal containment may be presents or (5) when requested by Chemistry Supervision. A batch that requires test solidification shall not be processed until such time as the test solidification proves acceptable. < LOO 415>
Upon failure of a test solidification, additional samples shall be obtained and testing vill continue until a successful solidification has been performed with revised mixing ratios as determined by Chemistry Supervision. Solidificatinn of the batch may then be continued using the alternate solidife.estion parameters defined by testing.
4.2 Product Quality Solidification process product quality shall ba ensured by the use of predetermined mixing ratios of vaste and solidification agents.
Mixing ratios are based upon laboratory testing of non-radioactive vaste materials and are supported by (1) the test solidifications performed periodically, as mentioned above: (2) periodic checks, visual and physical, of actual processed containers filled with solidified vastes and (3) once every tvo years requalification of the vaste form. Requalification includes testing for compressibility in accordance with ASTM C-39-84, following an appropriate immersion period.
4.3 Acceptability The acceptability of the solidified product shall be verified by ensuring that less than 0.5% free standing vater exists and that the-solidified product appears to be able to hold its shape if it vere to be removed form the container.
Unacceptable solidified vaste shall be handled as follows: (1) if the reason for unacceptability is free-standing vater, the free standing vatar vill be removed. or extra. eenent/ sodium silicate vill.
be added to solidify the free vaters (2) 11 all or portions of the-product did not solidify, the vaste container vill be capped and placed in a storage location in the Radvaste facility and periodically checked until such time that the product is acceptable or it is determined that additional solidification agents can be
( added to achieve satisfactory solidification. This vill be determined by Chemistry Supervision. The handling of unacceptable solidified vaste vill be on a case-by-case basis. _
4
OM11Et PCP Pye 13 Rev. t 3 Adherence to approved devatering operating procedures ensure the. l final product vill meet or exceed the standing vater requirements of
t Devatoring of radioactive bead resin, filter desineralizer media sludge, and traveling belt filter cake shall be performed in i accordance with approved operating procedures which are based upon !
documented test data demonstrating the ability to remove free water i volumes below the applicable regulatory limits. .-
e i
b 5.0 VASTE C1.ASSIyICATION, CHARACTERIZATION AND MANIFEST REQUIREMENTS
/ :
5.1 Vaste Classification q
All vastes shall be classified in accordance with the requirements !
of 10CFR61 as implemented by OM1A PAP-1309 and ON1Es RAP-1102 and performed by the RADMAN computer code. Analyses shall be performed !
j on the waste streams at lesst annually (b1 annually for class A vaste), to determine the isotopic abundance of non-gamma emitting isotopes in the streams, Scaling factors, for the non-gamma i i
esitting and transuranic constituents, vill be developed from these
( analyses. Prior to the establishment of an acceptable data. -
estimated isotopic concentrations vill be those obtained from the j
" Data Base Analyris Report" prepared by Vaste Management Group. E r
The activity of each radionuclide ir the radioactive vaste shall be j determined by a calculational method employing the isotopic analysis :
of the vaste and scaling factors or a dose-to-curie conversion as to be determined by RPS supervision. Por DAV, a dose-to-curie i
conversion factor, percent. fraction of the radionuclides, and !
scaling factors viu be used to determine activity.
5.1 Vaste Characteristies and Manifcse Requiremants 1 AH vastes shan meet the characteristic requirements of 10CFR61.56 e (a) and (b), an applicable, and vaste packages shall be marked to '
identify the vaste class. The manifesting requirements of .
10CFR20.311 shsH be implemented by ONIA: PAP-1309 and performed by
_[
the RADMAN computer code. Records are maintained. in accordance with !
10CFR71.91. I
-s ' :.:, -
}
Q
,, . - . _ , - _ _ - , _ , , . . . _ . . . . ~ . . . . _ _ - . _ . _ - . , _ .. .- _. . . - . . - . _ , , __ . . _ . . . _ . , . . _ _
OH12E PCP
, Page : 14
,' Rev. : 5 6.0 ADHINISTRATIVE CONTROLS Compliance vith applicable state and federal regulations, and with burial site criteria is ensured by compliance with the solid radioactive vaste surveillance instructions, OH7As SVI-G51-T5284 The implementing instructions and procedures for radioactive vaste solidification, devatering, and segregation describe the requirements which must be met prior to processing radioactive vaste, as well as the expected condition of the resultant vaste form. Test solidifications, full scale calculations and operation of solidification, devatering and segregation equipment shall be performed by qualified plant staff and vendor personnel. Plant staff personnel shall provide Health Physics and Quality Assurance covocage, operate plant radioactive vaste systems, collect vaste strsam samples, and perform isotopic analyses. Copies of all referenced documants are available onsite for use by personnel angaged in vaste processing activities.
Any thanges to the Process Control Program shall be reviewed by the Plant Operations Review Committee (PORC) and shall be detailed in the Semiannual Radioactive Effluent Release Report covering that period.
7.0 QUALITY ASSUPJLNCE Quality Assurance related activities for the solid radvaste program are implemented as described in the Perry Nuclear Power Plant Quality Assurance Plan. To prevant unacceptable solidified vaste from being released for shipment, test samples vill be verified for acceptability by Chemistry Supervision. These activities shall provide verification that all solid radioactive vaste meets applicable State and. Federal regulations and burial site criteria.
A flow chart illustrating the sequence of events for a vaste solidification process is provided in Figure 3.
The Quality Assurance Plan also includes a. management review of vendor's Topical Report. This vill ensure that the vendor's operations and requireacnts are compatible with the responsibilities and operations of thecplant.
Training and qualification of operators vill be performed per Regulator Guido 1.8 and. ANSI N18.1 - 197I.
For accountability of filled vaste containers, a clearly legible storage diagram vill be permanently displayed near the radvaste control panel. It vill show the position of containers holding vastes, the date the vastes were processed, and their dose rate (s).
The storage diagram vill be updated to reflect any changes, additions, or deletions to storage. .
1 I
ON12E PCP
, , Page : 15
't'n 4 Rev. : 5 Radvaste Process Plow Chart u<
6 e.o=
es e
. ... 1
... ..... I l
'*d:::.
s ..
b Fut A L.
w%ry ?f5 i PtF*
- l Te s a OtwaTEC%
al A T 40
.e.a.
e.es.e. e.e * .. ee e m , .ree s.
, .... ,,, _ e..e ]
(. 86fl itt* ~ sees es i .. 4 4 4 # 4. ,
per?
l e.en87 ! h h.es...f ,, eles,a,i etr .e t
.I a. (. .... . -
l Dt i tes.4 6 unee e ..
Gees feet i
1
- s e, -
u..
h I
et e amens feet:9ee et Class-If8' 808'885 g g f1&e en.
l * *"'** "
essef s w"**
I r.u. eo.e4 ...est6 .
EBf s.;.
u.39 su. e* Figure 3
.eM
. - - . ,. . - . . , , ___ . - _ _ . - . . , _ , _ . . . . . , - . ~ . . . . _ , . . - - _ . . _ . _ _ . . . _ _ , . - . _ _ _ . _ _ . . , _ _ _ _ . - . - _ _ _ _ __ _ _ _ _ _ _ _ -
. r
. I r
I e ;
i OM12E PCP i f" Fase : 16 l Rev. : 5 8.0 RECORDS The following records are generated by this program !
I Ouality Assurance Records !
None .
I Non Quality Records !
None i t
i 9.0 ATTACHMENTS i i
None i t
[
i i
10.0 REFERENCES
/r 10.1 Commitments
[
i The following commitments are wholly or in part met by this i document ',
h B00301 F01412 F01464 LOO 415 500245 I t
t t
i
.I i E v
k l
f I
r E
4 5- , ;
e b
r
,e.,,,-.. .,
OM12E PCP Page : 17 Rev. : 5 gFERENCES,
- 1. Title 10, " Energy", Chapter 1, Code of Pederal Regulations Parts 20, 50, 61, and 71, U.S. Government Printing Office, Vashington, D.C. 20402, January 1,1984.
2' .
Title 49, " Transportation", Chipter 1. Code of Federal Regulations, :
Parts 170-178, U.S. Government Printing Office, Vashington, D.C. [
20402, November 1, 1983.
s
- 3. U.S. Nuclear Regulatory Commission, " Standard Radiological Ef fluent !
Technical Specifications for Boiling Vater Reactors", USNRC NUREG-0473, Revision 3, Vashington, D.C. 20555, September 1982, i
- 4. U.S. Nuclear Regulatory Commission, "Lov-Level Vaste Licensing [
Branch Technical Position on Radioactive Vaste Classification " :
Revision 0, May 1983.
- 5. U.S. Nuclear Regulatory Commission, " Branch Technical Position on Vaste Form", Revision 0, May 1983.
j
- 6. " Standard Test Method for Compressive Strength of Cylindrical l
{- Concrete Specimens" ASTM C39-84, American Society for Testing and !
Materials, Philadelphia, Pennsylvania 19103, 1984. -
- 7. Regulatory Guide 1.8, " Personnel Selection and Training", U.S.
Nuclear Regulatory Commission Vashington D.C. 20555, S<sptember, 1975.
- 8. " Selection and Training of Nuclear Power Plant Personnel", [
ANSI-N18.1-1971, American National Standards Institute, New York, New York 10018, 1971.
9 .- "Radman - A Computer Code to Classify and Document Packaged LLV in Accordance with 10CFR Part 61 Regulations", VMG-NP-A, Vasta Management Group, Inc. Croton-on-the-Hudson, New York 10521, May 1983.
l 10. " Data Base Analysis Report - Perry Nuclear Power Station", Veste ;
l l Management Group, Inc. , Croton-on-the-Hudson. New York, New York.
- 10521,. May 1983.
11 SEG Process Control. Program for Devatering, Bead or Powdered Resin with Quick Dry Devatering-System No. 2893, DiLOO4. i
- 12. SEG Operating Procedure for LNPSC Radvaste Solidification System No. S5-001. i k 13. SEG Process Services Topical Report on Radveste Solidification '
System, PS-33-0378.
i i
OM12E PCP L L..
Page : 18 j Rev. : 5 i REFERENCE 3
- 14. Stock Equipment Co. Quick Dry Process for Devatering of Bead Resin and Filter Sludge, SRS-003.
- 15. " Perry Nuclear Power Plant Unit 1 Technical Specifications," Rev. O, The Cleveland Electric Illuminating Company, Perry, Ohio 44081.
- 16. " Perry Nuclear Power Plant Units 1 and 2, Updated Safety Analysis
' Report". Amendment 14, The Cleveland Electric Illuminating Company,
- Perry, Ohio 44081.
- 17. Perry Nuclear Power Plant Operations Manual, " Radioactive Shipment Criteria",-OM1A PAP-1304, The Cleveland Electric Illuminating Company, Perry, Ohio 44081.
- 18. Perry Nuclear Power Plant Operations Manual, " Shipment of Radio-active Vaste Pee Disposal", OM1A: PAP-1309. The Cleveland Electric l Illuminating Company, Petty, Ohio 44081. l
- 19. Perry Nuclear Power Plant Operations Manual, " Dry Radioactive Vaste i Volume Reduction Program", OM1A PAP-1901. The Cleveland Electric '
( Illuminating Company, Perry, Ohio 44081. l
- 20. Perry Nuclect Power Plant Operations Manual, " Plant Chemistry l Control Program ,a OM1A PAP-1102, The Cleveland Electric :
Illuminating Company, Perry, Ohio 44081. i
- 21. Perry Nuclear Power Plant Operations Manual, "10CyR61 Compliance Sampling *, OMlE RAP-1102 The Cleveland Electric Illuminating &
Company, Perry, Ohio 44081.
i
- 22. Perry Nuclear Power Plant Operations Manual, " Miscellaneous Sampling-Systems", OM12C CHI-42, The Cleveland Electric Illuminating Company, Perry,. Ohio 44081. )
l 23 Perry Nuclear Power Plant Operations Menual, "PCP Test Solidification", OM12A: CHI-78, The Cleveland Electric Illuminating Company, Perry, Ohio 44081.
- 24. Perry Nuclear Power Plant Operations Manual, " Solid Radvaste Solidification System", OM13A: RVI-GS1-SRV,. The Cleveland Electric Illuminating Company, Perry, Ohio 44081.
- 25. Perry Nuclear '1ver Plant Operations Manual, " Solid Radvaste t Compaction Sys<en", OM13As RVI-G51-SRVC, The Cleveland Electric Illuminating Company, Perry, Ohio 44081. !
- 26. Perry Nuclear Power Plant Operations Manual, " Process Control
!- Program Solidification", OM7A SVI-G51-T5284, The Cleveland ;
Electric Illuminating Company, Perry, Ohio 44081.
g I
p
. , , - . . , . - . , . , - , , n., , - - ..,,,,,..-.em _ . - -
e.._.-4 , ,. , , , , , . , , .
i i
t i OM12Es PCP (c- Page 19 - LAST ,
Rev. 5 '
REFERENCES ;
r
- 27. "Barnve11 Vaste Management Pacility Site Disposal Criteria".
Document 520-AD-010, Revision B, Barnwell, South Carolina 29812, i January 1,1982. !
t
- 28. "Racioactive Materials License VN-I-019-2", Amendments 13 and 14 U.S. Ecology, Inc., Banford Reservation, Richland, Vashington i 99352, December 23, 1983. '
- 29. " Perry Nuclear Power Plant Qualj .4 uran <.e Plan", The Cleveland Electric Illuminating Company . . Ohio 44061.
- 30. Homer, J. C. and I,utz, G. P. , " Stock " Quick Dry" Vacuum Compression i System for Devatering and Volume Reduction of P11ter Sludge -
Summary of Test Results", Stock Equipment Company,1986. .
- 31. NUPAC Operating Procedure for Resin Drying (Devatoring) System, t
OH-43-N S .
?
- 32. Topical Report Covering Nuclear Packaging, Inc. Devatoring System, TP-02-P-A. ,
/t
- 33. Ches-Nuclear Topical Report for Radioactive Vaste Devatoring System, ;
RDS-25506-1-A.
- 34 Chen-Nuclear Topical Report for Mobile Cement Solidification System, CNSI-2.
- 35. Setup and Operating Procedure for the RDS-1000 Unit, PO-OP-032.
- 36. Operating Procedure for the Mobile Cement Solidification Unit i No. 221, SD-OP-050. .
- 37. Topical. Report covering Pacific Nuclear Systems Radvaste-Solidification System. TP-05. I
- 38. Operation and Maintenance Manual for the NUPAC Radvaste '
i Solidification Systes. OH-114.
- 39. System
- Description of Pacific Nuclear Systems' Radioactive Vaste i Volume Reduction Systar, KVR-800.
i
, 40. Operation Procedure for SVR-800 Liquid Volume Reduction System, f
! OH-0022-NS. '
N: i w: - - - - . - - - .e . - - - ,w,,.m , ~.. .r i.9m- , - , _ ,,y ,,-_ em
Attachment 11 Offsite Dose Calculation Manual (ODCM) Changes v
i 4
i h
h k
9
?
?
I L
I t
I i
I I
i
- ,k
?
I
'I f
I I
C t
i-L m -- , , , , w,,w,wm-w,_,--,w- _s,+,w,- -
.-,,,wn _m.a,
- , - ., - - . - . , - - - - - .-wv. , - ~ , . ,---,,,,,-.w~,,
I l
s 4
NONINTENT .
~a INSTRUCTION TEMPORARY CHANGE l w a rme n m wem "*~R -
,,.st%w a mev p4Thicnomrnta 3 n r h ,+e ocu e b l u M ,e n Wh , sal oun o a s cAs.cs4.4 n:pos6 AlA e usa cens arucmas pact
.47 W fl y'1 Se a "18 b '79 T D , f l. I '7 f8 f9.90<g 91.113 mm-c i a i
~3"LN i Is-n-m u
dmes T fM e. hen
'N j kmp Ante.os 30; 50, and y* Mded .
"t b u. ; ,,/
. . u. . 14s -u odd ed,4* Leg C ;v tee, Sen Louhana 15 4 To .r.e h byid % as+= d.h,b.n 41.w ge 6., y y bN Ser. ten 3,3 T*We 2.3-n3 is W h incJude ina.,,,g,a g.gd. f. M fe. mh p+.ue waAc e-intose w ,% n se ~$,3 ., rup Yak 2.) *)i g3 nelsdeM h trisLdC andswedesd div+nn fe44,r4 [as ect), gr/d loc.ation Fo n 4c N h in gea b .n pH Raferenws fan 4 ucs 2.3. is .nd 2,3 - H am added, g,, res, s. t - 1, C. 4 - 2 ,
5.t-3, demp '"aP5 ycCNDmCNAL AP*MQVAL Y $ t. h \ f'N '
lhu/RN \ l:7 hi
/' '
C misnam.outr -,
e arve.u a.ra dk 1 ,
, =----- , . . ma **==== m i [4 M I \ #"4 db \
M
' ~
m - m MA
. db i ;
j -~~ g- 7 75 w~O Q l- 14 d-08-9l c- :
ren couomenat c s enm
.wu
- ' 0'***"'*50 g
k~ a xw em c=-
?
( OM12D ODCM 1;. -
Page : iv Rev. 3 List of Tables .
Table Title M
2.3-1 Organs Used for Liquid Effluent Dose calculations 15 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations 15 2.3-3 Liquid Effluent Dose Fathways 15 2.3-4 Bioaccumulation Factors 16 2.3-5 Ingestion Dose Factors for Adult 17 2.3-6 Ingestion Dose Factors for Teenager 19 2.3-7 Ingestion Dose Factors for Child 21 2.3-8 Ingestion Dose Factors for Inf. ant 23 3 2.3-9 External Dose Factors for Standing on Contaminated 25 Ground 2.3-10 Liquid Effluu t Dilution factors (Np) 27 2.3-11 Transit Times Required for Nuclides to Reach the 27 Foint of Exposure-2.3-12 Usage Factors (U,p) 28 ,
( 2.3-13 Dilution Fectors for Each of the Potable Vater Intakes Vithin 50 Miles of FNFP 28a 2.3-14 Dilution Factors for the Fish Ingestion Pathway ic' Individual. Grid Zacations q
28b e
3.1-1 Total Body and Skin Dosa Factors 37 3.2-1 Organa Used for Gaseous Effluent Dose calculations 44 l
3.2-1 Age Groups Used for Gaseous Effluent Dose Calculations 44 3.2-3 Gaseous Effluent Dosa Fathways
.. 45 3.2-4 Dose Factors for Exposure to a Semi-Inifinite Cloud 46 of Noble cases i
( 3.2-5 External Dose Factors for Standing on Contaminated 47 i Ground 3.2-6 Inhalation Dose Factors for Adult 49 ;
3.2-7 Tah=1= tion Dose Factors for Teenager 51 TC/VAX/Fage 1-of 14 !
t i
OM12D ODCM !
I' , ' Page a y
{
Rev. : 3 ;
g, q List of Tables (Cont.) .}
Table Title a Page 3.2-8 Inhalation Dose Factors for Child 53 l 3.2-9 Inhalation Dose Factors for Infant 55 :
4 3.2 10 Ingestion Dose Factors for Adult 57 !
i 3.2-11 Ingestion Dose Factors for Teenager 59 .
3.2-12 Ingestion Dose Factors for Child 61 3.2-13 Ingestion Dose Factors for Infant 63 3.2-14 Annual Usage Factors for the Maximum Exposed 65 t Individual l
3.2-15 Annual Usage Factors for the Average Individual 65 !
t 3.3-1 Ca - and Beta Air Dose Factors for Semi-Infinite 71 Plume 5.1-1 . INFP Radiological Environmental Monitoring Program 79 f
5.1 2 Reporting Levels for Radioactivity concentrations 82 l in Environmental samples 5.1-3 Detection capabilities for Environmental Sample 83
- Analysis and 14ver Limit of Detection (LLD) l 5.1 -4 Sample 14 cations and Media for the Radiological 85 Ravironmental Nonitoring Program ,
i A-1 Atmospheric Depletion and Deposition Factors 95 i
A-2 Site Boundary Atmospheric Dispersion and Deposition 97 Parameters for FNFP Unit 1 ,
. I A-3 Atmospheric Dispersion (y/0) as a Function of 98 Distance ;
l A Atmospheric Deposition (D/0) as a Function of '103 )
Distance 1 i i
TC/VAX/Page 2 of 14 :
ON12D ODCM f;. - .
Page : 12 IW # Rev. : 3 a
gP
- the equilibrium bisecumulation factor for radio-nuclide i in pathway p, expressed as the ratio of +
the concentration in biota (in pC1/kg) to the radionuclide concentration in water (in pC1/1), from Table 2.3-4, in 1/kg; D,gp j = *the dose factor, speelfic to a given age group a", radionuclide 'i', pathway "p', end organ "j",
which can be used to calculate the radiation dose fna an intake of a radionuclide, in eres/pcit or from exposure to a given concentration of a radio-nuclide in sediment, empressed as a ratio of the dose rate, in area /h, agd the areal radiooue.lide concentration in pci/s , from Tables _2.3-5 through 2.3-9:
F = the flow rate of the liquid effluent in ft /sg NOTg The normal dilution flow will be between 30,000 W and 61,500 gpa (UEAR 11.2.3.2) 9 M,- the dilution factor at the midpoint of exposure (or the point of withdrawal of drink.ing veter-or point of harvest of aquatic food), from Table 2.3-10, dimensionless:
Og . the release of radionuclide 'i', in Cis t b . the period of time for which the sediment or soil is exposed to the contaminated veter,1.75 s 103 h (20 years):
Tg - the hain4ie of radionuclide 'i', in days; t, - ther average transit time required for radionuclides to reach the- point of. exposure, free Table 2.3113-for internal. dose, t is the total tima elapsed between release of tee radionuclides and the ingestion of food or water, in h1 U"P = intake the usage factor that specifies the exposure time or-rate for an individual.of age group a associated with pathvey 'p*, from Table 2.3-12, in-l_ h/yr,1/hr, or kg/hrt ...
I V - the shoreline width hetor. 0.3 (from Regulatory cuide j 1.109):
Ag . the rgdioactive decay constant of radionuclide "i",
in h~ ;
1100 = a factor to convert from (C /yr)/(ft 3/s) to pCi/1; TC/YAX/Fage 3 of 14
fu OM12D ODCM
( Page : 28a Rev. t 3 Table 2.3-13
- Dilution Factors for Each of the Potable Vater Intakes Vithin 50 Miles of FNPP The total population dilution factor of 314 is population weighted using dilution factors for each of the potable water intakes within 50 miles of PNPP.
Veighted Dist. Fraction Dilution Dil.
Intake (Mi) D,ir i Population of Pep Factor Factor Ohio American 20 INE 38,500 1.123-2 187.7 3.98b0 Vater Serv. Co.
Conneaut 33 INE 13,500 7.43E-3 238.2 1.77E+0 Avon Is e 50 V57 99,500 5.485-2 388.5 2.13E+1 Clevelat' 35 SV 1,437,000 7.92h1 326.7 2.59E42 Fairport urbor 7 VSV 3,200 1.76E-3 154.2 2.71E-1 Lake County East 3.5 V57 10,258 5.65E-3 107.4 6.07E-1 Lake County Vest 15 V5V 85,000 4.68b2 220.0 1.03E+1 Ohio Vater Serv. 10 V5V 60,000 3.30b2 181.9 6.00 b0 Fainesville 7.5 USV 27,000 1.49b2 159.3 2.37E+0 Kant County 50 NV 42,000 2.31b 2 388.5 8.97E+0 &
Vater Supply TOTALS 1,815,958 1.00E+0 TCtfAL D.F 3.14E+2' Dist, Lir Population - distance, direction, and population values obtained from the ~.989 Engineering Report " Lake Erie Pot'able Vater Facilities and intakes Within 50 Miles of FNPP* (Ref. S0-11551 *E").
Fraction of Population - The ratio of the population receiving drinking veter from that intake to the total population number for all drink.ing vater intakes located within 50 miles of FNFF.
Dilution Factor Values obtained from the Perry- Environmental Report -
Operating License Stage, Table 5.1-10 ' Annual Average Dilution Factors for Lake Vater Intakes Vithin 50 Miles of FNFF" and O&R Page 2.1-2. Lake County Vest dilution factor per interpolation. Eant County Vater Supply dilution factor was estimated. ,
The Veighted Dilution.Factoe - (Fraction of Population) x (Dilution Factor),
based on the population for anch. drink.ing water intakes the sum of which is to be used as the potable water total population. dilution. factor for radi'osctive liquid affluent releases from FNFF.
l l
TC/VAX/Page 4 of 14
p~" , ON12D: ODCN Page : 28b Rev.y 3 I Table 2.3-14 .
Dilution Factors it,r the Fish Ingestion Fathway Individual Grid Locations The total population dilution factor of 77.4 is catch distance and volume weighted using dilution factors at those locations. Fish harvest is based on Ohio Department of Natural Sesources the total angler catch (1987 annual) values for Lake Erie within 50 mile of FNFF.
No. of Fraction Dist. Dilution (FracFish)x Crid Fish of Fish laij, Factor (D11 Factor)-
617 52823 3.91b7 29 92 3.60E+0 618 76004 5.633-2 36 100 5-63E+0 714 101522 7.595-2 9 52 3.965+0 715 10743 7.95E-3 9 52 4.135-1 716 19817 1.473-2 -11 56 8.21b1 717 73401 5.435-2 24 83 4.515 0 718 118676 8.78b2 33 95 8.34bo 809 0 0.00E+0 48 115 0.00E+0
, 810- 3953 2.935-3 39 105 3.075-1 811 13648 1.01b2 30 92 9.295-1 g 812 33923 2.513-2 12 78 1.96b0 iS 813 182663 1.351-1 13 61 8.25E+0 Sie 164369 1.22b1 4 34 4.14E+0 909 80753 5.98L2 -50 116 6.93b0 910 43800 3.245-2 42 110 3.57b0 911 117430 8.69b2 33 95 8.265+0 912 256529 1.905-1 24 83 1.585+1 TOTAL 1551054 1.00E+0 TOTAL D.F. 7.74E+1
, No of Fish. Total angler catch (1987 annual) for each grid leontions per lettar from Michael E. Rawson, Fairport Fisheries Essearch- Station, Ohio Department of Natural Sesources to Eichard Cochnar (6/20/88). i
, Comaarcial harvest data were not used as they were differentiated by harbor location only, not by asographical grid location.-
Fraction of. Fisk - The ratio of the fish caught in that. grid to the total.
nuabac of fish caught in all. grids located within.50 miles of FNFF.
Distance - Distance to- the center of that grid from FNFF, in miles.
Dilution Factor - Derived, for the appropriate distance (center of each grid), from annual average dilution factor data (non-adjusted), per Ferry Environmental Report - Operating License Stage, Table 5.1-10 " Annual
? Average Dilution Factors for Laka Unter Intakes Within 50 Miles of FNFF'.
(Fraction of Fish) x (Dilution Factor) The weighted dilution factor, based on. catch, for each gridt the sua of which is to be used as the fish
-ingastion total population = dilution factor for radioactive liquid-eifluent releases from FNFF.
TC/VAX/Page 5 of 14-
1 Table 5.1-1 MIPP ltediological Environmental Monitoring Fw Analysis g Type Frequency locations
- Sampling Frequency
} Sample Media h *
- l' Airborne Continuous sampler operation Radioiodine Weekly following
$radiefodine 4, 3, 4, 5, 6, 7, 35 with collection weekly or as I-131 canister change
,,and Particulates Weekly following required by dust loading, aparticulates whichever is more frequent Gross Beta (s) filter change d'
Z c-o Composite, by Isotpic(b) location quarterly Continuous sampling, one TID cama Dose Quarterly Direct Radiation 1 through 24, 35 41, 42, 43, 45, , 36 excharged quarterly Annually (3 TLDs/ location) Continuous sampling, one TID Gamma Dose 53, 54, 55, 56, 58 exchanged annually Quarterly or Continuous sampling, one TID r.m== Dose under emergency exchanged quarterly or tnier emergency situations situaticus B-3 Composite, by Camposite(c) location, quarterly F 'I blVaterborne surface 28, 34, 36, 59, 60- Gross Beta Monthly 66
(.gldrir11ng(d)
Gasma Isotopic Monthly l
l E7E l Sealannually - Spring ard r* - Isotopic Semiannually . <Q g Sediment from 25, 26, 27, 32, 63 - l 64,65 Fall as veather permits l
)& shoreline Quarterly Gamma Isotopic Quarterly "%o SollI *I ' 1, 2, 4, 6, 12, 14, Sr-89/90 h l
18, 20 l t f See footnotes at end of table.
m____ ___
~ - _ _ _ _
Tabla 5.1-1 (Cont.)
Ph7F Radiological Envirmeental Monitoring Program f Analysis Type Frequency locations
- Sampling Frequency Sample Media
<! 4 I-131, Monthly & N, lhIr.gectg 29, 31, 47, 51 Monthly when animals are not 9 y Milk 57, 61, 69 on pasture Gama 8-5 g Isotopic I-131, Semimonthly Semimonthly when animals are
[ on pasture r- ,
l es Isotopic 5 c= - Semiamually l 25, 32 Semir : ally - Spring and )
Fish Fall as veather permits Isotopic (edible portion)
Food Products I-131, Monthly during (* A fu 39,62,67,10 Monthly Curing growing season 1 9 yl Bunan Consw m i<a c= - growing season i Jh Isotopic Annually, location determined by I-131, Amually ,
Animal Consumption 29, 31, 47, 51, e - Isotopic fe 57, 69, 61 annual milk animal and 8 l@1 hg garden census I-131, Monthly during 6, 7, 33, 44,*48 Monthly during growing season j- Vegetation Camma Isotopic graving season r- Isotopic, Monthly PrecipitationI 'I 3,4,6,7,12,35 Monthly Gross Beta, f7@
Tritius . *QC 9
"8 Sampling locations were selected on the basis of local ecology, meteorolegy, Other factors considered physical charactizations were applicable regulatory of the region,h and demographic and land use features of $be site vicinity.
Fuldelines (Appendix I to 10cTA50, Regulatory Guides 4.1, 4.2, and 4.8), population distribution (froe environmental report), ease of access to sampling stations, security, future program integrity (e.g., not placing TLD's near areas under constructic or where the potential for vandalism is high, and the NRC Radiological Assessment Branch Tecimical In addition, Position on radiological environmental monitoring as revised in Revision 1, Novuber 1979 (reference 1).
certein locations where PhTP operations are unlikely to affect levels of radiation or radioactivity were selected as control locations.
= y Tabla 5.1-4 (L t.)
$ sapling locations and Media for Ehvirerseestal Monitorist Perry lameleer Power P! suit Imcation Distance Description' (Miles) Direction Media III Ito.
LE i
15 Madison Substation (Eagle Street), On utility pole inside 5.1 ESE TID f
l . substation fasce. -
i
-. 16 Dayton paed (aerth of Interstate 90) en ple $572203 en left after 5.0 SE - 7ta
- '* dirt drivesey which is just after the shery lef t on Dayton Road lft-3 Chadwick Boed (cul de see south of Interstate 90) en pole 5.2 SSE TID Z 17 3276222/1183011; last po2e en left 18 alair Road eqs pie on just af ter read enkes 90' degree lett curve 5.0 s Tin, so doun hill bendiss teueres river 19 Lane Road and South Ridge Seed en pie OfC5648,100 feet north of 5.3 SSV TID intersection-20 Nursery Road at Soute 2 ....; r , on ple 9828976 across frun 5.3 SW 7tD, so
^
entrance to paute 2 21 Bardy Road at Painesville Township Park, en pie 0378345, east of 5.1 vsv Tta park entrance 22 Painnsville, og south side of Ilmin Street across from Evergreen 6.9 SW TID Cemetery on tree with elitte det 60 feet east of pole 90eEG296 23 Fairport partor (BI hE Street and Itew Street), an pole on meer 7.9 USE Tra substation facinE street 24 St. Clair Avenue Substatlan (Cuatrol), in IIentor, en rest fence 15.1 SW TID coreer peer railreed $recke -
25 FMer Discharse 0.6 left SED, FSE 26 offshore at poetrd, vicinity of GInto Ester Service Cow Intake 4.2 DE SED Offsbere, yic$nity of Fairport Barbec Ester Supply Systen Intake 7.9 vst sus 4,g l 27 28 (Ashtabula (Control), CEE Generstlag Station Intake) 22.0 1.3 EME ESE WM IEJt, F5 I ,E9. *@ U 29 Milk Farm, Waltes residence, datloch Reed, Perry
.9 "go
- E I .
-mum"" -rm ^-m e + e-o--m.-%e.m c.m,y,,,,, , , _ , , ,
Tabla 5.1-4 (Cont.)
Sampling locations and Media for Environmental Monitoring Perry Nuclear Power Plant
- e Distance Q Location (Miles) Direction 'Ledia III 4 No. Description k
M
$ *(l 30 Deleted lNO Milk Farm, Hoffer residence, Antioch Road, Ferry 1.4 ESE MIK, FS
, 31 m 15.8 VSW FSH, SED 32 Mentor-on-the-4 ks (Control) MIK, FS Deleted (Brookglen Taru [ Con $rol), Greig Residence, 10.2 S
- fyl 33 Callow Food, kroy) 34 FNPP Intake 0.7 NW FTR Site Boundary, porth of transmission line, next to transformer, 0.6 E AFT, AI, TID, 35 follow tree line 7, PR VIR, UD lj, 36 Fainesville Water Supply Intake 3.9 VSV Deleted (Ohio Water Service Co, pump station, Green Road, Madison) 4.1 ENE FIR 1.-
3 37 38 Deleted (Seith Tara, 2861 Antioch Road, 0.5 alles from North 1.1 E FF [j, Ridge Foad 39 Goldings Farm Stand, 3515 North Itidge Road 1.8 SSV FF i(.;
1.1 E FP T l 40 Deleted (2767 Antioch Road) TlD Clark Road one-half mile from Center poed, on pole 1.1 SV 41 Ho. 561969, south side of road Paraly Road, one4alf alle free Center pond, located on 0.8 5 TID 42 utility pole No. 382923 near southwest corner of plant fence TIR 43 Parmly Road, approximately 0.6 miles from Centa.c Road next to 1.0 SSE stream, $ree with white dot 50 feet from oed, left of stream p5 l 44 Parmly Road 1.0 SSE Y 0.9 SSW TID 45 Clark Road, approximately 0.2 alles from Center Road on bole No. 561960, south side of road FE T'j l 46 Deleted (Milk Farm, Rrill, Mocth Ridge Rand) 1.5 SE PEK, FS 5Q C MIK, FS :
6.5 E E' 47 Milk Farm, Zoldak residence, Middle Ridge Road, Nadison
'. wmo t
F : e,.
- E ,
Tabla 5.1-4 (Cont.)
Sampling incations and Media for Envirweental Monitoring Ferry Nuclear Power Plant- ,
incet5on Distance Description (Miles) Direction Media III N . ro. -
=
' 48 . Antloch Road 1.1 M V p 0.8 tat l
E
~J 49 Deleted Garden, 4385 tackwood Road-Deletion FP
$ g!IQ_ ,
j l hjl50 51 RettgerFarm,(Control),Re(tgerresidence,Painesvi?le-Varren' 9.6 S htK, FSh o Road,14roy l 4
, a Deletion ' l N,1 J 0.5 VSV Tim 1
[*- p l52 53 Neff retkins, Co., utility pole 50' east of driveway, 200' south of fence ,
54 Bale Rd. School, pole No. 395910, 2nd from corner on tae 4.6 SV T1D l 55 Ferry School District Offices, on pine in tree line by 2.5 S TLD baseball diamond 56 Madison High School, 1st c1 tsp of pine trees from library 4.0 ESE TID 57 Butler Residence, 6244 krth Ridge Road 8.5 E PRK, FS
.p iS8 on tree la PI( corner of Nur wry off Antioch Road, 0.8 DIE TID 9I approximately 100 yards north of location 48 l
59 4.0 ENE m '
!ake Lake shorelina; shoreline atal porth retirec.n4 boat'{of Greer, pond m
$ 60 61 the Milk Farm, l teller r*.sidence, Dewey Road, Madison launch area in Ferry Park 1.0 7.4 VSV SE MIK, FS 1% l62 Shreve farm, 2431 Antioch Road, commerical produce fara 1.2 ENE FP lg, 3 lg, g 63 Ninor stream outlet at take Erie 0.1 Net SED ,
Ts- 64 Northwest lepc-..? t outlet at iaka Erie - 0.1 NV SED 6 65 Major stream outlet at take Erie 0.2 V SED 66 Deletion 1 67 Sabo Farm, 5674 Morth Ridge pond 2.9 E m
FP b Ohio American Vater Company-Ashtabula Flant (Control) 19.5 Erst i,' 68 18.7 MIK, FS p 69 70 John Rhodes Farm (Control),11640 Sper2y Road,Chester Township Route 6 Chardon (control) BMI faru Stand 16.2 SSU SSV FF lh. E'j d.Mof (1) AI - Air Iodine IRK - Milk SO - Soil API - Air Parilculatg FF = Food Products TID - Ambient Ca=== Dose Rate "30 4't. FS -Feed /S}1 age PR - Precipitation V - Vegetation h ,
8 FSH - Fish SED - Sediment M - Vater.
~
-va -_ _ _ _ _ _ _ _ _ _ _u________
LEGEND: ?
N NNE ~
NNW-i / NE HW L. ^ $ "4 DIRECTION STAllON H0.
SW ,
s APT.N.TLD N ^"*"I'"' "'"" "' I Q ENE 7
a TLD E lpI l N
y WHW ,
S TLD ESE 25f Lockwoodi R $3E f*
.a sa s2 ,
TLD.PR,50 WSW C PERR HUCLEAR /! 32 NHW o PGWER PLAN e 5 f.[8J6$ 25 SED.FSH ESE
- uitM rEEaiSitsoE f* 65 a, E 2, W HILES j $4E -
MILM, F EED/ SILAGE ESE Me H 5 31 s12 WIR HW 34 lg.3
,.- a. 's 38 '
31 SSW
- TLD
[j o I
p 4e J
) \ 45 48 VL ENE ^~9 g
j ,,
, ENE g.
3 g 58 TLD
- re a gg@
ns
- y naomLoacAL Envmonuf gi AL won:Tonmo rnoon Au S AMPLlHO.LOCAitoHS Aff 80Xltf AT8LT 2 MrLEs enou site "$
TEMMY HUCLEAR FGyrER PLANT x THE CLf yELAND Et ECTMC 8LtummAimo courany FIGURE 1
,)l l
'L #
N i g I's ( (5 O l l g- Em
_ I W WEWW " EE i
T C EE E E SE SS W WSWS N SS sEwS*ENSE a- ,
Oj. ' ' E NNES EE S E S S SWSWEWW " E E R - ,'
I D
E E E .
G G G WT t Y .
A A A As N O R L t
D/D I D D
/
OR M A L TT LT E E E RF O I
T NN E E F5 D o EE .E F 1 C 0 O F F G1 MW R E l S S , . Y G M A 8 . I ! E K
N9 I
N N TDDDDDDDDDDDDD
. . T Ra lod"KRK A L T LI I L L E E tL I P A T MWMF O I
L P L LLL L LL ATTTTTTT TRTTSSwMi1 T I t o L A P N O N R I
E M
- 2 H O D N W Y L WLU 2 N O LE O L I 1 1241 5s7 e5 sS"75 S 8 8 B 8 7 A AT P Z E 1 i1 88 t i 0 2 21 II 222 878 2 3 Y C I
T 4 T R NI M R I U
G A T
EX A R T G E S MO E L C F O
L NR P C E E E OP U E L
~
N S mA N D
VS E E E NN Y N
" E EO R A E
R L
. -'_ - A s LT w N
- 7 ib A a.Q, U ; j\*
E E ^
AA P V C
s O C I r
,$I QL L C s.
.I .
i OG
{yg - j .I N
RN L E
H -
, . 7[-
e D P T AMA k - f R 3 7j [
3 1
g
- 4
[*
W g
u \ W e s
E E
N N
5 pE A
' 4.[ 5 I
Y .
s s
m M
o 2 h 0~
\-
1
- /' - I
_ .@, g
. t f .
, i s ,
t n
- ~ I s
N u g 8 8 4 3 8 S .
p/ k 1 _
.[" 5 8 l 3
" i W w 6 g p
f I'
'JJ W 1
s s
3 N L* ,
N 1 2
. 0 2 f
's ~:
e S
i
~
P .
[
- p3, '~~
2 /j .
dW oc SW F N -
W W W N S I W W
- g"M"
< O g 5 lli : ll !'l l lljlfrf ;f l!lll i
m.
4.
4 WNW c-. EM i.ane enia g ,,,s._ -
, ' ,,,,,,,A a 1***** .n
. X 0 ... ,," .
5 N ..
Nm
.t , , , , , , ./ ,
.w g,
W aO
) ,: , .. - -a .
. g e E
=_y[L, g ~,,- y a g,', .
- io .- ..
w,. - Miles ' .- se,_
- 1 s ,,, ,, ,,
~'
X m.J.*D"~
in. t.c. '6.', ,,, .
. o r. -4 , . .. ~ , ,,,,
%='
e 1,",,i/. p Tydp "' ;
4'.ys_,A s = ._
/ i
.;: _e wew f
,';ESE i
,- .i
, 70 ,, t- _.
g , i , ,,_~ t
av t Euci . y ..,,
( "O
- n. ,
- d4 ae 1 Cher n ne 'l Wdow t .
' . a. ' " ',
.a %g* #e, e " i "M_ __ k g LN~F _
5;;,,, +
- c ~
t : .. , -
n .. i.r- ,
0 8 10 15 20 MILES 5
LEGEND; se o plRECTION 1/8".1 MILE *c 4' 5 STATION NO. MEDIA s Ary,Al,TLo,P8,so,yl. ssw "
naciot oolcAL EMvinoNMENTAL MONITORING PROGRAM SW CON 1MOL S AMPLpeG LOCAT:ONS w*O 24 TLD GRE ATER THAM 10 MILES FROM SITE
- g 32 WSW x
- (1% . $$DiMENT PERRY N'JCLEAR POWER PLANT S
51 PKl(' [EEDt5K AGE THE CLEVELAND ELECiniC ILLUMINATING COMPANT
- FNa ,,,,,,,
W1R as pipc, rstorsnAna ssw to FP ssw v.w.--.ve ,.,.,w,i.w,,,-. . ,
. .,.y.,,,,em w-. = - -. 'w,-. *g. e s.w,-w---,,eee,r-e-. v w-e . a w- ,u.w... +w,w1 n+ %.s--m -,..,,.r-.-~ = - -
o OM12D: ODCM Page : 113 - LAST
['. Rev. 3
.J REFERENCES (Corir.)
- 11. Regulatory Guide 4.15. " Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Streams and the Env ' consent," U.S. Nuclear Regulatory Commission, Vashington, D.C.
201 i, February 1979.
- 12. U.S. Nuclear Regulatory Commission, " Branch Technical Position,"
Revision 1, Vashington, D.C. 20555, November 1979.
- 13. Perry Nuclear Power Plant, Unit 1 and 2, "Pinal Safety Analysis Report," Amendment 14, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, August 1984.
- 14. Perry Nuclear Power Plant, Units 1 and 2, " Environmental Report.
Operating License Stage " Supplement 3. The Cleveland Electric
- Illuminatin: Company, Perry, Ohio 44081, November 1981.
- 15. Perry Nuclear Power Plant. Units 1 and 2, ' Radiological Environmental Monitoring Program Manual." The Cleveland Electric ILit.ainating Company, Perry, Ohio 44081, February 1985.
( 16. ' Midas User's Manual, for the Cleveland Electric Illuminating Company, Perry Nuclear Power Plant," Pickard, Love and Garrick, Washington, D.C. 20036, July 1983.
- 17. Kocher, D.C., " Radioactive Decay Data Tables." Technical Information Center, %5. Department of Energy, Springfield, Virginia 22161, September 1985.
18.. 1989 Engineering Report ' Lake Erie Potable Vater Facilities and Intakes Vithin 50 Miles of PNPP, (Ref. 50 ,11552 *E*).
19 Perry Environmental. Report operating License Stage, Table 5.1-10
" Annual. Average. Dilution Factora for Lake. Vater Intakes Vithin 50 ,p.
Milas of PNPP and QUL Page 2.1-2. ye
- 20. PNPP' Ohio Power Siting" Commission application of August 1974, h Appendix.1304-C-2, Table IV-A-2.
.L Total Angler Catch (1987 annual) for Each Grid locationi per letter From: Michael R Rawson, Fairport Fisheries Research. Station, Ohio Department of. Natural Resources (6-20-88). .-
I TC/VAX/Page 14 of 14
. ..