ML20206P066
| ML20206P066 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/31/1985 |
| From: | Alden W, Fleischmann R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8608270084 | |
| Download: ML20206P066 (17) | |
Text
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC. POWER STATION Unit Nos. 2 and 3 Docket Nos. 50-277 & 50-278 SEMI-ANNUAL EFFLUENT RELEASES REPORT NO. 20 JULY 1, 1985 THROUGH DECEMBER 31, 1985 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 & DPR-56 e
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PHILADELPHIA ELECTRIC COMPANY PEACH 30T'IVM ATOMIC' POWER STATION Unit Nos. 2 and 3 Docket Nos. 50-277 & 50-278 SEMI-ANNUAL EFFLUENT RELEASES REPORT NO. 20 JULY 1,, 1985 THROUGH DECEMBER 31, 1985 Submitted to The United States Nuclear Regulatory Commission Pursuant to i
Facility Operating Licenses DPR-44 & DPR-56 Preparation Directed By:
R.
S. Fleischmann, II, Manager Peach Bottom Atomic Power Station
TABLE OF CONTENTS Page No.
I.
Introduction
.i i II.
Tables A - Liquid Radioactive Release Data 1
B - Isotopic Analysis of Liquid 2
Radioactive Releases C - Gaseous Radioactive Release Data 5
D - Isotopic Analysia of Gaseous 6
Radioactive Ef fluents E - Classes of Solid Radioactive 8
Waste Shipments III.
Attachments
/
A - Summary of Lower Limit of Detection 10 for Gamma Isotopic Analysis B - Summary of Unplanned Liquid Release 11 C - Unplanned Liquid Release Table 13 i
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'I INTRODUCTION in accordance with the Unique Reporting Requirements of Technical Specification 6.9.2.h(2) applicable during the reporting period, this report summarizes the Effluent Release Data for Peach Bottom Atomic Power Station Units 2 and 3 for the period July 1 1985 through December 31, 1985.
The notations P and N are used to denote poedtive and i
negative exponents to Ehe base 10.
i The release of radioactive materials during the reporting period was within' the Technical Specification limits.
There were no changes to the Off-site Dose Calculation Manual (ODCM) during the reporting period.
During the reporting period some discrepancies were noted in the Lower Limit of Detection for the gamma isotopic analysis of the liquid radwaste discharges for 1985.
These discrepancies are detailed in the attachment section. -
The unplanned release of liquid radioactive material from the High Pressure Service Water -
during July 1 through December 31, 1985 reporting i
period is found in the attachment section of this r
report.
An unplanned release which occurred during the January 1 through June 30, 1985 reporting period has also been included in this section, as stated in our previous submittal.
This release began during the January 1 through June 30 report period (June 16, 1985), but did not end until the July through December report period (July 18, 1985).
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c-TAB M A PFAO{ BOPIEM LNITS 2 & 3 - 1985 LIQUID PADIOACrlVE REMASE DATA JULY AUG.
SIPP.
OCP.
NOV.
DEC.
'IUPAL Gross Activity T)
'Ibtal Curies ept Trititan 1.37N1 5.26N2 7.49N2 5.92N2 1.05N1 1.27N1 5.55N1 Average uCi/ml Gross Activity (except (1)
Tritium) at Point of Release 6.30N9 4.83N9 3.12N9 2.70N9 3.67N9 4.46N9 4.08N9
'Ibtal Curies of Trititan 2.76 9.97N1 3.50 2.22 2.55 2.49
_1.45P1 Average uCi/ml Trititan at (1)
Point of Release 1.28N7 9.162 1.46N7 1.01N7 8.902 8.732 1.07N7
'Ibtal Curies, Alpha 1.10N5 7.84N6 1.33N5 1.88N5 2.02N5 3.81N5 1.09N4 Average uCi/ml Alpha at Point (1) of Release 5.09N13 7.19N13 5.54N13 8.57N13 7.05N13 1.33N12 8.01N13
'Ibtal curies of Dissolved Noble Gases 3.98N2 7.70N4 6.49N3 9.24N4 8.45N3 1.67N2 7.31N2 Average uCi/ml of Noble Gases (1) at Point of Release 1.84N9 7.06N11 2.70N10 4.22N11 2.95NIO 5.86N10 5.38N10 Maximun uCi/ml Released (except Tritium) - at Point of Release _,
1.25N8 6.75N9 2.242 9.97N9 2.072 1.60 2 N/A
'Ibtal Voltane Gallons:
4.84P5 3.63P5 8.56P5 7.30P5 7.84P5 1.23P6
'4.45M of Waste Liters:
- 1.83P6 1.38P6 3.2414 2.76P6 2.97M 4.65P6 1.68P7
'Ibtal Voltme Gallons:
5.71P9 2.88P9 6.35P9 5.80P9 7.57P9 7.54P9 3.59P10 of Dilution Liters:
2.16P10 1.09P10 2.40PlO 2.19P10 2.86P10 2.85P10 1.36Pll (1) Average for 6 month period e
'INIIE B PFAOI BOPITN LNITS 2 & 3 - 1985 ISOIDPIC MULYSIS CF LIQUID RADICACTIVE RELFASES (In Q2 ries)
ISOPOPE JULY AUG.
SIPP.
OCP.
NOV.
DEC.
Ci TOTAL i Strontium-89 1.43N4 7.66N4 5.83N5 6.90N5 5.34N5 9.29N5 1.18N3 Strontite-90 2.75N5 1.10N5 2.66N5 3.31N5 3.26N5 9.76N5 2.28N4 Cesium-134 1.90N2 4.28N3 1.64N2 1.57N2 3.35N2 2.19N2 1.llN1 Cesium-137 2.OlN2 4.46N3 1.54N2 1.56N2 3.46N2 2.42N2 1.14N1 Iodine-131 1.06N2 2.31N3 2.73N4 8.27N3 1.49N2 3.63N2 Cbbalt-58 2.78N4 ' 8.18N4 2.41N4 7.63N5 6.89N5 2.37N4 1.72N3 Cbtmlt-60 1.15N2 1.46N2 8.37N3 7.38N3 4.41N3 7.40N3 5.37N2 Zine-65 9.86N3 2.25N2 2.26N2 1.79N2 1.17N2 3.98N2 1.24N1 Manganese-54 2.03N4 7.42N4 2.15N4 6.62N5 1.14N5 1.24N3 Otromium-51 2.88N4 1.72N3 2.0lN3 Zirconium-95 1.61N4 3.62N4 5.23N4 Manganese-56 Ianthanum-140 2.37N4 7.91N5 2.71N5 1.50N5 3.58N4 Niobium-95 6.23N4 5.52N4 6.19N5 9.28N5 3.90N5 1.37N3 Sodium-24 2.%N3 4.55N5 1.40N4 5.53N4 1.89N4 3.89N3' Yttrium-91M 3.58N5 3.58NS Xenon-135M 4.50N3 4.50N3 Iodine-133 5.38N3 9.18N4 2.34N4 6.53N3 Iodine-135 1.28N3 1.28N3 Strontitan-92 3.34N5 2.90N5 2.47N5 9.32NS 1.00N4
E
'IABIE B (Continued)
PEACH BOI'ICM LNI'IS 2 & 3 - 1985 ISOIUPIC ANEYSIS T LIQUID IMDICACTIVE RELFASES (in Curies)
ISOIDPE JULY AUG.
SIPr.
OCT.
NOV.
DEC.
Ci '1UTAL Silver-110M 1.67N4 9.95N5 4.19N4 6.86N4 Xenon-133 9.98N3 5.35N5 3.33N3 5.07N4 6.33N3' l.51N2 3.53N2 Xenon-135 2.52N2 1.55N4 3.16N3 4.17N4 2.13N3 2.30N4 3.13N2 Phosphorus-32 3.48N4 8.42NS 1.43N4 1.99N4 7.72N4 3.21N4 1.87N3 Iron-55 1.79N4 7.87N4 4.54N4 8.28N4 1.31N3 4.09N4 3.97N3 Nickel-63 Barium-140 2.49N4 2.49N4 Neptunium-239 1.07N2 1.07N2' Iodine-132
~
Tellurium-132 1.16N3 1.16N3 Xenon-131M 1.43N4 5.61N4 1.34N3 2.04N3 Krypton-85M Antimony-124 1.85U4 8.37N5 5.34N5 9.07N5 4.13N4 Iron-59 9.81N5 9.81t5 Cbpper-64 Strontium-91 Cerium-144 1.01N3 1.01N3 Technetium-99M 7.65N6 7.65N6 Pblybdenum-99 6.03N5 7.00N6 6.73N5 Cadmium-109 1.85N3 1.85N3 TABIE B (Continued)
PEAOI BOI'KM INITS 2 & 3 - 1985 ISO 1IFIC ANALYSIS T LIOUID i
IRDIOACTIVE RETASES (in Curles)
N.
JULY AUG.
SEPT.
OCT.
NOV.
DBC.
Ci 'IUPAL e
Cesium-136 3.68N4 1.77N4 5.45N4 TOTAIS 1.37NL 5.2EN2 7.49N2 5.92N2 1.05N1 1.27N1 5.55NL, Body Dose (Milliren) 1.08N1 7.16N2 2.80N1 1.34N1 2.45N1 3.22N1 1.16
% of Year Tech. Spec. 1.80 1.20 4.67 2.23 4.08 5.37 19.35 Bone Ibse (Millirem) 8.07N2 5.33%
2.04N1 9.87N2 1.84N1 2.40N1 8.61N1
% of Year 'Ibch Spec. O.40 0.27 1.02 0.50 0.92 1.20 4.31
- Iess than minimum detectable
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TABIE C PFACH BOP 101LNITS 2 & 3 - 1985 GASEDUS FADICACrlVE RELEASE DATA JULY M II.
SEPT.
OCP.
NtN.
DEC.
'IUTAL Mixed Noble Gases (Ci) 1.74P4 3.27P2 3.97P2 4.15P2 1.03P3 4.83P2 2.01P4
. % of Tech. Spec. for Gama 0.32 0.16 0.10 0.11 0.10 0.10 0.89 Air Dose (2)
% of Tech. Spec. for Beta 0.19 0.03 0.02 0.02 0.03 0.02 0.31 Air Dose (2)
Iodine-131 (Ci) 1.26N2 9.82N4 4.91N4 2.49N4 7.16N4 1.86N3 1.69N2 (uCi/Sec.)
4.16N3 4.06N4 2.0'"*
8.22N5 2.%N4 7.69N4 1.07N3
% of Tech. Spec. for Critical 0.19 0.02 0.008 0.004 0.006 0.03 0.26 Organ (I-131) (3) t Particulates >8 Day Half Life (Ci)'
l.48N3 3.16N4 2.07N4 2.28N4 1.50N4 3.58N4 2.74N3 (uCi/Sec.)
4.89N4 1.31N4 8.56N5 7.54N5 6.20N5 1.45N4 1.74N4 l
Particulate Al ha (Ci).
2.36N5 9.56N6 1.29N5 5.46N5 1.17N5 9.65N6 1.22Ni I
i f
Tritilum (Ci)
(4) 7.03N1 5.62N1 5.62N1 2.06 1.65 1.65 7.19 i
(uCi/Sec.)
(4) 2.32N1 2.32N1 2.32N1 6.81N1 6.81N1 6.81N1 4.57NL Max. Nticle Gas Release Rate 6.06P4 8.58P2 2.31P4 8.57P3 5.03P4 6.2]P3 N/A l
(uci/Sec.)
Date:
7-15 8-13 9-19 10-17 11-29
, 12-26 N/A Maximum % of Tech. 'IUPAL BODY (1) 19.7 0.45 2.35 0.91 5.15 0.60 N/A Spec. Limit for SKIN (1) 3.95 0.09 1.27 0.48 2.77 0.34 N/A Noble Gases (1) Basis Tech. Spec. 3.8.C.,1 (applicable during reporting period)
(2) Basis Tech. Spec. 3.8.C.2 (applicable during reporting period) i (3) Basis Tech. !bec. 3.8.C.3 (applicable during reporting period)
(4) Quarterly analysis used for armthly estimate TABIE D 6
PFAW BOI'KM LMITS 2 & 3 - 1985 ISOIT)PIC ANALYSIS OF GASEOUS RADImCTIVE REIEASES (In Curies)
ISOIOPE JULY AUG.
SEPP.
OCf.
NOV.
DEC.
Ci 'IUTAL Krypton-87 5.08P1 1.82P1 4.48P1 1.14P2 Krypton-88 8.52P1 2.80P1 3.40P1 1.21P2 2.68P2 Xenon-133 1.56P4 2.60P1 1.88P2 4.10P1 6.80P2 2.34P2 1.68P4 Xenon-133M 3.86P2 9.49 2.09 3.98P2 Xenon-135 9.43P2 1.23P2 1.42P2 2.16P2 1.72P2 9.56P1 1.69P3
~
~
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Xenon-135M '
l'.46P2 2.27P1 3.76P1 5.77P1 3.91Fl' 3.03P2 Xenon-138 1.28P2 1.28P2
~ ],
- 3
'Ibtal
' l.73P4 1.72P2' 3.67P2 3.60P2 9.77P2 4.82P2 1.97P4'
/
-I N2 9.82N4 4.91N4 2.49N4 7.16N4 1.%N3 1.69N2 Strontita-89 6.09N4 4.91N5 5.34N5 7.57N5 6.04N5 i.62N5 8.64N4 Strontita-90
-7.89N6 3.66N6 6.34N6 1.11N5 6.60N6 6.35N6 4.19N5 Baritan-139 9.39N3 5.66N4 3.81N4 1.12N3 4.79N4 1.07N4 1.20N2 Desita-134 9.87N5 3.94N5 2.52N5 1.09N5 4.80N6 2.19N5 2.OlN4 Cesitan-137 1.24N4 4.59N5 2.63N5 8.97N6 8.20N6 3.88N5 2.52N4 Ianthanum-140 2.45N4 2.36NS 2.62N5 2.67N5 3.27N5 3.54N4 02 alt-58 2.61NS 9.50N6 2.28N5 5.84N5 O& nit-60 l.13N4 2.99N5 3.58N5 6.OlN6 3.4N6 9.19NS 2.80N4 TABLE D (Continued)
PEAO! BOI"IIM LNITS 2 & 3 - 1985 ISOIDPIC MRLYSIS T GASIDUS '
RADIOACTIVE RE1 EASES (In Curies)
ISOIDPE JULY ALX3.
SIPP.
OCP.
NOV.
DEC.
Ci 'IUPAL Zinc-65 5.67NS 1.14N4 2.40N6 1.25N5 8.2N6 1.42N4 3.36N4 Msnganese-54 2.95N6 2.95N6 i
Strontita-91 8.18N4 1.30N4 5.10N5 6.llNS 3.08N5 1.09N3 s
Iodine-133 9.62N5 2.80N6 1.10N6 1.00N4 Otrcznism-51 Soditm-24 3.97N5 1.34N5 5.31N5 Cesinn-138 9.53N2 1.44N3 7.13N4 2.87N3 9.51N4 8.04N4 1.02N1 Baritan-140 4.26N4 2.51N5 4.49N5 4.90N5 4.7N5 5.60N6 5.98N4 -
Yttrita-91m 4.54N3 8.04N5' l.67N4 2.15N4 9.50N5 5.10N3 Rubiditan-88 1.67N2 1.22N4 1.68N2 Ctpper-64 1.31N3 1.31N3 Rubiditm-89 1.23N4 6.01N5 1.83N4
'1UrAIS 1.30N1 2.56N3 1.53N3 4.70N3 1.79N3 1.27N3 1.42N1
- Iess than minimum detectable.
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o TABLE E PEA m BOPIM IEITS 2 & 3 July 1 to Decemter 31, 1985 CIASSES CF SCLID PADIOACTIVE WASTE SHIPMENTS Total #
mate Description Cbntainer/ Type Individual Total
'Ibtal Principal
'of Shipnents (Souwe of Waste)
~(bntainer (Waste & Cbntainer) Curie Ihdionuclides Voltme Volume Class A 37 Dewatered Resin HIC /IEA 7.5 Ft.
3885 Ft.
3.388Ci Zn-65, Cs-134 i
Solidified Liquid 55 Cal. Drum /
7.5 Ft.
2805 Ft.
4.854Ci Zn-65, C W ISA Type A Cask Cs-137, H-3 C-14 t
12 Oczyncted Trash Strong Tight 98 Ft.
15197 Ft.
4.893Ci Cb-60, Cs-137 Cbntainer/ISA C-14, H-3 Type A Flatbed 6
Non Otmpacted 55 Gal. Drum /
7.5 Ft.
1545 Ft.
3.803Ci O W, Cs-134 Trash IEA Type A Cask Cs-137, C-14 11-3 15 Ocznpacted & Non Strong Tight 98 Ft.
19972 Ft.
4.891Ci Co-60, Cs-134 CcunIncted Trash Cbntainer/ISA C-14, H-3 Mixed Shipments Type A Flatbed Za-65 4
Non-Otzupacted 55 Gal. Drum /
7.5 Ft.
1785 Ft.
8.749Ci Zn-65, Cb-60
& Solidifled ISA Type C-14, Cs-134 Trash & Liquid A Cask Cs-137, H-3 Class B 36 Dewatered Resin HIC /IEA 7.5 ft.
3675 Ft.
900 Ci Zn-65, Cs-134 Type A Cask Cb40, Cs-137 -
TABLE E (Continued)~
PEAm BOPITM LNI'IS 2 & 3 July 1 to December 31, 1985 CLASSES OF SOLID IMDIOPCTIVE NNTIE SHIPPENTS 1
'Ibtal #
mate Description Cbntainer/ Type Individual
'Ibtal
'Ibtal Principal of Shipments (Source of Waste)
Container (Waste & Cbntainer) Curie Ibdiornclides Volume Volume 2
Class A & B 3
3 i
20 Dewatered Resin HIC /LSA 7.5 Ft.
2100 Ft.
304.51Ci Zn-65, Cs-134 Type A Cask
, Co40, Cs-137 Class A & B 3
.Dewatered Resin HIC /ISA 7.5 Ft. 3 315 Ft. 3 36.753 Ci Zn-65, Cs-134 Pbn Conpacted Trash Type A Cask 0o40, Cs-137 Class C
~
3 D e tered Resin HIC / Type B 7.5 Ft. 3 105 Ft.3 570.21Ci CR-51,th-54 0o-58, Zn45 Cs-134, Cs-137 0o40 i
t l
15 (bntrol Rod Blades HIC / Highway 26.2 Ft. 3 393 Ft.3 108364.26Ci (b40, 1%-55 Route controlled th-54, Ni-63 (Iarge Quantity)
p Attachment,A
SUMMARY
OF LOWER LIMIT OF DETECTION FOR GAMMA ISOTOPIC ANALYSIS PEACH BOTTOM UNITS 2 AND 3 JANUARY 1 THROUGH DECEMBER 31, 1935 During the period of January 1985 through June 1985, seventy-nine liquid radwaste tanks of a total of 175 ta'nks were processed for release based on analytical results from one of two high resolution gamma detectors which failed to meet the lower limit of detection (LLD) for Ce-144 as defined-in Technical Specification, Table 4.8.1.
The LLD for the two detectors were determined to be 6.25 E-07 uCi/ml and 9.58 E-07 uCi/ml which are respectively 25% and 92% above the minimum allowable value of 5.0 E-07.
All other releases were analyzed on a third detector which meets LLD requirements.
The two detectors failed to meet the LLD requirement due to higher background count rates than that of the third detector.
These highe'r background count rates caused interferences in the measurement of the Ce-144, and thus reduced the sensiti'vity of the instrumentation.
Initial determinations of the LLD values for the two detectors were performed in January, 1985.
These results had indicated that all LLD values were within the acceptable limits.
However, a follow-up determination in June, 1985 revealed that the January results had been based on incorrect efficiency calibration data.
Re-analysis with the correct calibration data produced the aforementioned values.
Upon discovery of the problem, the two detectors in question were placed out of service, and all liquid radwaste gamma scans were performed on the other detector.
Subsequently, a daily monitoring program was initiated to determine the LLD on the detector being used for liquid radwaste discharges.
It was noted that on three occasions during the period from October 24, 1985, through December 31, 1985, the LLD requirement was exceeded despite the fact that background activities had not increased.
These occurrences are regarded as statistical fluctuations.
In addition to the immediate corrective action for placing the two detectors out of service, a long-term corrective action is currently being investigated.
Since a more efficient analytical geometry (one liter Marinelli beaker) would produce a lower limit of detection than our current geometry (one liter bottle), a one liter Marinelli beaker geometry will be put in use if the NBS-traceable standard shows a significant improvement in the LLD values.
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Attachtsnt B SUMNARY OF UNPLANNED LIQUID RELEASES PEACH BOTTOM UNIT 2 AND 3 JANUARY 1985 THROUGH DECEMBER 1985 i
3A AHR Heat Exchanger Release via HPSW A leak was found to have occurred in the 3A RHR hhat exchanger from June 16, 1985 to July 18, 1985.
A leak test was performed on July 19, 1985.
Nuclide fractions from the highest activity HPSW sample were applied to the average. concentrations based on the radiation monitor's strip chart.
The sample pump flow rate of 3 GPM was used as the leak rate.
This is a conservative estimate since the sample pump was not continuously running.
The calculated doses are based on the methodology presented in the ODCM.
3D RHR Heat Exchanger Release via HPSW A leak was found to have occurred in the 3D RHR heat exchanger from October 2, 1985 to October 11, 1985.
A leak test was performed on October 9, 1985, with a leak rate of 1 liter per minute identified with the HPSW side pressurized.
The sample l
pump flow rate of 3 GPM was used as the leak rate, which is more conservative than the identified leak rate, even though.the sample pump was not operating continuously.
Nuclide fractions from a HPSW sample were applied to the average concentrations 3
based on the radiation monitor's strip chart.
The calculated doses are based on the methodology presented in the ODCM.
Unplanned Liquid Release via 3A HPSW This possible leak was detected by a peak occurring on the HPSW radiation monitor on October 19, 1985.
No grab sample could be obtained because of the short duration of the release.
The calculated doses are based on the methodology presented in the ODCM assuming a release rate' ef 3 GPM and average release concentrations based on the radiation monitor's strip chart.
Due -
to the short duration of this leak it is suspected to be a i
possible radiation transient at the radiation monitor.
l Unplanned Liquid Release via 2B HPSW This possible leak was detected by a peak occurring on the HPSW i
radiation monitor on October 20, 1985.
No grab sample could be i
obtained because of the short duration of the release.
The calculated doses are based on the methodology presented in the ODCM assuming a release rate of 3 GPM and average release
~
concentretions based on. the radiation monitor's strip chart.
Due to the short duration of this leak, it is suspected to be a possible radiation transient at the radiation monitor... -
Attachm2nt B (Continusd)
Unplanned Liquid Release via 3A HPSW This leak was detected by a peak occurring on the HPSW radiation monitor on October 21, 1985.
A grab sample during the peak was l
obtained which showed detectable activity but later samples had no activity identified.
Thc calculated doses are based on the methodology presented in the ODCM assuming a release rate of.3 GPM and average releasc concentrations based on the grab sample obtained.
No leak test ' was performed because samples following the radiation monitor's spike showed no levels of activity.
4 2D RHR Heat Exchanger Release via HPSW A leak was found to have occurred in the 2D RHR heat exchanger
~
with a duration of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> on December 1, 1985.
A leak test was performed on December'2, 1985 with the RHR side pressurized and a leak of 0.3 liter per minute was identified. 'Nuclide fractions from the HPSW sample were applied to the average concentrations based on the radiation monitor's strip chart.
The sample pump flow rate of 3 GPM was used as the leak rate.
This is a, conservative estimate since the sample pump was not continuously running.
The calculated doses are based on the methodology presented in the ODCM.
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O PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 2isi e414ooo February 26, 1986 Docket No. 50-277 50-278 Mr. T.
E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.
19406
Subject:
Semi-Annual Effluent Releases Report No. 20, July 1 through December 31, 1985 Peach Bottom Atomic Power Station Unit Nos. 2 and 3
Dear Mr. Murley:
Enclosed are two copies of the Semi-Annual Effluent Releases Report No. 20, July 1 through December 31, 1985, for Peach Bottom Atomic Power Station Unit Nos. 2 and 3.
This report is being submitted in compliance with the Technical Specification of Operating Licenses DPR-44 and DPR-56, and to fulfill the requirements of, Regulatory Guide 10.1 Very truly yours,
/
W. M. hlden Engineer-in-Charge Licensing Section Attachme'ts n
cc:
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 T. P. Johnson, Site Inspector
_