PY-CEI-NRR-0590, Semiannual Radioactive Effluent Release Rept,1986:Quarters 3 & 4
| ML20211P404 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/31/1986 |
| From: | Edelman M, Hyster M, Tadych R CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PY-CEI-NRR-0590, PY-CEI-NRR-590, NUDOCS 8703020357 | |
| Download: ML20211P404 (136) | |
Text
{{#Wiki_filter:-- i THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NCCLEAR POWER PLANT UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1986: QUARTERS 3 AND 4 e. Approved By _ bMMb
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TABLE OF CONTENTS Page Introduction ...................................... 1 Radiological Impact on Man ........................ 2 Supplemental Information .......................... 4 Liquid Effluents .................................. 6 Gaseous Effluents ................................. 8 Solid ~ Waste ...................................... 10 Meteorological Data .............................. 10 Abnormal Releases ................................ 10 Applicable Technical Specification Requirements .. 11 11 V
c ATTACHMENTS ' l Attachment 1: Radiological Impact on Man (Dose Summaries) Attachment 2: Technical Specification Limits Attachment 3: Liquid Effluents Attachment 4: Gaseous Effluents Attachment'5: Solid Waste Attachment 6: Meteorological Data Attachment 7: Process Control Program Changes Attachment 8: Offsite Dose Calculation Manual Changes Attachment 9: Major Changes to Radioactive Waste Treatment Systems Attachment 10: 1986 Land Use Census 111
INTRODUCTION This Semiannual Radioactive Effluent Release Report (SRERR), for the period of July 1 through December 31, 1986, is submitted in accordance with Section 6.9.1.7 of Appendix "A" (Technical Specifications) to Perry Nuclear Power Plant (PNPP) License No. NPF-45 (5% power license) and NPF-58 (full power license -- issued November 13, 1986). It is designed to meet the requirements of Regulatory Guide 1.21, as applicable to the PNPP Technical Specifications. Portions of the Technical 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 (RETS). All liquid and gaseous radioactive releases to the environment during this reporting period were sampled and analyzed in accordance with the requirements of the Technical Specifications. All effluent releases were within the concentration and release limits specified in the RETS. Calculations and terms utilized in this report are those outlined in the PNPP Offsite Dose Calculation Manual (ODCM). 1
m - RADIOLOGICAL IMPACT ON MAN Sampling and analysis of liquid and gaseous effluents was performed in accordance with the frequencies, types of analysis, and Lower Limits of Detection (LLD) outlined in the PNPP Unit i Technical Specifications. Radioactive material was detected at low levels in several liquid and gaseous effluent samples analyzed. Dose calculations, using measured effluent flow and meteorological data, resulted in dose to individuals at levels well below 10 CFR 20 or 10 CFR 50, Appendix I limits. Direct radiation resulting from plant operation did not contribute any measureable dose to members of public for the reporting period and as there are no other nearby uranium fuel cycle sources, 40 CFR 190 limits were not exceeded. Summaries of maximum individual and population doses are given in Attachment 1. Note that with no radionuclide activities input, the dose calculation computer code uses arbitrarily preselected defaults for gaseous pathway receptor direction and distance. Technical Specification 6.9.1.7 requires assessment of radiation doses from radioactive liquid and gaseous effluents to members of the public while onsite. These onsite doses are assessed relative to offsite dose values, with adjustment for appropriate dilution, dispersion, and occupancy factors for onsite activities. The onsite liquid effluent pathway of concern is shore exposure while fishing along the Lake Erie coast. Occupancy is assumed to be 60 hours / year and the dilution factor for the point of exposure is 10. Ratioing this exposure pathway to doses calculated for offsite locations yields the following maximum onsite, dose values. Fourth quarter onsite dose values are zeros because all activity released was pure beta emitting isotopes which do not contribute to shore exposure dose. ONSITE DOSE FOR LIQUID EFFLUENTS Total B2dz Organ Quarters 3 & 4 2.5 E-11 mrem 2.9 E-11 mrem (skin) Quarter 3 2.5 E-11 mrem 2.9 E-11 mrem (skin) Quarter 4 0.0 E+0 mrem 0.0 E+0 mrem 2
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 assumed to be 60 hours per year. Accounting for this and the difference between annual average dispersion values for the onsite point of concern, 6.6 E-5 s/m cu, and the highest offsite, i.e., site boundary value, 4.2 E-6 s/m cu, (a unity occupancy factor is used for this location), the following maximum onsite dose values are generated: ONSITE DOSE FOR GASEOUS EFFLUENTS Total Bodr QIgan Quarters 3 & 4 9.9 E-5 mrem 7.8 E-5 mrem (skin) Quarter 3 3.5 E-8 mrem 1.2 E-6 mrem (bone) Quarter 4 9.9 E-5 mrem 7.8 E-5 mrem (skin) Average total body dose to individual members of the public is determined for the popualtion that lives within fifty miles of the plant for gaseous effluents (2.42 E6 persons) and the popualtion that receives drinking water from intakes within fifty miles for liquid effluents (2.37 E6 persons). These doses are calculated using the total population dose figures found in Attachment 1. AVERAGE INDIVIDUAL TOTAL BODY DOSES Gaseg Liquids Quarters 3 & 4 5.1 E-7 mrem 2.2 E-7 mrem Quarter 3 4.6 E-7 mrem 8.7 E-11 mrem Quarter 4 5.1 E-8 mrem 2.2 E-7 mrem l l ) 3
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 1 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. The Technical Specification limits are listed in Attachment 2.
Maximum Permissible Concentrations The Maximum Permissible Concentrations (MPC) in liquids are those outlined in Technical Specification 3.11.1.1 (10 CFR 20, Appendix B, Table'II, Column 2, with the lower of the soluble and insoluble MPC being used; for dissolved or entrained noble gases, concentrations are limited to 2 E-4 uCi/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. Avgrane Energy Average energy requirements for radioactive effluent mixtures do not apply to PNPP Unit 1 Technical Specifications or Offsite Dose Calculation Manual. Usamurements and ADDIQXimations of Total Radioactivity Analyses of specific radionuclides in effluent samples are used with effluent path flow measurements to evaluate the radionuclide composition and concentration of effluents. 4
Batch Releases Liquid effluent ~ releases were continuous, runs of Emergency Service Water (ESW) loops A and B, es well as batch, liquid radwaste discharges. All gaseous effluent releases were continuous. LIQUID RELEASEE July 1 - September 30, 1986 Batch Continuou.a Number of Releases 142 62 Total Time of Releases (min) 2.53 E4 1.48 E5 Maximum Time for a Release (min) 3.29 E2 1.82 E4 Average Time for a Release (min) 1.78 E2 2.39 E2 Minimum Time for a Release (min) 4.6 El 6.2 El Average Effluent Stream Flow 2.46 E5 2.23 E5 During Periods of Release (1/ min)
* - The total of ESW Loop A (8.56E4 min) and ESW Loop B (6.26E4 min)
October 1 - December 31, 1986 Entsh continuoua Number of Releases 99 49 Total Time of Releases (min) 1.72 E4 1.12 E5 Maximum Time for a Release (min) 2.27 E2 1.63 E4 Average Time for a Release (min) 1.73 E2 2.28 E2 Minimum Time for a Release (min) 1.0 EO 7.2 El Average Effluent Stream Flow 2.52 E5 2.50 E5 During Periods of Release (1/ min)
* - The total of ESW Loop A (7.00E4 min) and ESW Loop B (4.17E4 min) 5
LIQUID EFFLUENTS i For the! third quarter of 1986 there were 142 batch and 62 ' continuous releases. Batch release total waste volume for the third quarter was 1.40 E7 liters; total continuous release waste volume was 7.60.E9 liters; total plant discharge during periods of release was 2.91 E10 liters.
~
For the fourth quarter of 1986 there were'99 batch and 49 continuous releases. Batch release total waste volume for the fourth' quarter was 9.71 E6 liters; total continuous release waste volume was 5.06 E9 liters; total plant discharge during periods of release was 2.29 E10 liters. Summaries of the radionuclide total curie activities, average diluted concentrations and percentage of MPC (in Regulatory Guide 1.21 format) are included in Attachment 3. There,was no detectable activity in the majority of the liquid effluent releases for the period covered by this report. If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that the radionuclide was not present at a level greater than the Lower Limit of Detection (LLD) of the instrumentation used. In all cases, these LLDs were less than the level required by the Technical Specifications. The following are typical LLDs: Radionuclide LLD (uCi/mi) Mn-54 2.4 E-8 Fe-59 5.8 E-8 Co-58 1.9 E-8 Co-60 3.4 E-8 Zn-65 ~4.6 E-8 Mo-99 2.1 E-7 I-131 2.3 E-8 Cs-134 2.3 E-8 Cs-137 2.6 E-8 Ce-141 3.2 E-8 Ce-144 1.3 E-7 Sr-89 3.0 E-8 Sr-90 3.7 E-8 Fe-55 5.7 E-9 H-3 4.6 E-6 Gross Alpha 6.0 E-8 6
r. 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'others are interlaboratory comparison results. Discharge and dilution volume (flow rate instrumentation) error is assessed using loop instrumentation accuracy terms. Gamma Analysis 10% H-3 Analysis 8% Sr-89/90 Analysis 10% Fe-55 Analysis 21% Gross Alpha Analysis 4% Service Water Volume (Dilution) 31% Emergency Service Water Volume (Discharge) 25% Liquid Radwaste Volume 1% 7
GASEOUS EFFLUENTS Summaries of the radionuclide total curie activities and average release rates (in Regulatory Guide 1.21 format) are included in Attachment 4. There was no detectable activity in the majority of the gaseous effluent samples for the period covered by this report. If a radionuclide was not detected, zero activity was used for that isotope in' dose calculations. A zero activity indicates that the radionuclide was not present at a level greater than the' Lower Limit of Detection (LLD) of the instrumentation ased. In all cases, thes't LLDs were less than the level required by the Technical Specifications. The following are typical LLDs: Radionuclids LLD (uCi/ml) Kr-87 1.7 E-8 Kr-88 2.3 E-8 Xe-133 1.8 E-8 Xe-133m 5.3 E-8 Xe-135 6.4 E-9 Xe-138 1.0 E-7 Mn-54 2.7 E-13 Fe-59 5.6 E-13 Co-58 3.2 E-13 Co-60 4.6 E-13 Zn-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-13 Ce-144 1.5 E-12 I-131 2.8 E-13 I-133 4.9 E-13 f Sr-89 3.8 E-14 Sr-90 6.8 E-14 H-3 3.0 E-10 Gross Alpha 5.4 E-12 8
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% Sr-89/90 Analysis 10% Gross Alpha Analysis 4% Sample Flow Rate 10% Effluent Flow Rate 9% 4 9
r SOLID WASTE There were no solid radioactive waste shipments or' irradiated fuel transported from PNPP for the time period covered by this report. See Attachment 5. METEOROLOGICAL _Q&I6 s Cumulative joint frequency distribution (JFD) of wind speed and direction for each stability class, as well as for all stability classes combined, are given in Attachment 6 for the semiannual period and for each annual quarter of the time period covered by this report. These JFD tables are the results obtained from processing hourly meteorological data collected at the PNPP site met tower. It should noted that the 1-3 mph JFD columns include wind speeds down to 0.1 mph and that hours of zero wind speed appear only in the totals columns. Periods of calm tallies include wind speeds from 0.0 to 0.7 mph. Differential temperature (10 and 60 meters) is generally used for atmospheric stability classification. AERQBMAL RELEASES There were no abnormal liquid or gaseous effluent releases during the reporting period. J 10 i
APPLICABLE TECHNICAL SPEQIEIGATION 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): There were no occurrences of inability to restore inoperable radioactive liquid effluent monitoring , instrumentation, listed in TS Table 3.3.7.9-1, to the required minimum channels operable within the time period specified in the applicable action note. Radioactive Gaseous Effluent Monitoring Instrumentation noncompliance (PNPP Technical Specification 3.3.7.10, Action b): There were no occurrences of inability to restore inoperable radioactive gaseous effluent monitoring instrumentation, listed in TS Table 3.3.7.10-1, to the required minimum channels operable within the time period specified in the applicable action note. Liquid Holdup Tanks noncompliance (PNPP Technical Specification 3.11.1.4, Action a): There were no outside temporary tanks containing radioactive liquid on the PNPP site during the reporting period, therefore, the applicable TS activity limit was not exceeded. Radiological Environmental Monitoring Program (REMP) changes (PNPP Technical Specification 3.12.1, Action c): For the reporting period, samples were obtained at their respective locations as required by the specified collection frequencies. The program underwent several changes during this reporting period. A large portion of these relate to the milk medium: two locations returned to the 11
program after drying their animals (locations 30 and 31) and three were added (locations 29, 51, and 52). Vegetation sampling was added to present sampling locations 6, 7, and 35 and started at new locations 44 and 48 to supplement milk sampling. Also, locations 49 and 50 were added for food products and TLDs.were added as locations 53, 54, 55, and 56. See Attachment 8, Offsite Dose Calculation Manual Changes for details. Land Use Census findings (PNPP Technical Specifiestion 3.12.2, Actions a and b): The 1986 Land Use Census was completed in November 1986. The findings include three new garden locations (at approximately the same distance frqm the plant as the ones observed last year); one new milk animal location, three identified last year no longer have milk producing animals; and seven new non-dairy animal locations, approximately half of the 23 locations identified last year still have their animals. See Attachment 10. Process Control Program changes (PNPP Technical Specification 6.13.2): There were several changes to the Process Control Program made during the reporting period. These changes were made in the form of temporary changes (TC). The following changes were made by TC-3 &
- 4. TC-1 & 2 were incorporated into TC-3 & 4 (TC-1 incorporated reference changes; TC-2 provided
, increased quality control). These changes will be incorporated into the PCP in the next formal revision. See Attachment 7.
Page Changt 11 Addition of listing for new attachment 111 Inclusion of 10 CFR 50.59 Applicability Check 2 Addition of HIC definition 4 Elaboration on dewatering process; change of procedure reference 5 Elaboration on dewatering process 7,8 Update of equipment room layout 10 Addition of reference to dewatering; discus-sion of newly incorporated attachment 11 Elaboration on dewatering process; change of procedure reference 12
Enan Ghanan 14 Elaboration on dewatering process 15 Inclusion of added attachment listing 17 Reference change 18 Addition of dewatering reference 18a,b New attachment designed to ensure appropriate documentation Offsite Dose Calculation Manual changes (PNPP Technical Specification 6.14.2): Changes to the Offsite Dose Calculation Manual were made via TC-2, 3, & 4. REMP sampling changes covered by TC-2 were sent with the last Semiannual Radioactive Effluent Release Report but are incorporated here as well. TC-5 was made just after this SRERR period but is included as it affects this report's contents. These changes will be incorporated into the ODCM in the next formal revision. See Attachment 8. Enan Ghanan i Added typed effective date viii inclusion of 10 CFR 50.59 Applicability Check 2 Change to location of text 2a Incorporation of Technical Specification change; text overflow page 4,5,6 Flow trip unit part number (MPL) change; LRW setpoint methodology change to allow operational flexibility and minimize spurious alarms 6a Text overflow page 8 Text change to reflect continuous nature of ESW releases 11 Correction of typographical error 30 Incorporation of Technical Specification change 30a Text overflow page 33 Default gaseous effluent flow rate changes 33a Text overflow page 37 Correction of typographical error 73 Inclusion of " Dose to Members of the Public While Onsite" section 73a Text overflow Page 82, REMP sampling and location changes 84-88 108 Incorporation of Technical Specifiention chango 109 Incorporation of Technical Specification change; inclusion of accidently deleted text 13
Major Changes to Radioactive Waste Treatment Systems (PNPP Technical Specification 6.15.1): There was one major change to a radioactive waste treatment system during this SRERR period. The change involved incoporation of a dewatering system to the solid radwaste system presently in use. See Attachment 9 for complete details. 14
4 Attachment 1 Radiolonical Innaet on Man (Dome S"==="ies) Quarters 3&4
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES I 1 8 h SASEOUS AIR 86711-861!31!486 7 1 1-861 31 4 APPLICABLE ESTIMATED AGE LOCATION X OFLIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MR) (MREM) (M) LIMIT ___. -- --. D) (TOWAR LIQUID TOTAL BODY 3.94E-06 CHILD RECEPTOR 1 1 3E-04 3.0 LIQUID BCNE 2.31E-05 CHILD RECEPTOR 1 2.3E-04 10.0 NOBLE GAS AIR DOSE 1.48E-02 273. NW 1.5E-01 10.0 (GAMMA-MRAD) NOBLE GAS AIR DOSE 7.66E-03 273. NW 3.8E-02 20.0 (BETA-MRAD) NOBLE GAS T. BODY 3.97E-04 ALL 1450. S 7.9E-03 5.0 NOBLE GAS SKIN 7 24E-04 ALL 1450. S 4.8E-03 15 0 IODINE 1 GI-TRACT 5 24E-04 TEEN 1290. NE 3.5E-03 15.0 PARTICULATES
SUMMARY
OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS! S 67 1- 6 1h ' EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM) LIQUID TOTAL BODY 1.2E-03 -
- LIQUID THYROID 9 8E-06 GASEOUS TOTAL BODY 5.3E-04 GASEOUS THYROID 5.3E-04 .
4 e 8 e 4 e e
Attachment 1 (Continued) Radiological Imoact qn Man (Dose Summaries) Quarter J.
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS: LIQUID 86 7 1 1-86 93024 GASEOUS 86 7 1 1-86 93024 - - AIR 86 7 1 1-86 93024 APPLICABLE ESTIMATED AGE LOCATION % OFLIMIT EFFLUENT ORGAN DOSE 8ROUP DIST DIR APPLICABLE (MR) (MREM) (M) (TOWARD) LIMIT LIQUID TOTAL BODY 3.50E-06 CHILD RECEPTOR 1 1.2E-04, 3.0 LIQUID BONE 2.09E-05 CHILD RECEPTOR 1 2.1E-04 10.0 NOBLE GAS AIR DOSE 0.00Ef00 804. N 0.0E+00 10.0 (GAMMA-MRAD) NOBLE GAS AIR DOSE 0 00Ef00 804. N 0.0Z+00 20 0 (BETA-MRAD) NOBLE GAS T. BODY 0.00E+00 ALL 0. 0.0E+00 50 NOBLE GAS SKIN 0.00E+00 ALL 0. 0.0Et00 15.0 10 DINES BONE 1.14E-05 CHILD 1450. SSE 7.6E-05' 15.0 PARTICULATES
SUMMARY
OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS! LIQUID 86 7 1 1-86 93024 GASEQUS 86 7 1 1-86 93024 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM) LIQUID TOTAL BODY 1.1E-03 LIQUID THYROID 1.8E-06 ' GASEOUS TOTAL BODY 2.1E-07 . GASEOUS THYROID 1.SE-11 ,, O
Attachment 1 (Continued) Radiolonical Imnact on Man (Dome En=== ries) Quarter 4
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODSt 10 1 1-861 3124 gEID AI UAlli1211'111: APPLICABLE ESTIMATED AGE LOCATION I 0FLIMIT . (
) ( kTOND)
LIQUID TOTAL BODY 4.34E-07 CHILD ACCEPTOR 1 1.4E-05 3.0 . LIQUID 2.20E RECEPTOR 1 2.2E-05 10 0
. . . . . . . .DONE
. . _ . . _ _-06 CHILD
_....-.............. , s. 273. NW 1.5E-01 10.0 / NOBLE GAS AIR DOSE
- 1.48E-02 (GAMMA-MRAD)
NOBLE GAS AIR DOSE 7.66E-03 273. NW 3 8E-02 20.0 (BETA-MRAD) - ny '. NOBLE GAS T.B0DY 3.97E-04 ALL 1450. S 7 9E-03 5.0 NOBLE GAS SKIN 7 24E-04 ALL 1450. S 4.8E-03 15.0 .
/y 10 DINES GI-TRACT 5.24E-04 TEEN 1290. NE 3.5E-03 15.'0 ,
PARTICULATES
SUMMARY
OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS! LIQUID 8410 1 1-84123124 GASEQUS 8410 1 1-84123124 ., EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE ' (PERSON-REM) LIQUID TOTAL BODY 1.2E-04 ' ' LIQUID THYR 0ID 8.1E-06 GASEOUS TOTE 80DY 5 3E-04 . GASEQUS THYROID 5.3E-04 Y a 1 I i
ye 1. Attachment 2
'a . Technical Soecification Limits r, .hIQUID EFFLUENTS:
- Concentration 10 CFR 20 - release rate limit per Appendix B, Table II, TS 3.11.1.1 D Column 2" -
/ - 31.5 mrom total body - quarterly dose limit per ,
55 mrem any organ TS 3.11.1.2
- 13 mrem total body - annual dose limit per
$10 mrem any organ TS 3.11.1.2 GAliEAC1.ZEFJ4UENTS:
Noble Gases
- 1500 orem/yr total body - dose rate limit per
$3000. mrem /yr any organ TS 3.11.2.1
~
- 15 arad air gamma - quarterly air dose limit
, , fl0 mrad air beta per TS 3.11.2.2
.' - 110 mrad air gamma - annual air dose limit per TS 3.11.2.2 1,20 mrad air beta
+ I-131. I-133. H-2, and Particulates with Half-Lives > 8 Days
- 11500 mrem'/yr any organ - dose rate limit per
, TS 3.11.2.1 it ' -
- 47 5 mrem any organ - quarterly dose limit per
. TS 3.11.2.3 1 - 115 mrem any organ - annual dose limit per
.' TS 3.11.2.3
- * - Dissolved or entrained noble gas concentration is limited.
/to 2 E-4 uC1/ml.
i U
$4 }
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y ..,, i
)
Attachment 3 Liould Effluents l f' OUARTift 3 START DATE 84070101 4 OUARTER 4 8 START DATE 86100101 kNN ATc 6 AT[16kbkh4 EFFLUENT AND VASTE DISPOSAL REPORT d LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
/~
!! UNITS !* GUARTER ! QUARTER
- 1 3 3 4 8 A. FISSION AND ACTIVATION PRODUCTS ~
!2IR,*AltlH9k!c'
! ' 385- 3 1 2 3sE_04 ;
t 2. AVERACE DILUTED !UCI/ML 8 1.74E-09 8 1.62E-10 t i CONC. DURIN3' PERIOD ! ! ' 1 t 3. PERCENT OF t 8 MFC ! I i 2.12E-04 1 2.02E-05 3 ______ _ _ _ - - t i O B.' TRITIUM 8 1. TOTAL RELEASE ! CI 't 0.00Ef00 t' 2.47E-03 : 8 2. AVERAGE DILUTED !UCI/ML t 0.00Ef00 t 1.44E-07 '
! CONC. DURING PERIOD 8 t 8
t 3. PERCENT OF t
! MPC 8
% ! 0.00Et00 t 4 87E-05 8
8 - 1 1 C. DISSOLVED AND ENTRAINED GASES . i - t 1. TOTAL RELEASE CI ! 0 00E+00 t '0.00E+00 t t 2. AVERAGE DILUTED !UCI/ML 8 0 00Ef00 1 0 00E+00 t 3 C0NC. DURING PERIOD 8
! ! 3 .
! 3. PERCENT OF ! - Z !i 0.00Ef00 8 0.00Ef00 !
~
t FC
- t t .
s - D. GROSS ALPHA RADI0 ACTIVITY . t 1. TOTAL RELEASE t CI i 0.00Ef00 8 0.00Ef00 t l < i t E. VOLUME TO WASTE RELEASED
! ! LITERS : 7.61E+09 3 5.0TEt09 8 '
l ! (PRIOR DILUTION)
! i l
F. VOLUME DILUTION WATER ! LITERS ! 3 t USED DURING PERIOD 8 8 2.91E+10 : 2.29E+10 t8 , 4 J
- -r,w y-
i l Attachment 3 (Continued) Liauid Effluents I i EFFLUENT AND WASTE DISPOSAL REPORT - < LIQUID EFFLUENTS FOR ALL RELEASE POINTS - QUARTER 3 : START DATE 86070101 END DATE 86093024 ' OUARTER 4 : START DATE 86100101 END DATE 86123124 CONTINUQUS MODE BATCH MODE - NUCLIDES UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
- RELEASED. : : 3 4 3 : 4 : -
! H3 : CI : -- -
- 0.00E+00 2 67E-03 :
CR51 : CI
- 5.07E 04 0.00E+00 :
.- - FE55 : CI : -
2.35E-03 2 95E 04 : l C058 : CI : ----- --
! 2.30E-05 0.00E+00 :
! TOTAL FOR : : : . : :
PERIOD : CI : -- : : 3.38E-03 2.97E-03 :
- (ABOVE) : : : : : : <
O e 0 e o D t
Attachment 4 Gaseous Effluents QUARTER 3 : START DATE 86070101 END DATE 86093024 GUARTER 4 : START DATE 84100101 END DATE 84123124 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNITS : QUARTER : QUARTER E , 3 : 4 : A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE : CI : 0.00Et00 1.23Et00 e.'
- 2. AVERAGE RELEASE UCI/SEC: 0.00E+00 1 1.55E-01 :
RATE FOR PERIOD : : : :
- 3. PERCENT OF TECHNICAL: % : 0.00E+00 0.00Et00 : ~
, 1 SPECIFICATION LIMIT : : :
B. 10 DINES
- 1. TOTAL IODINE-131 : CI : 0.00E+00 1 0.00E+00 :
- 2. AVERAGE RELEASE UCI/SEC: 0.00Et00 0.00Et00 :
RATE FOR PERIOD : : : :
- 3. PERCENT OF TECHNICAL: % : 0.00E+00 : 0.00E+00 :
SPECIFICATION LIMIT : : : : C. PARTICULATES
- 1. PARTICULATES WITH : CI : 8.04E-07 3.22E-07 :
- HALF-LIVES >B DAYS : : : :
- 2. AVERAGE RELEASE !UCI/SEC: 1.01E-07 : 4.05E-08 :
RATE FOR PERIOD : : : : ,
- 3. PERCENT OF TECHNICAL: % 0.00Ef00 : ~0.00Et00
- SPECIFICATION LIMIT : : : :
l __ __ ______________________ ! 4. GROSS ALPHA : CI : 0.00Et00 3 0.00Ef00 : - 1 RADI0 ACTIVITY : : ; D. TRITIllM 1.1. TOTAL RELEASE
- CI 0.00Et00 : 1.49Et00 :
- 2. AVERAGE RELEASE UCI/SEC: 0.00Et00 : 1.8SE-01 :
- RATE FOR PERIOD : : : :
l l : 3. PERCENT OF TECHNICAL: % 0 00Ef00 : 0.00Ef00 : SPECIFICATION LIMIT : : : : t {
)
~
Attachment 4 (Continued) Gaseous Effluents EFFLUENT AND WASTE DISPOSAL REPORT GASEQUS EFFLUENTS FOR ALL RELEASE POINTS
. QUARTER 3 : START DATE 86070101 END DATE 86093024 , QUARTER 4 : START DATE 84100101 END DATE 86123124 CONTINUOUS MODE BATCH MODE 1
____ _ _ __ ____________ i i NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :
- RELEASED : : 3 4 3 4 :
- 1. FISSION AND ACTIVATION GASES
- H3 : CI : 0.00E+00 1.49Et00 0.00E+00 0.00E+00 :
- AR41 : CI : 0.00E+00 8.53E-02 1 0.00E+00 0.00E+00 :
XE138 : CI 0.00Ef00 1.15E+00 1 0.00E+00 0.00E+00 : TOTAL FOR : : : : : :
- PERIOD : CI : 0.00E+00 : 2.73Ef00 0.00E+00 : 0.00Ef00 :
(ABOVE) : : : : : :
- 2. 10 DINES
- TOTAL FOR : : : : : :
- PERIOD . : CI : 0.00E+00 : 0.00Ef00 0.00E+00 : 0.00E+00 :
1 (ABOVE) : : : : :
- 3. PARTICULATES
- SRS9 : CI 8.04E-07 : 3.22E-07 0.00Et00 1 0.00Ef00 1 TOTAL FOR : : : : : :
PERIOD : CI 8.04E-07 : 3.22E-07 : 0.00E+00 : 0.00E+00 : (ABOVE) : : : : : : -
Attachment S
, Solid Waste Solid Waste Shipped Offsite for Disposal During Period from July 1, 1986 to December 31, 1986 Waste True Cubic Meters Curies % Error (Ci) .
N/A 0 0 0 , Estimates of Major Radionuclides by Waste Type Waste True Nuclide Abundance Curies . N/A N/A 0 0 Solid Waste Disposal Summary No. of Shipments Mode of Transportation Destination 0 Truck Barnwell 0 Truck Richland 0 Truck Beatty 0 Truck Other I e e t
'S Attachment 6 Meteorological Data .e I
e
\
Attachment 6 (Continued - Page 1 of 12) Joint Frecuency Distribution Tables - Quarters 3 & 4 HOURS AT EACH WIND SPEED AND DIRECTION-PERIOD OF RECORD = 86070101-86123124 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT60 WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 18 97 49 4 0 0 168 NNE 13 79 49 2 0 0 145 NE 26 58 49 11 0 0 146 ENE 48 68 30 12 0 0 158 E 102 76 11 1 0 0 193 ESE 152 124 36 8 0 0 331 SE 82 139 83 17 1 0 327 SSE 76 130 53 2 0 0 270 S 80 236 84 2 0 0 402 SSW 53 237 160 26 0 0 478 SW 38 186 168 24 0 0 417 WSW 19 80 121 65 15 0 301 W 24 78 212 49 4 0 367 WNW 12 72 134 29 3 0 252 NW 16 77 107 29 9 0 238 NNW 17 87 93 20 0 0 220 TOTAL 776 1824 1439 301 32 0 4413 PERIODS OF CALM (HOURS): 56 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86123124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT60 WIND SPEED (MPH) ' WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 18 9 0 0 0 27 NNE 1 24 29 0 0 0 54 NE O 13 23 3 0 0 39 ENE 2 6 7 1 0 0 16 . E O 6 2 0 0 0 8e ESE 0 2 4 0 0 0 6 SE 0 2 3 0 0 0 5 SSE 1 1 1 0 0 0- 3 S 0 1 1 0 0 0 2 SSW 0 0 3 1 0 0 4 SW 0 1 1 0 0 0 2 WSW 1 0 2 1 0 0 4 W 0 2 16 2 0 0 20 WNW 0 2 17 0 0 0 19 NW 1 13 9 0 0 0 23 NNW 0 7 6 0 0 0 13 TOTAL 6 98 133 8 0 0 245 - PERIODS OF CALM (HOURS): 0 i VARIABLE DIRECTION O , HOURS OF MISSING DATA: 3
Attachment 6 (Continued - Page 2 of 12) Joint Frecuency Distribution Tables - Quarters 3 & 4 HOURS AT EACM WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86123124 STABILITY CLASS: B DT/DZ
. ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT60 WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 8 5 0 0 0 13 NNE 1 10 5 0 0 0 16 NE 2 4 4 0 0 0 10 ENE 1 2 1 0 0 0 4 E O 1 0 0 0 0 1 ESE 0 7 5 0 0 0 12 SE 0 1 5 1 0 0 7 SSE O 2 4 0 0 0 6 S 0 2 8 0 0 0 10 SSW 0 0 5 1 0 0 6 SW 0 1 6 .0 0 0 7 WSW 0 2 8 3 1 0 14 W 0 2 32 2 0 0 36 WNW 0 12 24 0 0 0 36 NW 0 8 14 0 0 0 22 HNW 0 7 5 0 0 0 12 - TOTAL 4 69 131- 7 1 0 212 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86123124 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SPD10P DIRECTIDH:DIR10P LAPSE:DT60 WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 10 3 0 0 0 13 NNE~ 0 7 1 0 0 0 8 NE O 6 5 2 0 0 13 ENE O 3 0 2 0 0 5 E 0 0 0 0 0 0 0 ESE O 3 0 0 0 0 3 SE 1 3 3 0 0 0 7 SSE O 0 5 0 0 0 5 S 1 6 5 0 0 0 12 SSW 0 7 13 2 0 0 22 SW 1 9 21 2 0 0 33 WSW 0 5 14 6 3 0 28 ! W 0 10 24 5 0 0 39 ! WNW 1 14 26 1 0 0 42 NW 0 12 5 0 0 0 17 NNW 0 10 4 1 0 0 15 i TOTAL 4 105 129 21 3 0 262 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 c
Attachment 6 (Continued - Page 3 of 12) Joint Frecuency Distribution Tables - Quarters b %__4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = B6070101-86123124 {i STABILITY CLASS: D DT/DZ ; ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE:DT60 ! WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 7 40 31 4 0 0 82 NNE 7 26 13 2 0 0 48 NE 10 28 12 6 0 0 57 ENE 10 36 16 9 0 0 71 E 14 38 7 1 0 0 60 ESE 10 36 20 8 0 0 74 SE 9 33 32 16 1 0 91 SSE 10 34 20 2 0 0 66 : S 12 63 30 0 0 0 105 SSW 11 103 95 12 0 0 221 SW 12 83 104 17 0 0 216 WSW 3 43 71 47 11 0 175 .i W 11 52 119 39 4 0 225 i WNW 9 33 61 28 3 0 134 , NW 8 32 67 28 8 0 143 , NNW 12 39 65 19 0 0 135 TOTAL 155 719 763 '238 27 0 1903 PERIODS OF CALM (HOURS): 4 _ VARIABLE DIRECTION O HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION , PERIOD OF RECORD = 86070101-86123124 i STABILITY CLASS: E DT/DZ i ELEVATION: SPEED SPD10P DIRECTION:DIR10P LAPSE:DT60 l WIND SFEED(MPH) I WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 11 3 21 " 1 0 0" 0 33 NNE 12 1 0 0 0 17 NE 11 7 5 0 0 0 23 ' ENE 20 19 6 0 0 0 45 E 34 30 2 0 0 0 67 - ESE 29 51 7 0 0 0 88
~
SE 12 65 39 0 0 0 116 SSE 18 47 23 0 0 0 89 , S 27 96 40 2 0 0 165 l SSW 29 104 44 10 0 0 187 4 SW 16 65 36 5 0 0 142
- WSW 14 30 26 8 0 0 78
- W 10 12 21 1 0 0 44 WNW 1 10 6 0 0 0 17 NW 6 12 12 1 1 0 32 NNW 5 24 13 0 0 0 44 TOTAL 246 625 282 27 1 0 1187 PERIODS OF CALM (HOURS): 8 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3
- .- ._, - - - - - - . , - - - _ , - --a , - n-- .n, , , , , , - , - , - - - - , - , , - - - - - mv
Attachment 6 (Continued - Page 4 of.12) Joint'Freauency Distribution Tables - Quarters 3 & 4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86123124 STABILITY CLASS: F DT/DZ ELEVATION: SPEED SPD10P DIRECTION:DIR10P LAPSE:DT60 WIND SPEED (MPH)
-WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL
- N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1
'NE 3 0 0 0 0 0 3 hh 26 f
16 h 0 0 0 h 0 h 0 hh 43 ESE SE 14 25 1 0 *0 0 40 SSE 14 22 0 0 0 0 37 S 14 . 40 0 0 0 0 54 SSW 7 21 0 0 0 0 28 - SW 6 7 0 0 0 0 14 WSW 0 0 0 0 0 0 0 W 1 0 0 0 0 0 1 WNW 1 1 0 0 0 0 3 NW 1 0 0 0 0 0 1 4 NNW 0 0 0 0 0 0 1 TOTAL 120 135 1 0 0 0 261 PERIODS OF CALM (HOURS): 88 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =- 86070101-86123124 STABILITY CLASS: G DT/DZ ELEVATION: SPEED SPD10P DIRECTION:DIR10P LAPSE DT60 WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0 0 0 0 0 4 NNE O 0 0 0 0 0 1 , NE 0 0 0 0 0 0 1
- i ENE 5 0 0 0 0 0 5 E 32 0 0 0 0 0 34 i .
ESE 87 9 0 0 0 0 105 ' i SE 46 10 0 0 0 0 61 j SSE 33 24 0 0 0 0 64 S 26 28 0 0 0 0 54 2 0 0 0 0 10 i SSW 6 SW 3 0 0 0 0 0 3 WSW 1 0 0 0 0 0 2 W 2 0 0 0 0 0 2 WNW 0 0 0 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 TOTAL 241 73 0 0 0 0 343 PERIODS OF CALM (HOURS): 36 VMIABLE DIREC"3N 9 HCURS OF riISS!aG DATA: 3 _ i
Attachment 6 (Continued - Page 5 of 12) Joint Frecuency Distribution Tables - Quarter 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86093024 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE:DT60 y WIND SPEED (MPH) l DIRECTION >24 TOTAL _________ 1_3 __ 4_7 __ _ 8_12 __ __13-18 _ __ __19_24 ___ _____ N 11 60 29 3 0 0 103 NNE 9 55 39 0 0 0 104 NE 13 41 23 3 0 0 82 31 30 4 2 0 0 67 ENE 0 100 E 75 22 0 0 0 ESE 115 74 10 0 0 0 210. SE 44 79 21 0 0 0 148 SSE 40 84 13 1 0 0 144 S 36 119 41 1 0 0 197 SSW 21 95 53 19 0 0 .190 SW 17 60 47 4 0 0 129 WSW 12 42 50 14 0 0 118 W 14 46 117 13 0 0 190 WNW 6 46 79 9 0 0 142 NW 9 53 78 7 0 0 147 NNW 11 56 58 6 0 0 134 TOTAL 464 962 662 82 0 0 2205 PERIODS OF CALM (HOURS): 50 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = ~85070101-86093024 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE!DT60 ________________________________s_____ --_________________._-- WIND SPEED (MPH) WIND DIRECTION >24 TOTAL _________, 1_3 __ 4-7 S _12 13__18 19_24 N 0 16 7 0 0 0 23 NNE 1 20 28 0 0 0 49 . NE 0 10 17 3 0 0 30 ENE 1 4 1 0 0 0 6 - E O 4 0 0 0 0 4 4 ESE O 2 2 0 0 0 4 SE O 2 1 0 0 0 3 SSE 1 1 0 0 0 0 2 S 0 0 0 0 0 0 0 ' SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 1 0 0 1 0 0 2 W 0 2 12 2 0 0 16 i WNW 0 1 14 0 0 0 15 ! NW 0 11 9 0 0 0 20 NNW 0 5 4 0 0 0 9 TOTAL 4 78 95 6 0 0 183 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 3
Attachment 6 (Continued - Page 6 of 12) Joint Frecuency Distribution Tables - Quarter 3
. HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86093024 STABILITY CLASS . B DT/DZ ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE:DT60 WIND SPEED (MPH)
WIND ! DIRECTION >24 TOTAL , _________ 1_3 __ 4_7 __ _ _.8_12 __ __ __13_18 __ 19_24 ___ _____ t N 0 6 4 0 0 0 10 NNE 1 9 3 0 0 0 13 . NE 2 4 1 0 0 0 7 ENE 1 1 0 0 0 0 2 E 0 1 0 0 0 0 1 ESE 0 6 4 0 0 0 10 SE O 1 0 0 0 0 1 SSE 0- 1 0 0 0 0 1 . S 0 2 1 0 0 0 3 ' SSW 0 0 1 0 0 0 1 SW 0 1 1 0 0 0 2 WSW 0 1 2 3 0 0 6 W 0 0 29 2 0 0 31 WNW 0 10 22 0 0 0 32 NW 0 7 14 0 0 0 21 NNW 0 6 5 0 0 0 11 TOTAL 4 56 87 5 0 0 152 hkRf E DIkEbfINN 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86093024 STABILITY CLASS: C DT/DZ ELEVATION: SPEED SPD10P DIRECTION:DIR10P LAPSE DT60 WIND SPEED (MPH) ' WIND DIRECTION 13 >24 TOTAL _________ ___ 4_7 __ _ _ 8__12 13_18 19_24 nNE NE 8 O t 6 i 1 8 0 8 0 8 0 i 7 ENE 0 3 0 0 0 0 3. - E 0 0 0 0 0 0 0 ESE 0 3 0 0 0 0 3 SE 0 2 0 0 0 1) 2 SSE 0 0 1 0 0 0 1 S 1 4 3 0 0 0 8 SSW 0 3 4 1 0 0 8 SW 1 2 7 0 0 0 10 WSW 0 3 8 3 0 0 14 W 0 8 20 2 0 0 30 WNW 1 8 19 1 0 0 29 NW 0 8 4 0 0 0 12 NNW 0 9 4 1 0 0 14 TOTAL 3 69 74 8 0 0 154 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3
Attachment 6 (Continued - Page 7 of 12) J_qint Frecuency Distribution Tables - Quarter 3 i HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD = 86070101-86093024 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SPD10P DIRECTION DIR10P LAPSE:DT60 WIND SPEED (MPH) WIND DIRECTION >24 TOTAL ___..____ 1_3 __ 4_7 8__12 13__18 19_24 N 3 16 15 3 0 0 37 NNE 4 13 6 0 0 0 23 NE 4 17 1 0 0 0 23 ENE' 3 9 1 2 0 0 15 E 9 9 0 0 0 0 18 - ESE 4 13 4 0 0 0 21 SE 0 14 7 0 0 0 21 SSE 2 18 4 1 0 0 25 S 5 26 14 0 0 0 45 SSW 3 28 31 8 0 0 70 SW 3 16 24 1 0 0 44 WSW 1 21 21 4 0 0 47 W 5 30 39 6 0 0 80 WNW 3 18 21 8 0 0 50 NW 6 17 40 6 0 0 69 NNW 7 14 33 5 0 0 59 TOTAL 62 279 261 44 0 0 647 PERIODS OF CALM (HOURS): 3 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 66070101-86093024 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE DT60 WIND SPEED (MPH) WIND DIRECTION 13 >24 TOTAL _________ ___ __ .._ 8-12 4_7 .... __13-18 __ 19_24 __. _____ N 8 16 1 0 0 0 25 NNE 2 9 1 0 0 0 12 NE 4 4 3 0 0 0 11 ENE 15 11 2 0 0 0 28 E 21 8 0 0 0 0 30 ESE 13 29 0 0 0 0 43 SE 4 33 13 0 0 0 50 SSE 2 27 8 0- 0 0- 37 S 8 42 23 1 0 0 74 SSW 10 51 17 10 0 0 88 SW 7 37 15 3 0 0 62 WSW 9 17 19 3 0 0 48 W 7 6 17 1 0 0 31 WNW 1 8 3 0 0 0 12 NW 3 10 11 1 0 0 25 NNW 4 22 12 0 0 0 40 TOTAL 118 330 145 19 0 0 616 PERIODS OF CALM (HOURS): 5 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3
Attachment 6 (Continued - Page 8 of 12) Joint Frecuency Distribution Tables - Quarter 3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86093024 STABILITY CLASS: F DT/DZ ELEVATION: SPEED 1SPD10P DIRECTION DIR10P LAPSE:DT60 WIND SPEED (MPH) WIND . DIRECTION 13 >24 TOTAL 4_7 8_12 13_18 19_24 N 0 0 0 0 0 0 0 NE $ h h h h h k ENE 7 2 0 0 0 0 9 . E 17 0 0 0 0 0 17 ESE 20 13 0 0 0 0 34 SE 9 18 0 0 0 0 27 SSE' 12 15 0 0 0 0 28 S 8 27 0 0 0 0 35 SSW 4 12 0 0 0 0 16 SW 4 4 0 0 0 0 9 WSW 0 0 0 0 0 0 0 W 1 0 0 0 0 0 1 WNW 1 1 0 0 0 0 3 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 1 TOTAL s 87 92 0 0 0 0 184 PERIODS OF CALM (HOURS): 8 VARIABLE DIRECTION 0-HOURS OF MISSING DATA: 3 . i HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86070101-86093024 STABILITY CLASS: G DT/DZ ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE:DT60 WIND SPEED (MPH) WIND DIRECTION 13 >24 TOTAL (. . _________ ___ 4-7 8 __ ___ _12 13-18 _ _____ 19_24 N 0 0 0 0 0 0 0 NNE .0 __0 0 0 0 0 .1 NE 0 0 0 0 0 0 1 ENE 4 0 0 0 0 0 4 E 28 0 0 0 0 0 30 ESE 78 8 0 0 0 0 95 SE 31 9 0 0 0 0 44 SSE 23 22 0 0 0 0 50 S 14 18 0 0 0 0 32 SSW 4 1 0 0 0 0 7 SW 2 0 0 0 0 0 2 WSW 1 0 0 0 0 0 1 W 1 0 0 0 0 0 1
- WNW 0 0 0 0 0 0 1 1
NW 0 0 0 0 0 0 0 l NNW 0 0 0 0 0 0 0 TOTAL 186 58 0 0 0 0 269 PERIODS OF CALM (POURS): 34 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3 i l
~ - - - - - . , ___ - . . _ _ . _ _ _ .__ _ _-_ - _ . _ _ _ _ _ - - _ _ _ _ _ - - -
Attachment 6 (Continued - Page 9 of 12) J_qint Fresuency Distribution Tables - Quarter 4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86100101-86123124 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10P DIRECTION DIR10P LAPSE DT60 WIND SPEED (MPH) WIND DIRECTION 4-7 >24 TOTAL _________ 1_3 __ 8__12 13_18 19_24 N 7 37 20 1 0 0 65
, NNE 4 24 10 2 0 0 41 .
NE 13 17 26 8 0 0 64 ENE 17 38 26 10 0 0 91 E 27 54 11 1 0 0 93 - ESE 37 50 26 8 0 0 121 SE 38 60 62 17 1 0 179
- SSE 36 46 40 1 0 0 126 S 44 117 43 1 0 0 205 SSW 32 142 107 7 0 0 .288 SW 21 126 121 20 0 0 288 WSW 7 38 71 51 15 0 183 W 10 32 95 36 4 0 177 WNW 6 26 55 20 3 0 110 NW 7 24 29 22- 9 0 91 NNW 6 31 35 14 0 0 86 TOTAL 312 862 777 219 32 0 2208 PERIODS OF CALM (HOURS): 6 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 0 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86100101-86123124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10P LAPSE DT60
_____________________________' DIRECTION:DIR10P WIND SPEED (MPH) , t WIND DIRECTION >24 TOTAL l _________ 1_3 __ __ _ _ __8__12 4_7 __ __ __ 13_18 19_24 ___ _____ N 0 2 2 0 0 0 4 NNE 0 4 1 0 0 0 5 NE O 3 6 0 0 0 9 ENE 1 2 6 1 0 0 10 ! E O 2 2 0 0 0 4 l ESE 0 0 2 0 0 0 2 l SE O O 2 0 0 0 2 l SSE o 0 1 0 0 0 1 ! S 0 1 1 0 0 0 2 l SSW 0 0 3 1 0 0 4 SW 0 1 1 0 0 0 2 WSW 0 0 2 0 0 0 2 i W 0 0 4 0 0 0 4 l WNW 0 1 3 0 0 0 4 l NW 1 2 0 0 0 0 3 l NNW 0 2 2 0 0 0 4 l TOTAL 2 20 38 2 0 0 62 i ______________________________________________________________ PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: . 0 l
Attachment 6 (Continued - Page 10 of 12) Joint Frequenev Distribution Tables - Quarter 4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86100101-86123124 STABILITY CLASS: B DT/DZ ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE:DT60 WIND SPEED (MPH) WIND DIRECTION 1-3 >24 TOTAL _________ ... 4_7 8__12 __ _ _ __ __ __ __ 13_18 19_24 ___ _____ N 0 2 1 0 0 0 3 NNE . 0 1 2 0 0 0 3 NE 0 0 3 0 0 0 3 ENE 0 1 1 0 0- 0 2 ' E - 0 0 0 0 0 0 0 ESE 0 1 1 0 0 0 2 SE 0 0 5 1 0 0 6 SSE 0 0 0 0 5 1 4 S 0 0 7 0 0 0 7 SSW 0 0 4 1 0 0 5 SW 0 0 5 0 0 0 5 WSW 0 1 6 0 1 0 8 W 0 2 3 0 0 0 5 WNW 0 2 2 0 0 0 4 NW 0 1 0 0 0 0 1 NHW 0 1 0 0 0 0 1 TOTAL 0 13 44. 2 1 0 60 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 0 ., _ HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86100101-86123124 STABILITY CLASS: C DT/DZ ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE:DT60 WIND SPEED (MPH) WIND DIRECTION 4-7 >24 TOTAL _________ 1_3 __ 8_12 13_18 19_24 N 0 4 1 0 0 0 5 NNE O 3 0 0 0 0 3 NE 0 0 4 2 0 0 6 ENE 0 0 0 2 0 0 2 E O 0 0 0 0 0 0 ESE 0 'O O 0 0 0 0 SE 1 1 3 0 0 0 5 SSE 0 0 4 0 0 0 4 S 0 2 2 0 0 0 4 SSW 0 4 9 1 0 0 14 SW 0 7 14 2 0 0 23 WSW 0 2 6 3 3 0 14 W 0 2 4 3 0 0 9 WNW 0 6 7 0 0 0 13 NW 0 4 1 0 0 0 5 NNW 0 1 0 0 0 0 1 TOTAL 1 36 55 13 3 0 108 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0
. _ _ _ . _ - - _ - _ _ . _ . _ - . _ _ . _ _ _ J
Attachment 6 (Continued - Page 11 of 12) Joint Frecuency Distribution Tables - Quarter 4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86100101-86123124 STABILITY CLASS: D DT/DZ .
- ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE DT60 WIND SPEED (MPH)
WIND DIRECTION , ____ ___. 1_3 __ 4_7
._ _ __ 8_12_. __13_18
__ __ 19_24 . >24 TOTAL N 4 24 16 1 0 0 45 NNE 3 13 7 2 0 0 25 NE- 6 11 11 6 0 0 34 ENE 7 27 15 7 0 0 56 E 5 29 7 1 - 0 - 0 42 ESE 6 23 16 8 0 0 53 SE 9 19 25 16 1 0 70 SSE 8 16 16 1 0 0 41 S 7 37 16 0 0 0 60 SSW 8 75 64 4 0 0 151 SW 9 67 80 16 0 0 172 WSW 2 22 50 43 11 0 128
.W 6 22 80 33 4 0 145 WNW 6 15 40 20 3 0 84 NW ~2 15 27 22 8 0 74 NNW 5 25 32 14 0 0 76 TOTAL 93 440 502- 194 27 0 1256 PERIODS OF CALM (HOURS): 1 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 0 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86100101-86123124 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT60 WIND SPEED (MPH)
- WIND DIRECTION 13
___ 4_7 8__12 __ _ _ __ __ __ __ 13_18 19_24
>24 TOTAL N 3 5 0 0 0 0 8 NNE . 1 3 0 0 0 0 5 NE 7 3 2 0 0 0 12
'ENE 5 8 4 0 0 0 17 E 13 22 2 0 0 0 37 ESE 16 22 7 0 0 0 45 SE 8 32 26 0 0 0 66 SSE 16 20 15 0 0 0 52 S 19 54 17 1 0 0 91 SSW 19 53 27 0 0 0 99 SW 9 48 21 2 0 0 80 WSW 5 13 7 5 0 0 30 W 3 6 4 0 0 0 13 WNW 0 2 3 0 0 0 5 NW 3 2 1 0 1 0 7 NNW 1 2 1 0 0 0 4 TOTAL 128 295 137 8 1 0 571 PERIODS OF CALM (HOURS): 3 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 0
Attachment 6 (Continued - Page 12 of 12) Joint Frecuency Distribution Tables - Quarter 4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86100101-86123124 STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SPD10P DIRECTION DIR10P LAPSE DT60 WIND SPEED (MPH) . WIND DIRECTION >24 TOTAL _________ 1_3 __ 4_7 8_12 13_18 19_24 N- 0 0 0 0 0 0 0 NNE O 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 3 0 0 0 0 0 3 E 5 1 0 0 0 0- 6 ESE 6 3 0 0 0 0 9 SE 5 7 1 0 0 0 13 SSE 2 7 0 0 0 0 9 S 6 13 0 0 0 0 19 SSW 3 9 0 0 0 0 12 SW 2 3 0 0 0 0 5 WSW 0 0 0 0 0 0 0. W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 TOTAL 33 43 1 0 0 0 77 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 - HOURS OF MISSING DATA: 0 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86100101-86123124 STABILI1Y CLASS: G DT/DZ i ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE:DT60 i WIND SPEED (M?H) i WIND l' DIRECTION >24 TOTAL l _________ 1_3 __ 4-7 8-12 ___ ____ __ _ 13__18 __ __ 19_24 ___ _____ l N 0 0 0 0 0 0 0 Nk h h h h h h h ENE 1 0 0 0 0 0 1' l E 4 0 0 0 0 0 4 i ESE 9 1 0 0 0 0 10 SE 15 1 0 0 0 0 17 SSE 10 2 0 0 0 0 14 S 12 10 0 0 C 0 22 l SSW 2 0 0 0 ' 1 0 3 SW 1 0 0 0 0 0 1 WSW 0 0 0 0 0 0 1 W 1 0 0 0 0 0 1 WNW 0 0 0 0 0 0 0 i NW 0 0 0 0 0 0 0 l NNW 0 0 0 0 0 0 0 TOTAL 55 15 0 0 0 0 74 l PERIODS OF CALM (HOURS): 2 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 0 l {
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Attachment 7 Process Control Program Changes a e b n ' ' _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ .
NON-INTENT : R& C a = ---'n
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OM12E FCP TEMP Q6ANGE Page $$
# 'l PAGE l OF S .8 : 3 Process Control Program (PCP)
Table of Contents Page, section Title 3
3.0 INTRODUCTION
3 3.3 befaattsons 2 2.0 UASTE TYPES 2 2.3 Evaporator Concentrates (Bottoms) 2 2.2 Send Resias 2 2.3 Filter Dominera11:er Media Sludge Traveling Belt Filter Cake 3 2.4 3 2.5 Filter Cartridges 3 2.6 Oily Waste 3 2.7 Dry Active Weste (DAW) i
- 3 l 2.8 Other Haierials 3
3.0 PROCESS DESCRIPTION Filling of Tanks 3 3.1 4 3.2 Sampling / Analysis 4 3.3 Freconditioning 4 3.4 Mixing Ratios 4 3.5 Dewatering l 5 3.6 solidification Processing Cartridge Filters 9 3.7 30 3.8 Dry Active Waste , 10 4.0 PRODUCT CONTROL 30 4.1 Test solidification Il 4.2 Product Quality II 4.3 Acceptability I 5.0 . WASTE CLAS$1FICAT10N AND CHARACTER 12ATION 11 l 5.1 Waste Classifiestion - 32 5.2 waste Characterisation 12 6.0 ADMINISTRATIVE CONTROLS i ' 12 7.0 QUALITY ASSURANCE 15 8.0 RECORDS 25 - 9.0 ATTALgnEWTE
- e. Attachment 1 - PCP Product Contral Bata Package id.A 16 REFERENCES l
l l I .- -- . . . . - . - _ _ . _ . . _ _ _ _ _ _ _ _ __ __
t TEMPCHANGE Ob #M9 PAGE l 0FJ O OM12E: PCP N~ Page : iii g3
. Rev. : 3 10CFR50.59 Applicability Check Yes No Is there a change to the plant as described in the TSAR?
Reason: 'Th;> rd .~a,'.m ah.es v3 en s e /Je es ch w a
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in the FSART Reason: T/> ;2 , c. 3/m r . . ':- A : ,,l,/.4.- ./ Ir * $ . .-* . 4 + n.. . / a/c.e . . t. + e , .,9 f o. ^r 4 . o rA rf e P :r ? Is there a test or experiment not described in the FSAR? i Reasoa: ~7fi: _. l.a 4 e < 4l.s , , ,r. ~' < ..t -r e. e < , m . .%.e.cl, Is there a change to the Technical Specifications? Is there an effect on the environment or change to the Environmental Protection Plan? Reason: 77' 3 ro . 3 l._ A, .- U n: C Iici-* c.,-r,' i: r , . r ~ w .c ..-f n. . a l . A . . , . : .(,. . .r,'. z , m. . c c .. ., W. 4 : .- + -:,. . s p' : a s, Answers to all questions are "No", no potential for an Unreviewed Safety or Environmental Question exists, no further review required. Answers to one or more questions is "Yes", further review required. Prepared /Date t="4=ued/Date Approved /Date k?be.. I w n old w ~ h- W-Ble YO s I 'I'ff-
# /
SCOPE OF REVISION: Rev. 3 - Revise PCP to meet draft NRC Guidelines of a Solid Waste Process Control Program and provide more detailed description of NUS mobile system's interconnections with plant installed system. I
TEMP CHANGE -
' as on PAGE A 0F' Q ~
- g OM12E
- ' PCP Page : 2 l
, . Rev.
- 3 outline on all sides (free standing), with a free water content of less than 0.51 by volume. ,
i HIC - a container for burial having an expected life of 300 years. All High Integrity Containers (HIC) eust have an approved Certifi- TC cate of Compliance. 003 I 2.0 WASTE TYPES There are numerous types of radioactive material expected to be generated at FNFP that will require processing. including i solidification or dewatering, prior to their disposal. These . i radvaste types can be categorised based on their chemical and physical properties. The waste types expected at FNPP are evaporator concentrates (bottoms), bead resins, filter demineraliser media sludge, traveling belt filter cake filter eartridges, oily waste, and dry active waste (DAW). The following waste types (other than DAW) may be solidified individually or in combination, with the provision that the chemistry of the waste falls within the acceptable envelope for solidification. 2.1 Evaporator Concentrates (Bottoms) ( Evaporator concentrates (bottoms) result from the processing of the chemical waste tanks which contain condensate domineralizer regeneration solutions and/or low concentrations of the following: trisodium phosphate, minute amounts of other chemicals used for l chemistry analyses, or decontamination solutions. They will j normally 6e in the range of 5Z to 25% sodium sulfate by weight. . ) 2.2 Bead Resins Bead resins are collected from the condensate. liquid radvaste, and suppression pool domineralizers and stored in the spent resin tank. 2.3 Filter Demineralizer Media Sludte - !.'. Sludge is the waste product generated by the backwash of the condensate filters, the reactor water cleanup filter /demineralisers, 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 to approximately 301 by weight prior to l, . solidification / dewatering in the appropriate settling tank. i 4 St
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1 GE TEMP ANGE ON1,2Ei FCP bNN lPAGL A.UF 9 . .3 i " 3.2 Esoplinz/ Anal'ysis i
'ssaples will be obta'ined and analysed for each batch of waste in accordance with W12A: CEl-42. M 11A: M 1-73, and W1A FAP-1102 f.
l sespectively for the plant erstas, er wendor'procet eres l and PCP for' ( wendor supplied systems. Frier to esapling. tasas will underse
*ewfficient minist and/or rectreviaties to ensare representative .
l asselias. et a sinteue, for solidtiscation, analyses e111 te per-formed der radionuclide content, pH, ett content, and settled solids (ell and concentrates only). At a etnisua, for desatoring, analyses e mill be performed der radionuclide and oil content. These analyses J are necessary to ensure that the easte falls within the acceptable envelopes f or solidification /dematering. Weste preconditioning is the chemical er physical adjustment of the l waste to bring it withis sa established acceptability envelope to l curure solidification. The need for and type of precondittoaing j shall be determined using sample analysis results sad will be < performed la accordanice with W12A: G1-78 er vendor precedures and PCP. Upon coupletion of waste preconditioning. additional samples shall be obtained as required, to determine solidification sizing ratios. Oily wastes may require specist preconditioning. Bandling of oily wastes will be conducted in accordance with burial ground requirements. 3.4 tiiming Ratios Mixing ratios give the respective amounts ,ef weste and solidification agents required for acceptable solidification. The determination of sizing ratios shall be perforwed for each batch of waste to be solidified. Solidification mixing raties are dependent upon percent settled solids 'and sediva sulfate concentration. The
- waste type and' ratios of eenent. waste, sedian sulfate (for Ciass A weste), and water are determined ta M12A: CEl-78 or vendor procedures and PCF. .
3.5 Dewaterior Dewaterlag is the removal of water free solid material to a teacentraties of less than 0.51 er,1.01 by welume, as appitcable to containers used and burial site 11mits. Dewaterlat of red,ioactive , l
' spent resias, filter sledges and traveling helt filter, cake shall be lft/ >
performed in accordamee 61th approved operettag' proceeeres wance - are based spen documented test data demonstrat$ag .the ability to achieve drainable water limits as specified in applicable regulattens. 1
TEMPCHANGE 66 d OM PAGE.M._0F.lO OM12E: FCF Page : 5 ( , Rev. : 3 4 . 3.6 Solidification Processing 3.6.1 Description of Flant Processing System Solidification and/or devatoring of wet solid radioac'tive waste will be processed by NUS, Process Service Corporation's - mobile system. This system is discussed in detail in Section , . 3.6.2. The fo11pving description applies to the plant installed solid radwaste system that will interface with NUS's l equipment (see Figure 1). After the proper amount of waste has been transferred to the
~
i vaste mixing tank, the tank is decanted to remove excess free ! . water (except when the waste 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 transfer of the contents). The vaste slurry is transferred at a preset rate to the vendor's equipment, in accordance with OH13A: RWI-14 where it is either dewatered or solidified with cement. The vaste mixing tanks have recirculation capabilities where a representative sample can l be drawn. If needed, a dewatering connection is available which is routed to the liquid radwaste system. An additional ( connection has been provided back to the vaste mixing tank for use in the event of a liner overfill condition. Hot water flush connections are provided to thoroughly flush the plant ' and the vendor equipment into the liner used for processing. l l The waste transfer line and dewatering return lines are located behind a two foot thick shield wall to reduce exposure to the operator during processing. 3.6.2 Description of the Vendor's Waste Processing System The wet solid radioactive waste will be transferred to NUS's i equipment to be dewatered (per NUS Process control Program f or Dewatering Bead and Powdered Resin with Quick-Dry Dewatering Sys-tesNo.8814,No.DW-002)orsolidified(perNUSProcessControl Program for NUSPSC Radweste solidification systems No. SS-001, Rev. Hl. A complete process description for the NUS sobile TC solidification systee is contained in NUS Process Services Topical q) Report on Radmaste Solidification Systes, PS-53-0378, Rev. O. A-description of the NUS dewatering system is contained in the NUS
- Process Control Progras, No. DW-002. The only exceptions to those NUS documents ares (1) test solidifications will be run on each batch of the same waste type instead of every tenth batch, and (2) waste will be supplied to the NUS equipment at 20 gpa instead of 40 gpa due to pump limitations. \
8
TEMP CHANGE Y#00%
. PAGE E OFl O , [
Rev. : 3-
. The vendor's equipment is located in the Radweste Building in the fill aisle and storage area adjacent to the truck bay (see Figure 2). All processing of radioactive waste will be performed in the fi.11 aisle with only the vendor's cement
. transfer equipment being located in the cement silo room.
The areas where the processing of r,adioact,tve maste, takes place are IC specifically designed for this purpose. Concrete walls and floors in
. this area have protective coatings and shield walls are provided between the vendor's equipment and potential 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. .
3.6.3 . Radiological Effluent Controls and Monitoring All processing with the vendor's equipment will be performed in a room with a volume sufficient to contain any postulated spill. A floor drain, routed to the liquid radwaste system, \ provides drainage in this area. All liquid radwaste discharges are sampled and monitored prior to their release to the environment. ( Gaseous discharges from liners are processed through the vendor's off-gas blower system as described in the NUS Topical Report PS-53-0378. The vendor's equipment incorporates radiation monitors on the fill head assembly and the process piping skid. Ventilation from the areas housing the radwaste treatment and processing equipment, including the vendor's off-gas blower system, is routed through REPA filters and charcoal beds prior to release to the environment via the Unit 1 Vent. Radiological monitoring is provided for Regulatory Guide 1.21
. compliance to meet applicable Federal Code requirements.
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; Pigure 2 NUS Mobile Solidifcation Equipment layout
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TEMP CHANCE _ 6,5 y (WB - TEMPCH NGE m12Er PCP PAGE 9 Orl O ' o Pere 50 lev. : 3 PAGE 3_.OF 9 stability criteria of the Branch Technical position en Waste Fern. i I
- Cartridge filters may also be disposed of by placement in MIC's that are certified by the land disposal f acility's state agencl.
3.5 Dry Active Waste . Potentially contasir.ated dry wastes will be collected in containers located throughout the radiologically controlled areas within the plant. The waste will be periodically collected sad transported to a temporary storage area prior to waste segregation (as 'per OMIA: PAP-1901). Vaste segregation will be performed to reduce waste volume-end to recover reusable mat'erials.
' In order to reduce the waste volume, compressible waste will be compacted into shipping containera go accordance with OM13A:
RVI-15. Castion will be taken to avoid items that would cause f ree water forsation as well as other compressibility hazards. Noncompressible waste will be loaded manually into suitable ' shipping containers. l 4.0 PROWCT coqEOL TC pewateri olidification processes will be conducted by gus11f fed PFFF cr vendor personnel in accordance with approved plant and/or vender ld operating instructions and procedures. D To ensure appropriate documentation and compliance with this q. , I, PCP Product Control Data Package will be ! program, Attachment filled out by plant personnel for each solidification process. 1.) Test Solidification Test solidifications are perforwed on waste strea= samples to verify plant and/or vender calculated solidification forwulae. Test shall'he. performed to support solidification sizing formulae (2) when i as follows: (1) every hatch of the same warte type; sampling analysis falls outside the norsal established envelope ar.d preconditioning is ineffective. (3) following an! liner of the ssze waste type where solidification has been determined to be enacceptablet (4) when it is believed that some unexpected er abnormal contaminant may be preseart er (5) when requested by Chemistry Supervision. A batch that requires test solidification shall not be processed satil such time as the test solidification proves acceptable. Upon failure of a test solidification, additional samples shall be obtained and testing will continue entil a successful solidification has been performed with revised mixing ratios asSolidification of the determined by Chemistry Supervision. may then be continued using the alternate solidification parameters defined by testing. l l I
l ~/P Ct(ANGE CMS * " f PAGE.3.OF O i _ ( TEMP CHANGE *evr r-5 ip 4 4.2 Prodoet qualter PAGE.d 0F A Solidification process product quality shall be ensured by the use of predetermined mining ratios *ef weste and solidification agents. Stizing ratios are based upon laboratory testing of non-radioactive waste, materials and are supported by (I) the test solidifications performed periodically as mentione,A above; (2) periodic checks. visual and physical. of actual processed containers filled with solidified waste; and (3) esce every two years requalification of the waste form. Requalification taclodes 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 0.51 free standing water exists and that the solidified product appears to be able to hold its shape if it were to be removed from the container. U' nacceptable solidified waste shall be hand' led as follows: (1) if the reason for unacceptability is free standing water, the free standing-water will be removeJ or ptra cement / sodium silicate will be added to solidify the f ree water; (2) if all or portions of the product did not solidify. the waste container will ,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 will be determined by Chemistry Supervision. The handling of unacceptable solidified waste will be on a case-by-case basis. Adherance to approved dewatering operating procedures ensure the final product will seet or exceed the standing mater requirements of 10CFE61. De=atering of radioactive bead resin, filter desineralizer sedia IC' sisdge, and traveling belt filter cake shall be performed in accord- @ ante with approved operating procedures which are based upon docu-sented test data (see reference 291 demonstrating tha ability to remove free mater volumes below the applicable regulatory limits. 5.0 WASTE CLAS$1FICATION, CHARACTE111AT15 AND MANIFEST RICJIRDGNTS l 5.1 _ W este Classification W All wastes shall be classified ta accordance with the requirements q ef 10CFR61 as implemented by OK1A: FAP-1309 and OK1A PAF-1102. and performed by the RADNAN camputer code. Analyses shall be performed on the waste.' streams at least aans. ally (biananally for Class A waste). to detetuime ghe footopic abundance of non-gamma emitting footopes sat the streams. Scaling facters, for.the non-gammaa emitting and transuranic constituents, will be developed - from these smalyses. Prior to the establishment of an acceptable data, estimated isotopic concentrations will be tho'se obtained from the " Data Base Analysis Report" prepared by Waste Management Croup.
TEMPCHANGE OM22E: PCP ypmg Page : 11. E'"*
- 3 PAGE 9 OF/ C.
Figure 3
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OM12E: PCP TEMP CHANGE Foge : 15 p 9 F.ev. : 3 PAGE 5.OF 9 5.0 RECORDS . The following documents are generated by this program: I + TC-Quality Assurance Records PCF Product Centrol Data PacLage Non Quality Records l None '
\
j Waste classification records, vaste form records, and other records j required for the preparation of the Sesiannual Radioactive Effluent
' Release Report shall be prepared and retained in accordance with 10CTR71 requirements.
~
i 9.0 ATTAC1 DENTS 9.I Attachment 1 - PCP Product Control Data Package , ( l i i i L
TEMPCF ANGE OM)2E: PCF
, y Page : 17
"'" 3 PAGE It.0F 9 REFERENCES
- 14. " Ferry Nuclear Feuer Plant Unit 1 Technical Specifications."
l Rev 0. The Cleveland Elwetric illuminating Company. Ferry. Ohio l 44081. l ' 15. " Ferry Muclear Power Plant Units 1 and 2. " Final Safety Analysis r Report." Amendment 14. The Cleveland Electric illuminating Company. I Perry. Ohio 44081.
~
' ' 16. " Records Retention / Disposition Schedule." The Cleveland Electric I
Illuminating Company. Ferry. Chio 44081.
- 17. Ferry Nuclear Power Plant Operations k nual. " Radioactive Shipment Criteria." OM1A: PAF-1304. The Cleveland Electric Illuminating l
l Company. Ferry. Ohio 44081. I ' l **1F.'__ Ferry Nuclear Power Plant Operations Manual '" Shipment of Radioactive ! Waste for Disposal." OH1A: FAF-1309. The Cleveland Electric Illuminating Company 3 Ferry. Ohio 44081.
- 19. Ferry Nuclear Power Plant Operations Manual. "Radwaste Volume Reduction Program." OM1A: PAF-1901. The.Clevel.and Electric Illuminating Company. Ferry. Ohio 44081.
N 20. Ferry Nuclear Power Plant Operations knual. " - Flant Chesiistry Control Pro, gras ."0H1A: FAF-1102. The Cleveland i q Electric Illuminating Compny. Ferry. Ohio 44081. l 21. Ferry Nuclear Power Plant Operations k nual. "10CFR61 Compliance Sampling." OM1E: RAF-1102. The Cleveland Electric Illuminating , Company. Ferry. Ohio 44081.
- 22. Ferry Nuclear Power Plant Operations knual. " Miscellaneous Sampling Equipment." OM12A: CHI-42. The Cleveland Electric Illuminating i
Company. Ferry. Ohio 44081.
- 23. Ferry Muclear Power Plant Operations knual. "Radwaste l Solidification Testing." OH12A: CEl-78. The Cleveland Electric Illuminating Company. Ferry. Chio 44081.
l
- I
- 24. Ferry Nuclear Power Flant Operatins k nual. " Solid Radwaste Solidification System." OH13A: RWI-14. The Cleveland Electric Illuminating Company. Ferry Chio 44081.
i l 25. Ferry Nuclerr Power Plant Operations k nual. " Solid Radwaste Compaction fystaa." OH13A: RWI-15. The Cleveland Electric Company Ferry. Ohio 44081. i i
. - - ~ - , . . - - _ , . - . _ _ , _ _ _ _ _ _ _ - .
-' EMPCHANGE '
OM
. PAGE / C W $ . TEMPCFANGE ip 4
.eul2E: Pct Page : 18 g- -
I
. PAGE 7 OF 9 .Rev. : 3' h' .
' l
. REFERENCES
- 26. "sarsivell Wste knastement Facility site Dispo,sa'1 Criteria."
Document 520-AD-010. Revision 3. SaraveII. South Carolina 29832 - January I. 1982.
- 27. " Radioactive hterials License W-1-Ol9-2." Amendments 13 and la 5.5. Ecology. lac.. Ranford Reservation. Richland, hshington 99352. December 23. 1983.
- 28. " Ferry' helear Power Plant Quality Assurance Flan." The Cleveland Electric 111wainating Com'pany." Perry. Ohio 44081.
- 29. Homer, J.C. and Lutz, S.F., ' Stock "Guick Dry" Vacuus Compression System f or Bewatering and Volume Reduction of Filter Studge - Sun- TC sary of Test Results", Stock Equipment Company, 1986. mg 9
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i Attachment 8 Offsite Dose Caletilation Manual Changes ) l
INTENT 't=" c*u e ! 7 1046 INSTRUCTION TEMPORARY CHANGE ,AP.os222_3I_E______ ! INSTRuti!0N IG. REV INSTRutil0N IIILE OM12 D : ODCM 2 Offsite Dose Calculation Manual CANCEL 5 ICN(5): N/A ORIGINATOR g DATE Ig4FpgpPACE: R. M. Cochnar l 1 87 ,3 3 ,3 7 ,7 3 ,7 3 a ,8 2,8 4 ,8 5 ,8 6,8 7,8 8,334 38 54 J REASON: Ad j u s tR e n t[ of defSult Vent flow rates (gaseous ADNIN USE ODA.Y effluent radiation monitor set point determination); correction of typo; inclusion of Doso to Members of the Public while Onsite section; changes to Radio-logical Enviromental Monitoring Program locations; incorporation of 10CFR50.59 Applicability Check. DAIE REVIEWED l i
/1/
l l/Y!Of I / 10CFR5059 APP (ICA8kiffC(CK Q g Is there a Change to the plant as described in the FSAR? REASON: There is no chance to the olant. Is there a Change to a procedure / instruction as described in the FSAR? X REASON: This doen not change a nrocedura /i n a tene& 4 nn me described in FSAR. Is there a Test or experiment not described in the FSAR7 X REASON: This does not involve a test or exnariment Is there a Change to Technical Specifications? X Is there en effect on the environment or change to the Environmental Protection Plan? X REASON: There is no adverse offoct on the environs or chance to the E.P.P. Answers to all questions are 'N0'. No potential for en threviewed Safety or Environmental Question exists. No further review required. Answers to one or more questions is 'YES'. Further review required. ED wE0 DATE APPROVED 04fL PRdE 4fo~ . DAg$dg e 8R m r /, v/i, sh s. I, g r/ 7 4 -
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n,, me. me INTENT - INSTRUCTION TEMPORARY CHANGE PAP-0522-2 aov SI::5
!amimCTIS TITLE IN5TRUCTIOh fe.
Ogsart bosc bts md psW@<- pMit b : opee, anastanton ontt mEv. . [. A NAlttA. l 7-14-h A SEAEM LIST EACH AFFECTED PAE; CAng6E % /Enf EggctMy - f g, G, (,,,, f4, Loc *fTo #5 (#3', 4 ?); %Isc .
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~
Reason: ' Tilts is Alor h eAAAfGE 7b TWe /Mr oR sVS1YMs N /M, Is there a Change to a procedurelinstruction as described in the FSAR? ( ntAsan: 74L5 (S Afor # d4WCA 'tv A- /Loccodd //NSTROLT7od M Wl85b ik 'Tlk!' f:%iA Is there a Test or experiment not described in the r$4R? g REASON: N [$ /d MBf d MI Od CYd//lf[Mb Is there a Change to Technical Specifications? Is there en effect on the envirorment or change to the Environmental Protection Plan? REAsan: L fs) RADI+1ketMcAf tow dlT70HT tscT7/oboleC>y GMody,.; CouLb AFMCT LA M) AFLMcW 7b =rf6 fMV/toNheW C fSM f fgn4f d O" W OIMk'O W 40 b Alif ~NfiLE W dinfVIM NM W Cf f. Answers to all questions are 'NO'. No potential for en rcviewed Safety or Environmental Guestion exists. No further review required. Answers to one or more questions is 'YES'. Further review retwired. . DATE PREP"E$yw(k 7-14-sc fEyJE DATE
, % '> 9- / S~~%
APPROUED Sy DATE
' $' . NIL l9<-
PORC #EETIPC 90, REVIDER DATE h '"
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Ot1A: FAP-0522 Page ! _d Page: 15 - EAST
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. Attachment 2 Form: PAF-0522-2 DmNT - Instruction Tescorary Change Form Inst. No./Rev. CM 12.D ' ODGM ,fevloriainator A.Medm/ 4/io / u -
Inst. Title cm w c ~ esw%h ,L.2 10CFR50.59 Applicability Check Yes No mange to the plant as described in the FSAR? Reason TH-Ki IS Afo t*JIMM 7b 9N: n.WTM M,Titad /&N ! l] Q . W /. tK cv s Thrn Terre riv. Change to a procedure / instruction described in the FSAR7 Reason: 7ft6 kMA'. r" c4'M6t* / ('CrrFAQ el l] @
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hst or experiment not described.in the FSAR? Reason lj @
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. Change to h ehnical specifications
. l] lE Affect on the environment or change to the Environmental Protec) ion yF17,y agon: 7#/16 /,? f%%T!f/AF'/' e A/ 7M*, l] @
'Vis.s W lJY/ An DR.3 fi Gr E f:,f.
Answers to all questions a/d%i re "No".7tN No potential for an Uhreviewed safety or twironmental Question exists. No further review required. O Answers to one or more questions is 'Yes". Further review required. Pr red By: kv e Date / - / !-16 Rev ewed By: / 4.,_ -se A -s Date: ww /<L Approved By: '/(TLw ' Date: 4 h t-/ vu A,, roved ah F=c .etin, . % - , s Approved: 7 . Disapproved:
' vg.oeg Approved: . tu ifective Date: I/ '/ ' / 86
._.=. . . . . .
ETge m- ~ ~ h Tescorary Change M-N=r l cc -$ Reason: (% p ten t soon1,.rt (*)s LRw fs==' n.sorsOwn. Nwuf suo vonp!' - - Tcx r eM utre.1 % teFwer eMwo ame* cf nw /LM G l.
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*e Attachment 2 OM1A: FAP-0522 Form: FAP-0522-2 .
Page: 15 Rev.: 0 INTEtrf - Instruction Temporary Chante_ Fog , Inst. No./Rev. OM12D: ODCM N f. Originator R. M. Cochner / 1_/29/86 - Inst. Ticle Offsite Dose Calculation Manual 10CFR30.59 Applicability les No _ ' Change to the plant as described in the FSAR? Reason: [] pd
%s Chan n e a4r3 m 4- c/A~ne 41e n /w i v a <
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n, r , Change to Technical Specifications [] (>4-N Answers to all questions are "No". No potencial for an Unreviewed Safety Question exists. No further review required. , i [] Answers to one or more questions is "Yes". Further review required. Date: .2 f/p(, Prepared by: . Reviewed by: (idLfTmo Date: / /fl 9/'ETo VL "M" WL Date: t Approved by: _ Approved: N M' PORC Meeting # ((o"N Approved: Approved: Effective Date: b/ /bb I lfnper PPTD U , , d _ Tempo 2agy,,C,h,a,n,g,e,,NJ,e,b,er ?do*C Reason: Cancellation ...l.pc //27]#......p _ _ - of TC #001; incorporation of Technical Specification changes; update of Radiological Environmental Monitoring Program table and figure (deletion of two sampling locations); and correction of typos. YJ Change Entered - 4 ,-sd#'W _Date:
TEMPORARY. CHANGE
# OM12D: ODCH PaseMoth Pase : i
_ l Rev. : 2 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT OPERATIONS MANUAL TITLE: OFFSITE DOSE CALCULATION MANUAL GC' REVISION: 2 - EFFECTIVE DATE: I 86 ddC. i l . DATE l PREPARER: Richard M. Cochnar - jpp,pg l REVIEWER: ((
- fri PdRC MEETING NO: 85-131 .
12-I6-85
+ APPROVED: y Q -
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TEMP CHANGE
- g E PAGE L OF./,,3 OM: OM Page : viii Rev. 2 10CFR50.59 Applicability Check fC,"
6 Yes No ' Is there a change to the plant as described in the FSART ' Reason: There is no ch -4 4ds o(4.4f. J I 4 Is there a change to a rocedure/ instruction as described in the FSAR7 Reason: c CDCM is Aef a. arecedww .c 06fne Ne# lh a. ma.Muel adladM-Ka med,d,W, owJ -h' m(cuWe afhete d ca_. Ot6ar faMou/Mwt4 Is there a h le**XY M mefiedelgy test or experimen}t not described in the FSAE7 Reason: Mis i6 det a 4est er exper.'meaf. I IM j Is there a change to the Technical Specifications? U Is there an effect on the environment or change to the I I Environment 1 Protection Plan? Reason: Tlare fs no adverst e. 4 on de ea v;e,ns or- c Lacee -+. rk E.P.p.
- Answers to all questions are "No", no potential for an Unreviewed Safety or Environmental Question exists, no further review
. required.
O A====== ca === ar ==== <===tia== i= required.
"T==", further reviev Prepared /Date Reviewed / Data Approved / Data l-j4-67 //fjff 7 %Q y&
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PAbE / OF M [* Rev. : 2 2.0 LIQUID EFFLUENTS 2.1 Batch Releases , { A batch release is the discharge liquid radioactive waste of a discrete volume. Batch releases from the liquid radweste system may occur from any of the following tanks: waste sample tank, floor drain sample tank, chemical waste distillate tank, and detergent drain tank. (See Figure 2.1-1). The maximum release j* rate possible, due to pump capacity, is 200 gallons per minute from all release tanks except the detergent drain tank, which has a maximum release rate of 50 gallons per minute. All of the above liquid radvaste releases go to the Emergency Service Water dis-charge which is then released through the discharge canal after mixieg with Service Water affluent, and blowdown from Circulating Water system if present. The type and frequency of sampling and analysis required by the PNPP Technical Specifications is given in Table 4.11.1.1.1-1. Prior to sampling for analysis, each batch should be isolated, and thoroughly mixed to assure representative sampling. For mixing, the contents of the tank are racirculated by isolating the tank and turning on equipment that takes suction from and discharges back into the tank.. Recycle lines are provided with one or more mixing eductors located near the bottom of the tanks to promore better mixing as well as reducing recirculation time. This ensures that the water in the tank will be mixed and will be representative of the activity in the tank. The minia'.um recirculation performed is the equivalent of two volumes of the tank contents. Monitor alarm setpoints will be determined in order to ensure compliance with 10CFR20. The radioactive content of each batch release will be determined prior to release in accordance with Table 4.11.1.1.1-1 of the PNPP Technical Specifications. p Concentrations for tritium and other non-gamma emitting isotopes will be those most recently determined (previous month / quarter). 003 Initial source terms, until monthly / quarterly analysis results become available, for non-gasma emitting isotopes listed in the Technical Specifications will be those generated by the CALE code, Revision 0 for PNPP (FSAR Table 11.2-13). 2.1.1 Monitor Alarm Setpoint Determination This method will be used to calculate the setpoint for the lW Radweste Discharge Radiation Monitor - ESW Discharge (D17K606) which provides alarm and automatic termination of liquid affluent releases from the site to unrestricted areas before concentrations specified in 10CFR20, Appendix B. Table II, , Column 2 for radionuelides other than noble gases are exceeded. ODCM/TC-002/mac/1
p-e TEMPORARY CHANGE HANGE
= az TEMPJoa ,
Page E - of 8 ;PAGE.a? oF 4 oxi20: ooCu Page : 2a Rev. : 2 b O NOTE: Liquid radweste discharge flow rate shall be 3 verified at least once per four hours, whenever the fg. g flow rate measuring device (s) is inoperable during , actual releases. e ODCH/TC-002/mac/2
I TEMP CHANG ~- l OM12D: ODCM p og3_ TEMPCHANGE Page : 4 PffiE a3.0F g Rev. : 2 Were: l 8 W_ ( EAGE. 4 0F f = the maximum allowable radwaste tank discharge flow rate for *he batch to be released, in gpm; DF = the conservative dilution factor, as per equation 2.1-2; l adf = the minimum dilution flow - supplied by the Service Water system, i.e., the low flow alarm setpoint of the Service L'ater Flow Transmitter P41-N443 = 30,000 gpm; 0.64 = an engineering factor to prevent spurious alarms. l The liquid radwaste tank discharge flow should be maintained at or below this f value by proper regulation of the high volume or low volu,m,e, discharge throttle valves (C50-F153 or G50-F155). 2.1.1.3 Liquid Radwaste Discharge Flow Monitor Alarm Setpoint t Monitor alarm setpoints are determined to ensure that the concentration of radionuclides in the liquid radwaste effluent I released from PNPP to unrestricted areas doe not exceed the l limits specified in 10CFR20, Appendix B, Table II, Column 2 forradionuclidesothertgandissolvedorentrainednoble gases. An MPC of 2 x 10" uCi/mi has been established for noble gases dissolved and entrained in liquid effluents. SPg = 1.25 f,,g (2.1-4) go Were: SP = Liquid Radvaste Adjustable High Flow Trip Unit I (G50-K805A and G50-K805B) alarm setpoint, in sym; l1C.-003 f = The actual allowable radwaste tank discharge
*** flow rate for the batch to be released; not to 16-exceed the max $ mum allowable radwaste discl:arge flow rate (f ) as defined in equation 2.1-3; M 1.2'S = The engineering safety factor to prevent spurious alarms.
2.1.1.4 Liquid Radwaste Discharge Radiation Monitor Alarm / Trip Set . point
. Monitor alarm / trip setpoints are determined to ensure that the concentration of radionuclides in the liquid radwaste effluent DW/0DCM/TC-004/ cap /1
TEMP CHANGE g Bad Pg E al.OF 1 O 2D: CM p Rev. : 2 released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20 Appendix B, Table II, Column 2 for radionuclides other g an dissolved or entrained noble gases. An MPC of 2 x 10 uCi/ml has been established for noble gases dissolved and entrained in liquid effluents. CR c
= CgEg (2.1-5) i Were:
CR = the calculated monitor count rate above background, c in epm;
= the concentration of radionuclide i in the batch to C' be released, in uCi/ml; k Eg = the detector efficiency of the monitor for radio-nuclide i in cpm /(uCi/ml).
S.R, CR =R,F,[C g (2.1-6) Where: CR *
= the cross-calibrated monitor count rate above background, in epm; F = the cross-calibration factor used to ratio the Liquid Radwaste Discharge Radiation Monitor actual response to the Cs-137 calibrated response; R
= the response of the Liquid Radvaste Discharge Radiation Monitor to a Cs-137 calibrated. standard, in cpa/(uci/ml).
b'0 00
/t.,)
m SP, = (1.25) f,,g (CR) + BC (2.1-7) Were: SP ~ = the Radvaste Discharge Radiation Monitor - ESW Dis-charge (D17K606) alarm / trip setpoint, in cpm; e
TEMPCHANjE. TEMPCHANGE ip BA5 if M M__ OM12D: ODCM PgE V 0F1 S GE.1 OF f Page : 6 Rev. : 2 BG = the background count rate due to internal contami-nation and radiation levels in the area of the monitor; CR = the monitor count rate, as per equation 2.1-5 or 2.1-6; 1.25 = the engineering safety factor to prevent spurious alarms; f max = an adjustment factor (to account for the difference f between actual radvaste discharge flow rate to be used for the discharge and maximum allowable radvaste discharge flow rate) to allow operational flexibility and to minimize spurious alarms; , Where: i
'act = the actual radwaste discharge flow rate; this value must always be less than or equal to f,,x; I
max = the maximum allowable radvaste discharge flow rate, per equation 2.1-3. 2.1.2 Compliance with 10CFR20 - Liquid Effluent Concentration In order to show compliance with 10CFR20, the concentrations of radionuclides in liquid affluents will be determined and compared with the limiting maximum permissible concentrations (MPC) as defined in Appendix B. Table II, Column 2 of 10CFR20. Concentrations of radioactivity in affluents prior to dilution will be determined. Concentration in diluted affluent will be calculated using these results prior to each batch release, and following each batch release. TO" 2.1.2.1 Prerelease The radioactivity content of each batch release will be determined prior to release. PNPP will show compliance with 10CFR20 in the following manner: The concentration of the various radionuclides in the batch release prior to dilution is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation: Cg f , Conc i
=
(2.2-1) adf DW/0DCM/TC-004/ cap /3
OM12D: ODCM TEMPCHAN E Page : 6a
#M Rev. : 2 PAQE 4/ OF .g.,
Were: Cone g = the concentration of radionuclide i at the c od unrestricted area, in uCi/al; Ci = the concentration of radionuclide i in the batch to be released, in uCi/ml; f = the radwaste tank discharge flow rate for the batch to be released, in spa; this value equals f (Equation 2.1-3) if f, , does not exceed system liEffations;
= _ . _ . -- - -
i O TEMF CHANGE 6 00% OM12D: ODCM PAGE I O'F /0 Page : 8
.Rev. : 2 Y = the actual volume of the liquid radweste tank dis-
** charged for the batch, in gallons.
The concentrations in the unrestricted area are compared to the maximum permissible concentrations in Appendix B. Table II, Column 2 of 10CFR20 in order to demonstrate final compli-ance with 10CFR20, i.e., the following equation must be met: { Cone A
- E 1 (2.2-4)
L i MPC g j' Where: l i Cone 1
= the concentration of radionuclide i at the - '
l unrestricted area, in uCi/ml; MPC g = the limiting maximum permissible concentration of radionuclide i, from Appendix B. Table II, Column 2 l of 10CFR20, in uCi/al. 2.2 Continuous Releases A continuous release is the discharge of fluid wastes of a l non-discrete volume, i.e., from a volume or system that has an input flow during the continuous release. Continuous radioactive releases are not planned for PNPP although the potential does exist for RHR heat exchanger leakage into the Emergency Service Water system. Potentially contaminated dicharges from the ESW are monitored by an installed radiation monitoring system. This system consists of two channels, one for monitoring downstream of equipment in Emergency Service Water System Loop A and the other for Loop B. Monitors are set to alarm at three times background level. If radiation is detected, the affected Emergency Service Water line can be manually isolated. Whether to isolate or not is dependent upon other conditions. The PNPP staff will take appropriate action to limit release. The Emergency Service Water system, water discharged will be l IO' sampled and analyzed in accordance with PNPP Technical (X923 Specification Table 4.11.1.1.1-1. To show compliance with 10CFR20, the sum of the concentrations of radionuclide "i" in unrestricted areas due to both continuous and batch releases divided by that isotope's MPC must again be less than 1. l l l l l ODCM/TC-002/mac/S
o TEMPCHANGE gTA PAGE_d2.0F d OM12D: CDCM Page : 11 Rev. : 2 Where: R = the dose to individuals of age group a to organ j P from all the radionuclides in pathway p in ares; B = the equilibrium biaccumulation factor for radio-ip nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/1), from Table 2.3-4, in 1/kg; 9 D,gPy = the dose factor, specific to a given age group a, radionuclide i pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in ares /pci, or from exposure to a given concentration of a radio-nuclide in sediment, expressed as a ratio of the f dose rate, in aram/h, agd the areal radionuclide concentration, in pCi/m , from Tables 2.3-5 ((1 through 2.3-9; 3 F = the flow rate of the liquid effluent in ft 7,; M p= the dilution factor at the midpoint of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food), from Table 2.3-10, dimensionless; Q g = the release of radionuclide i, in Ci; t = the period of time for which the sediment or ' b 5 exposed to the contaminated water, 1.75 x 10 h (20 years); , , T g= the halflife of radionuclide i, in days; tp = the average transit time required for radionuclides to reach the point of exposure, from Table 2.3-11; for internal dose, t, is the total time elapsed between release of the radionuclides and the inges- - tion of food or water, in h; U sp
= the usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway p, from Table 2.3-12, in h/yr, 1/yr, or kg/yr; W W = the shoreline width factor. 0.3 (from Regulatory lCO3 Guide 1.109);
- ODCM/TC-002/mac/6
___ ___ _ _ _ _ _ __ _ n
TEMPORARY CHANGE OM12D: ODCM
#_007- Page : 30 Page 3 of
- 3.1 Monitor Alarm Setpoint Determination The following calculation methods provide a means of determining the high alarra se: point (HSP) and the alert setpoint (ASP) to ensure compliance wi:h 10CFR20 dose rate limits to areas at or beyond the site boundary for the noble gas channels of the following monitors:
- 1. Heater Bay / Turbine Building Vent Radiation Monitor (1D17K856)
- 2. Offgas Vent Pipe Radiation Monitor (1D17K836)
- 3. U1 Ven: Radiation Monitor (1D17K786)
- 4. U2 Ven: Radiation Monitor (2D17K786)
The Uni: 2 Vent Radiation Monitor is included in the operation of Uni: 1 methodology because the second train of the Unit 1 Annulus Exhaus: and the Control Complex and Intermediate Building ven:ilations are exhausted through the Unit 2 Vent. The High Alarm Se: point (HSP) for each release point radia: ion monitor will be set at 70 percent of the 10CFR20 dose rate limits and the Aler: Setpoint (ASP) will be se: at 10 percent of these limits. .' NOTE: The values of 70 percent for the HSP and 10 percent for the ASP are set as fractions of the total activity that may be released via the monitored pathways to ensure l that the site boundary dose rate limits are not exceeded. Any single ASP can be exceeded without the 10CFR20 timits being exceeded. Upon receipt of an alert alarm a sample from the alarming effluent path will be obtained and analyzed. If two or more monitors exceed the ASP or any one exceeds the HSP it is possible that N, the limits have been exceeded. In this case all four O effluent paths will be sampled and analyzed. Appropriate action will be taken to limit gaseous releases to below 10CFR20 limits. NOTE: If an HSP or two or more ASP's continue to be exceeded, verification shall be made at least once per 4 hours via the gaseous effluent radia: ion monitors that plant {c' g releases are below Technical Specification 3.11.2.1 dose rate limits, and sampling and analysis shall be - performed on the four gaseous effluent release points at least once per 12 hours.
l TEMPORARY CHANGE OM12D: ODCM
$$ Page :
30a 2 L,1*yl <.fL This procedure determines the monitor alarm setpoints that indicate if the dose rate beyond the site boundary due to noble gas radionuclides in gaseous effluent released from the site exceeds 500 mrea/ year to the whole body or 3000 ares / year to the g skin. g 3.1.1 Determination of the " Mix" (Noble Gas Radionuclide Composition) of the Gaseous Effluent
- a. Determine the gaseous source terms that are representative of the " mix" of the gaseous effluent. Gaseous source terms are the concentrations of the noble gas radionuclides in the affluent as determined by routine analysis of the various sources of gaseous effluents. During the early period of operation, O
e
4 3. TEMP Cl,lA,NGE
# h
#~
PAGE 3 0F /3 OM12D: ODCM
- U, Page : 33 ,
e V Rev. : 2.
-M 1.11 = the air-dose to tissue dose equivalent conversion l factor, in ures/arad; l.
.c 3000 = the skin dose rate lini::, in eres/yr;
'f&
. (Lg + 1.H Mg) values are shown in Tame 3.M.
i 3.1.4 Determination of the Maximum Acceptable Total Radioactivity
.c0 Concentration of all Noble Gas Radionuclides in the Gaseous
- b Effluent i~
. g.j -
j'+ 2.12 x 10 Q
?L. C = (3.1-4) t .Q t-t Where:
gl ,
;t- C* = the maximum acceptable total radioactivity concen-if tration of all noble ' gas radionuclides in the Y effluent, in uCi/ce; t.: ,
f = the actual flow at the point of releage from the respective flow rate recorders, in ft / min; NOTE: When actual flow rates are not available, the l[ following design flow assumptions will be used: .M (These flow rate values incorporate a 10% i[ flow rate inaccuracy correction.) 'N~ Flow Rate ft 3/ min Vent ll(A:j j.. - Heater Bay / Turbine Building 400,000 (summer)
.220,000 (winter) TC'
{ '. - Offgas 19,000 $ ! !$. b :- 140,000 'k
- Unit 1 ,
v ,I - Unit 2 (Control Complex and Intermediate Building Vent 11ations) 47,000 o iO and Q , calculated in Equations Q" = the smaller of Q3.1-2 and 3.1-3,brespecEively, in uC1/s; !? 2.12 x 10" = the conversign factor to convert !' (uci/s)/(ft / min) to uC1/cc. 'L 4, r(^ f$ \ <. DW/TC/0DCM1/K/mac/1 l' I
TEMPCHANGE g S OM12D: ODCM Page : 33a Rev. : 2 TC' 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides CE, = 0.8 (C,) (E,) (3.1-5)
. I Du/Tc/OccMt/K/ sac /2
)
l l TEMP CHANGE i 0 S l PAGE 4 0Fd OM12D: ODCM Page : 37 Rev. : 2 3.2 Compliance with 10CFR20 - Gaseous Effluent Dose Rate Dose rates resulting from the release of noble gases, radioiodines, tritium, and radionuclides in particulate form must be calculated to show compliance with 10CFR20. The limits of 10CFR20 are conservatively applied on an instantaneous basis at the controlling location. 3.2.1 Noble Gases 1 The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mram/yr to the total body and ! 3000 mrea/yr to the skin. Only the external dose pathway will be considered for noble gases. Because all gaseous effluent l ' releases from PNPP are considered ground level, the controlling location for these dose rate limits is the site l boundary location (see Figure 3.2-1) with the highest relative dispersion factor (I/Q) for the period of release. (See Appendix A for elaboration on atmospheric dispersion). ( The alarm setpoint determinations discussed in the previous section should ensure compliance with these dose rate limits. However, if any one high alarm or two or more alert alarms occur, the dose rates in unrestricted areas resulting from the ' release of noble gas radionuclides from all vents will be calculated. The calculations will be based on the results of analyses obtained pursuant to the PNPP Technical Specifications. 3.2.2 Radioiodines, Particulates, and Other Radionuclides TC~ ' The dose rate in unrestricted areas resulting from the release of iodine-131, iodine-133, critium, and all radionuclides in particulate form with half-lives greater than eight days is limited to 1500 mram/yr to any organ by PNPP Technical Specifications. The calculation of dose rate from these radionuclides will be performed weekly based on results of analyses obtained persuant to those Technical Specifications. The controlling location for this limit is a function of the noble gas controlling location, i.e. , the location of the highest relative deposition (D/Q) for the period of release (See Appendix A for elaboration on atmospheric deposition), as well as the actual receptor pathway. The receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of residences in each sector, and garden and farm animal locations. DW/TC/0DCM1/K/mac/3
TEMf' OlANGE , ,e i PAGE ,,f,of /3 OM12D: ODCM g e Page : 73 . Rev. : 2 thermoluminescent variety (TLDs) with analyses performed quarterly and annually. ( 4.3 Dose to Members of the Public While On-site
*@; , ' PNPP Technical Specification 6.9.1.7 requires " assessment of the radiation doses from radioactive liquid and gaseous effluents to ;
6 members of the public due to their activities inside the site !
< boundary." This assessment is included in Semiannual Radioactive i 'l Effluent Release Reporting.
hl A member of the public is defined in Technical Specifications to t y f include all persons who are not occupationally associated with the L. plant, i.e., not utility employees, contractors or vendors. Also y excluded frca this category are persons who enter the site to service equipment or make del.iveries. { e Maximum dose to member of the public while on-site is conservatively I assessed relative to off-site' dose values. The assessment methodology
@ incorporates use of appropriate dilution, dispersion, and occupancy-factors for on-site activities.
il[ h The only liquid effluent d'ose pathway affecting members of the if public while on-site is shore exposure. Fishing on the Lake Erie 7: Q shoreline is the assumed activity for this exposure. On-site dose assessment is made via ratio to the maximum calculated off-site d: shore exposure dose incorporating adjustments for occupancy factor TC'
- and liquid affluent dilution factor. g
[ Several cases are considered for gaseous effluent dose assessment to members of the public while on-site including: traversing a public road within the site boundary, lakeshore fishing, non-PNPP related training sessions at the Training and Education Center, car pooling
, to the Primary Access' Control Point (PACP) parking lot, and job i applicant interviews. This evaluation is made using " relative X/Q" ..M ,
(atmospheric diepersion) values. " Relative X/Q" values are the product jiy of the highest annual average X/Q for the point of concern, and occupancy j factor for the case. An adjustment factor is derived by ratioing this highest on-site " relative X/Q" to the highest site boundary i " relative X/Q." (A unity occupancy factor is used in the determination L of the highest site boundary " relative X/Q.") Conservative on-site b dose determination is made by applying the " relative I/Q" adjustment [ factor for the highest potential on-site dose activity to the highest
.s calculated gaseous effluent off-site dose. 'e
{ c U-{' p( y [f DW/TC/0DCm /C/mac/4 {
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~i
. TEMP CHANGE 9 5 PAGE4-OFM ,
OM12D: ODCM Page : 73a 9fC'(( Rev. : 2 5.0 RADIOLOGICAL ENv RONMENTAL MONITORING FROGRAM 5.1 Fonitoring Program Environmental samples shall be collected and analyzed according to Table 5.1-1 at locations shown in Figures 5.1-1 and 5.1-2. Table 5.1-4 describes sample locations, associated media, and approximate distances and directions from the site. Analytical techniques used shall ensure that the detection capabilities in Table 5.1-3 are achieved. Ground water sampling vill not be conducted as part of PNPP's REMP because this source is not tapped for drinking or irrigation purposes in the area of the plant and the hydraulic gradient is not suitable for useful groundwater contamination. The position of the plant and the underdrain system with respect to the hydraulic gradient is such that any leakage or overflow from the underdrain system vill flow north towards Lake Erie. Local domestic wells outside the exclusion area boundary are up-gradient from the plant. As part of the REMP samples vill be routinely collected from the closest potable water intakes on Lake Erie. The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring by verifying that the censurable concentrations of l radioactive materials and levels of radiation are not higher than l expected on the basis of the effluent measurements and codeling of
" the environnental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for
those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. The initial radiological environmental nonitoring program should be conducted for the first three years of commercial operation; i
following this period, program changes may be proposed based on I operational experience. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every reasonable effort shall be i made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shs11 be documented in the annual report. l DW/TC/0DCM1/K/mac/5
R-re g Q Table 5.1-4 hE Sampling Locations and Media for Environmental Monitoring k $ g Perry Nuclear Power Plant
]$
N n _c location Distance No. Description (Hiles) Direction Media ( } R Redbird (Naines Road, North of West Chapel Road) 3.4 ENE APT, AI, TLD, l ' [1 o on pole 3303609; first pole south of first driveway of left PR, SO j S 2 Site Boundary; Tree line 0.7 E TLD, SO l Ash tree 1000 feet NNW of second transmission tower from road 3 Meteorological Tower 1.0 SE APT, AI, TLD On fence surrounding the equipment shelter 4 On pole #W79/SPG5-30; inside auxiliary road gate of Parmly Road 0.7 S APT, AI, TLD, SO 5 Site Boundary, Quincy Substation 0.6 SW APT, AI, TLD On pole #L1283/9300, east side of substation 6 Concord Service Center (Control) 11.0 SSW APT, AI, TLD, Auburn Road south of Rt. 90; on inside rear fence next to gate PR, SO, VL TC' 7 Site Boundary; Lockwood Road Bus turnaround, on the right, 100 feet 0.6 NE TLD, AIR,VLl 6 past the turnaround on tree with white dot. 8 Site Boundary; Tree Line, behind nursery off Antioch Road, follow 0.8 ENE TLD to end of nursery. On tree near creek with white dot. 9 Site Boundary; Transmission Line Tower 0.7 ESE TLD Third tower from Antioch Road toward the plant 10 South-southeast Corner Security Fence 0.8 SSE TLD On pole at turn in the fence 11 Transmission Line Tower 0.6 SSW TLD On tower at SW corner of Center and Parmly Roads 12 Site Boundary; Transmission Line Tower 0.6 WSW TLD, PR, SO Access road from N side of Parmly just W of location f 5 yyg 45 y
""8 9
2 5 m Es$, ,,51k.e* EA - - Table 5.1-4 (Cont.) 4 o b! D bg i yN[gi-a 49 Sampling Locations and Media for Environmental Monitorini gQ gk ggl @ $ f l Perry Nuclear Power Plant b m g g $ M - 3ocation Distance gg} No. Description (Miles) Direction Media w g 23 Fairport Harbor (High Street and New Street) 7.9 WSW TLD n On pole on rear substation facing street D 24 St. Clair Ave. Substation (Control) 15.1 SW TLD In Mentor; on rear fence corner near railroad tracks 25 PNPP Discharge 0.6 NNW SED, FSH 26 Offshore at Redbird, vicinity of Ohio Water Service Company Intake 4.2 ENE SED 27 Offshore, vicinity of Fairport Harbor Water Supply System Intake 7.9 WSW SED 28 Ashtabula (Control), CEI Generating Station Intake 22.0 ENE WR g 29 Milk Farm. Waites residence Antioch Road, Perry 1.3 ESE MLK F 30 31 Milk Farm, Manley residence, North Ridge Road, Perry Milk Farm, Hoffer residence. Antioch Road, Perry 2.3 1.4 SSW ESE MLK g. llfC'(03 MLK as 32 Mentor-on-the-Lake (Control) 15.8 WSW FSH, SED lTC'#J+ 33 Brookglen Farm (Control), Greig residence, Callow Road, Leroy 10.2 S MLK 34 PNPP Intake 0.7 NW WR 35 Site Boundary; north of transmission line, next to transformer, 0.6 E follow tree line APT,AI,TLD,6 VL fc,- 36 Painesville Water Supply Intake 3.9 WSW WTR 37 Ohio Water Service Company Pump Station, 4.1 ENE WTR Green Road, Madison 38 Seith Farm. 2861 Antioch Road. 1.1 E FP 0.5 miles from North Ridge Road 39 Goldings Farm Stand 1.8 SSW FP 3515 North Ridge Road W?O 9 i..j 9
3 8 * $o m
..E Table 5.1-4 (Cont.) m b s 2, hy ,
f# (,Q$; Sampling Locations and Media for Environmental Monitoring
% $ % cn g Perry Nuclear Power Plant @ "
nn 3.ocation Distance No. Description (Miles) Direction Media (l) R Deleted [40 n 41 Clark Road 1.1 SW TLD D One-half mile from Center Road. On pole No. 561969, south side of road 42 Parmly Road 0.8 S TLD One-half mile from Center Road, located on utility pole No. 582923 near southwest corner of plant fence 43 Parmly Road 1.0 SSE TLD Approximately 0.6 miles from Center Road next to stream. Tree with white dot 50 feet from road left of stream, 44 Parmly Road 1.0 SSE VL l lIC'g 45 Clark Road 0.9 SSW TLD Approximately 0.2 miles from Center Road on Pole No. 561960, south side of road 46 Deleted 47 Milk Farm, Zoldak residence Middle Ridge Road Nadison 6.5 E MLKllfC~8'+ 48 49 Antioch Road Garden, 4385 Lockwood Road 1.1 0.8 ENE NE VL FP pd
.1g "38 9
m N l Table 5.1-4 (Cont.) $4 3 r o Sampling Locations and Media for Environmental Monitoring o I ts Perry Nuclear Power Plant $ k M
$M b eation Distance No. Description (Miles) Direction Media (
S e 50 Garden, 13271 Radcliffe Road 10.9 S FP
$ 51 Rettger Farm, 13863 Painesvilla-Warren Road 9.2 S MLK D 52 Hilk Farm, Pollack residence, Wood Rd. 4.5 SE MLK 53 Neff Perkins, Co., southeast fence corner 0.5 WSW TLD 54 Hale Rd. School, pola No. 395910, 4.6 SW TLD 2nd from corner on Lee 55 Perry School District Offices - On pine in tree line by 2.5 S TLD baseball diamond 56 Madison High School, 1st clump of pine trees from library 4.0 ESE TLD (1) APT = Air particulate WTR = Water FP = Food Products AI = Air f odine FSH = Fish SO = Soil TLD = Ambient gaussa dose rate MLK = Milk PR = Precipitation SED = Sediment VL = Vegetation IIS Tc'
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JP CHANGE TEMP CHANGE TEMPCHANGE . TEMP CH ANGE > 5 o 009 o .Q0.3 o 004
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813 LOGICAL ENVIRONMENTAL MOpiTORING PROGRAM Aperture Card a~
-3 CONTROL SAMPLING LOCATIONS GREATER THAN 10 MILES FROM SITE u en o c= g
- c 8700000357-o3 e
TEMPCHANGE OM12D: ODCM d $25 3 Page : 108 CAGE 9 OF /d Rev. : 2 Y = the fractional radiochemical sample collection or concen-tration yield (when applicable); At = for plant effluents, the elapsed time between thu ,, and of sample collection and time of counting; for lIU environmental samples, the elapsed time between sample gy}{ collection (or end of the sample collection period) and time of counting; A = the radioactive decay constant for the radionuclide in question. For the purpose of routine analyses, count times for both the sample (s) and background (s) are equal. This satisfies the given Technical Specifica-tion lower limit of detection definition, as the numerator of equation B-1 simplifies to 4.66 S , where Su is the standard deviation of the back-ground count rate or the bcount rate of a blank sample as appropriate. The LLD is defined as an "apriori" (before the fact) limit representing the espability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. For gamma ray spectroscopy analyses (Canberra Spectran - F Version 2): L exP (0.693 At/ty ) D (C)(E)(t)(V)(Y )(Yy) Where: LLD = the lower limit of detection, in uCi or pCi per unit mass or volume; C = the conversion factor of transformations per unit time
. per uCi or pCi; E = the detector efficiency for the energy in question; t = the data collection (counting) time of sample; t
g = the half-life of the radionuclide in question; ODCM/TC/-002/mac/11 .
- OM12D: ODCM
- 109
- F:31 Rev. 2 ,
Y " the 88mPl e size. in units of mass or volume; TEMP (NGE
#- S- Y = the fractional radiochemical sample collection, or con-PAGE 4 0F /d
- centration yield (when applicable);
Ty = the yield of the gauna ray in question; At = for plant effluents the elapsed time between end of lTV l sample collection and time of counting; for environmental ! samples, the elapsed time between sample collection (or end of the sample collection period) and the time of I counting; l I g = the detectica limit
=k +2 (1 + ) (B 1*I)+I+e (B-2a) 2 nihere:
B = the number of counts in a background channels below the g peak due to Compton scattering, etc., determined at the l same time a photopeak is measured; By = the number of counts in the a background channels above the peak; k = an abscissa of the normal distribution corresponding to confidence level.
= 1.645 at a confidence level of 95%;
I = the measured value of interference in the photopeak of interest due to environmental background.* detector contamination, etc., determined by a separate measurement with no sample; N = the number of channels in the photopeak of interest; , n=then[mberofbackgroundchannelsoneachsideofthe photopeak of interest; ey = the standard Mation of I.
/
Typical values of E. V. Y, and A t shall be used in the calculation. I# In calculating the LID for a radionuclide determined by ganna-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). j Analyses shall be performed in such a manner that the LLD's listed in ! Tables 4.11.1.1.1-1. 4.11.2.1.2-1. and 4.12.1-1 of the Radiological Effluent Technical Specifications for the Ferry Nuclear Power Plant will be achieved under routine conditions. Occasionally, background ' fluctuations, unavoidably small sample sizes, the presence of
- interfering nuclides, or other uncontrollable circumstances may render j
l these LLDs unachievable. In such cases, the contributing factors will I be identified and described in the Annual Radiological Ensironmental Operating Report or the Semiannual Radioactive Effluent Release Report. I f -
O Attachment 9 Maior Channes to Radioactive Waste Treatment Systems l I l l
' (
PNPP No. 7125 Rev.11/85
.. NED SAFETY EVALUATION -
I. Description of I, tem to be Evaluated (Include Document Number and Revision Level}; , MdL4sn of fdlA.6 D e- W a 4 e A n o kA" D cf ST6 0 9I 9 Pea. b II. Safety Evaluation (attach written basis for answers as required)
- 1. Is the probability of occurrence or the consquences of an accident or malfunction of equipment important to safety previously evaluated in the FsAR increased:
YEs NO Reasons SW O O P
- 2. Is the possibility for an accident or malfunction of a dif ferent*
type than any evaluated previously in the FsAR created? YEs b NO Reasons W ha P l
- 3. Is the margin of safety as defined in the bases for any Technical' l
specification reduced? YEs h NO Reasons $ C*C* GYS r er i If the answer to any of the above questions is yes, an Unreviewed Safety ! Question is involv d. Prepared By: ', / 'A $'. / //-h84 Signature Discipkme Date Reviewed By: h.D& V Sign gr4
~
/ W Mrc h-L.
Discipline
/ l{ ~l"$l*
Date Submitted By: (4. A4_,.d J t R , R. hc1_ / k /Nik b
'Date PORC Review and Re endation for Approval Meeting No.: R[,- 2 23 Approved: l/l ,i 4.AA / b I / //- 6 [K Mafiagers,' PPOD/PPTD Date('
SAFETY EVM.UATiDN i , ,,,
~
( Attachment to Safety Evaluation 86- 0410 DCP 860919 The scope of this safety evaluation is limited to the evaluation of the dosign change as a " major change" to a radioactive waste treatment system and , its offect on the F3AR. A seperate safety evaluation will be written to address tho necessary changes to the Process Control Program (0M12E:PCP). SYSTEM DESCRIPTION 'NUS Process Services Equioment The purpose of the NUS Process Services (now called LN Technologies) 4
" Quick Dry" dewatering process is to remove any free water in the package of bacd or powdered resin so that it complies with all transportation and burial rcquirements. This is achieved by drawing a vacuum in the waste container (using c voeuum pump) after it is full of waste, thereby removing all of the free water in the package. Any air displaced during either the filling or dewatering procoss is routed through a HEPA filter which vents to atmosphere.
Bead resin is dewatered in a special container with a conical bottom. Tha water drains freely to the bottom of the container where it is drawn through internal filters and then pumped back to the liquid radwaste system. Powdered resin is dewatered in.a special container that is fitted with a largo plastic bag. Inside the plastic bag is a series of flat filters through which the vacuum pump draws water. After the waste completely fills the container, a vacuum is maintained inside the bag. Atmospheric pressure squeezes the outside of the bag forcing out the last amounts of water. This squeezing
- process contributes to a significant volume reduction of powdered resin. ,
The NUS equipment consists of a plant connection skid, a " Quick Dry" dowatoring skid, and a specially modified liner. This equipment is used to i d weter both bead and powdered resins. The plant connection skid,provides the interface between the plant and the dewatering system. The waste feed line, ,corvice air, and flush water are routed through this skid. The " Quick Dry" dawatoring skid combines the dewatering equipment along with the process l tank, controls. and The dewatering a water equipment transfer pump (to consists pump waterof aback vacuum pump, to the water plant). Thecollection process controls include level and pressure sensing devices and a closed circuit talovision. These controls will be seperated from the dewatering skid at a futuro date and located in the truck bay to reduce radiation exposure. The spaciolly modified liner is a standard carbon steel or High Integrity Container vossol that has an internal filter arrangement. Plant Interface The plant connections for the waste feed and the return water will be l ._ - _. . . . .. -_ - _ _ - _ . - _ . _ _ _
( ~tha some a the ones used for' solidification. These lines are located in the same
;oroc where the dewatering equipment will be. The air vented during the filling innd dowatering processes will be allowed to exhaust into the process aisle.
All of the dewatering equipment to be leased from NUS Process Services
- will be located in the fill aisle adjacent to the truck bay (see the attached
- cquipment layout drawing). This area is is surrounded by a 2 foot thick concrete
; wall. A floor drain routed to the liquid radwaste system provides drainage in (this area. The area is ventilated by the radwaste building ventilation system ithat has a filtered exhaust.
l l i (EVALUATION l ispill and overflow Evaluation The uncontrolled release of radioactive material into the processing crea could be a results of three component failures:
- 1. A failure of the connection between the plant and the dewatering )
system. l
- 2. A rupture of the plastic bag inside of the disposable liner, j
- 3. A rupture of the disposable liner.
I Plant Connection Failure l The radwaste dewatering system will be connected to the plant connection through a flexible hose. A rupture of this hose.could* result in a spill in the processing area. The radwaste technician could detect this failure by noting an internal waste level that is unchanged or by viewing the loss of waste flow inside of the liner with the closed-circuit television. When this situation was detected the flow could be ' immediately stopped from a local control panel to minimize the volume of spill. The small amount of waste spilled from this event would be contained behind the radwaste building shie'id' wall ar.d could be drained l to the liquid radwaste system to be processed. Plastic Bag Rupture i A rupture of the plastic bag used for processing powdered resin could i' i result in a small amount of waste being spilled in the processing area. i This failure could be detected by an increase in the internal liner l pressure. Pressure is the main parameter controlled when dewatering. The consequences of such an accident could be alleviated by stopping flow to j the liner. The technician monitoring the process will detect this failure very quickly and can stop the flow from a local control panel. . This spill would be handled in the same manner as the plant connection ! i failure. l
)
l l l
~
, (
- Disposable Liner Rupture A rupture of the disposable liner is the worst case scenario. In this event, 1500 gallons of radioactive slurry would be released into the processing area. This volume of water would be contained inside the radwaste building walls in the same manner as with the plant connection failure. Another concern would be airborne contamination. The air flow patterns in the processing aisle are such that any radioactive gas release would pass into the radwaste ventilation system, where it is filtered prior to being released to the environs. Credit for this was taken in the original design of the plant as discussed in Section 11.4.2.1 of the FSAR.
GEscous Waste Evaluation During normal operating conditions, air is exhausted into the processing misla during the waste transfer and dewatering steps. Prior to being exhausted into the area, this air is routed through a HEPA filter located on the NUS downtoring control skid. Any air exhausted in the processing area during this procoss will be routed through the building ventilation system as described in 5 action 11.4.2.1 of the FSAR. Therfore, no unmonitored release path for gaseous wasto exists as a result of using the NUS dewatering system. As noted above, local airborne contamination is minimized by routing the exhoust through a HEPA filter prior to being released into the area. Radioactive gosos that are not removed by filtering, will be drawn into the building vontilation system. To facilitate this, the exhaust hose from the dewatering skid will be located near the air intake to reduce the possibility of local
- mirborne contamination.
Rtgulatory Guide 1.143 Compliance NUS Process Services Process Piping - All of the process piping used in the " Quick Dry" dewatering system is designed, fabricated, and tested in accordance with ANSI B31.1. The piping is designed so that crud traps are minimized wherever possible. Welding - All welding performed on the NUS system is performed by welders and procedures qualified to ASME Section IX. System piping is designed for an opeating pressure of 150 psig and is hydrostatically tested at 225 psig for a minimum of 30 minutes in accordance with ANSI B31.1. . Hoses - All hoses used are designed for a 150 psig system pressure and are hydrostatically tested after fabrication to assure the integrity i
~
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of the end fittings and the absence of defects in the hose material. Electrical - All of the system electrical components are selcted and installed in accordance with the National Electric Code (NEC). Motors and process controls are mounted in NEMA Type 4 enclosures to meet hosedown, dust, external icing, and rust-resistance tests. Design and Procurement Control - Design and procurement documents are independently reviewed for compliance with the system QA requirements. Each " Quick Dry" system has a complete set of as-built drawings prior to release to the field. Changes to these drawings are verified and controlled in accordance with NUS Process Services (now called LN Technologies) procedures to maintain conformance with QA requirements. Purchasing - Suppliers of major equipment items, such as liners, skids, shields, etc.,'are surveped to verify that the supplier has the capability to meet the quality requirements as specified in procurement documents. Suppliers of equipment or materials to be used in fabrication of the process piping must provide Certificates of Compliance showing conformance with the purchase order requirements. Testing and Inspection - Each " Quick Dry" system undergoes thorough functional and hydrostatic testing prior to release. Documentation and procedures provide for the identification of items which pass required inspections and tests. Items of nonconformance and the corrective actions required are identified and documented during QA inspection of supplied items. Maintenance - Maintenance of the " Quick Dry" system is performed regularly by the on-site technician in accordance with established schedules and procedures. Permanent Plant Equipment l l All of Perry's permanent plant equipment meets the requirements of l Regulatory Guide 1.143 as outlined in Table 1.8-1. . Exposure to " MEMBER OF PUBLIC" l All of the dewatering system components are located inside the Radwaste Building behind a shield wall. In the event of a spill, all of the radoactive wasto is contained in the building as described above. Since the Radwaste
- Building is a seismic category 1 structure, all of the radioactive material is
- contained even af ter a seismic event. This prevents radionuclide concentrations lfron exceeding the limits of 10CFR20 in the same manner as what has been involunted in Table 1.8-1 of the FSAR. Therefore, no increased exposure to a
" MEMBER OF PUBLIC" will result from inadvertant liquid effluents using the NUS dswatering system. -
The exposure to a MEMBER OF PUBLIC from a direct dose of stored
( downtored resin is less than 0.3 mR/ year. This is a small percentage of the c0xitum allowable dose rate of 25 mR/ year per 40 CFR 190. It is also a small porcontage of the allowable yearly dose per 10 CFR 20 and 10 CFR 100. As required per 10 CFR 20, no areas outside the exclusion area will have radiation lovols in excess of 2 mR/hr., nor will any dose for seven consecutive days oxcood 100 mR as a result of dewatering resin waste. Exposure Analysis to Plant Workers The design of the " Quick Dry" system and the layout of the equipment in ,the plant is intended to reduce radiation exposure as low as reasonably - Ochoivable (ALARA) in accordance with NRC Regulatory Guide 8.10. Tins-shielding-distnace principles are applied to minimize radiation exposures by the following methods:
- 1. Minimizing the time that the technicians are exposed to liners containing radioactive materials.
- 2. Use of process shields to shield personel from liners of radioactive waste.
- 3. Remote control of system operations.
Exposure resulting from dewatering operations is normally 30 mR per linar dewatered. This number is based on a normal operating sequence and a liner dono rate of 18 Rem on contact. Based on the average of 88 liners per year, the tochnician exposure due to the dewatering process should not exceed 2.6 Rem during any calendar year. ' Activity Time Exposure Disposable Liner Inspection 45 min. O mR Fillhead Installation 30 min. O mR Westo Transfer 2 hrs. O mR Dswatoring Operation 4.5 hrs. . O mR Fillhoad Removal 2 min. 15 mR
- Liner Closing 1 min. 15 mR
- Total 7 hrs 45 min. 30'mR
- These numbers are actual dose rates received from processing a liner at anoth2r plant with radioisotopic activities similar to the postulated 18 Rem linor.
The following discussion presents the specific method by which ALARA principles are applied: i umi a umaei i si m ma s
( Minimizing Exposure Time When operating the " Quick Dry" system, the technician is exposed to unshielded liners only when removing the fillhead and capping the resin liner. The fillhead has aquick connect mechanism which reduces its removal time. Quick-connect hose couplings are used to minimize exposure during system maintenance and dewater liner changeout. Hose couplings are required by procedure to be secured with tie-wraps to prevent inadvertant disconnection. Process / Storage Shield Two 1 foot thick concrete shields (or equivalent) are to be installed in the process aisle to provide effective gamma attenuation. The dewatering control and the plant connection skids are separated from the liner by these shields. These shields are primarily used to protect the technician during the fillhead removal and the liner closing processes. Operations involving the liner and the plant interface skid are performed prior the resin transfer to minimize radiation exposure. These shields will provide protection when performing normal operation and maintenance activities. Remote Operation All resin transfer and dewatering operations are controlled remotely from the permanent plant control panel or the NUS dewatering skid. This makes it unnecessary to approach the liner until the fillhead needs to be removed and the liner capped. At a later date, the dewatering controls will be relocated in the truck bay to effectively shield the operator as high activity liners of waste are generated. .
SUMMARY
- 1. The probability of occurrence or the consequences of an accident or Dolfunction important to safety previously evaluated in the FSAR are not incrossed based on the following reasons:
l a. All realistic failures / malfunctions of the equipment do not result
,in potential safety hazards. Existing equipment and structures are available to eliminate, mitigate, or control the hazards to an acceptable level. The release of vented air into the area meets or exceeds the original design when processing solid radioactive waste.
l b. The NUS equipment meets the intent of Regulatory Guide 1.143 to i reduce the potential for an inadvertant release of radioactive material i in the processing area. 1 ____ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ . . . _ . _ ~ _ . _ _ _ _ _ _ _ . _ . _ . , _ _ _ _ _ _ . _ - . - _ _ _
\ , ( i ' l 2. Tha possibility of an accident or malfunction of a different type than any l ovolunted in the the FSAR are not created based on the following reasons: l a. All realistic failures / malfunctions of the equipment do not result in potential safety hazards. Existing equipment and structures are available to eliminate, mitigate, or control the hazards to an acceptable level.
- b. Exposure to plant workers is kept within administrative limits by the use of the time-distance-shielding approach,
- c. Exposure to the MEMBER OF PUBLIC is kept below the limits of 40 CFR 190, 10 CFR 20, and 10 CFR 100.
- 3. The margin of safety as defined in the bases for any Technical specification 10 not being reduced for the following reason:
- a. The processing of radioactive waste by dewatering does not introduce a new exposure pathway to the MEMBER OF PUBLIC. Dose from direct radiction to the MEMBER OF PUBLIC is well within the limits of 40 CFR 190, 10 CFR 20, and 10 CFR 100.
e e
PNPP No. 7124 Riv.11/85 l, i NED 10CFR50.59 APPLICABILITY CHECK I. Description of Item to be Evaluated (Include Document Number and Revision
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- 1. Yes X No is the item under evaluation a change t he plant as de cribed in the FsAR? Reason: 15 6 NM18\ ritG12/k? b 61 M:OC( NMb
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- 2. Yes I No Is the i e u der o a h ge to a
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- 3. Yes [ No is the item under evaluation a test experiment not de ibed in the FSAR7 Reason: 4fr
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- 4. Yes No 1 Does the item under evaluation involve a ch nge to the Technical Specifications? Reason bizcthtom tsh Was-{c der-s vtf a@cf b clo ss ece[ded b4 a MfrrisER BF Puota c.
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-g Q Answers to all questions are "N0", no potential for an Unreviewed HM/66 Safety Question exists, no further review required:
Preparer: / / Signature Discipline Date Reviewer: / / Signature Discipline Date Approved: / GS/GSE Date
@Answerstooneornorsq tions is "YES"., urthe view required:
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9 Attachment 10
. 986 Land Use Census h
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i i I NUS-4739 PERRY NUCLEAR POWER PLANT LAND-llSE SLRVEY i FOR 1986 l i i
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Prepared for THE CLEVELAND ELECTRIC ILLUMINATING COMPANY November 1986 By ! I I l l l Helene L. Kasser i NUS Corporation Envirornental Services Division l 910 Clopper Road Gaithersburg, Maryland 20878 - l Approved: Approved: . i Y $[dw ?>IA bil / 1-f,1 chard H. Holder L Edgar ,Mitenel'1, Jr. y Department Manager Project Manager Radiological Envirornental Technology Department
, TABLE OF CONTENTS - i Section Ntsnber Page 1.u Introduction 1-1 i 2.0 Methods 2-1 3.0 Results and Discussion 3-1 3.1 Nearest Gardens and Residences by Sector 3-1 3.2 Site Boundary Receptor Locations 3-5 3.3 Dairy Animal Locations 3-5 3.4 Non-Dairy Animal Locations 3-7 3.5 Control Dairy Animal Locations 3-11 3.6 Ohio Cooperative Extension Information 3-11 4.0 Conclusions 4-1 5.0 References 5-1 Appendix A A-1 i
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' i LIST OF TABLES Table i Er Page 4
i i 1 Nearest Residences by Sector Identified During 3-2 y; the 1986 PNPP Annual Land-Use Survey t
'2 Nearest Gardens by Sector an1 D/Q Identified
! 3 ; During the 1986 PNPP Annual Land-Use Survey ' l 3 -- D/Q Values for Site Boundary Receptor Locations 3-6
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3
- for the PNPP (Reference 3) 1; 4 Milk Animal Locations by D/Q Identified During 3-8 the 1986 PNPP Annual Land-Use Survey 5 Other Non-Dairy Animal locations Identified l 3-9 During the 1986 PNPP Annual Land-Use Survey 6 Control Milk Sampling Locations by D/Q Identified During the 1986 PNPP Annual Land-Use Survey 3-12 l q
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t LIST OF FIGURES .< I Ficure Number . s Pa ce 1 Nearest Residences and Gardens by Sector and 2-3 Dairy and Other Animal Locations Within 5 Miles of PNPP j Y s 2 e 1 . s 4 6 l 4i t 11i
r: 4 , s 1.0 Introduction A land-use survey was conducted for the Perry Nuclear Power Plant (PNPP) dur- ,
-ing the period 2 June 1986 through 4 June 1986. The closest garden (greater
.than 50 square meters, producing broad leaf vegetation) and residence in each radial sector were determined and all dairy animals within five (5) miles of the PNPP were identified. In addition, " control" milk sampling locations were verified. The control locations are outside the 5-mile radius.
The USNRC Branch Technical Position on "An Acceptable Radiological Environmen-tal Monitoring Program" states that "a census shall be conducted annually during the growing season to determine the location of the nearest milk animal and nearest garden greater than 50 square meters (500 sq. ft.) producing broad
. leaf vegetation in each of the 16 meteorological sectors within a distance of
.8 km (5 miles)" (Reference 1). The census of milk animals and gardens producing broad leaf vegetation is based on the requirements in Appendix I of 10 CFR Part 50 to " Identify changes in the use of unrestricted areas (e.g.,
for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure" (Reference 4). Similarly, the land use census section (3/4.12.2) of the Radiological Effluent Technical Specifications (RETS) for the Perry Nuclear I l Power Plant provide for the conduct of an annual lad-use census. The consumption of milk from animals grazing on contaminated pasture and the consimption of leafy vegetation contaminated by airborne radiciodine are pstential sources of exposure. l! This report describes the methods used in and the results of the 1986 land-use survey. The report also includes a process for selecting new milk sampling ! stations for the radiological envirornental monitoring program (REMP) if one ! cf the current locations drops out of the program. Conclusions are provided that include recommendations for the Perry Radiological Envirornental Monitor-l ing Program based on the 1986 Perry Nuclear Power Plant Comprehensive Dairy Survey (Reference 8) that reported results of milk animal locations identified within ten miles at one plant (see Appendix A). l l 1-1 l
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l 2.0 Methods ; The land-use survey was conducted in accordance witn NUS Work Instruction P0.5.2.15.107, "Perforwance of the Annual Residence, Garden, and Milk Animal survey for the Perry REMP" (Reference 2). Participants in the survey were Jim i Webb (CEI), Christine Brewer (CEI), and Helene Kasser (NUS). j The survey was conducted by visual inspection of the study area and by talking f directly to home owners and farmers. The nearest residence was identified by j driving the public roads in the sectors closest to the plant. The nearest j garden was identified by going to the location identified in the 1985 land use survey. CEI and NUS personnel verified the presence of the garden and the type of vegetation grown. If a garden was cultivated, but the vegetation was not fully germinated, discussions with home owners facilitated determining ( c hether broad leaf vegetation was planted. If a garden was no longer present at the 1985 location, homes nearby (next door or across the street) were sur- ! veyed to determine whether a vegetable garden was present. The location of dairy and non-dairy animals was determined by traveling all roads in the 5 mile radius (approximately 270 miles). CEI and NUS personnel payed particular attention to those locations that were listed in the 1985 land use survey and , on the computer printout supplied by the Lake County Agricultural Extension , Service (see Section 3.6), and to those locations where barns and fences indi-cated the presence of cattle. Discussions with farmers were conducted to l obtain information on the number and type of livestock raised. A field map (showing 1 through 5 mile radial distance arcs and sector lines) ! and a field log were used to record data. The nearest residences and gardens by sector, and all dairy and other animal locations within 5 miles of PNPP are shown in Figure 1, which was derived from the field map. , i i The 0/Q (nonnalized deposition) values listed in Tables 2, 3, 4, and 6 were extracted from the deposition values listed in Appendix A of the Offsite Dose Calculation Manual (Reference 5). The values were determined for a ground-level release to a ground-level receptor and are annual averages based on the 2-1
seven year onsite meteorological data base (5/1/72 - 4/30/74; 9/1/77 - 8/31/82). . The Lake County Planning Commission in Painesville was visited to determine l whether a comprehensive plan was available, whether the plan established goals and objectives on how to maintain the county's rural character, and where growth would occur. The plan could inform CEI personnel on the county's planning activities and how they might affect land uses within the 5 mile radius of the plant. It was found that the Lake County Comprehensive Plan is 26 years old. However many of the communities have their own plans which are kept up to date. The Planning Commission has also conducted studies (e.g., soil suitability, transportation, employment) which can serve as input to a l canprehensive plan. There is also a Baseline Allocation Land Use Map for the year 2000. I U
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. 3.0 Results and Discussion 3.1 Nearest Gardens and Residences by Sector i 3.1.1 Nearest Residences l The nearest residences identified in each sector surrounding the PNPP are listed in Table 1 and depicted in Figure 1. The results of the 1986 survey are nearly identical to the 1985 results (Reference 5), with the exception of i the residence in the northeast sector. The residence identified in this ' sector during the 1985 Land Use survey was found to be unoccupied. 3.1.2 Nearest Gardens The nearest gardens identified in each sector surrounding the PNPP are pre-sented in Table 2 and depicted in Figure 1. ! Three new garden locations were observed this year. The first new location was observed in the northeast sector at 4385 Lockwood Road. The garden loca- , tion observed last year 4384 Lockwood Road, was determined to be currently , unoccupied and there were no signs of a garden being cultivated. The second I new garden location was observed in the east sector at 2740 Antioch Road. The residents at the 1984 location (2684 Antioch Road) are not growing a garden. The last new location was observed in the southwest sector at 3440 Clark Road. This location is also the closest residence observed for this secter. These new garden locations are approximately the same distance from the plant as the - ones observed last year. . In Table 2, the nearest gardens are listed by order of decreasing D/Q. As D/Q decreases, the dose received through applicable pathways decreases. The j application of this ordering to the selection of new sampling locations is l discussed in Section 3.3. The garden receptor site, with the highest esti-mated D/Q, is 3119 Parmly Road (0.9 mile SSE). ' l 3-1 l_ _ ._ . = - . _ - - - . - . - - - . - . - - - - - - - - - - - - - - -
Table 1. Nearest Residences by Sector Identified { During the 1986 PNPP Annual Land Use Survey (1)(2) 7 Nearest Residence Direction (Distance / Address) Map Locator l 0.8 miles 1 NE 4385 Lockwood Road (3) 1.0 miles 2 ENE 4602 Lockwood Road 3 ! E 1.2 miles 2684 Antioch Road 1.2 miles 4 ; ESE 2774 Antioch Road . i SE 1.2 miles 5 4495 North Ridge Road , 0.9 miles 6 SSE 3119 Parmly Road S 0.9 miles 7 3121 Center Road SSW 0.9 miles 8 . 3850 Clark Road ;! i SW 1.2 miles 9 3440 Clark Road WSW .1.1 miles 10 3462 Parmly Road (1) Closest residences are not identified for sectors over water. These sectors are as follows: W WNW, NW, NNW, N, and NNE. (2) Some of the positiens for the same locations in this table are reported - slightly differently from the positions reported orior to 1985. Consistency and site boundary considerations led to refinements in distance and direction data. These changes are considered insignificant since the data have not been used in calculations, assessments, or evaluations. (3) The closest residence identified in this sector for the 1985 Land Use Survey (4384 Lockwood Road) was found to be unoccupied in 1986. 3-2
Table 2. Nearest Gardens (1)(2) by Sector and D/Q Identified During the 1986 PNPP Annual Land-use Survey (Sheet 1 of 2) Nearest Garden Comments Map Locator Direction D/Q(m-2)(3) (Distance / Address) 6 Residents are growing kale SSE 1.22 E-08 0.9 mile 3119 Parmly Road 78 Same location as last year, but 1.09 E-08 1.0 mile 5 3157 Center Road the house is for sale 1 New location from the 1985 survey. NE 1.09 E-08 0.8 alle . The residence where the garden was 4385 Lockwood Road located in 1985(4384 LockwoodRoad) was found to be unoccupied 5 Garden observed. Plants have not 28 ENE 4.77 E-09 1.1 mile germinated enough to identify 4611 Lockwood Road specific crops 38 1 4.56 E-09 1.2 mile New location. Residents at the
- E 2740 Antioch Road 1985 location (2684 Antioch Road) l are not growing a garden this year 48 1.3 mile Three plots used for gardens ESE 2.97 E-09 l
2846 Antioch Road 58 1.2 mile Garden is a bit smaller than 50 SE 2.90 E-09 sq mtrs 4521 North Ridge Road 10 1.2 mile Property actually belongs to WSW 2.31 E-09 . 2971 Perry Park Road 2970 Perry Park Road
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Table 2. Nearest Gardens (1)(2) by Sector and D/Q Identified During the 1986 PNPP Annual Land-Use Survey (Sheet 2 of 2) Nearest Garden Direction D/Q(m-2)(3) (Distance / Address) Comments - Map Locator SW 1.95 E-09 1.3 alle New location 9 3440 Clark Road SSW l.48 E-09 1.5 mile 88 3787 North Ridge Road (1) Closest gardens are not identified for sectors over water. These sectors are as follows:~ W. WNW, NW, NNW, N, and NNE. u E (2) Some of the positions for the same locations in this table are reported slightly differently from .the positions reported in reports prior to the 1985 report. Consistency and site boundary considerations led to refinements in distance and direction data. These changes are considered insignificant since the data have not been used in calculations, assessments, or evaluations. (3) D/Qs are based on a seven-year set of meteorological data observed at Perry. l
e & i i 3.2 Site Boundary Receptor Locations Table 3 presents the distances and D/Q values for the nearest locations to the , site boundary in each sector. The site boundary is indicated by the shaded j area in Figure 1. Minimum distances to either Unit 1 or Unit 2 are used. I Distances to ' Unit 1 are included for sectors N, NNW, NW, WNW, NNE, W NE, ENE, and SW while distances to Unit 2 are included for sectors E, S, WSW, SSE, ESE, { SE, and SSW. Minimum distance data was obtained from the PNPP Environmental Report (Reference 3). In Table 3, the nearest site boundary locations are listed by order of decreasing D/Q. The application of this ordering to the selection of new sanpling locations is discussed in Section 3.3. The site boundary receptor site with the highest D/Q is 0.4 miles NE. Sampling cannot be conducted for sectors over water. These sectors are footnoted in Table 3. ' 3.3 Dairy Animal Locations Dairy animals identified within 5 miles of the PNPP are listed in Table 4 and
- depicted in Figure 1. The Comprehensive Dairy Survey conducted in January and February,1986, identified dairy animal locations in Lake, Geauga, and Ashtabula Counties out to ten miles from the plant. The results of the survey are summarized in Appendix A of this report.
There are 6 locations with milk-producing animals within 5 miles of the plant-- compared to eight locations observed in the 1985 survey. This
~ decreasing trend will be monitored in future land use studies. Of the six locations, there are three dairy cow locations and three goat locations. Two of the goat locations, 2897 Antioch (1.3 miles ESE) and 3203 North Ridge (2.4 miles SW) are regular milk sampling stations in the PNPP Radiological l Environmental Monitoring Program (REMP).
One new milk animal location was observed during the survey at 4566 Wood Road there one dairy cow was sited. Three of the locations identified in the 1985 3-5
i Table 3. D/Q Values for Site Boundary Receptor Locations for the PNPP (Reference 3) I Receptor Direction Distance (m) Distance (miles) D/Q (m-2)(2) l N(1) 294 0.2 1.595 E-07 ,' NNW II) 280 0.2 1.181 E-07 NW(1) 273 0.2 1.133 E-07 l WNW(1) 283 0.2 8.421 E-08 NNE(1) 402 0.2 7.947 E-08 ; W III 430 0.3 4.623 E-08 ! i NE 678 0.4 3.108 E-08 E
, 1072 0.7 1.800 E-08 l
ENE 1079 0.7 1.605 E-08 5 1298 0.8 1.574 E-08 WSW 893 0.6 l 1.457 E-08 l 1 SSE 1316 ' 0.8 1.440 E-08 ESE 1083 0.7 1.325 E-08 SW 1047 0.7 1.149 E-08 SE 1269 0.8 1.076 E-08 SSW 1284 0.8 6.837 E-09 (1) Vegetation is not available from these sectors since they are bordering on the lake. ! (2) D/Qs are based on a seven-year set of meteorological data observed at Perry. l u
i h , survey--2908 Antioch Road, 2541 Townline Road, and 4776 North Ridge Road--no ; ( longer have milk producing animals. In Table 4, the dairy animal locations are listed by order of decreasing D/Q. l The application of this ordering to the selection of new sampling locations [ follows. If one of the existing milk sampling locations drops out of the i REMP, a new milk location could be chosen according to D/Q values. The milk l locations should be approached in the order listed in Table 4. Two of the l milk locations listed in Table 4, 2897 Antioch and 3203 North Ridge, are cur- [ 0 rently REMP sampling stations. Of the four remaining locations listed in Table 4, two owners declined to participate in the REMP in December,1985, l' another had expressed interest if CEI personnel are willing to collect milk samples themselves and the residents at the new location (4566 Wood Road) h' ave ; yet to be contacted. If, af ter inquiry, there are no available milk locations, broadleaf vegetable sampling from local gardens could be conducted during harvest season. Gardens are ranked by D/Q in Table 2 and should be approached for availability of broadleaf vegetable sanples in that order. If broadleaf vegetable samples from local gardens are not available, fencepost broadleaf vegetation sampling could be cor. ducted. Fencepost broadleaf vegeta-tion includes grasses, weeds (such as dandelions) and other small herbaceous plants. Table 3 ranks the closest boundary points in each sector by D/Q and should be approached for sampling in that order. Since the boundary property is owned by CEI, availability of fencepost broadleaf vegetation will not be a problem. However, vegetation will not be available from st.ctors over water. These sectors are footnoted in Table 3. l 3.4 Non-Dairy Animal Locations ' Non-dairy animals identified within 5 miles of the PNPP are listed in Table 5 l and depicted in Figure 1. ' Twenty-two locations were observed in 1986 compared to twenty-six locations in ; the 1985 survey. Seven of the twenty-two observed locations are new locations 3-7
i j 1 } 4 Table 4. Milk Animal Locations by 9/ll Identified During the ig86 PNPp Annual Land-Use Surveytl) i thauber/ Type Comments from Research Con-j Location (2) S/ll(m-2)(3) of Animals Map comments from Survey ducted After Igt(j) Land Use Survey Locator 1.0 mile SSE 3.48 E-Og 3 goats 1. 329I Paraley Road Location was visited, however no Resident declined to partict-one was home to confirm the 1- , pate in the REMP nassber of goats ! 1.4 alles ESE 2.g7 E-Og 4 goats 1 2897 Antioch Road Mofer, RE N sampling location (5) 2 ? - 2.3 milesS5W 6.71 E-10 33 goats 3203 north Ridge Road Manley, REN sampIlng location (5). Forty-five goats identified in 16 i 1985 4 2.g miles 55E 4.43 E-10 1 dairy cow
- 4761 Davis Road Resident will participate in 21 the REW if CEI personnel j s'. would be willing to collect 2
olik samples themselves j 3.6 miles SE 4.03 E-10 2 dairy cows once the helfers are fresh, they 5320 South Ridge 2 freshening Resident declined to partict- 11 are sold pate in the REMP 4.5 alles SE 2.58 E-10 1 dairy cow l 4566 Wood Road new location. Used for owner's 13 I consianption. j II) All locations are within 5 miles of the plant. } (2) i to 1985.Some of the posillans for the same locatless in this table are reported slightly differently from the pos'ltlens reported Consistency and site boundary considerations led to refinements in distance and direction data. in r l These changes are considered insig-I nificant since the data have not been used in calculations, assessments, or evaluations. { ( 3) D/l)s are based on a seven-year set of meteorological data observed at perry. (4) Memorandum from J. Webb to L. 8. Rock (Reference 7). participant in the Ig86 pNPp Radiological Environmental Monitoring program. l i 1 i a
Table 5. Other Non-Dairy Animal Locations Identified During The 1986 PNPP Annual Land-Use Survey (l) (Sheet 1 of 2) F Ntaber/ Map Location (2) Type of Animals Comment Locator 1.3 miles ESE 1 heifer New location 3 2861 Antioch Road 1.3 miles ESE 7 beef cattle New location 4
- 2821 Antioch Road 3 pigs 2.0 miles E 2 beef cows New location 5 2620 Townline Road 2.1 miles E 2 billy goats 6 2541 Townline Road 2.1 miles E 1 billy goat New location 7 2447 Townline Road 3.7 miles SSW 3 beef cattle 8 Friendly Stock Farm I heifer Sheppard Road 4.8 miles S 17 beef 9 3588 River Road I heifer 4.7 miles S 6 beef 10 3920 River Road
, 3.7 miles SE 40 cattle 11 i 5320 S. Ridge Road 4.6 miles SE 4 beef cattle New location 12 4145 Dayton Road 2 sheep - 4.5 miles SE 4 beef cattle New location 13 4566 Wood Road 4.8 miles SSE 4 beef cattle 14 5551 River Road 3.7 miles E 19 heifers Owner sells heifers 15 Green and North once they are fresh Ridge Road i i 3-9
Table 5. Other Non-Dairy The 1986 Animal PNPP Annual Locations Land-Use Identi)fied Survey (l During (Sheet 2 of 2) Nunber/ Map Location (2) Type of Animals Comment Locator 2.2 miles SW 1 beef cow seen No one home to confinn 17 3340 Blackmore Road the nunber of cattle 1.8 miles S 1 bull Rest of cattle was 18 3590 Center Road 2 steers taken to pasture on 2 heifers Route 84 2.0 miles SSE 3 beef cattle 19 3608 Call Road 2.8 miles SSE 2 beef cows New location 20 4686 Davis Road Both are pregnant 3.1 miles SE 8 beef cattle 22 3941 Townline Road ! 2.6 miles ESE 22 beef cattle 23 3234 McMackin Road hogs 3.8 miles ESE 5 beef cattle 24 3304 Dayton Road 4.6 miles E 42 beef cattle 25 Woodworth Farm Middle Ridge Road 4.5 miles ESE 17 beef cattle 26 5960 Middle Ridge Road (1) All locations are within 5 miles of the plant. 1 (2) Some of the positions for the same locations in this table are reported slightly differently from the positions reported in reports prior to 1985. Consistency and site boundary considerations led to refinements in distance and direction data. These changes are considered insignificant since the data have not been used in calculations, assessments, or evaluations. 3-10
~ _ . _ . _ . . . _ . . - _ _ _ . . _ _ _ . _ _ _ _ . _ _ _ -
since the 1985 land use survey. Non-dairy animals were not observed at thirteen of the twenty-six locations observed in 1985. 3.5 Control Dairy Animal Locations Control dairy animal locations (approximately 9 miles or more from the plant) were verified and the results are listed in Table 6. One of the two control locations, 8187 Callow Road (10.2 miles S), is a regular milk sampling station in the 1986 Perry REMP, however, the owner will not be participating in the REMP as of January 1, 1987, because he will be selling his cattle to the United States Government as part of the Dairy Buy Out Program. D/Q values for the two control locations are provided in Table 6. 4 i 3.6 Ohio Cooperative Extension Information Mr. Barry Jolliff, 4-H Extension Associate from the Ohio Cooperative Extension service was contacted to determine what information is being kept on dairy l animal owners in the PNPP area. A computer printout of 4-H members who raise l dairy animals was obtained. Additional dairy animal locations that were indi-l cated on the computer printout include: 129 Lyndale Road, 370 Hale Road, and 100 Fruitland Road. Dairy animals at these locations were not observed during the survey. Telephone calls to residents at these locations verified that there are in fact no dairy animals present. O 3-11
Table 6. Control (l) Milk Sampling Locations by D/Q Identified During the 1986 PNPP Annual Land-Use Survey Nunber/ Type Location (2) D/Q (m-2) of Animals Coments t 9.2 miles S 5.088 E-11 M'a jor Dairy Hard Owner: Rettger ! 13863 Painseville-Warren Road , 10.2 miles S 4.296 E-11 Major Dairy Herd Owner: P. James Greig(3) 8187 Callow Road (BrookglenFarm) (1) Control locations are approximately 9 miles or more from the plant. (2) The positions for the sane locations in this table are reported slightly differently from the positions reported in reports prior to 1985. Consistency , 4 and site boundary considerations led to refinements in distance and direction data. These changes are considered insignificant since the data have not been used in calculations, assessments, or evaluations. (3) Participant in the 1986 PNPP Radiological Environmental Monitoring Program. Sanples will not be available at this location next year because Mr. Greig will be selling his cattle to the United States Goversnent as part of the Dairy Buy Out Program. I ( I 3-12
l 4.0 Conclusions The nearest residences identified in this survey are identical to those observed in the 1985 survey with the exception of the residence in the north-east sector. Three new garden locations were observed in the northeast sector at 4385 Lockwood Road, the east sector at 2740 Antioch Road, and in the south-west sector at 3440 Clark Road. These new garden locations are approximately the same distance from the plant as the ones observed in these sectors last year. . The residents at the two indicator milk sampling locations continue to par-ticipate in the Perry REMP. There are four additional potential indicator locations where milk producing animals were observed for a total of six loca-tions within the 5 mile radius. Eight milk producing animal locations were observed in the 1985 land use survey. This decreasing trend should be moni-tored in the years ahead. Since there are only two indicator milk sampling stations, a third indicator milk sampling location could be chosen from Table 4. The preferred location would be one with a higher D/Q value. Although the control and alternate control locations were confirmed, the owner at 8187 Callow Road (10.2 miles 5) stated that he is planning to sell his cat-t1e to the United States Government as part of the Dairy Buyout Program. Therefore, milk samples may not be available from this control station in 1987. It is reconnended that milk samples be collected from both locations for the remainder of 1986 to enable the comparison of the readings at the alternate location with those at the current control location. During this time, the readings from the two locations can be compared to determine if there are differences that can be attributed to the change in location. If new milk sampling stations are not available, then broadleaf vegetation sampling from local gardens can be conducted. If vegetable gardens are not available, then fencepost broadleaf vegetation can be sampled. The 1986 Com-prehensive Dairy Survey explains in greater detail methodologies that can be used to select additional milk sampling locations (Reference 8). 4-1
The land-use census conducted during 1986 provides valuable information on agricultural and dairy conditions in the vicinity of the PNPP. Current data can provide the criteria for the selection of new supling locations and enable useful and timely supling in the event of a radioactive release during operation. i I a 4-2
- - - " ~ - - * - ' - . - ~ ,
5.0 References
- 1. U.S. Nuclear Regulatory Commission,1979. An Acceptable Radiological Enviromnental Monitoring Program, Radiological Assessment Brancn Tecnnical Position, Revision 1, Washington, D.C.
- 2. NUS Corporation Work Instruction, P0.5.2.15.107,1983. Perfonnance of Annual Residence, Garden, and Milk Animal Survey for the Perry REMP, Revision O.
- 3. Perry Nuclear Power Plant Units 1 and 2 Environmental Report, Operating License Stage, Vol. 1, Chapter 2. The Cleveland Electric Illuminating Company.
- 4. 10 CFR Part 50, Appendix I,1984. Domestic Licensing of Production and Utilization Facilities. U.S. Nuclear Regulatory Commission, Washington, D.C.
- 5. Letter from A. E. Mitchell to R. F. Zucker, PY-NUS/CEI-1089 dated August 9,1985.
- 6. Yates , Carl R. ,1984. Perry Nuclear Power Plant Land-Use Survey for 1985, NUS-4739, prepared by NUS Corporation for The Cleveland Electric ,
~
ITTiiminating Company, November.
- 7. Webb, J., 1985. memorandun "E" - 50/2366, from J. Webb to L. O. Beck:
Radiological Environmental Monitoring Program, Milk Samples." The - Cleveland Electric Illuminating Company, December 27, 1985.
- 8. Yat es , Carl R. , 1986. Perry Nuclear Power Plant Comprehensive Dairy Survey of Early 1986, NUS-4846, prepared by NUS Corporation for the Cleve: and Electric Illuminating Company, May.
i 5-1 +
A APPENDIX A SupMutY (F THE PERRY NUCLEAR POWER PUUIT C WPREHENSIVE DAIRY SURVEY OF EARLY 1986 - - - , ,. . , , - - , - - -,-. - , _. -- ,m, , , - . - - , -. - - - _ , - , , , - - _ _ -,,,---n------,--,- ---,,---e, -------,wa-_..,-,,--,
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The following tables present the information collected for the report entitled Perry Nuclear Power Plant Comprehensive Dairy Survey of Early 1986. Table 3-1 snows the twelve dairy animal locations identified during the survey, out to 10 miles from the plant. These locations are depicted in Figure 3-1. In Table 3-3, the dairy animal locations are listed by order of decreasing D/Q. This ordering of locations can be used as a basis for the selection of new dairy animal locations for the Perry RD4P. For comparison purposes. Table 3-4 lists the locations and D/Q values for the control and indicator locations in the REMP as of September 1985. As shown in Table 3-4, the highest D/Q for a previous RD1P milk station (2.6 x 10-2) is approximately an order of magnitude larger than the highest D/Q (2.1 x 10-10) for the new locations listed in Table 3-3. D A-1
IndLE 3-1. CIW9(MfN5tTE 941WY SURVEV Nf 5HLT5 Foe Tete Pfauf muCt(An PtwEn PLAuf Neseher of Type of Feed /Graalog Personal or usee 4J. tress Cons / Goats Cous/ Goats Inforestien Ceasercial Use est sellkt neferrels
- 5. 4. . u.enell Relger BAhs) Painseville. Warren Read 55 Cows elstein lear, Corn, Gats; Primarily Commercial, Some Laessin and stesely Palaseville, elet 44017 selataal Grating Personal use (.es tk startet-4::g, Igc, and egid.80elleid Cheese factoryl
- 2. 4 .1.mo erusth.k isle tester a m 5 Goats Saanen, Alpine Clever lesy; Personal use Greig2 Palasevil!<, Oil 4407F Itinistl Gra:Ing
- 1. es.. ss:ry 4 ios.s.k 14sg ses449e aldge Seed 14 Gsats liablan Cross Buchere Goat Feed; Graring Personal Use, So.ae m et teller
- m. tis. =, sus 4405F During Ison-5now Covered Consesption Time
- 4. 'b s. ab.gningel rsten e s. ( res, time saml 7 Goats 14agenberg Chitten Scratch; Graalag Personal Use IIene p %.lisae, est evnt in the Summer e s'.ownty L ina Fee (as 4 ter, r.eller s+rtsk.cs w l 8 Goats French Alpine Buckeye Goat Feed Personal use leone fen.c es.m. est
- 6. :n . 4re msely 61st m ia..eseumaa 60 Cows Guernsey On Pasture Hay through Primarily Coasseri:lat, tausin end j
Ih esa.e. aug October; fat Feed Grown en some Personal use mobison Fare Ouring Ison-Pasture (Dalrymen,Inc.) Season
- t. so.. 1 s.n teasin sets s sp naad . 120 Cows skilstein On Pasture stay 15 through Cameercial use (Middle. Hobison aning.sen, ses Nov.1; Eat Feed Grown en field Cheese and eillk Farm during Ison. Pasture Marketing, Inc.)
Seese.t O. 'e. Iwo Nehlsen .prkt %s ry qued 50 Cows .lersey Fed in earn; May, Corn, Commercial use stasely,Lausin Ih gr g, aus Osts, all Gro.m on Farm (etiddlelleid Oseesul S l i
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TABLE 3-3. DISTANCE ANO DIRECTION AND D/Q VALUES FOR LOCATIONS INDENTIFIED IN THE COMPREHENSIVE DAIRY SURVEY FOR THE PERRY NUCLEAR POWER PLANT. Number / Type Map Name Address of Animals Distance / Direction D/Q (m-2)1 Locator
- 1. Zoldak 7459 Middle Ridge Road 14 Goats 6.5 miles E 2.1 x 10-10 3 Madison, OH 44057
- 2. Henninge 2846 S. County Line Road 2 Goats 6.8 miles E 1.9 x 10-10 4 Madison, OH 44057
- 3. Burhenne 4236 Wheeler Creek 2 Cows 8.1 miles ENE 1.3 x 10-10 12
- 4. Mosely 6153 Madison Road 60 Cows 7.9 miles SE 9.6 x 10-11 6 Thompson, OH
- 5. Stoltz 6229 Cold Springs Road 28 Cows 9.2 miles ESE 8.9 x 10-11 9
?- Geneva, OH 44041 v.
- 6. Scibona 810 Stoltz Road 100 Cows 9.3 miles ESE Geneva, OH 44041 8.7 x 10-11 10
- 7. Grabelsek 920 Stoltz Road 20 Cows 9.4 miles ESE Geneva, OH 44041 8.6 x 10-11 11
- 8. Lausin 7243 Ledge Road 120 Cows 9.8 miles SE 6.8 x 10-11 7 Thompson, OH
- 9. Rettger 13863 Painseville-Warren Road 55 Cows 9.3 miles S 5.0 x 10-11 1 Painseville, OH 44077
- 10. Keller 5888 Dewey Road 8 Goats 9.8 miles SSE 4.8 x 10-11 5
. Thompson, OH l
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_ _ _ - _ __ __~,, TABLE 3-3. DISTANCE AND DIRECTION AND D/Q VALUES FOR LOCATIONS IDENTIFIED IN THE COMPREHENSIVE DAIRY SURVEY FOR THE PERRY NUCLEAR POWER PLANT. (Cont'd) Number / Type Map Name Address of Animals Distance / Direction D/Q (m-2)I locator
- 11. Haruschak 7812 Lester Road 5 Goats 9.7 miles S 4.7 x 10-11 2 Painseville, OH 44077
- 12. Robison 8098 Dewey Road 50 Cows 10.8 miles SSE 4.1 x 10-11 8 Thomspon, OH I
D/Q' values are based on a seven-year set of meteorological data observed at Perry. 2 os f tl l l
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e f THE CLEVELAND ELECTR P.O. BOX 5000 - CLEVELAND! OHIO 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLOG. - 55 PUBLICSOUARE Serving The Best Location in the Nation MURRAY R. EDELMAN NUc February 25, 1987 PY-CEI/NRR-0590 L U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Semiannual Radioactive Effluent Release Report Gentlemen: We are hereby submitting the Semiannual Radioactive Effluent Release Report for the Perry Nuclear Power Plant, Unit 1, for the period of July 1 through December 31, 1986. This report meets the requirements of the Regulatory Guide 1.21, as applicable to the Perry Technical Specification, Section 6.9.1.7. All effluent releases were within the concentration acd release limit.s specified in the Radiological Effluent Technical Specifications. Please feel free to contact me if you have any questions. ours, Very g truly / Murray R. Edelman Senior Vice President Nuclear Group MRE:njc cc: Jay Silberg, Esq. Paul Leech (2) NRC Resident inspector USNRC Region III A
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