ML20196F266
| ML20196F266 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/31/1987 |
| From: | Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Russell W NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8803020143 | |
| Download: ML20196F266 (19) | |
Text
i PHILADELPHIA ELECTRIC COMPANY PHILAD ELPHI A PEACH BOTTOM ATOMIC POWER STATION Unit Nos. 2 and 3 Docket Nos. 50-277 & 50-278 SEMI-ANNUAL EFFLUENT RELEASES REPORT NO. 24 JULY 1, 1987 THROUGH DECEMBER 31, 1987 Submitted to The United States Nuclear Regulatory Commission Pursuant to Fac!;ity Operating Licenses DPR-44 & DPR-56 8803020143 871231 PDR ADOCK 05000277 R
j PEACH BOTTOM ATOMIC POWER STATION Unit Nos. 2 and 3 Docket Nos. 50-277 & 50-278 SEMI-ANNUAL EFFLUENT RELEASES REPORT-NO. 24 JULY 1, 1987 THROUGH DECEMBER 31, 1987 i
l l
l Submitted to The United Statvs Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 & DPR-56
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. 24 JOIY 1, 1987 THROUGH DECEMBER 31, 1987 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPK-44 & DPR-56 Preparation Directed By:
D. M. Smith, Vice President Peach Bottom Atomic Power Station i
t
'i. +
TABLE OF CONTENTS Pace No.
.I.
Introduction 11 II.
Tables' IA.
Gaseous Effluents - Summation 1
of All Releases IB.. Gaseous Effluents For Release 2
Point - Main Stack IC.
Gaseous Effluents For Release 4
Point - U/2 & U/3 Roof Vents 2A.
Liquid Effluents - Summation of 6
All Releases 2B.
Liquid Effluents 7
3.
Classes of Solid Radioactive 9
Waste Shipments
.III.
Attachments A.
Supplemental Information 10 l
B.
Summary of Unplanned Releases 12 l
l l
Technical Concurrences: (for accuracy of information) l
'r lWC W$n kt h?, fh.l.f4d$ c$
N&
l f7 Director-Radiation Protection D' ate o/,!
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_I
-2.' 2 i. ?? /!
ll A(lk Q/ bh I
L Director-Radwastes Date !
I.
INTRODUCTION In accordance with the Unique Reporting Requirements of Technical Specification 6.9.2.h(2) applicable during the report period, this report summarizes the Effluent Release Data:for the Peach Bottom Atomic Power Station Units 2 and 3 for the period July 1 through December 31, 1987.
The notations E and E-are used to denote positive and negative exponents respectively, to the base 10.
The release of radioactive materials during the report period was within the Technical Specification limits.
There were no changes to the Offsite Dose Calculation Manual (ODCM) during the reporting period.
Two unplanned releases of liquid radioactive material occurred from High Pressure Service Water (HPSW) during the report period.
These events are discussed in the attachment section of the report.
Iodine was not detected from either the roof vents or main stack (see Gaseous Effluents - Table 1A), thus, the critical organ dose for iodines, in mrem, was zero.
Therefore, a conservative approach was taken in accordance with a proposed revision to the Offsite Dose Calculation Manual (ODCM) to calculate the critical organ dose using the particulates with half-lives greater than 8 days.
These calculations are incorporated into Attachment B of the report.
Upon approval of the proposed revision to the Offsite Dose Calculation Manual (ODCM), the iodine dose calculation will be written into the appropriate tables of the next Semi-Annual Report.
In section labeled Liquid Effluents (Table 2B) the l
Phosphorus-32 reported value is less than the Lower l
Limit of Detection.
Phosphores-32's half-life has been exceeded by a factor of eight half-lives, therefore, Phosphorus-32 is reported as zero for this reporting l
period.
In general, any isotopes experiencing decay by i
a number of half-lives greater than a factor of eight j
are reported as zero.
I l t
f TABLE lA
~
- EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT (19878) f,A UM C rFFLUFWTS StJMMATION OF All REl.EtC Unit
. Quarter Quarter Est.. Total 2&3 3
4 Error,.%
1
^
TA.' Fission & activation! gases
.l.. Total release Ci 3.19 E2 3.05 E2
- 54.0 EO 2.-Average reiease rate for period uCi/sec 4.06 El 3.88 El
- 3. Samma Air Dose Millirad 5.24 E-2 3.74 E-2 Percent of Tech. Spec.
5.24 E-1 3.74 E-1 4.-Beta Air Oose Millirad 2.24 E-2 1.83 E-2
~
Percent of Tech. Spec.
i.12 E-1 9.15 E-2 B. Iodines t
s
<l.-Total iodine-131 Ci 0
0 61.0 E0 4
- 2. Average release rate for period uCi/sec 0
0
- 3. Critical Organ Oose Millirem 0
0 Percent of Tecn. Spec.
0 0
C. Particulates
- 1. Particulatet wit.5 Acif-lives greater than
~8 days (ir.cludes Alpha-and Strontium 89-90)
Ci 4.53 "-4 4.23 E-4 61.0 E0
. 2. Avertge release rate for period uCi/sec 5.76 E-5 5.38 E-5
- 3. Gross Alpha Radioactivity Ci 3.31 E-5 3.39 E-5 e
D. Tritium
- 1. Total release Ci 1.96 E0 1.90 EG-94.0 E0
- 2. Average release rate for perioo uCi/sec 2.48 E-1 2.41 E-1 4
(1)
4-TABLE'lB' T
EFFLUENT AND WASTE-DISPOSAL SEMIArmuAL REPORT (1987L) 2 GASE0US EFFLUENTS FOR RELEASE POINT: MAIN SIACK j;7 f
~
CONTINUOUS MODE BAiCH MODE
- Nucliaes Released Unit Quarter Quarter Quarter-Quarter 2&3 3
4
. 3~
4-1
- 1. Fission gases
-Krypton-85M Ci 0
0 0
0 Krypton-87 Ci 0
0 0
0 Krypton-88 Ci 0
0 0
0 Xenon-133 Ci 0
0 0
0 Xenon-135 Ci 0
0 0
0 Xenon-135M.
Ci 0
0 0
0 Xenon-138 Ci 0
0 0
0
.L l
Unidentified C1 2.35 E2 2.46 E2 0
0 Total for period C1 2.35 E2 2.46 E2 0
0-2, lodines l
. lodine-131 Ci 0
0 0
0 lodine-133 Ci 0
0 0
0 lodine-135 Ci 0
0 0
0 Total for period Ci 0
0 0'
O i
L3.Particulates Strontium-89 Ci 4.50 E-7 4.50 E-7 0
0 Strontium-90 Ci 2.40 E-7 2.20 E-7 0
0 l=
Strontium-91 Ci 0
o 0
0 i
i Cesium-134 Ci 0
0 0
0 (2) l
/
4
,e>
-v s
a y
TABLE IB (Continued)
CONTINUGUS MODE BATCH MODE Nuclices Released Unit Quarter Quarter Quarter Quarter 2&3 3
4 3
4 Cesium-137 Ci 0
0 0
0 Cesium-138 Ci 0
0 0
0 Barium-139 Ci 0
0 0
0 Barium-140 Ci 0
0 0
0 Lanthanum-140 Ci 0
0 0
0 Cobalt-57 Ci 0
0 0
0 Cobalt-58 Ci 0
0 0
0 Cobalt-60 Ci 0
0 0
0 Zinc-65 Ci 0
0 0
0 Yttrium-91M Ci 0
0 0
0 lodine-133 Ci 0
0 0
0 Copper-64 Ci 0
0 0
0 Rubidium-88 Ci 0
0 0
0 Manganese-54 Ci 0
0 0
0 Strontium-92 Ci 0
0 0
0 Caamium-109 Ci 5.24 E-6 0
0 0
Totals Ci 5.93 E-6 6.70 E-7 0
0 (3)
TABLE 1C EFFLUENT AND WASTE DISPOSAL SEM1AkkUAL REPORT (19878)
~
GASE005 EFFLUENTS FOR RELEASE POINT: U/2 & U/3 Roof Vents CONTlhuGUS MODE BATCH MODE Nuc'lides Released Unit Quarter Quarter Quarter Quarter 2&3 3
4 3
4
- 1. Fission gases Krypton-85M Ci 0
0 0
0 Krypton-87 Ci 0
0 0
0 Krypton-88 Ci 0
0 0
0 Xenon-133 Ci 0
0 0
0 Xenon-135 Ci 0
0 0
0 Xenon-135M
~
Ci 0
0 0
0 Xenon-138 Ci 0
0 0
0 xenon-133M Ci 0
0 0
0 Unicentified Ci 8.41 il 5.84 El 0
0 Total for perica Ci 8.41 El 5.84 El 0 -
0
- 2. lodines lodine-131 Ci
-0 0
0 0
~~' lodine-133 Ci 0
0 0
0 locine-135 Ci 0
0 0 ~~
0 Total for period Ci 0
0 0
0
- 3. Particulates Strontium-E9 Ci 1.99 E-5 2.21 E-5 0
0 Strontium-90 Cl 9.86 E-6 1,20 E-5 0
0 Strontium-91 Ci 0
0 0
0 Cesium-134 Ci 0
0 0
0 Cesium-137 Ci 6.53 E-5 2.87 E-5 0
0 (4)
TABLE 1C (Continuec)
CONTIt4UOUS MODE BATCH MODE t<uclides Released Unit Quarter Quarter Quarter Quarter 2&3 3
4 3
4 Cesium-138 Ci 0
0 0
0 Barium-139 Ci 0
0 0
0 Barium-140 Ci 0
0 0
0 Lanthanum-140 Ci 0
0 0
0 Cobalt-57 Ci 0
0 0
0 Cobalt-58 Ci 0
0 0
0 Cobalt-60 Ci 1.64 E-4 1.80 E-4 0
0 Zinc-65 Ci 1.58 E-4 2.12 E-4 0
0 Yttrium-91M Ci 0
0 0
0 lodine-133 Ci 0
0 0
0 Copper-64 Ci 0
0 0
0 Rubidium-88 Ci 0
0
~0 0
s Manganese-54 Ci 0
0 0
0 Strontium-92 C1 0
0 0
0 Totals Ci 4.17 E-4 4.55 E-4 3
0 l
(E)
+
1 AEd '2A EFFLUENTJAND' WASTE DISPOSAL SEMIANNUAL REPORT (19678)
LIQUID EFFLUENTS - SUMMATION OF ALL. RELEASES Unit Quarter-Quarter Est. Total 2L3 3
4 Error, %
. A; Fission'& activation gases
- 1. : Total release (not including Ci
-8.99 E-2_ 4.96 E-2 32.0 E0 tritium, gases, alpha)
- 2. Average diluted concentration uti/ml 2.64 E-9 2.34 E-9 during period
- 3. Whole Body Dose Millirem 2.26 E-1 1.94 E-1
-Percent cf Technical Specification 7.53 EO 6.47 EO
- 4. Bone Dose Millirem 1.80 E-1 1.55 E-1 Percent of Technical Specification 1.80 E-0 1.55 EO B.' Tritium
- 2. Average diluted concentration during period uCi/mi 2.70 E-7 2.36 E-7
_C; Dissolved and entrained _ gases
- 1. -iotal release Ci 0
0 42.0 E0
- 2. Average diluted concentration during period uCi/mi 0
0 D. Gross alpha radioactivity 1.-Total release Ci 1.39 E-4 4.03 E-4 39.0 EO 2._ Average dilutec concentration
.during period uCi/ml 4.09 E-12 1.90 E-11 E. Volume of waste released (prior to dilution) liters 6.05 E6 5.11 E6 32.0 E0 F. Volume of dilution water useo during perioc liters 3.40 E10 2.12 E10 30.0 EO
TABLE 2B
. EFFLUENT AND WASTE DISPOSAL-SEMI ANNUAL REPORT (19878)
' LIQUID' EFFLUENTS CONTIN 0005 MODE BATCri MODE Nuclides Released Unit Quarter-Quarter.
Quarter
~ Quarter 2L3.
3 4
3 4^
> Strontium-89.
Ci 0.
0 9.73 E-5 6.08 E-5 LStrontium-90 Ci 0
0 4.32 E-5 -4.40 E Alpha-Ci 0-0 1.39 E-4 4.03 E-4
-Iritium Ci 0
0 9.18 EO 4.99 E0 2Phospnorus-32 Ci 0
0 0
0 fron-55 Ci 0
0 6.30E-4 5.02E-4 Xenon-131M Ci
.0 0
0 0
Xerton-133 Ci 0
0 0
0 Xenon-133M Ci 0
0
-0 0
Xenon-135 Ci 0
0 0
0 Xenon-138 Ci 0
0 0
0
. Krypton-85M Ci-0 0
0 0
Krypton-87 Ci 0
0 0
0 Krypton-88 Ci 0
0 0
0
' Xenon-135M Ci 0
0 0
0 Manganese-54 Ci 0
0 1.07 E-5 3.81 E-5 Celsium-134 Ci 0
0 1.94 E -2 1.01 E-2 Cesium-137-Ci 0
0 2.91 E-2 1.50 E-2 Cesium-138 Ci 0
0 0
0 Zinc-65 Ci 0
0 2.88 E-2 1.82 E-2
- Socium-24 Ci 0
0 0
0
' Cobalt Ci 0
0 1.25 E-4 0
Cobalt-60 Ci 0
0 8.91 E-3 4.96 E-3
' lodine-131 Ci 0
0 0
0 lodine-133 Ci 0
0 0
0 Molybaenum-99 Ci 0
0 0
0 17\\
w, s:
' TABLE l2B (Cor.tinuec)-
g.
CONTlhu0VS MODE BATCH MODE lNuclides Released Unit
-Quarter Quarter Quartar Quarter; 2&3 3
4 3-4-
lodine-135 Ci 0
0 0-0
! Barium-140 Ci 0
0 0
0 LNep$unium-239 Ci 0
0 0
0
. Chromium-51 Ci-0 0
0 0
Yttrium-91M Ci 0
0 0
0 LStrontium-91 Ci 0
0 0
0 l Antimony-122 Ci 0
-0 0
0 l Tellurium-132 Ci 0-0 0
0 Niobium-95 Ci 0
0.
0 E.41 E-6 l Lantnanum-140 Ci 0
0 0
0 l
- Cacmium-109 Ci 0
0 0
0 l
ICostum.136 Ci 0
0 0
0 Silver-110M Ci 0
0 3.96 E-4 0
Cesium-144 Ci 0
0 0
0
'l Antimony-124 Ci 0
0 0
0
, iron Ci 0
0 0
l
' Tellurium-129M Ci 0
0 0
0
-Tellurium-131M Ci 0
0 0
0 l Zirconium-95.
Ci 0
0 0
0
' Cerium-141 Ci 0
0 0
0
. Total-for Period (above)
Ci 0
0 9.27 EO 5.04 E0 (8)
L
TABLE 3 P(ACH f0TTOM UNITS 2 A 3 JULY 1 TO DECFMDED 31 19R7 - CLASSES Or sot.!D RADIOACTIVE WASTE 5HIPMENTS Individunt Total Container (Wnste & Container)
Total a Waste Description Volume Volume Total Principal of Shipments (Source of waste)
Container / Type
( c uri t e feet)
(cuote feet)
Curie Radlonuclides CLAST. A 7
De=ntered Resin HICi 1.74.3 ft.3 1220.1 ft.3 132.469 Zn-65. CO-60 Type A Cash Cs-734 Cs-137 34 0.A.W.
Metal Crum 7.5 ft.3 11737.5 ft.3 72.292 2n-65. Co-60 LSA 10.9 ft.3 34R8.0 ft 1 Fe-55.Cs-134 12.25 ft.3 3136.0 ft.3 Cs-137
- 116 D.A.w.
Metal B-25 96.0 ft.3 15.629.2 ft.3 18.829 Zn-65. Co-60 (en=)
r,.55.
C=-134 Cs-137
- 6 0.A.w.
A Metal Bon R0.3 ft.3 1R64.1 ft.3 1.118 Co-60 Cs-137 Cs-134 Fe-55 Sollutifled Oil Zn-65 9
SnelditIce uit retal Bo.
On.3 ft.3 3409.1 ft. 9 0.273 re-55. Za-65 Co-60 f.s-13 7
- f. L A *>5 B
20 (newatered Re?. t re HIC 17A.3 ft.3 34R6 ft.3 969.316 2n-65. C o-F.0 re-55,03-114 type A Cas6 CS-137 1
Dewatered Resto HIC 132.4 ft.3 132.4 ft.3 75.716 Zn-65. Co-60.
Fe-55. (s-134 Type A Cash Cs-137 t'ewa'ered Resto HIC 132.4 ft.3 132.4 Ft.3 680.497 2n-65. Co-60 fe-55 (s-134 Type O Cash ts-137 Indtoate. nctuni tutat $'Eco rad =aste sh i ppert feom Quadaen after volume reductton, to the burtal site.
(9)
ATTACRMENT A SUPPLEMENTAL INFORMATION Facility: '
DPR-44 Peach Bottom Units 2 & 3 Lic3nses:
DPR-56 1.
Rnoulatory Limits (Technical Specification Limits)
A'.
Noble Gases:
1.
5 500 mrem /Yr.- total body "instantaneous" limits per 5 3000 mrem /Yr - skin Tech. Spec. 3.8.C.1.a 2.
$ 10 mrad - gamma air
- quarterly air dose limits per 5 20 mrad - beta air Tech. Spec. 3.8.C.2.a 3.
5 20 mrad - gamma air
- yearly air dose limits per 5 40 umad - beta air Tech. Spec. 3.8.C.2.b
'B.
Iodines, Tritium, Particulates with Half Life > 8 days:
1.
$ 1500 mrem /Yr - any organ "instantaneous" limits per (inhalation path)
Tech. Spec. 3.8.C.l.b 2.
515 mrem - any organ
- quarterly dose limits per Tech. Spec. 3.8.C.3.a 3.
5 30 mrem - any organ
- yearly dose limits per Tech. Spec. 3.8.C.3.b C.
Licuid Effluents:
1.
Concentration < 10 CFR 20, "instantaneous" limits per Appendix B, Ta51e II, Col. 2 Tech. Spec. 3.8.B.1 2.
5 3.0 mrem - total body
- quarterly dose limits per 5 10 mrem - any organ Tech. Spec. 3.8.B.2.a 3.
5 6.0 mrem - total body
- yearly dose limits per 5 20 mrem - any organ Tech. Spec. 3.8.B.2.b 2.
Maximum Permissible Concentrations MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.
The MPCs specified in 10 CFR 20, Appendix B, Table II, Column 2, for identified nuclides are used to calculate permissible release rates and concentrations for liquid releases per Peach Bottom 1-Technical Specifi:ation 3.8.B.l.
(10) i l
M 1*-
ATTACHMENT A'-(Continued) 3..' Average Energy 1 Notf applicable ~..
l4.
Measurements'and Approximations of Total Radioactivity A.
. Fission and' Activation Gases The method used is th?. Nuclear Data 6600/5700 counting System
- Gas Marinelli B.
Iodine The method used in the Nuclear Data 6600/6700 Counting System
. Charcoal Cartridge C.
Particulate:
The method used is the Nuclear. Data 6600/6700 Counting System
- Air. Particulate Sample, 47 mm filter D.
Liould Effluents:
The method used is the Nuclear Data'6600/6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter bottle..
5.
Betch Releases A.
Liould Q3 04
- of Batch Releases:
71 79' Total Time for' batch releases, minutes 18948 20340 Maximum time period for a batch release, minutes 340 340 Average time period for batch release, minutes 267 257 Minimum time. period for a batch release', minutes 15 23 Dilution flow (Liters) 3.41 E10 2.12 E10 B
Gaseous:
N/A 6.-
Abnormal Releases A.
Licuid:
See Attachment B l
B.
Gaseous:
None (11)
.g
-l l
ATTACHMENT F
SUMMARY
OF UNPLANNED RELEASES Unplanned Licuid Release Via the 3B High Pressure Service Water On August 31, 1987, a suspected release was detected by a peak which occurred on the 3B High Pressure Service Water (HPSW) radiation monitor.
A grab sample was obtained during the 5 minute duration of the event which showed detectable activity; however, activity could'not be detected in later samples.
The calculated doses are based on the methodology presented in the Offsite Dose Calculation Manual (ODCM), assuming a release rate of 4500 gpm (flowrate of one HPSW pump) and average release concentrations based on the sample obtained.
A leak test was not performed because periodic monitoring of the system by recorder and grab samples indicated no levels of activity.
The whole body-dose as a result of the release was calculated at 5.42E-5 mrem, and the bone dose was calculated at~6.08E-5 mrem.
Unclanned Licuid Release Via the 2A High Pressure Service Water On August 20, 1987, a suspected release was detected by a peak which occurred on the 3B HPSW radiatien monitor.
No grab sample was obtained during the 15 minute duration of the event.
The calculated doses are based on the methodology presented in the ODCM e4sucing a release rate of 3 gpm and average release concentrations based on the radiation monitor strip chart.
Because of the short duration, it is suspected that the indication may have been a possible radiation transient at the monitor.
.The whole body dose as a result of the release was calculated at 3.37E-6 mrem, and the bone dose was calculated at 3.84E-5 mrem.
i F
l b
h
i ATTACRMENT B (Continutd)
Calculations For Critical Organ Dose Using Particulates With Half-Lives Greater Than 8 Days The following doses were calculated using particulates identified during the third and fourth quarter reporting period of 1987; PARTICULATE CRITICAL ORGAN DOSE, LIVER, (MREM)
Ouarter 3 Quarter 4 Sr-89 7.69 E-8 4.58 E-9 Sr-90 3.26 E-6 3.60 E-7 Cs-137 4.15 E-5 1.82 E-5' Co-60 1.50 E-7 1.68 E-7 Zn-65 3.18 E-5 4.26 E-5 Total 7.68 E-5 6.13 E-5 The percent of Technical Specification for the critical organ (liver) for the third quarter is 5.12E-4, fourth quarter is 4.09E-4.
(13)
~
PHILADELPHIA ELECTRIC COMPANY 23ol M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.191o1 (215)841 4000 February 25, 1988 Docket No. 50-277 50-278 Mr. William T. Russell, Administrator Rcgion I U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555
SUBJECT:
Semi-Annual Effluent Releases Report No. 24 July 1, 1987 through December 31, 1987 Peach Bottom Atomic Power Station Unit Nos. 2 and 3 Daar Mr. Russell:
Enclosed are two copies of the Semi-Annual Effluent Releases
,j Rcport No. 24, July 1 through December 31, 1987 for Peach Bottom Atomic Power Station Unit Nos. 2 and 3.
This report is being submitted in compliance with the Technical Specifications of Operating Licenses DPR-44 and DPR-56, and to fulfill the requirements of Regulatory Guide 10.1.
Very truly yours, W. M. Alden Director Licensing Section Attachments cc:
Addressee T. P. Johnson, PBAPS Site Inspector
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