ML20246J943

From kanterella
Revision as of 19:30, 12 February 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Semiannual Effluent Releases Rept 27 for Jan-June 1989
ML20246J943
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 06/30/1989
From: Hunger G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8909050315
Download: ML20246J943 (17)
v • d • e


Text

--

9 10 CFR 50.36a(c)(2)

. , T.S. 6.9.2.h(2) 4"

  • PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS 955 65 CHESTERBROOK BLVD.

WAYNE, PA 19087-5691 (zt s) sao.sooo August 29, 1989 Docket No. 50-277 50-278 U.S. Nuclear Regulatory Ccmmission ATTN: Document Control Des; Washington, D.C. 20555

SUBJECT:

Semi-Annual Ef'luent Releases Report No. 27 January 1 through June 30, 1989 Peach Bottom Atomic Power Station Unit Nos. 2 and 3

Dear Sir:

Enclosed are two copies of the Semi-Annual Effluent Releases Report No. 27, January 1 through June 30, 1989 for Peach Bottom Atomic Power Station Unit Nos. 2 and 3.

This report is being submitted in compliance with 10 CPR 50.36a(a)(2) and the Technical Specifications of Operating Licenses DPR-44 and DPR-56, and to fulfill the requirements of Regulatory Guide 10.1.

During the report period, no revisions were made to the Offsite Dose Calculation Manual (ODCM) or to the Solid Radwaste System Process Control Program (PCP).

Very truly yours,

/ . 0. f, h ,

G. A. Bunger, Jr Director Licensing Section l Nuclear Support Division

( Enclosures cc: W. T. Russell, Administrator, Region 1, USNRC T. P. Johnson, Senior Resident Inspector Y

8909050315 890630 PDR ADOCK 05000277 /

R rDC 7

I .

YOs

~

I SERVICE ,(

  • I *p+cy I

E j, ,

I r I .

I I

I g

._. ggf -

I ,d ._ Ut7 I di g _

- _E =

=

- - _ :=, __ _ _ , - _ 2-m m___ o =-

g I

E PEACH BOTTOM g ATOMIC POWER STATION I -

I I I I PEACH BOTTOM ATOMIC POWER STATION Docke s b-27 & 50-278 I SEMI-ANNUAL EFFLUENT RELEASES REPORT J

l NO. 27 I

JANUARY 1 TO JUNE 30, 1989 I

I-Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 & DPR-56 I

I I

I I

I I

I

FI g:

I PHILADELPHIA ELECTRIC COMPANY l3 PEACH BOTTOM ATOMIC POWER STATION l5 Unie Nos. 2 and 3 Docket Nos. 50-277 & 50-278 I

I l I SEMI-ANNUAL EFFLUENT RELEASES REPORT NO. 27 JANUARY l TO JUNE 30, 1989 I

I Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 & DPR-56 I

I Preparation Directed By:

I D. M. Smith, Vice President Peach Bottom Atomic Power Station I

I .

I - - - - - - - . - - - - ------_---_-.----------____----_--J i

Table of Contents Page No.

I. Introduction 11 II. Tables lA. Gaseous Effluents - Summation of 1 All Release; 1B. Gaseous Effluents For Release 2 Point - Main Stack Gaseous Effluents For Release 4 1C.

Point - U2 & U3 Roof Vents 2A. Liquid Effluents - Summation of 6 r All Releases Liquid Effluents 7 2B.

Classes of Solid Radioactive 9 3.

Waste Shipments i

III. Attachments A. Supplemental Information 10

)

{

)

Technical Concurrences: (for accuracy of information)

X M nw H~tm+& k e -: H 't Director-Radiation Protection Date

~

Oasd'b D3%htor-Radwastej{

.naoDatW f

-i-

\'

1

~

I SEMI-ANNUAL EFFLUENT RELEASE REPORT I JANUARY 1 TO JUNE 30, 1989 I.. INTRODUCTION In accordance with the Unique Reporting Requirements of Technical Specification 6.9.2h(2) applicable during the reporting period, this report summarizes the Effluent Release Data for Peach Bottom Atomic Station-Units 2&3 for the period January 1 through June 30, 1989. The notations E and E- are used to denote positive and negative exponents to the base 10.

The release of radioactive materials during the reporting period was within the Technical Specification limits. There were no changes made to either the off-Site Dose Calculation Manual (ODCM) or the Solid Radwaste o

System Process Control Program (PCP) during the~ reporting period.

There were no unplanned releases of liquid radioactive materiL1 from the High Pressure Service Water (HPSW) system.

I I

l l

l  ?

I e

I t

I TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)

GASEOUS EFFLUENTS - SU M TION OF ALL RELEASES Unit Quarter Quarter Est. Total 2&3 1 2 Error, %

A. Fission & activation gases

1. Total release C1 2.59 E2 6.50 E2 54.0 E0
2. Average release rate fe>r period uC1/sec 3.29 El 8.27 El
3. Gamma Air Dose Millirad 1.40 E-2 1.46 E-2 Percent of Tech. Spec.  % 1.40 E-1 1.46 E-1
4. Beta Air Dose Millirad 1.42 E-2 1.44 E-2 Percent of Tech. Spec.  % 7.10 E-2 7.20 E-2 B. Iodines
1. Total iodine-131 Ci 0 8.46 E-6 61.0 E0
2. Average release rate for period uCi/sec 0 1.08 E-6 Millirem 9.87 E-7 5.20 E-3

.I3.CriticalOrganDose Percent of Tech, Spec.  % 6.58 E-6 3.47 E-2 C. Particulate

1. Particulate with half-lives greater than 8 days (includes Alpha and Strontium 89-90) Ci 7.07 E-5 2.65 E-4 61.0 E0
2. Average release rate for period 8.99 E-6 3.37 E-5

^

uCi/sec

3. Gross Alpha Radioactivity C1 1.97 E-5 2.80 E-5 D. Tritium I 1. Total release Ci 2.70 E-1 2.39 E-1 94.0 E0
2. Average release rate for period uCi/sec 3.43 E-2 3.04 E-2 l

(1) l__..___ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ . - _

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989) j GASEOUS EFFLUENTS FOR RELEASE POINT: MAIN STACK l '

CONTINUOUS MODE BATCH MODE A

ENuclides Released Unit Quarter Quarter Quarter Quarter 2&3 1 2 1 2

1. Fission gases Krypton-85M Ci 0 1.50 E2 0 0 5 Krypton-87 Ci 0 3.00 El 0 0

. Krypton-88 Ci 0 6.74 El 0 0

~

Xenon-133 Ci 0 1.07 E2 0 0 Xenon-135 Ci 0 1.75 E2 0 0

. Xenon-135M Ci 0 3.34 EO O O E

g Xenon-138 Ci 0 5.52 E0 O O E

Unidentified Ci 2.18 E2 6.56 El 0 0 Ci 2.18 E2 6.04 E2 0 0 g Tr.tal for period

2. Iodines Iodine-131 Ci 0 8.46 E-6 0 0 Iodine-133 Ci 0 0 0 0 Indine-135 Ci 0 0 0 0 Total for period Ci 0 8.46 E-6 0 0 I 3. Particulate Strontium-89 Ci 4.85 E-7 9.18 E-5 0 0 Strontium-90 Ci 2.20 E-7 2.20 E-7 0 0 Strontium-91 Ci 0 0 0 0 Cesium-134 Ci 0 0 0 0 (2)

TABLE IB (Continued)

CONTINUGUS MODE BATCH MODE tuclides Released Unit Quarter Quarter Quarter Quarter 2&3 3 4 3 4 Cesium-137 C1 1.41 E-6 0 0 0 Cesium-138- Ci 0 3.57 E-3 0 0 Barium-139 Ci 0 2.87 E-4 0 0 Barium-140 Ci 0 0 0 0 Linthanum-140 Ci 0 2.21 E-6 0 0 Cobalt-57 Ci 0 0 0 0 Cobalt-58 Ci 0 0 0 0 Cobalt-60 C1 1.21 E-5 4.00 E-6 0 0 Zinc-65 Ci 6.76 E-6 0 0 0 Yttrium-91M Ci 0 3.41 E-8 0 0 lodine-133 Ci 0 0 0 0 C pper-64 Ci 0 5.90 E-4 0 0 Rubidium-88 Ci 0 0 0 0 Mang nese-54 Ci 0 0 0 0 Strontium-92 Ci 0 0 0 0' Tctals 2.10 E-5 4.55 E-3 0 0

)

l' i

(3)

TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)

GASEOUS ' EFFLUENTS FOR RELEASE POINT: U/2 & U/3 Roof Vents CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 2&3 1 2 1 2

8. 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 X:non-135M Ci 0 0 0 0 Xcnon-138 Ci 0 0 0 0 X:non-133M Ci 0 0 0 .O Unid:ntified Ci 4.14 El 4.58 El 0 0 Tctal for period Ci 4.14 El 4.58 El 0 0 l
2. Iodines Iodine-131- Ci 0 0 0 0 Iodine-133- Ci 0 0 0 0 lodine-135 Ci 0 0 0 0 Tctal for period Ci 0 0 0 0
3. Particulate l

1.74 E-5 8.75 E-5 0 0 Strontium-89 C1 1.26 E-5 1.23 E-5 0 0 Strontium-90 C1 Ci 0 0 0 0 Str:ntium-91 Ci 0 0 0 0 C:sium-134 f

m

I TABLE IC (Continued)

I COWTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 2&3 3 4 3 4 I 0 4.33 E-5 0 0 Cesium-137 Cl Cesium-138 Ci 0 2.01 E-3 0 0 Darium-139 Ci 0 8.10 E-5 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 I. Iodine-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 Totals Ci 3.00 E-5 2.23 E-3 0 0 I

I I

g <5>

I

!I I E _- _ l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)

LIQ:!ID EFFLUENTS - SupMATION OF ALL RELEASES E

Unit Quarter Quarter Est. Total 2&3 1 2 Error, %

. Fission & activation gases 1 Ci 6.19 E-2 2.11 E-2 32.0 E0 I.Totalrelease(notincluding tritium, gases, alpha)

2. Average di' luted concentration uCi/ml 2.19 E-9 8.05 E-10 during period
3. Body Dose Milliren 6.63 E-1 2.96 E-2 Percent of Technical Specification  % 2.21 El 9.87 E-1
4. Teen Liver Dose Millirem 9.59 E-1 4.34 E-2 Percent of Technical Specification  % 9.59 EO 4.34 E-1

. Tritium g1.Totalrelease Ci 2.38 E0 2.99 EO 39.0 E0

2. Average diluted concentration during period uCi/ml 8.41 E-8 1.14 E-7

. Dissolved and entrained gases g1.Totalrelease Ci 0 3.58 E-4 42.0 EO

2. Average diiuted concentration during period uCi/ml 0 1.37 E-11 10.Grossalpharadioactivity
1. Total release C1 1.04 E-4 1.22 E-4 39.0 E0
  • 2. Average diluted concentration during period uCi/a1 3.67 E-12 4.66 E-12 E. Volume of waste released (prior to dilttion) lit.. 7.19 E6 4.60 E6 32.0 E0 m

E F. Volume of dilution water used during pr.riod liters 2.83 E10 2.62 E10 30.0 E0 (6)

TABLE 28 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)

LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE I Nuclides Released Unit Quarter Quarter Quarter Quarter 2&3 2 2 1 1 Strontium-89 Ci 0 0 1.10 E-4 6.58 E " Strontium-90 Ci 0 0 5.65 E-5 5.05 E-5 Alpha Ci 0 0 1.04 E-4 1.22 E-4 Tritium Ci 0 0 2.38 E0 2.99 E0 mm gPhosphorus-32 Ci 0 0 1.12 E-3 2.09 E-4 Iron-55 Ci 0 0 7.92 E-4 1.05 E-2 EX:non-131M Ci 0 0 0 0 X:non-133 Ci 0 0 0 1.48 E-4 X:non-133M Ci 0 0 0 0

==

ci 0 0 0 2.09 E-4 Ex:"oa- 35 Krypton-85M Ci 0 0 0 0 WKrypton-87 Ci 0 0 0 0 Krypton-88 Ci 0 0 0 0 X:.non-135M Ci 0 0 0 0 Manganese-54 Ci 0 0 4.12 E-6 0 i C21sium-134 Ci 0 0 1.47 E-2 1.10 E-3 Cesium-137 Ci 0 0 3.74 E-2 3.15 E-3 C:sium-138 Ci 0 0 0 0 Zinc-65 Ci 0 0 1.34 E-3 9.51 E-4 Sodium-24 Ci 0 0 0 0 Cobalt-58 Ci 0 0 0 0 I

m g

I _ -- _

I TABLE 28 (Continu:d)

CONTINUOUS MODE BATCH MODE lNuclidesReleased Unit Quarter Quarter Quarter Quarter W 2&3 3 4 3 4 Cobalt-60 Ci 0 0 6.36 E-3 4.94 E-3 Iodine-131 Ci 0 0 0 0 lodine-133 Ci 0 0 0 0 holybdenum-99 Ci 0 0 0 0 Iodine-135 Ci 0 0 0 0 Barium-140 Ci 0 0 0 0 Heptunium-239 Ci 0 0 0 0 Chromium-51 Ci 0 0 0 9.85 E-5 Yttrium-91M Ci 0 0 0 0 Strontium-91 Ci 0 0 0 0 Antimony-122 Ci 0 0 0 0 Tellurium-132 Ci 0 0 0 0 Niobium-95 Ci 0 0 0 0 Linthanum-140 Ci 0 0 0 0 Cadmium-109 Ci 0 0 0 0 Antimony-124 Ci 0 0 0 0 Iron-59 Ci 0 0 0 Tallurium-129M Ci 0 0 0 0 Tallurium-131M Ci 0 0 0 0 Zirconium-95 Ci 0 0 0 0 C;rium-141 Ci 0 0 0 0 T::.tal for Period (above) Ci 0 0 2.4420 EO 3.0115 E0 l (8)

L l

\

,iIIl lil a

M M

M 6 5 5 5 5 5 5 5 E 6 6 6 6 6 6 6 T

- - - - - - - 6 I

- S S n n n n n n n n E Z7 Z Z Z7 Z7 Z Z Z L M LDI A L 01 ,3

,7 ,7 013 03 01 ,301 ,3 1 01 3

,7 031

,7 01 7

,3 A

I R

P C I

6- 6- 6 6- 6- 6- 6- 6- U s - s s s s s s s CU cC oC oC oC oC ,C, oC O C oC B NN C,C,C C,C C C, E M I RO PD I

53

,4 .4 4 S3 5 3 53 53 53

,4 ,4 ,4 ,4 5 3 53

,4 H T

51 S1 51 51 51 51 51- 51 O A - - - - - - - - - -

T R es es es es es es es e s FC FC FC FC FC FC FC FC N M LEI O

I T

A 2 2 9 1 9 2 9 5 9 S TR 8 7

C U

T OU 0 0 4 3 3 8 6 TC 7 0 5 5 D N

M E 1 1 1 3 E R

M E r. 5 E P LM t 1

s. 90 2

. 9 8 5 4 3 M I A TU cr 4 0 08 4 4 1 2 4 U H 1 0 49 7 1 8

7 7 3 2 L M S OL e 6 6 5 3 8 1 5 O TO u 1 1 V

3,_ 99 E V ct 2 6 1 1

T

  • R

& S E 1 S L 1 T 2 M A E r. F M S 0H 3 UMr D

3 5 50 0 3 8 3 4 A T E I Uc 4 7

7 78 6 8 8 4 2 X, I

EV VL i s 9 9 3 7 7 3 N 1 1 1 1 E NI IO u R 3 U UT DV N

c D E

M JC A I

t A

U L

B O OO E K K K K Q A T TI S C C S S S T T D P A T T A A A M

1 A Y S S O O C C C M B YR T

/

C A

/

M

/CC MTS ST A

/

RK A B R

F R D R U U/ / ES D H AI E E R E NA E E E C UL N P D R

DO O XX P IC L P P P A

E NO I A

Y L B B Y A Y Y P P

AS T T

/

L A A5 5 T

/

L EE T

/

T

/

I H

J F N C T T C EP C C S O O C

I E E-2 2

- ( TY I I H E H M MB B V ST H T S S M E S N E M D

S O N G N N A A I l TEr I D I I R L S U S S o Pa E E M C I Rm R W

L S

E R R C

E _

P Cr D A D D D D So E E E F L E R / I R R A S T W D t Enu T

c E T

M R

E F

I D

I E

T E

T O

T o W W W T L M M L Ss E A A A L

I C E E A Mt D D D D F S D D U T

C A

FS S OT A B E N S T

  1. E S S L 2 A

7 C M LM AP S 6 A

1 1 1 5 1 1 S

A 6 1 A T8 I D

TI L L O N OH C C T I TS

  • M

,8 M

ATTACHMENT A SUPPLEMENTAL INFORMATION

  • PCcility: Peach Bottom Units 2 & 3 Licenses: DPR-44 DPR-56
1. Regulatory Limits (Technical Specification Limits)

A. Noble Gases:

1. $ 500 mrem /Yr - total body " instantaneous" limits per 5 3000 mrem /Yr - skin Tech. Spec. 3.8.C l.a
2. 1 10 mrad. gamma air quarterly air dose limits pe

$ 20 mrad - beta air Tech. Spec. 3.8.C.2.a

3. 1 20 mrad gamma air yearly air dose limits per 5 40 mrad - beta air Tech. Spec. 3.8.C.2.b B. Iodines, Tritium, Particulate with Half Life > 8 days:

I 1. $ 1500 mrem /Yr - any organ (inhalation path)

" instantaneous" limits per Tech. Spec. 3.8.C.l.b 115 mrem - any organ I 2. quarterly dose limits per Tech. Spec. 3.8.C.3.a

3. $ 30 mrem - any organ - yearly dose limits per Tech. Spec. 3.8.C.3.b C. Liquid Effluents:
1. Concentration < 10 CPR 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 I 3. $ 6.0 mrem - total body 5 20 mrem - any organ

- yearly dose limits per Tech. Spec. 3.8.B.2.b Maximum Permissible Concentrations I2. MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.

I The MPCs specified in 10 CFR 20, Appendix B, Table II, Column 2, for identified nuclides are used to calculate permissible release I rates and concentrations for liquid releases per Peach Bottom Technical Specification 3.8.B.l.

I (10)

I -

ATTACHMENT A (Continu d) l

3. Average Energy I Not applicable.
4. Measurements and Approximations of Total Radioactivity A. Pission and Activation Gases The method used is the Nuclear Data 6600/6700 Counting System

- Gas Marinelli B. Iodine The method used in the Nuclear Data 6600/6700 Counting System

- Charcoal Cartridge C. Particulate:

I The method used is the Nuclear Data 6600/6700 Counting System

- Air Particulate Sample, 47 mm filter D. Liquip Effluents:

The method used is the Nuclear Data 6600/6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter Marinelli

~

5. Batch Releases A~. Liquid Q3 04 i of Batch Releases: 93 63 Total Time for batch releases, minutes 26098 16243 Maximum time period for a batch release, minutes 340 340 Average time period for batch release, minutes 281 258 Minimum time period for a batch release, minutes 35 16 Dilution flow (Liters) 2.83E10 2.62E10 B Gaseous: N/A
6. Abnormal Releases A. Liquid: None i

I B. Gaseous: None (11) o I _

Retrieved from "https://kanterella.com/w/index.php?title=ML20246J943&oldid=3162984"