ML20082M308

From kanterella
Jump to navigation Jump to search
Effluent & Waste Disposal Semiannual Rept for Monticello Generating Plant for Jan-Jun 1991
ML20082M308
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 06/30/1991
From: Fey F
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9109050130
Download: ML20082M308 (11)
v • d • e


Text

_ _ _ _ _ - - - - _ _ _ _ _ - _ _.

f s

Northom States Power Company 414 thcollet Mall Minneapohs. Minnesota 55401 1927 Telephone (61?) 330 5500 August 27, 1991 Monticollo Technical Specification TS6.7 4A U.S.

Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555 Monticello Nuc1 car Generating Plant Docket No. 50-623 Licenso !!o. DPR-22 Effluent and Waste Disposal Somiannual Report 1_qr January 1, 1991 throngtLitune 30, 1991 In accordance with the Monticello Technical Specifications, Appendix A to Operating License DPR-22, wo are submitting the Effluent and Waste Disposal Semiannual Report covering the last half year of 1991.

The Offsite Doso Calculation Manual (ODCM) and Process control Program (PCP) Manual are not attached since they remained unchanged during the reporting period.

'\\L C

)

Fred L.

Fey, Jr., Manager Nuclear Radiological Services Attachment l

l C4C014

_ DOCK 0500 g 3 DR A

TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR GENERATION DEPARTMENT MONTICEll0 NUCLEb3 GENERATING P.LARE Effluent and Waste Disposal Scalannual Report for Janyty_1 1991 throvoh June 30, 1991 Manifest Date: August 2?, 1991 USNRC 4

ANI Library 1

Regional Admin-lil General Electric 2

NRK Project Manager San Jose Cust. Serv.

DCD San Jose fuel Proj. Hgr.

Resident inspector Shaw Pittman Potts &

Trowbridge 1

K M Beadell 1

J Sf1 berg J P Jepson 1

Safety Audit Committee 10 P H Kamman i

K J Albrecht J E Windschill 1

A B Cutter Prairie Island Plant Manager 1

R L Hannen Monticello Site General Manager 1

W J Hill ERAD Department 1

0 0 Lanning Attn: Records Clerk D M Musolf Communications Department 1

G H Neils NRS File 1

T H Parker NSS File 1

J A Thie MDH 1

Secretary Attn: Commissioner of Health Manifest File MPCA 1

Attn: J W Ferman

=_

= _ _

4 NORTilERN STATES POWER COMPANY MONTICELLO NUCLEAR CENERATING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period i Jan - Jun 1991 Supplemental Information

1. RQgulatory Limits - Quarterly levels requiring reporting to Nuclear Reguletory Commission A.

Noble Gases :

5 mead / quarter gamma radiation 10 mrad / quarter beta radiation B.

Long Lived Iodines, Particulates, and Tritium 7.5 mrem / quarter dose to any organ C.

Liquid Effluents :

1.5 mrem / quarter dose to the total body f

5.0 mrem / quarter dose to any organ i

2. Maximum Permissible Concentrations

- r l

l A.

Noble Gases :

10 CFR Part 20, Appendix B, Table II, Column 1 i

B.

Long Lived Iodines, Particulates, and Tritium

{

10 CFR Part 20, Appendix B, Table II, Column 1 C.

Liquid Effluents :

l 10 CFR Part 20, Appendix B, Table II, Column 2 2.0 E-4 uci/ml for dissolved and entrained gases i

3. Average! Energy (Not Applicable) i t

i i

\\

r

---n

Page 3

ErrLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period Jan - Jun 1991 t

Supplemental Information (continued) i

4. Measurements and Approximations of Total Radioactivty j

A. Noble Gases :

Continuous gross activity monitors in Reactor Building Vent and Plant Stack exhaust streams.

Weekly isotopic analysis of exhaust streams.

B.. Iodines in Gaseous Effluent :

3 continuous monitoring with charcoal cartridges in Reactor Building i

' vent and Plant Stack exhaust streams with weekly analysis.

[

C. Particulates in Gaseous Effluent :

Continuous monitoring with particulate filters in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis, t

I D. Tritium in Gaseous Effluent :

Continous monitoring with silica gel cartridges in Reactor Building Vent and-Plant Stack exhaust streams with weekly analysis.

E._ Liquid Effluents :

Tank sample-analyzed prior to each planned release and continuous monitoring of gross activity during planned release.

4

5. Batch Releases l

A.

Liquid

-1. Nunher of Batch-Relecses 0

2. Total Time Period for Batch Releases NA min

'3. Maximum Time Period for a Batch Release NA min l

4. Average Time Period for a Batch Release NA min
5. Minimum Time Period for a Batch Release NA min
6. Average River Flow During Release NA cf/sec B.

Gaseous :

5

1. Number of Batch Releasen 15623.0 min
2. Total-Time. Period for Batch Releases 3 : Maximum Time Period for a Batch Release 10607.0 min
4. Average Time Period for_a Batch Release 3124.6 min
5. Minimum Time Period for a Batch Release 440.0 min i

l i

l l

l i

Page 3

ErrLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT j

Period : Jan - Jun 1991 Supplemental Itformation (continued)

6. Abnormal Releanes A.

Liquid :

1. Number of Releases 0
2. Total Activity Released NA Ci D.

Gaseous :

1. Number of Releases 0
2. Total Activity Released 0.0 Ci

,I Page 4

i ErrLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

(

Period : Jan - Jun 1991 Table lA caseous Effluents - Summation of all Releanes l

Units l 1st Qtr l 2R"d Qtt lEst. Total l

i I

I E r tp r, 4 g

A.

Fission & Activation gases 1.

Total Release Ci 8.3fE+02 1.68E+02 2.00TTUT~l

~

2.

Average __ Release Rate _

uci/sec

1. 0 0 EiF2
2. l TETFI~

i

~

~

3.

Percent Tech Spec Qtrly Reporting Level 1

i Gamma nadiation l

4 1.16E+00 5.07E-01 Deta Radiation I

t 3.06E-01 3.31E-01 B.

Iodines l

1.

Total I-131 helease ci 772TE!U3 4.31E-03 1.00E+01 l

[

3. Average 1-13T~helease Rate uci/sec 9.27E764 5.49E-04 l

~~

C.

Particulates l

1.

Total ) articulates Ci 9.16E-04 1.99E-03 3.0VE+01 l 1

~

~

2. Average Release Rate uci/sec IECOBE!61 2.54E-04 l

~

3.

Gross-Alpha Radior.ctivity Ci 3.53E-06 1.45E-05 i

l D.

Tritium-A.

Total Release Ci 177EEIDI 1.25E+01 1.00E+01 l 2.

Average Release Rate uci/sec 2.26E+00 1.5YET60 i

i E.

Percent Qtrly Tech Spec Reporting Levels f

l I

l1.27E400_l

(

1.

Iodines, Particulates, and Tritium i

1.13E+00 i

f r

i r

i t +,

,-t---

w e w

a

=

. r m -- rwm---,--w,

,,w-<-

m-ee ro-

-w

-,,.--,--.-.-*--r---+www erve-.m---

  • e----w

=~se

+ - + - = - - - - -

e*r-ea-.

e

- ~ -.---=n-er-

Page 5

EPPLUE!4T A!4D WASTE DISPOSAL SEMI AlifiUAL REPORT Period : Jan - Jun 1991 Table IB Gaseous Effluents - Elevated Releases I

l Continuous Mode

{

Batch Mode Nuclides Released

! Unit ! lst Qtr l 2nd Qtr

[ 1st Qtr l 2nd Qr

1. rission Gases KR-85 Ci 0.00E+00 4.43E-02 0.0TE+00 0.00E+FO '

KR-85M 61 T. 0 7 E-01 T'~DTE 01 D'~UD E + 0V

0. 0VtTUr KR-87 di 6.24E+03 23 TE400 0.001 TOT 0. 00tTEU'-

KR-98 Ci 3.17E+00 9.4Tf-71 0.00t+00 0.00E+00 KR-89 C1 3 93E+00 0.0VE+00 U~TUE+00~

0.00E4DD-

~

XE-131M Ci 0.00E400 2.87E-03 0.00E400

0. 0 0 E+ 0F XE-113 Ci 3.04E+02 27 TE+01 0.00E+00 0.0VETUD :

XE-173M C i-5. t"3 E + 0 0 3.57E-01 0.00E+00 0.00t+0F XE-135 Ci 1.lFE+01 4.52E+00 0.05E+00 1.16E-04 XE-lTER C1 3.76E+01 9.17t+00 0.00E+00 0.00E+00 XE-137 CT 1.94E+02 4.T7E + 01 0.00E+00 0.00E400

~

XE-138 Ci 1.16E+02 2 HTETD1 0.0VriUU~~~F0 0 E + 0 0

~

Total for Period Ci 6.62E+02 1.15E+02 0.00E+00 1.16E-04

2. Iodines 1-131 Ci 3.62E-03 2.42E-03 0.00E+00 0.00E+00 I-133 Ci 1.051-02 6.28E-03 0.00E+00 U~ TOE +00 I-135 Ci 7.16E-03 6.83E-03 0.0DE+00 0.00E+00 Total for Period Ci 2.16E-02 1.55E-02 0.00E+00 0.00E+00 3.

Particulates CR-51 Ci 0.00l+00 2.28E-06 0.00E+00 0.00E+00 MN-54 Ci 5.15E-07 8.90E-06 0.00E+00 0.00E+00 CO-57 Ci 5~47E-08 0.0FE+00 0.00E+00 0.00E+0D-CO-58 Ci 9.98E-08 7.36E-07 0.00E+00 0.00E+00 FE-59 Ci 0.00E+00 l.38E-06 0.00E+00 0.00E+00 l g

CO-60 Ci 3.1TETU~Il 3.51E-05 0.00E+00 9.37E-09 Z14-6 5 Ci 2.80E-06 1.35E-05 0.00E+00 0.00E+00

~~

CS-137 Ci 3.90E-06 6.48E-06 0.00E+00 0.00E+00 BA-140 Ci

3.47E-04 7.62E-05 0.00E+00 T.00E+00 CE-141 Ci 1.0TE-07 4.5TE-08 0.0'UE+00 0.00E+00 l

SR-89 Ci 6.55E-05

1. 0~3 E - 0 4 F.00E+00 0.00E+00 l

$R-90 Ci 3.83E-06 5~~5FE-07 0.00E+00 0. DTE + 0 0 l

.I Total for Period Ci 4.26E-04 2.48E-04 0.00E+00 9.32E-09 {

Page 6

ErrLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period Jan - Jun 1991 Table 1C Gaseous Effluents - Building Vent Releases Continuous Mode batch Mode l

Nuclides Released Unit 1st Otr l 2nd Otr 1st Qtr l 2nd Otr _l

1. Fission Gases KR-85 Ci 0.00E+00 1.00E-04 0.00E+00 0.0DE+00 l

~

K R-8 FM Ci 0.00E+00 1.62E-02 4.34E-03 0.00E+00 KR-87 Ci 0.00E+00 1.00E-01 1.42E-02 0.00E+00 KR-88 Ci 0.00E+00 6.43E-02 2.72E-02 0.00E+00 KR-89 Ci 0 00E+00 2.2DE+00

. 0.00E+00 0.00E+00 KR-90 Ci 0.00E+00 7.51E-02 0.00E+00 0.006T66-XE-131M Ci 0.00E+00 1.2TE-05 0.00E+00 0.0'Ut+00 XE-133 61 1.18E+01 1.59E+01 8.20E-01 0.0DE+00 XE~133M Ci 6~00E+00 3~07t-04

0. 0TE 60
0. 06ETUT XE-135 Ci 5.39E+01 2.52E+01 9.91E-01 7.91E-03 XE-135M Ci 8.74E+01 3.61E+00 1.17E231 0.00f766~

XECl37 Ci O.00E+00 2.86E+00 0.00E+00 0.00E+00~

XE-138 Ci 0.00E+00 2.42E+00 9.17E-02 0.00E+00 XE-139 Ci 0.00E+00 2.24E-01 6.32E-01 0.00E+00 AR-41 Ci 0.00E+00 0.00E+00 1.54E-02 0.00E+06~

Total for Period C1 1.53E+02 5.26E+01 2.71E+00 7.91E-03'

2. lodines I-131 Ci 3.42E-03 1.89E-03 1.65E-04 0.00E+00 1-133 C1 2.34E-02 1.95E-03 6.45E-04 0.00E+00 1-135 C1 2.38E-02 2.42E-03 5.17E-04 0.00E+00 Total for Period Ci-5.07E-02 6.26E-03 1.33E-03 0.00E+00
3. Partien1ates-CR-51 Ci 5.73E-05 5.55E-05 0.00E+00 0.00E+00 MN-54 Ci 2.43E-06 8.16E-05 0.00E+00 8.57E-06 CO-58 Ci 0.00E+00 2.49E-05 0.00E+00 0.00E+00 CO-60 Ci 8.14E-05 8.40E-04 7.92E-06 4.12E-05 ZN-65 Ci 7.92E-05 6.21E-04 0.00E+00 0.00E+00 CS-137 Ci 2762E-05 4.50E-05 0.00E+00 0.00E+00 BA-140 C1 2.lTh-04 1.99E-05 0. 0 0 E + 0'D 0.00E+00-CE-141-Ci 7.54E-06 1.93E-06 0.00E+00 0.00E+00 SR-89 Ci 8.06E-06 6.62E-06 0.00E+00 0.00E+00 Total for Period Ci 4.81E-04 1.70E-03 7.92E-06 4.98E-05 i

--.w-+,v 3

s-

,,r

,-,-2,

--7

,,,,.,-.e,c,---

-,y_.

,,+,,e.,-+-w w-r-_--,_

.__,-v-.----

-.---,---a-e---

Page 7

EFFLUENT AND WASTE DISPOSAL StM1 ANNUAL REPORT Period Jan - Jun 1991 j

i Table 2A Liquid Effluents - Summation of all Releases l

Units I lst Qtr l 2nd QEr Est. Totall I

l l

Error, % !

A.

rission & Activation products l

1.

Total Release (not including l l

)

l 2.

Avg Diluted Concentration uci/ml 0.00E+00 0.00ETTO-~ 0.00E+00 tritium, gases, alpha)

Ci 0.00E+00 0.00E+00 D.

Tritium 1.

Total Release 6T 0.00E+00 0.00E+00 0.00EIDD~l 2.

Avg Diluted Concentration uci/ml 0.66t+00 0.00E+60 C. Dissolved and Entrained Gases 1.

Total Release Ci 0.00E+00 0.00E+00 0.00t+00 l 2.

Avg Diluted Concentration uci/ml 0.UUETUD 0.06E+00 D. Percent Qttly Tech Spec Reporting Level

1. Whole Body Dose 0.00L+00 0.00E+05~l
2. Organ Dose 076DE+00 OTU~0E+06 1 E.

Gross Alpha Radioactivity l'

l.

Total Release l

Ci l 0.6DE+00 l 0.00EiOO ] 0.00E+00 l

~

lF. Volume of Wast'e Released l

1.i t e r s 1 0.U'6E400 T 0.00E+00 l 0.00E+00,1 lF. Volume of Dilution Water j)sj@ l Liters l 0.00E+00 l 0.00ETOO I 0.00E'66~l i

Table 2B Liquid Effluents l

Continuous Mode i

Batch Mode l

Nuclides Released Unit 1st Qtr 1 2nd Qtr l 1st Qtr l 2nd Qtr l

None Released This Per.od 1

Page 0

ErrLUE!dT AfiD WASTL DISPOSAL SEMI A!JtJUAL REPORT Period ? Jan - Jun 1991 Table 3 Solid waste and Irradiated ruel Shipments A.

Solid Waste Shipped offsite for Durial or Disposal (not irradiated fuel)

1. Type of Waste l

Units l

6-month Est. 'rotal Period Error, %

a.

Spent resins, fTTter sludges, cu. Meter

2. 4 3if7El evagorator bottoms, etc.

Ci 4.14r+02 3.70E+01

b. bry compress Efe waste, cu. Meter F.JTi'751 contaminated equipment,.etc.

Ci 2.50E+00 3.50E+01 c.

I r r ad i a t e d' c ompon'e n t s,

Cu. Meter 0.~03E+00 control rods, etc.

I Ci 0.00E+00 0.00E+01

d. Other (describe) l Cu. Meter 0.6DE+00

_[_

Ci l 0.00E+00 0.00E+01

3. Estimate of major nuclide

[~~TOilide Percent l

composition (by type of waste) l _

l A

l Cr-51 1 1.25E+00 l

Mn-54 l 3.02E+00 l

re-55 l 3.61E+01 l

Co-58 l 7.95E-01 l

re-59 l 2.53E-01 l

co-60 l 3.41E+01 l

t11-63 1.21E-01 l

n-65 2.10E+01 i

Sr-89 2.14E-01 S r-9 f' 3.94E-02 Ru-11$ ll l 3.73E-02 Sb-1@f 1.68E-03 l

I - l 'q l 2.17E-02 l Cs.Sj, 2.43E-01 l l

C s -1 16 9.05E-01 l Cs-:I37 1.69E+00 l Ba-140 9.65E-03 1 l

La-140

,1.86E-03 l l

Ce-141

<1.54E-02 l

\\

l i

D l

Mn-54 5.56E+00 li3.87E+01 l

re-55 l

l l

Co-60 l 3.58E+01 l I

tii-53 l 1.35E+00 l i

n-65 It6.19E+00 l l

3r-89 1: 2.58E+00 l

Sr-90 l4 5.35E-01 1

20-137 l 4.58E+00 l

1

Pa9e 9

EFTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1991 Table 3 Solid Waste and Irradiated fuel Shipments 3.

Solid waste disposal Number of (

Mode of l

Destination Shipments Transportation 4

Truck Chem-Nuc inc., Barnwell, SC.

3 l

Truck US Ecology, Richland, WA.

I 2

Truck US Ecology, Beatty, NV.

I B.

Irradiated Fuel Shipments

1. Disposition Number of l Mode of l

Destination Shipments l Transportaticn l Mone This Period C. Shipping Container and Solidification Method Activity l Type of Container Solidification l No.

~ Volume M3 Ci Waste Code Code 91-02 5.8TE+00 7.661+01 A

A D

I 91-03 1.70E+01 l 7.95E-01 B

L N

91-06 l 5.83E+00 1 4.90E+01 A

A D

91-27 3.41E+00 7.89E+01 A

\\

A l

D 91-58 3.26E+01 1.69E+00 l B

l L

l N

l 91-28 3.41E+00 6.74E+01 l A

A D

91-37 5.83E+00 1.42E+02 l A

A D

91-30 2.58E-01 6.69E-03 l B

L N

91-47 l 2.41E-01 l 1.34E-02 l B

l L

j N

1 1

I I

l Container Codes :

Solidification Codes :

L - LSA C - Cement A - Type A U - Urea Formaldehyde B - Type B D - Dewatering Q - Large Quantity N - Not Applicalble

_

Retrieved from "https://kanterella.com/w/index.php?title=ML20082M308&oldid=4370864"