ML20062H215
| ML20062H215 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/30/1987 |
| From: | CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | |
| Shared Package | |
| ML20062H213 | List: |
| References | |
| NUDOCS 9012040176 | |
| Download: ML20062H215 (8) | |
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Semi-Annual Radioactive Effluent Release Report For the Year 1987 Quarters 1 and 2 (Revision) r-l \\ (', 1, R
RADIOLOGICAL IMPACT ON MAN Sampling and analysis of liquid and gaseous effluents were performed in accordance with the frequencies, types of analysis, and Lower Limits of Detection (LLD) outlined in the PNPP Unit 1 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 and.0 CFR 50, Appendix I limits. Direct radiation 1 resulting from plant operation did not contribute any measureable dose to members of the public for the reporting period and, as there are no other nearby fuel cycle sources, 40 CFR-190 limits were not exceeded. Summaries of maximum individual and population doses resulting from liquid and gaseous radioactive, effluent releases are given, in Regulatory Guide 1.21 format, in Attachment 1. Technical Specification 6.9.1.7 requires assessment of. radiation doses from radioactive liquid and gaseous effluent to members of the public while onsite. These onsite. doses are assessed relative to offsite dose values,-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. CHSITE DOSE FOR LIQUID EFFLUENTS Total Body Organ
- 5.0 E-T mrem 5.8 E-7 arem (skin)
Quarters 1 & 2 Quarter-1 4.9 E-7 mrem 5.7 E-7 mrem (skin) Quarter 2 ' l.1 E-8' mrem 1.3 E-81 mrem (skin) 2
A Severa' 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-05 s/m cu, and the hightat offsite, i.e., site boundary value, 4.2 E-6 s/m cu, (a unity occupancy factor is used for this calculation), the following maximum onsite dose values are generated: ONSITE DOSE FOR GASEOUS EFFLUENTS Total Body Organ Quarters 1 & 2 2.2 E-02 mrem 4.2 E-02 mrem (skin) Quarter 1 1.7 E-02 mrem 3.3 E-02 mrem (skin) Quarter 2 5.2 E-03 mrem 9.5 E-03 mrem (skin) Average totcl body dose to individual members of the public is determined for the population that lives within fifty miles of the plant for gaseous effluents (2.42 E6 persons) and the population that receives drinking water from intakes within fif ty.ailes fot liquid effluents (2.37 E6 persons). These doses are calculated using the total population dose figures found in. AVERAGE INDIVIDUAL TOTAL BODY DOSES Gases Liquid j Quarters 1 & 2 4.0 E-7 meem 1.3 E-6 mren Quarter 1 3.1 e-7 mrem 4.0 E-7 mrem l Quarter 2 8.7 E-8 mrem 9.1 E-7 mrem l Sr-89, among other radionuclides, has a quarterly minimum analysis frequency (PHPP Technical Specification 4.11.2.1). The Sr-89 quarterly analysis result for a portion of the fourth l quarter of 1986, pericrmed in accordance vith that Tecnnical Specification, was not available when the last SRERE was generatec. (The quarterly composite period covered December 29. l 1986 to March 30, 1987.) Therefore, doses for the fourth quarter of 1986 have to be amended. l Done attributed to that Sr-89 composite analysis (1.69 E-7 C1) was 1.55 E-6 nrem. This conservatively increased the 1986 I Quarter 4 gaseous pathway dose f rom 5.24 E-4 to 5. 26 E-4 arem.- but population and onsite dose values reported are not affected. Administrative steps have been taken to preclude a recurrence of l this type, l 3 l l
LIQUID EFFLUEgli For the first quarter of 1987 there were 64 batch and 87 continuous releases. first Batch release total waste volume for the volume was 4.08 E9 liters; quarter was 8.38 E6 liters; total continuous release waste total plant discharge during periods of release was 1.95 E10 liters. For the second quarter of 1987 there were 51 batch and 92 continuous releases. Batch release total waste volume for the second quarter was 5.86 E6 liters; total continuous release l 1 l waste volume was 4.12 E9 liters; total plant discharge during periods of release was 1.67 E10 liters. 1 l Summaries of the radionuclide total curie activities, average l diluted concentrations, and percentage of MPC (in Regulatory Guide 1.21 format) are included in Attachment 4. 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 i the Lower. Level of: Detection.(LLD) of the-instrumentation used. In all cases, these.LLDs were less than the levels required by the Technical Specifications. The following are typical LLDs: Radionuclide LLD ( Ci/ml) Mn-54 2.4 E-08 Fe-59 5.8 E-08 Co-58 1.9'E-08 Co-60 3.4 E-08 Zn-65 4.6 E-08 Mo-99 2.1 E-07 I-131 2.3 E-08 Cs-134 2.3 E-08 Cs-137 2.6 E-08 Ce-141 3.2 E-08 Ce-144 1.3 E-07 Sr-89 3.0 E-08 Sr-90 3.7 E-08 re-55 5.7 E-09 H-3 4.6 E-06 l Gross Alpha 6.0 E-08 l 1 o l (Continued - Page 1 of 3) Radiolorical Imnact on Man (Dose Summaries) i Quarters 1&2 I
SUMMARY
OF MAXIh0M INDIVIDUAL DOSES LAST ACCUMULATIGHS FOR PERIODS: LIQUID 87 1 1 1-97 430:4 o GASEGUS 87 1 1 1-47 63004 AIR 87 1 1 1-37 $3004 APPLICABLE ESTIMATED AGE LOCATICH % OFLIh!T EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE <hA) (MREh) (M) (TOWARD) LIMIT LIQUID TOTAL BODY 2.51E.05 CHILD RECEFTOR 1 8.4E-04 30 LIQUID 01-TRACT 3.338 05 ADULT RECEPTOR 1 3.38-04, 10.0 -NOBLE GAS AIR DOSE 9 18E-01 273. NW 9.2E-01 10.0 (OAMMA-MRAD) NOBLE GAS AIR DOSE 8.17E-02 273. NW. 4 1E-01 20.0 (BETA-MRAD) NOBLE GAS T. BODY' 2.04E-01 ALL 273. NW 4.1Et00 5.0 NOBLE GAS-- SKIN .. 3.93E-01 ALL 273. NW 2.4Et00 15.0 IODINEt THYROID 3.35E-04 CHILD 283. WNW' 2.2E-03 15.0 PARTICULATES }
SUMMARY
OF POPULATION DP4ES. l LAST ACCUMULATIONS-FOR PERIODS:' i LIQUID 87 1 1 1 87 43024 OASEQUS 87 1 1 1-87 630 4 q EFFLUEhT APPLICABLF.- ESTIMATED LI QRGAN POPULATION DOSE' i (PERSOM-REM) .g./E.032E-03 'I LIQUID-TOTAL 80DY LIQUID THYROID-M OASEGUS' TOTAL BODY f.7E-04 0ASEQUS THYROID 1.0E-03 : 08 G l
l l (Continued - Page 3 of 3) Radiological Impact on t'en (Dose Summaries)- Quarter 2
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS: LIQUID 97 4 1 1-97 63024 GASEOUS 87 4 1 1-B7 63024 AIR 37 4 1 1-37 630 ...............................................24...................... APPLICABLE ESTIMATED AGE LOCATION
- . OFLIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MR)
(MREM) ( M -) (TOWARD) LIMIT LIQUID TOTAL BODY 1.91E.05 CHILD RECEPTOR 1 6.4E.04 3.0 LIQUID GI-TRACT 1.9BE-05 CHILD RE ...................... CIFTOR : 2.OE.04
- c.)
HOBLE GAS AIR DOSE 3.56E-02 430. V 3.6E 01 10.0 (OAMMA. MRAD) NOBLE GAS AIR DOSE 1.84E.02 430, y 9.2E.02 20.0 (3 ETA-MRAD) NOBLE GAS T. BODY 4.86E-02 ALL 273. NW 9.7E.01 5.0 . NOBLE GAS :SKIH- .............. 8. 87E 02.AL.L..,. 273....... 9E.01 15.0 NW 5 IODINEt THYROID 3.35E-04 CHILD 293. EMW 2 2E-03 15.0 PARTICULATES
SUMMARY
OF POPULAT!ON COSES LAST ACCUMULATIONS FOR PERIODS:'
- t. I GLTI-37 4 1 1-I' 510 4 JASIGUS 87 4 1 1-57~
........................................... 63024 EFFLUENT-AFF t.! C A BLE ESTIMATED GRGAN POPULATION-DOSE <PERS ............................................OH-REM LIQUID TOTAL BODY 2.2E.03' LIQUID THYROID 2.2E-03 GASEOUS TOTAL BODY 2.1E-04 GASEQUS THYROID 2.6E-04 1 1
c Att.achment 3 (Continued - Page 1 of 2) Licuid Effluents QUARTER : : START DATE S7010101 END DATE 3702:124 QUARTER 2 : START DATE 87040101 END DATE 87003024 LIQUID EFF',UENTS ! UNITi : QUARTEP. I' QUAPTER 1 2 A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (EXCL.: CI
- 8.31E-04 : 1.17E.03 TRIT.: GASES: AL?HA):
- 2. AVERAGE DILUTED
- UCI/ML : 4.27E-11 :
7.04E.11 CONC. DURING PERIOD : i 1.3.' PERCENT OF
- - 2.43E-04 :
2.72E-05 MPC
- 3. TRITIUM
.1 1 TOTAL RELEASE
- CI 1.53E.01 : 6.29E.01
- 2. AVERAGE DILUTED
- UCI/ML : 7.85E-09 : 3.78E.08 :
CONC. DURING PERIOD : 1 3. PERCENT OF. 1.60E-03 : 1.07E.02 MPC 1 C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE
- CI 1.77E-05 : -8.09E-05
- 2. AVERAGE DILUTED
. UCI/ML ' f.0tE-13 4.88E-12 CONC. DURIN6 PERIOD : 1-j3.PERCENTOF I
- 4 54E-07 :
MPC 2.428 06 i.. D. GROSS-ALPHA RADI0 ACTIVITY
- 1. TOTAL RELEASE'
- CI
.00E+00 : 6.02505l-E. VOLUME WASTE RELEASED LITERS : 4 08E+09 : 4 11E+09 : ,c (PRIOR TO DILUTION) F; VOLUME. DILUTION WATER : LITERS : 1 95E+10 : 1.47Et10 :
- ' USED DURING PERIOD e e
At achment 3 (Continued - Page 2 of 2) Liouid Effluents 1 LIQUID EFFLUENTS QUARTER 1 : START DATE 87010101 END DATE 87033124 QUARTEa 2 : START DATE 87040101 END DATE 87063024 CONTINUOUS MODE BATCH MODE NUCLIDES
- UNITS : QUARTER : QUARTER :
QUARTER QUARTER RELEASED 1 2 1 2 H3
- CI
- 0.00Ef00 : 0.00E+00 :
1 53E-01 : 6.29E-01 o CR51
- CI
- 0.00Ef00 : 0.00Ef00 :
1.39E-04 : 1.07E-03 C058
- CI
- 0.00E+00 : 0.00Ef00 : -6.92E-04 l' O.00E+00 AS76
- CI
- 0.00E+00 : 0.00Ef00.:
0.00E+00 : 1.01E-04 TOTAL FOR 'i.CI i 0.00EMC i 0.00E+00i 1.54E-01'i 6.30E-01 PERIOD (A30VE) 1 i XE135
- CI
- 0.00EM0 : 0.00E+00 :
1.77E-05 : 1.91E.05 XE133
- CI
': 0.00E+00 : 0.00E+00 : 0.00E+00 : 6.18E-05 i. l. r 4 i ( -}}