ML20012A278

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Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1989. W/900220 Ltr
ML20012A278
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 12/31/1989
From:
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003090141
Download: ML20012A278 (27)
v • d • e


Text

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. Commonwealth Edloon

" ~ ,. . LaSalle County Nuclear Sution L Rural Route #1, Box 220

~- Marseilles. lilinois 61341 i

, Telephone 815/357-6761 February 20, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.

Subject:

LaSalle County Nuclear Station l Semiannual Radioactive Effluent Release Report NRC Dockets 50-373 and 50-374 h'.

Enclosed is the Radioactive Effluent Release Report for July through December 1989. -Included with this report is a description of changes made to the Process Control Program.

A copy of this report will be furnished to the NRC Resident Inspector.

Sincerely, iM4 J. Diederich

.ation Manager Enclosure cc Director of Nuclear Reactor Regulation NRC Region III Illinois Department of Nuclear Safety American Nuclear Insurers B. P. I.

American Electric Power Service Corp.

U. S. EPA Illinois EPA Illinois EPA (Division of Water Pollution Control)

Murray and Trettel, Inc.

Teledyne Isotopes Midwest Laboratory Performance Assessments Chemistry Services Engineering nnd Construction Manager Emergency Preparedness Health Physics Services Supervisor NRC Resident Inspector Quality Assurance Supervisor g

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Chemistry Supervisor y Illini State Park Central File. gg 2CADBULL/266 9003090141 091231 PDR ADDCK 05000373 R PNV ,

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l LASALLE COUNTY NUCLEAR POWER STATION UNITS ONE AND TWO '

DOCKET NUMBERS 50-373 AND 50-374 ,

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989) i OASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Third Fourth ,

Quarter Guarter >

A. Fission and Activation Gases

1. Total release C1 1.08E+03 4.29E-03 ,
2. Average release rate for period uCi/sec 7.35E+01 2.73E-01 B. Iodines
1. Total iodine-131 Ci 2.55E-03 2.15E-03
2. Average release rate for period uCi/see 6.47E-04 1.13E-03 C. Particulates
1. Particulates with T1/2 >8 days Ci 6.55E-04 6.26E-04
2. Average release rate for period uC1/sec 1.80E-04 2.08E-04
3. Gross alpha radioactivity Ci <1.00E-11 <1.00E-11 D. Tritium
1. Total release Ci 0.00E+00 0.00E+00 ,
2. Average release rate for period uCi/sec <1.00E-06 <1.00E-06

'<* i-11 cates activity of sample is less than LLD given in uci/e1 t

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l CFFLUENT AND WASTE DISPOSAL REPORT (1989)  !

GASEQUS EFFLUENTS-ELEVATED RELEASE Nuclides Released July Aug. Sept. Third Quarter  ;

1. Fission Gases l Ar-41 C1 1.33E-07 4.51E-09 3.74E-08 1.75E-07 '

Kr-85s Ci <1.00E-06 6.89E*01 8.29E+01 1.52E+02 Kr-87 Ci <1.00E-06 4.79E+01 3.51E+01 8.30E+01 Kr-88 C1 <1.00E-06 1.85E+02 1.46E+02 3.31E+02 Xe-133 C1 <1.00E-06 2.21E+02 1.95E+02 4.16E+02 Xe-133s Ci <1.00E-06 <1.00E-06 2.16E-06 2.16E-06 Xe-135 Ci <1.00E-06 8.47E+01 9.19E+00 9.39E+01 Xe-138 Ci <1.00E-06 <1.00E-06 <1.00E-06 <1.00E-06 i Total for period C1 1.33E-07 6.08E+02 4.68E+02 1.08E+03 2, Iodines I-131 Ci 1.74E-04 2.55E-04 2.12E-03 2.55E-03 1-132 C1 1.16E-03 3.64E-03 <1.00E-11 4.80E-03 I-133 C1 1.89E-03 2.24E-03 4.53E-04 4.59E-03 I-134 Ci <1.00E-11 7.41E-03 <1.00E-11 7.41E-03 I-135 C1 1.00E-03 1.75E-03 <1.00E-11 2.75E-03 Total for period Ci 4.22E-03 1.53E-02 2.57E-03 2.21E-02

3. Particulates Mn-54 Ci <1.00E-04 3.81E-05 4.92E-05 8.73E-05 Co-58 Ci <1.00C-04 <1.00E-04 <1.00E-04 <1.00E-04 Fe-59 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Co-60 C1 1.04E-04 .2.21E-04 2.43E-04 5.68E-04 ,

2n-65 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Sr-89 Ci <1.00E-11 <1.00E-11 <1.00E-11 <1.00E St-90 Ci <1.00E-11 <1.00E-11 <1.00E-11 <1.00E-11 Hb-95 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Mo-99 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Cs-134 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Cs-137 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Ce-141 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Ce-144 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Total for period Ci 1.04E-04 2.59E-04 2.92E-04 6.55E-04

'<' indicates activity of sample is less than LLD given in uci/s1

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EFFLUENT AND WASTE DISPOSAL REPORT (1989)

GASEOUS EFFLUENTS-ELEVATED RELEASE Nuclides Released Oct. Nov. Dec. Fourth Guarter

1. Fission Gases Ar-41 Ci 2.35E-03 <1.00E-06 6.93E-10 2.35E-03 Kr-85s C1 <1.00E-06 <1.00E-06 <1.00E-06 <1.00E-06 Kr-87 C1 <1.00E-06 <1.00E-06 <1.00E-06 <1.00E-06 Kr-88 Ci <1.00E-06 <1.00E-06 <1.00E-06 <1.00E-06 Xe-133 Ci <1.00E-06 <1.00E-06 <1.00E-06 <1.00E-06 Xe-133m Ci <1.00E-06 <1.00E-06 <1.00E-06 <1.00E-06 Xe-135 Ci 1.94E-03 <1.00E-06 8.25E-10 1.94E-03 Xe-138 Ci <1.00E-06 <1.00E-06 <1.00E-06 <1.00E-06 Total for period C1 4.29E-03 <1.00E-06 1.52E-09 4.29E-03
2. Iodines I-131 C1 1.72E-03 2.28E-04 1.99E-04 2.15E-03 1-132 Ci <1.00E-11 <1.00E-11 <1.00E-11 <1.00E-11 I-133 C1 4.27E-04 1.5BE-03 7.40E-04 2.75E-03 I-134 Ci 5.91E-03 <1.00E-11 <1.00E-11 5.91E-03 I-135 C1 2.33E-04 1.41E-03 <1.00E-11 1.64F-03 Total for period Ci 8.29E-03 3.22E-03 9.48E-04 1.25E-02
3. Particulates _

Cr-51 Ci 0.00E+00 0.00E+00 1.33E-04 1.33E-04 Mn-54 C1 3.46E-05 1.41E-05 <1.00E-04 4.87E-05 Co-58 C1 <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Fe-59 Ci _<1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Co-60 C1 2.22E-04 1.80E-04 4.24E-05 4.44E-04 Zn-65 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 ,

Sr-89 Ci <1.00E-11 <1.00E-11 <1.00E-11 <1.00E-11 i

Sr-90 Ci <1.00E-11 <1.00E-11 <1.00E-11 <1.00E-11 Nb-95 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Mo-99 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Cs-134 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 ,

Cs-137 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Ce-141 Ci <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Ce-144 C1 <1.00E-04 <1.00E-04 <1.00E-04 <1.00E-04 Total for period C1 2.57E-04 1.94E-04 1.75E-04 6.26E-04

'<" indicates activity of sample is less than LLD given in uci/ml i

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EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT (1989) p.. .

UNIT ONE

~ LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES

.t Third- Fourth i Quarter ' Quarter (

t

'A. Fission and Activation Products

1. Total release (not including- Ci 0.00E+00 3.07E-02 ,

tritium, gases, alpha)

2. Average concentration released uC1/ml N/A 8.15E-06 .
3. Maximum concentration relsased uC1/ml N/A 9.10E-05 *

.i B. Tritium i i

1. Total release C1 0.00E+00 3.86E-01 f
2.~ Average. concentration released- uCi/n1 N/A 8.60E-04 C. Dissolved Noble Gases
1. Total release Ci 0.00E+00 0.00E+00
2. Average concentration ~ released uC1/mi N/A <1.00E-05  !

D. Gross Alpha.Redioactivity 1

1.JTotal release C1 0.00E+00 1.14E-06

2. Average concentration released uC1/ml N/A 6.00E-09 E. Volume of Waste Released liters 0.00E+00 4.47E+05 a

,s F. Volume of Dilution Water liters 0.00E+00 6.05E+08L

"<* indicates activity of sample in less than LLD given in uCi/al-S i

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e EFFLUENT AMD WASTE DISPOSAL REPORT (1989)

UNIT ONE 7,; ; LIQUID EFFI,UENTS Nuclides Releasedu July. Aug. Sept.' Third b Quarter Cr C1 'No No No Mn - Ci1 Releases Releases Releases Fe-55 C1' Co-58 Ci

-Fe-59 Ci Co-60 Ci Zn-65 Ci Sr-89 Ci Sr-90 Ci

.Mo-99 Ci I-131- Ci Xe-133 Ci-Xe-133m C1-Co-134 C1 Xe-135 C1 Cs-137 C1 Co-141 C1' Ce-144 Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 .

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EFFLUENT AND WASTE DISPOSAL REPORT (1989)

UNIT ONE LIQUID EFFLUENTS

, Nuclides Released Oct. Nov. Dec. Fourth Quarter Cr-51 Ci No No 2.64E 2.64E-03 Mn-54 Ci Releases Releases 5.37E-03 5.37E-03 Fe-55 C1 1.09E-03 1.09E-03 Co-58 C1 1.33E-04 1.33E-04 Fe-59 C1 3.52E-04 3.52E-04 Co-60 C1 2.11E-02 2.11E-02 2n-65 Ci <5.00E-07 <5.00E-07 Sr-89 C1 2.69E-06 2.69E-06

-Sr-90 C1 4.03E-07 4.03E-07 Mo-99 Ci <5.00E-07 <5.00E Tc-99m C1 4.60E-05 4.60E-05 I-131 Ci <1.00E-06 <1.00E-06 Xe-133 C1 <1.00E-05 <1.00E Xe-133m Ci <1.00E-05' <1.00E-05

-Cs-134 Ci < 5.00E-07 <5.00E-07 Xe-135 Ci <1.00E-05 <1.00E .Cs-137 Ci <5.00E-07 <5.00E-07 Ce-141 Ci <5.00E-07 <5.00E-07 Ce-144 C1 <5.00E-07 <5.00E-07

. Total for period Ci 0.00E+00 0.00E+00 3.07E-02 3.07E-02

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l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)

UNIT TWO

, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Third- Fourth Quarter Quarter A. Fission and Activation Products

1. Total release (not including Ci 0.00E+00 9.30E-02 tritium, gases, alpha)-
2. Average concentration released uC1/mi N/A 2.20E-05
3. Maximum concentration released uC1/ml- N/A 3.80E-04 B. Tritium
1. Total release Ci 0.00E+00 3.75E-01
2. Average concentration released uCi/ml N/A 8.80E-04 C. Dissolved Hoble Gases
1. Total release Ci 0.00E+00 0.00E+00
m. 2. Average concentration released uCi/ml N/A <1.00E-05 D. Gross Alpha' Radioactivity
1. Total release Ci 0.00E+00 2.57E-06
2. Average concentration released uC1/ml N/A 4.00E-09 E. Volume of Waste Released liters 0.00E+00 4.46E+05 F. Volume of Dilution Water liters 0.00E+00 5.69E+08

'<* indicates activity of sample is less than LLD given in uCi/ml

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EFFLUENT AND WASTE DISPOSAL REPORT (1989)

UNIT TWO LIQUID EFFLUENTS Nuclides Released July Aug. Sept. Third Quarter Cr-51 Ci- No No No Mn-54' Ci Releases Releases Releases Fe-55 C1 Co-58 C1 Fe-59 C1 Co-60 C1 2n-65 .C1 Sr'-89 Ci Sr-90 Ci Mo-99 'Ci 1-131 Ci Xe-133 C1 Xe-133m C1 Co-134 Ci Xe-135 C1

.Cs-137 C1 Ce-141 C1 Co-144 Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s

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i EFFLUENT AND WASTE DISPOSAL REPORT-(1989)

UNIT TWO LIOUID EFFLUENTS Nuclides Released Oct. Nov. Dec. Fourth Guarter Na-24 'Ci No No 4.60E-06 4.06E-06 ,

Cr-51 Ci ' Releases Releases 2.73E-03 2.73E-03.

Mn-54 C1 1.59E-02 1.59E-02 j Fe-55 C1 1.44E 1.44E-02 L Co-58 C1 1.86E-04' 1.86E-04 L Fe-59 C1 4.36E 4.36E-04 i Co-60 C1 5.85E-02 5.85E-02 l' Zn-65. Ci 7.40E-04 7.40E-04 -'

Sr-89 'C1 1.73E-05 1.73E-05

  • l Sr-90 C1 4.25E-07 4.25E Mo-99 Ci <5.00E-07 '<5.00E-07 4 Tc-99m Ci- 6.40E-05 6.40E-05 Ag-110m Ci 6.50E-05 6.50E-05 I-131 C1 <1.00E-06 <1.00E-06 Xe-133 C1 '<1.00E-05. <1.00E-05 ,

Xe-133a C1 <1.00E-05 <1.00E-05

-Cs-134 Ci: ~<5.00E-07 <5.00E-07 Xe-135- Ci <1.00E-05 <1.00E-05

Cs-137 Ci <5.00E-07 <5.00E-07 Ce-141 C1 <5.00E-07 <5.00E-07 Ce-144 Ci <5.00E-07 <5.00E-07 (

Total for period Ci 0.00E+00 0.00E+00 9.30E-02' 9.30E-02 1 i

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)  !

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

[# July Aug. Sept. Third i Quarter

1. Spent resins, filter sludges, evaporator bottoms, etc.
m. Quantity shipped. cu.a. 3.92E+01 3.64E+01 2.56E+01. 1.01E+02.

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b. Total activity Ci 4.07E+02 7.11E+02 2.01E+02 1.32E+03 j 1

c.-Ma]or nuclides (estimate) i Co-60  % 25 25 25 Fe-55  % 58 '58 58 Mn-54  % 13 13 13 Cr-51  % '02 02 02 a

d.' Container type LSA LSA LSA  !

e. Container volume cu.a. 2.12E-01 2.12E-01 2.12E-01 3.29E-01 3.85E+00 3.29E-01 3.94E+00- 3.94E+00 3.94E+00 5.07E+00 -)

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f. Solidification agent Cement Cement- Cement

' 2. Dry compressible vaste, contaminated equipment, etc.

a.' Quantity shipped cu.a. 1.33E+02 2.19E+01 1.82E+01 1.73E+02 b.-Total activity Ci 5.01E+00 1.46E+00 1.23E+00 7.70E+00 -;

c. Ma]or nuclides (estimate)

Co-60  % 10 10 10 Fe-55  % 71 71 71 Mn-54  % 06 06 06

d. Container type LSA LSA LSA
e. Container volume cu. a. 2.72E+00 2.12E-01 2.12E-01 3.51E+01 2.72E+00 3.29E-01 2.72E+00

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EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT'(1989) i .

SOLIDLWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL; July Aug. . Sept. Third.

Quarter

+4 3.~ Solid Weste Disposition

a. Number of Shipments' 16 12- ' 08 lHs b.LMode of Transportation Hittman Hittman Hittman-Number 16 12 08
c. Destination Beatty,RNV .Barnwell, SC Barnwell, SC' Humber 12 02 01

' Waltz Hill, PA Beatty,lNV Beatty, NV Number' 04 09 06 Dak Ridge, TN Oak Ridge, TN Humber 01 01

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! EFFLUENT AND WASTE DISPOSAL SEMIANHUAL REPORT (1989)

SOLID WASTE SHIPPED OFFSITE FOR BURIAL'OR DISPOSAL' Oct. Nov.- Dec. Fourth Quarter i ,

1. Spent _ resins, filter sludges,  :

evaporator bottoms, etc.

a. Quantity shipped cu. a. 2.22E+01 1.70E+01 3.47E+01 7.38E+01-
b. Total activity. C1 2.07E+02- 3.57E+02, 2.19E+02 7.83E+02
c. Ma3or nuclides (estimate)

Co-60  % 25- 25 25 Fe-55  % 58 58 58 Mn  % 13 13 13 Cr-51  % 02 02 02

d. Container type LSA LSA LSA
e. Container volume cu. a. 2.12E-01 2.12E-01 -2.12E-01 3.29E-01 5.07E+00 3.94E+00 3.86E+00 5.07E+00 3.94E+00 5.07E+00 f.1So11dification agent Cement Cement Cement.
2. Dry compressible waste, contaminated equipment, etc.
a. Quantity shipped. cu. a. 4.65E+01 3.71E+01 2.17E+01 1.05E+02 b.. Total activity _ C1 8.52E+00 1.90E+00 3.04E-03 1.04E+01
c. Maaor nuclides (estimate)

Co-60  % 10 10 10 Fe-55  % 71 71 71 Mn-54  % 06 06 06 d.' Container type LSA LSA LSA

e. Container volume cu. a. 2.12E-01 2.12E-01 2.12E-01 3.29E-01 2.72E+00 2.72E+00

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~ EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT'(1989)

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR. DISPOSAL

. ' 41 Oct.. Nov. Dec. Fourth Quarter i

0 3. Solid Waste Disposition

,s. Number of' Shipments ,08 07 12 27

b. Mode of Transportation Hittman Hittman 'Hittman

, i Number 07 07 12-U.S. Ecology.

Number 01 c.. Destination. Barnwell, SC Barnwell, SC Barnwell,fSC' Humber 02 01 01

, Beatty,.NV 'Beatty, NV Beatty,- NV Number '04 04 09 Dak Ridge,-.TN Oak Ridge, TN Oak Ridge, TN Number' 02 02 02 4

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a EFFLUENT'AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)-

l I

MAXIMUM DOSES RESULTING FROM RELEASES j Third Fourth Quarter Quarter

-A. Gaseous Effluents (Units One and Two)

L

1. Gamma air MRAD 2.57E-02 1.07E-07
2. Beta air MRAD 2.86E-03 1.28E-08
3. Total Body ~ MREM 1.49E-02 5.67E-08 j
4. Skin MREM 2.20E-02 9.32E-08
5. Organ (infant thyroid) MREM 7.35E-03 4.93E-03 B. Liquid Effluents (Unit One)  ;
1. Total body MREM 0.00E+00 2.05E-05 _i
2. Internal organ (infant GI-LLI) MREM 0.00E+00 2.10E-05 -'J C. Liquid Effluents (Unit'Two)  :
1. Total body _

MREM 0.00E+00' 5.16E-05

2. Internal organ _(infant GI-LLI) MREM 0.00E+00 5.33E-05:

COMPLIANCE STATUS A. Gaseous Effluents (Units One and Two)  !

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1. Gamma air  % of Tech. Spec. Limit 0.51 0.00- l
2. Beta air  % of Tech ' Spec. Limit 0.03 0.00- i 3.-Total body  % of Tech. Spec. Limit 0.60' O.00
4. Skin  % of Tech. Spec. Limit 0.29 0.00
5. Organ X of Tech. Spec. Limit 0.10 0.07 B. Liquid Effluents (Unit One)
1. Total body  % of Tech. Spec. Limit 0.00 0.00
2. Internal organ  % of Tech. Spec. Limit 0.00 0.00.

'C. Liquid Effluents (Unit Two)

1. Total body  % of Tech. Spec. Limit 0.00 0.00

> 2. Internal organ X of Tech. Spec. Limit 0.00 0.00 l

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J EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)

Supplemental Information r

~1.; Regulatory Limits

a. Gaseous effluents 1)I The air. dose due to noble gases released in gaseous effluents, from each reactor unit, from the site shall be limited to the

-followings. . .

a) During any calender quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta e radiation, and b) During any calendar years Less than or equal to 10 mrad for.

gamma radiation and less than or. equal to 20 mrad for beta-radiation.

2) The dose to an individual from radiciodines and radioactive e materials in particulate form, and radionuclides, other than --

noble gases,=with half-lives greater then.eight days in gaseous  :

effluents released, from each reactor unit, from the site shall' be limited to the following a) During any calendar quarter: Less than or equal to 7.5 areas to any organ, and b)'During any calendar years Less than or equal to 15:arens to any organ.

.i

b. Liquid effluents  ;
1) The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, j from the site shall be limited i a):During any calendar quarter to less than or equal to 1.5 arem to the total body and to less than or equal to 5 area to any organ, and ,

b) During any. calendar year to less than or equal to 3 arem to -

the total body and to less than or equal to 10 mrem to any.

organ,

c. Total dose
1) The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mres to the body or any organ (except the thyroid, which shall be limited to less than or equal to 75 arem) over 12 consecutive months.

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.. EFFLUENT AND WASTE DISPOSAL REPORT (1989)

Supplemental Information (continued)

2. Maximum Permissible Concentrations
a. Gaseous effluents
1) The dose rate due to radioactive materials released in gaseous effluents fron-the site shall be limited to the followings a) For noble gases: Less than or equal to 500 arems/ year to the

. total body and less than or equal to 3000 aress/ year to the

~s kin, and b) For all radiciodines and for all radioactive materials in particulate form, and radionuclides, other than noble gases,-

with half-lives greater than eight days: Less than or equal to 1500 arems/ year to any organ via the inhalation pathway.

b. Liquid effluents
1) The concentration of radioactive saterial released from the site shall be limited to the concentrations specified in.10 CFR Part.20, Appendix B, Table II, Column 2 for radionuclides other.

than dissolved or. entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to the following:

Nuclide MPC (uci/al)

Kr-85m 2.00E-04

'Kr-85 5.00E-04 Kr-87 4.00E-05 Kr-88 9.00E-05.

Ar-41 7.00E-05 Xe-131m 7.00E-04 Xe-133m 5.00E-04 i

Xe-133 6.00E-04

... Xe-135m 2.00E-04 Xe-135 2.00E-04

3. Average Energy
a. Not applicable.

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-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989) -

Supplemental Information (continued) l

-4. Measurements and Approximations of Total Radioactivity Vf a. Gaseous effluents

1) Containment vant and purge system is sampled by grab sample which is analyzed for principal gamma emitters and H-3.
2) Main vent stack'is sampled by grab sample which is analyzed for principal gamma emitters and H-3.
3) Standby gas treatment system is sampled by grab sample which is -t analyzed for principal gamma emitters, f
4) All release types as. listed in 1 and 2 above, at the vent stack and as listed in 3 above, at.the standby gas treatment system ,

whenever there is flow, are continuously sampled by charcoal, particulate and composite samples which are analyzed for iodines, principal gamma emitters,' gross alpha, Sr-89 and Sr- -

90. Noble gases, gross beta and gamma are continuously' '

monitored by noble gas monitors for the vent stack and the standby gas treatment system. 4

b. Liquid effluents
1) Batch waste release tanks are sampled each batch for principal gamma emitters, I-131, dissolved and entrained noble games, H- .,

3, gross alpha, Sr-89, Sr-90 and Fe-55. 4 2)' Continuous releases are sampled continuously'in proportion to the rate of flow of the effluent' stream and by grab sample, Samoles are analyzed for principal gamma emitters, I-131, 3 dissolved and entrained noble gases, H-3, gross alpha, Sr-89, Sr-90 and Fe-55. ,

f v +._ __ ___ __ - _ _ -_ ___ _ - - _ _ _ - - _ _

b~ .

. . .t ac <

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)

Supplemental Information (continued)

5. Batch Releases
a. Gaseous
1) Number of batch releases: None
2) Total time period-for batch releases N/A
3) Maximum time period for a batch release: N/A
4) Average time period for batch' releases N/A
5) Minimum time period.for.a batch releaset N/A
b. Liquid
1) Number of batch releases: 12 2)' Total time period for batch releases: 139 hrs 21 min
3) Maximum time period for a batch release: 12 hrs 38 min
4) Average time period for batch releases: 11 hre 37 min

, 5) Minimum time period for a batch release: 10 hrs 27 min

6) Average stream flow during periods of release of effluent into a flowing stream: 6.15E+06 gps

w r>

. . 4-r CICo L&SALLI $7&flos july-Ibceeber 1989 ~

g 375 ft. VIID SPED and V!RD D!IECT108 375 33 f t. DITTttm!AL TIRPtt479t!

< MBER OF ObstRVAfl055 * (195 SPtp ' 0111t!!06 CI. ASS ST&BILITT C:. ASS CL456 I _ WI REE DI t ESE St SSI $ $$t St. USV V MV M Bev 70!&L EU n = SU B SS : RS. IS ; MAL A

IIU ' .00 .00 .00 .00 .00- .00 .00 .00 .00 .00 .00 .00 .00 ' .00 ' .00 .00 .00 .00

. W ' .00 ' .00 .00 - .00 i '.00 . 00 .00 00 .00 .02 .00 . 00' .00- .00 .00 .00 f.02 .02 7 $U .00 .00 . 00 ' .00 = .00 .00 .00 .00 .00 .00 .02 .00 .00 .00 .00 : .00 - .02 .02 I , .05 .05 - .10 .10 ' .10 ? .02 .07 = .05 .07 .00 .02 .00 . 02 .05 .07 07 .83 .83 3SS .00 : .05 ' .05 -.00 02 .00 .02 .02 .02 .00 .07 .05 .02 .00 .05 .02 . ' .41 .41-RS i .00 .00 .00 .00 .05 .02 - .00 .00 .02 .05 .05 .10 .02 .02. '.00 ' .00 i .33 .33 IS ' :.00 .00 .00 .00 .00 .00 ' 00 .00 .00

.00 .00 .00 '.00 '.00 .60 .00 .00 - .00

. 4 1.62 IU . 00 .00 .00 .00 ~ .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00' ' .00 RU -

.00 < .00 : .00 .00 00 .00 .00 .00 : .00 .05 .07 .00 .00 .00 .00 .00 .12 .12 4$U .02 , .02 .00 .00 .00 .00 .00 . 05 .12 .05 .12 .00 .00 .00 .00 .00 .38 .38 I .41 ' ' .52 .79 .62 .45 .95 .79 .31 .57 .17 .43 .26 .29 .33 .24 .10 7.22 7.22 a - 7 SS x .07 .07 ~.29 - .29 .36 . .17 .14 .19 .10 .07 .05 .02 .05 .19 .21 .17 2.43 2.43 IS : .02 .02 .12 .07 .07 .07 ' .02 .26 .07 .21 .14 .07 .10 ' .05 .02 : .02 = 1.36 1.36 IS. .00 .00 ' .00 .00 .00 .05 .00 .02 .00 .00 .05 .07 .00 . 02 .02 .00 .24 .24 -

' 11.75 ,

EU ! . 00 .00 '.00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 - .00 : -.00 .00 .00 - .00 .00 W' .00 .07 .21 '.00 .00 .00 .00 .00 .00 .10 .05 .00 .00 .00 - .00 .00 .43 .43 8SU .02 .05 -.12 : 05 - .00 .00' .00 .05 .05 .05 .05 .07 .05 .00 .00 .00 .55 .55 I .57 .95 2.15 .69 .62 .60 .98 .74 ~ 74 .36 .21 .48 .29. A5- d4 .19 10.49 10.49 1 $$ .21 ^ .38 .67 .48 .64 .33 .50 .26 .14 .24 .17 .21 .17 .10 .12 .17 4.79 4.79

- 2 RS .07 1.05 .10 .05 .07 .26 .48 .36 .33' .12 .29 .26 .14 .10 . 10 .17 2.93 2.93

- ES .00 ' .00 ' .02 .00 .05 .02 .14 .05 .19 .02 .17 .10 .00 .07 .02 .02 .58 .88 20.07

.. EU .00 .00 .00 .00 .00 00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ~ .00 .00

1 RU - .00 .00 .00 .02 .00 . 00 .00 .00 .00 .02 .00 .00 .00 .00 .00 , .00 .05 .05 3 SO .00 '.17 - - .05 .05 .00 .00 .00 .02 .02 .00 .05 .07 .02 .00 .00 ' .00 .45 A5
I .81 1.00 .1.12 ' 1d5 .88 .43 .29 .72 .55 .72 .64 . 95 .81 .93- 1.26 1.38 13.95' 13.95 .

1 SS .17 .24 , .36 .45' .86 .36 ' .41 .29 .36 .31 .36 .44 .36 .48 .55 .41 6.41 6.41 8 R$ ! .21; .05 .05 .05 - .17 .55 .36 .55 .33 .48 .43 .29 .29 d5 .19 .45 4.89 4.69 t$ .02 .05 .00 .00 .02 .00 .02 .55 .33 .36 .24 .14 .02 .00 . 00 .10 1.86 1.86 a 27.60

50 .00 .00 .00 .00 .00 .00 '.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 - .00 .00 1R .02 .00 .00 .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .05 .05 9 $U .07 .02 - .00 .00 .00 .00 .00 .00 .00 .14 .07 .00 .00 .00 .00 .02 .33 .33 R 1.07' .93 .29 .07 .07 .05 .02 .21 .43 .76 .57 .48 .81 .41 A5 86 7.49 7.49 '

' 2 SS .17 .21 .00 .10 .21 .33 .14 .33 .48 .62 .72 .29 .31 d3 .50 A8 5.32 5.32 4 RS ' .17 .07 .00 .00 .02 .14 .31 .21 .36 .26 .48 .31 .41 .41 .57 .31 ' 4.03 4.03 IS .00 .00 .00 - .00 .02 .00 .02 .43 .24 .43 .31 .24 .17- .02 .00 .07 '1.95 1.95 19.17

' IU ; .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 - .00 .00 .00 2 W . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 5 $U .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .10 .10 .10 I .88 .24 .00 .00 .00 .00 .00 .02 .31 .43 .21 .17 .36 .57 1.07 .74 5.01 5.01 -

3 SS .05 .10 .00 .02 .00 .00 .07 .24 .60 .62 .79 .21 .48 .36 .67 .10 4.29 4.29 1 RS .05 .00 .00 .00 .00 .00 .33 .12 .17 .38 .38 .10 .07 .33 .17 .05 2.15 2.15 IS .00 .00 .00 .00 .00 .00 .05 .19 .69 .95 .26 .31 .12 .05 .02 .00 2.65 2.65 14.18 e ,- _ - - - - -_. _ _ _ _ _ . - _ - - _

, s i_ , as

. . ;; * ~

sL Cito IASELE STAT 105 ' hly December 1989 375 ft. WIND $ PEED and VIBD D!ticflos 375-33 f t. O!FTERD!!AL TDPDATUlt SPEG = D!ttCTIGO C1 ASS 57 ABILITY CIASS -

0 CLAES -I' III ' O! - DE . I DE $1 SEE < $ SSV 5t USv v: MV IV IN TOTA!. DH $U I $$ us ES TOTA!.

IO .00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 - .00 .00

(~ - 3m .00 .00 .00 .00 .00 ~ .00 .00 .00 .00 .00 .00 .00 - .00 .00 .00 .00 .00 .00 -

! - 2 50 ~ .00 .00 .00 '.03 .00 . .00 .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I .12 .00 .00 .00 .00 .00 .00 .M .19 .38 - .07 .00 .00 .45 .38 .07 "1.67 .1.67 Ew.  : 3 38 -.00 . 00 .00 .

.00 . 00 . 00 .02 .00 ' .29 ' .79 .29 .19 ' .24 .21 - .02 - .05 2.10 2.10

' 8 5 --.00 .00 . 00 .00 .00 _ .00 .00 , .00 .02 .26 .21 . 02 .05 .02 .00 .00 .60 .60

(! 2 :.00 .00 .00 .00 .00 .00 .00 . 05 .14 L .17 .05 .10 .10 = .00 :.00 .00 .60 .60 .

4.96 N .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 - .00 .00 3 go ' .00 .00 .00 .00 .00 .00 ' .00 .00 .00 .00 .00 . 00 .00 .00 .00 .00 .00 . .00 9 SU _ .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 - .00 .00 .00 .00 - .00

-I .05 .00 .00 .00 .00 .00 '.00 .00. .00 .02 .00 .00 .02 .07 .14 .00 .31 .31 c

4 55 .00 .00 t .00 _ .00 .00 .00 .00 ' .00 .07 .05 .00 .02 .07 .02 .00 .00 .24 .24 6 R$ .00 .00 ' . 00 .00 s .00 .00 .00 . 00 .02 . 02 .00 .00 .00 .00 .00 .00 .05 .05 ES : .00 .00 .00' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 .00 .00 .00 .00 .

.60 10 .00 .00 .00 .00 .00 ~ .00 .00 .00 .00 .00 .00 .00 00- .00 .00 .00 .00 .00 0 50 .00 --.00 .00 .00 .00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 - .00 .00

- T SU .00 : .00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ' .00 .00 .00 5 .00 .00 .00 ' .00 .00 .00 .00 .00 .00 00 .00 00 .00 .05 -.00 .00 .05 .05 4 $$ .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6 NS .00 !.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 IS .00 .00 .00 .00 .00 .00 . -.00 .00 .00 . 00 .00 .00 .00 .00 '.00 - .00 .00 ,

.00

.05 N .00 I .00 .00' .00 .00- .00 .00 .00 .00 .00 .00 .00 - .00 .00 .00 .00 .00 .00 RU .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ' .00 .00 -

C SU ' :.00 .00 .00 ' .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 ' .00 .00 '.00 .00 .00 A . I ; ~.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 =

= L SS ' .00 ~.00 . .00 = 00 .00 .00 .00 .00 ' .00 ,00 .00 .00 .00 . 00 .00 .00 .00 .00 R E , .00 .00 . 00 ' .00 . 00 . 00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 IS - 00 .00 ' . 00 ~ .00 .00 .00 '.00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ' .00

.00 Tot 5.32 5.32 6.46 4.55 4.70 4.36 5.20 6.29 4.03 9.66 0.08 '6.05 5.84 6.65 - 7.34 6.13100.00 .00 .67 1.64 47.01 25.98 16.33 8.18 100.00 S H . - _ .00 6 .00'. 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 .00 .00 .00 0 IU , .02 .07 .21 .02 .00 .00 .00 .00 .00 .19 .12 .00 .00 .00 .00 .02 .67 B 801.12 .26 .17 .10 .00 .00 .00 .12 .19 .24 .31 .14 .07 .00 .00 .12 1.84

' R ' 3.% 3.69 4.43 2.93 2.12 2.05 2.15 2.05 2.86 2.M 2.17 2.34 2.60 3.31 4.10 3.41 47.01 T SS .67 1.05 1.36. 1.33 2.10 1.19 1.31 1.33 2.05 2.69 2.43 1.48 1.69 1,79 2.12 1.38 25.98 0 85 .52 .19 .26 .17 .38 1.05 - 1.50 ' 1.50 1.33 1.79 1.98 1.14 1.07 1.36 1.05 1.00 16.33

' f IS . 02 - .05 .02 .00 .10 .07 .24 1.29 1.60 1.93 1.07 .95 .41 .17 .07 .19 8.18 i

N L g - . -

[*+ 9 i

' i

- EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1989)

CHANGES TO THE PROCESS CONTROL PROGRAM To support the chemical decontamination (LOMI) process of-the Unit One Reactor Recirculation piping in September of 1989,-various bead resin wastes were generated requiring dowatering and disposal. The present radwaste vendor was

. unable to process these LOMI wastes. LaSalle Station opted.to contract the services of-LN Technologies to process the LOMI :i wastes. {

Di Technologies' PCP uses an NRC accepted' system for the.

processing of LOMI wastes. LN's system has been designed to comply with all of the applicable codes, regulations and industry standards including: q 10CFR20, Standards for Protection Against Radiation 1 10CFR50, Licensing of Production and Utilization Facilities 10CFR61, Licensing Requirements for Land Disposal of Radioactive Wastes 10CFR71, Packaging of Radioactive Materials Therefore,: there has been no reduction in the conformance of ,

the waste product compared to the current waste criteria, i i

LN's dewatering operating procedures have been reviewed  !

and accepted by LaSalle Station's Onsite Review and l

- Investigative Function under Onsite Review 89-057 (LN's -!

' operating procedures, waste processing procedures onsite i review).

Technical Specification References to the Process Control Program:

6.7.2.a.1 A copy of this review will be included in the i Semiannual Radioactive Effluent Release Report,  !

and provides sufficient information to support the i' rational for the change.

6.7.2.a.2 The use of LN Technology in) dewater our waste does I not reduce the overall conformance of the waste product to existing criteria. LN's system is designed to conform to applicable codes, regulations and industry standards.

6.7.2.a.3 This change to the PCP has been reviewed by OSR 89-057 (LN's operating procedures, waste processing procedures onsite review).

1 6.7.2.b This change became effective after approval of OSR (89-057 (LN's operating procedures, waste i processing procedures onsite review).

. o

,, .=

.: .- .

  • LAP-1200-2 Revision 7

. April 16, 1985 4-e'

g. i .

ATTACHMENT A

~

.. L.O.S.R. REPORT

~

- Date Assigreent Made ~~ / 'O Review Number J/ NS 9/ao/g_

Date Findings and Recommendations are to be reported

-Subject of Review: m .

~

j Q Qwch je s ,Jb'u j he'c.on (Lb 5

  • s

'# f# U' je c.cc. laka 9.n a I Vce.1 b 'n M C ^ .

OP*"O % " E '*'* O ' "j '"c gf,' g,,, / ~'(,

-Findings and Recommendations:  % '

~ ' g pw eed w as 5'?C 2 -0 0 l -

yjg. cog - Quwn c,e4 U . P ' Removq.) 'Rs4 foe La '. brq b 0.s 4?3C.- ,

S-~' 3107-40.3 - PC P {0( Vemhrt $ . hd Re$,n e,; q gd 3g3 /enp

.-A - A 3934

.! pi i.pr u Attachments: l M PC i 3 7-o'.' -00/

3%: - coy s._, e cap a W A N 'f '~

e, g, '1

, - fgs, .

3102 -00.3 l jn.,q ,, .

Participants:

- ASSIGNER DISCIPLDRES SIGMATURE/ TE

- 3 err lJ,Ik c- G l'PTl2E U 4!G~ dJA > 9-Js-@

~ '

d LJ $I NS f MC2 l w R k it iLOIL/p-P 8/'L,,ADZ"$$Nh$j}1 4 Lakox 1

' PPT l, c / M lE W A 4.

J iAt- .

[

.a sJ Should this report be sent to the offaite Review and Investigation Function? M ]g,,,

L (If YES is checked, complete Attachment B.) g

[L Reason for submittal to offsite Review Function:

. hd// *WY4'y g '*/s Q'ff f V47 Approved: 8//4EWC-C L t '- / M' '

Station Manager

.,.. =

lC % .

Ms.D 2 Kuj {?N.Eb. 3, . 10196A/0035A

4# LAP-1200-13

  • R3 vision-1

.o

-' July 1, 1988 t'

10 Safety Evaluation Form

  • Systemi- RR/Radwaste OSR No Station: LaSalle- Unit 1

' ) Modification

= Item To Be Evaluated:'( )UFSAR ( ) Technical Specifications (X) procedure ( ) Test or Experiment ( ) Temporary System Change ( )Cther Pev 0

-Item Identification Number: LOSR-09-057

Title:

Unit One Reactor Recirculation Chemical Decontamination LN Proced9res

1. . The Change
a. -Description of the Change To onsite review LN TechnoloDies oDeratina crocedures for their eculoment for the L1R03 Chemical Decontamination of the RR eleino and waste crocessing of the LOMI waste.
b. Purpose of the Change: To onsite review LN'Technolooies oDeratina crocedures for their eautoment for the L1P03 Chemical Decontaminati on of

'the RR Dioina and waste crocessina of the LCMI waste.

2. Answer each of the following questions. If the answer to question 2.a. 15 "No", then Justify the "No" answer below (thereby, completing this form):
a. Is this a change to the facility or its operation as described in theNo f :0 Safety Analysis Report (UFSAR), or a test or experiment? Yes ( )
b. Is this a change to the Technical Specifications incorporated in the Operating License? Yes ( ) Jh? 1x)

'See attached.

AIR Number:

3. If the answer to question 2.a. above is "Yes", initiate an AIR and answer each of the following questions "Yes" or "No" and Justify each answers 9 a. Is the probability of an occurrence or the consequence of an accident,

'or malfunction of equipment important to safety, as previously evaluated Yes ( ) No (x) in the' Safety Analysis Report (UFSAR), increased?

N/Q b.. Is the possibility for an accident or malfunction of a different type

,than any-previously evaluated in the Safety Analysis Report (UFSAR)

Yes-( ) No (x) created?

N/n

c. Is the margin of safety, as defined in the basis for any Technical' 3pecification, reduced? Yes ( ) No (x)

N/4 4.- If the answer to que 'on 2.b then proceed by complying with procedure lap 1200 2, Oper tin Y 7" se / nical Specification Changes.

Prepared B b H M O M bd Md Date: 09-27-89 SRO Approval By: Yj -

avr Date l'-3-O 9

r - '-w V 7 L",D-11N -1 F . + ibvision 1

ct July 1, 1999 p  :.- 10 L

Continuation 2.ps

' Decontamination of the Reactor Recirculation piping and ; vessel with the Lcmi

- and Np. processes is not a change to the facility as described-by the UFSAR.

The reactor will be defueled and shutdown. Existing flanges in the Reactor ,

Recirculation System will be used. The effect of the decontamination solvent on existing plant systems was extensively reviewed, analy:ed=and approved by l Corporate Chemical Services. Material specification for the recirculation system allow for general corrosion (5.2.3.1.2), corporate review indicates

' that decontamination solvent corrosion is below this allowance, m

Deoxygenation of.the piping is performed prior to chemical additicn, this prevvets stress corrosion / cracking of stainless steel (UFSAR 5.2.2.2.1) a See LH procedure 3702-001 section 11 pages98-105 which outlines potentially abnormal operating' conditions which could occur during the decontamination process and the operator responses required to ensure pe.rsonnel-safety and ,

s pr' event. damage to system components. 'The DWEDS pumps will be 'taken Out of Service, and the sumps analysed' for TOC before and after the Decen. Check valves will be placed at the air and water drops.

) - The decontamination of the piping will be performed as a non-tafety related Job but the work performed such as the connections to the Reactor Recire, replacement of the vessel head (but not tensioned) and* drainage of the Recire piping will be performed as safety-related jobs. ,

An AIR, 373-251-89-00210, has been written to Chemical Services to address ->

- La Salle Station concerns on the effect of multiple decontaminations of the Reactor Recirculation piping. Corrossion problems are not a concern for a second LCMI decontamination, per Elaine White and her review of EPRI reports  ;

en decontaminations, "It is.a safe assumption to state that the nrrosion effect of a second decontamination will be the same as the one caused by the first application, and double the number from the first decontaminetion is within the general material speci-fied corrosion allowance for the Reactor Recirculation piping." Chemical services will be performing tests to address the concerns expressed by La Salle Station and an evaluation under the above AIR will be returned to the station.

1 Treatment of waste by portable equipment (vendor) is addressed in the UFSAR chapter 11.4 . processing of the waste will be done in conformance with the peceess Control program. All DOT and NRC regulations are met. Processing of the chelated waste has also been approved by Chemical Services.

See attached, Corporate Technical Evaluations for their reviews.

Ccntinuation 2.b

(

) Decontamination of the RR piping and vessel with the LCMI and Np processes is not a chanDe to the facility as described by the Tech Specs. Chemistry Tech Spec Limits (2/4.4.4) will be met since water in the piping will be

:m ,

p t=-nee-i. 3 R , m.  :

  • Ravision in

[ j ' '- -

-July 6 1983 e .. 10

(

(h Om ,

y

., f

- lef t af ery the' Decon at - (10 umho, Chloride is not a con:ern,' and PH will be.

,  ; 1 eft within 1imits, tech spec gives a 72. hour time clock, the LCMI precess

[1 i duraticn is 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> the NP duration is 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Chemical specs have_been j, reviewed-'and approved by corporate.

No new' liquid' releases are anticipated to occurred from this process (Tech

Spec 3/4.'11.1 ) . ..

Reviews of' Tech Specs 6.7.2 and 6.9 are included below with the actions taken.to meet.these specs.

MAJOR CHANGES'TO RADIDACTIVE WASTE TREATMENT SYSTEMS i

To support:the chemical decontemination (LOMI) process of the Unit 1 ..

- Peactor Recirculati in September of 1989, various bead resin wastes will be' generated requiring dewatering and disposal. ,0ur present radwaste vendor Wi'll' be'una'ble to process these LOMI wastes. LaSalle station has thecefore

, ' opted t'o bontract the services of LN Technologies to process 'the LCMI -

- wastes.- ,

/N = LN TechnoloD i es' PCP:uses an NRC accepted system for the processing of the -

j . LCMI wastes. ,LN's system has been designed to comply with al.1 of the applicable codes, regulations, and industry standards including:

.10CFR20,. Standards for Protection Against Radiation.

110CFR50, Licensing of Production and Utili:stion' Facilities

-10CFR61, Licensing Requirements for Land Disposal of Radioactive Wastes

. 10CFR71,, Packaging of Radioactive Materials Therefore,; there-is no reduction in the conformance of the waste product t compared to current waste criteria.

LN's dewatering operating peccedures will be-reviewed and accepted by LaSalle Station's Onsite . Review and Investigative Function under Onsite Review 89-057 (LN's operating procedures, waste processing procedures onsite

-review). t Technical Specification 6.9--Major Changes to Radioactive Waste Treatment Systems

6. 9.1. a.1 A copy of this review will be included in the Monthly Operating report to the Commission. This document provides sufficient information to verify that the change was made in accordance with 10CFR50.59.
p 5.9.1.a.2 A copy of this review, and the 10CFR50.59 review from CSR 89-i f 057 (LN's operating procedures, waste processing procedures onsite review) will be included in the Monthly Operating Report

r- --.

nm L0p-1200 2 :f

'[ .

R2visicn 1 f .,' ,..

July 1, 1983 '

[ .0 , g .: .

- 10 f: x_ E ,

k to-the Commission. These documents provide suf ficient

'information to verify the. rational fcr the change.. ,

t- .

6. 9.1'. a. 3 ' The; following procedures were included in CSR 89-057 (LN's '

operating procedures, waste processing procedures onsite f

review), and provide detailed' descriptions of the equipment, components, and processes involved in.the solidification,'and-describe interfaces with other plant systems:

3702-001,- Operating procedure for the-LaSalle Unit One F

Rectri culati Decontamination '

~3702-002,' System Set Up/ Removal for LN Quick Dry _ Dewatering >

System No. 3291.

3702-002, Process Control porgram for Dewatering Bead or powdered Resin with Quick dry Dewatering System No. 22?1.

6. 9. t. a. 4 There are no anticipated new gaseous' releases due'tc this processing. There are no anticipated new liquid releasesfdue ' #
,to this, processing. One .line'r . of
dewat ered resin (1-20 cu. . 'f,t. )

Lis expected to result from the decontamination. The license application and amendments did not predict any LOMI wastes.

+

,The expected maximum exposure to en individual in the

()/'

6.9.1.a.5 unrestricted area, and to the general population, will'not' change. The waste processing is being performed 'inside the ,

. restricted area, just as any other waste processing.-

6.9.1.a.6' There are no anticipated rad,icactive liquid effluents. There are no anticipated radioactive' gaseous effluents. Is'is anticipated to have one liner, with an estimated 140 curies <

total, as solid waste. This waste will supplement the normal.

s '.i d wate produced during the pericd.

6. 9. l . a. 7 pn estimated 10 man rem of exposure to plant personnel will  ;

result due to the decontamination and waste processing. _j t

6.9.1.a.B The processing of LOMI wastes will be reviewed and approved by the Onsite Review and Invest.igative Function under OSR 89-057 1 '

(LN's operating procedures, waste processing procedures onsite review). ,

6.9.1.b This change becomes effective after approval of OSR 89-057 (LN's operating ' procedures, waste processing procedures onsite

- review).

,l

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