ML20153E980
| ML20153E980 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/30/1988 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| WM-88-0211, WM-88-211, NUDOCS 8809070085 | |
| Download: ML20153E980 (86) | |
Text
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Wolf Creek Generating Station Docket No:
50-482 Facility Operating License No: 'NPF-42 SEMIANNUAL RADIOACTIVE EFFLUENP RELFASE REPORT Report No:
7 Reporting Period: January 1, 1988, through June 30, 1988 Subtitted by:
Wolf Creek Nuclear Operating Corporation l
8809070085 880630 PDR ADOCK 05000482 i t R
r:
e IWrRODUCTION This Semiannual Radioactive Effluent Release Report covers the period of January 1, 1988, through June 30, 1988, and satisfies the requirements specified in Technical Specification 6.9.1.7.
Section I provides a sunmary of the quantities of radioactive liquid and gaseous effluents for this reporting period. The ft. mat is similar to that provided.in Regulatory Guide 1.21, Revision 1.
An eievated release pathway does not exist at Wolf Creek Generating Station. Tnerefore, all airborne releases are considered to be ground level releases. The concurrent meteorological condition gaseous pathway dose determination is met by the Wolf Creek Offsite Dose Calculation Manual methodology of assigning all gaseous pathways to a hypothetical individual residing at the highest annual X/Q and D/0 location. This results in a conservative estimate of dose to a Member of the Public rather than determining each pathway dose for each release condition. A conservative error of thirty percent has been estimated in effluent data. Meteorological data for the period of January 1, 1988, through June 30, 1988, is available on site for review and inspection. There were four shipments of solid waste during this reporting period.
Section II provides Supplemental Infornation as described in Regulatory Guide 1.21, Revision 1.
Section III provides additional information required by Technical Specification 6.9.1.7.
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SICTION I Year 1988 REPORP OF RADIOACTIVE EETLUFMPS: LIQUID l
Unit Quarter Quarter 1
2 1
A.
Fission and Activation Products 1.
Total Release (not including tritium, gases, alpha)
Ci 1.24E-01 6.04E-02 2.
Average diluted concentration during period uCi/ml 5.05E-08 3.23E-08 l
II) 3.
Percent of Applicable Limit 2.48E+00 1.21E+WO
_B.
Tritium 1.
Total Release Ci 3.80E+01 1.66E+02 2.
Average diluted concentration during period uCi/ml 1.77E-05 9.44E-05 3.
Percent of Applicable Limit 5.90E-01(2) 3.15E+00 3
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C.
Dissolved and Entrained Gases j
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1.
Total Release Ci 2.62E-01 6.09E-01 2
Average diluted concentration during period uCi/ml 1.51E-07 3.68E-07 3.
Percent of Applicable Limit
- 7. 55E-02 (3) 1.84E-01 D.
Gross Alpha Radioactivity 1.
Total Release Ci 0.00E+00 0.00E+00 1
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E.
Volume of waste released liters 2.40E+06 1.57E+06 j
F.
Volune of dilution water used liters 7.61E+09 6.93E+09 t
1.
The applicable limit for the Wolf Creek Generating Station is five (5) curies per year.
l The value printed here is derived by dividing the total release curies by 5 curies and then i
multiplying the result by 100.
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2.
This value is derived by the following formulas
)
% applicable limit = (Average diluted concentration) (100)
(MIC, Appendix B, Table II 100FR20) l l
l 3.
This value is derived by the following formula i
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% applicable limit =
(Average diluted concentration) (100)
(2E-4 from Technical Specification 3.11.1.1) l l
Page 1 of 22
Year 1988 LIQUID EFFINENTS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter 1
RELEASED Unit 1
2 1
2 i
H-3 Ci 0.00E+00 0.00E+00 3.80E+01 1.66E+02
]
Cr-51 Ci 0.00E+00 0.00E+00 7.65E-03 9.93E-04 i
Mn-54 Ci 0.00E+00 0.00E+00 S.09E-03 3.87E-03 Fe-55 Ci 0.00E+00 0.00E+03 4.44E-03 1.42E-02 Fe-59 Ci 0.01E+00 0.00E+00 3.98E-03 3.02E-04 l
l Co-58 Ci 0.00E+00 0.00E+00 5.14E-02 1.22E-02 i
Co-60 Ci 0.00E+00 0.00E+00 2.82E-02 1.98E-02 i
Zn-65 Ci 0.00E+00 0.00E+00 3.47E-04 0.00E+00 Rb-88
_ Ci 0.00E+00 0.00E+00 9.13E-04 0.00E+00 Sr-89 Ci 0.00E+00 0.00E+00 6.19E-04 1.98E-03 Sr-92 Ci 0.00E+00 0.00E+00 1.25E-04 3.15E-05 i
Zr-95 Ci 0.00E+00 0.00E+00 1.08E-03
<7.22E-04 Nb-95 Ci 0.00E+00 0.00E+00 3.05E-03 1.80E-03 i
Mo-99 Ci 0.00E+00 0.00E+00 1.97E-03 3.82E-05 Tc-99M Ci 0.00E+00 0.00E+00 0.00E+00 1.42E-06 Ag-110M Ci 0.00E+00 0.00E+00 2.76E-03 5.13E-04 I-131 Ci 0.00E+00 0.00E+00 2.09E-04 2.89E-04 1-134 Ci 0.00E+00 0.00E+00 0.0FE+00 3.67E-06 Cs-134 Ci 0.00E+00 0.00E4 00 1.06E-04 2.53E-04 Page 2 of 22 b
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Year _
1988~
LIQUID EFFLUEfffS Continuous Mode Batch Mode NUCL '. DES Quarter Quarter Quarter Quarter RELEASED Unit 1
2 1
2 4
I i
{
Cs-137 Ci 0.00E+00 0.00E+00 1.llE-04 7.49E-04 Cs-138 Ci 0.00E+00 0.00E+00 3.25E-04 0.00E+00 l
l La-140 Ci 0.00E+00 0.00Ev00 0.00E+00 1.59E-05 Co-141 Ci 0.00E+00 0.00E+00 1.02E-04
<7.85E-04 Ce-144 Ci 0.00E+00 0.00E+00 1.36E-03 1.03E-04 Kr-85M Ci 0.00E+00 0.00E+00 2.28E-04 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 1.06E-01 0.00E-00 i
Kr-88 Ci 0.00E+00 0.00E+00 5.47E-05 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 4.45E-03 1.01E-02 j
Xe-133M Ci 0.00E+00 0.00E+00 1.22E-03 4.00E-03 l
Xe-133 Ci 0.00E+00 0.00E+00 1.42E-01 5.94E-01 Xe-135M Ci 0.00E+00 0.'3E+00 1.62E-03 0.00E+00 l
Xe-135 Ci 0.00E+UO 0.00E+00 6.51E-03 4.28E-04 I
Ar-41 Ci 0.00E+00 0.00E+00 1.40E-04 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 7.28E-06 2.32E-05 Co-57 Ci 0.00E+00 0.00E+00 3.27E-04 1.50E-04 Hf-181 Ci 0.03E+00 0.00E+00 1.39E-04 9.46E-05 1
j Sn-ll7M Ci 0.00E+00 0.00E+00 5.38E-06 0.00E+00 i
Sn-ll3 Ci 0.00E+00 0.00E+00 1.33E-03 2.41E-04 1
]
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Year 1988 LIQUID EFFLUENFS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1
2 1
2 Sb-124 Ci 0.00E+00 0.00E+00 7.91E-04 1.57E-04 Sb-125 Ci 0.00E+00 0.00E+00 6.06E-03 1.53E-03 Nb-97 Ci 0.00E+00 0.00E+00 1.19E-03 2.73E-04 Gross Alpha Ci 0.00E+00 0.00E+00
<2.40E-04
<1.57E-04 1
Note:
Less than values are calculated using the lower limit of detection (LID) values obtained at the Wolf Creek Generating Station nultiplied by the volume of waste discharged during the respective quarter.
Page 4 of 22
Year 1988 LIQUID CtMULATIVE DOSE StPMARY TABLE 1 CAIfULATED SPECIFICATION
% OF DOSE LIMIT LIMIT UNIT 1, QUARTER 1 OF 1988 TMAL DOSE (MRDi) FOR BONE 1.65E-03 5.00E+00 3.30E-02
- TOTAL DOSE (MRDi) FOR LIVER 6.95E-03 5.00E+00 1.39E-01 TOTAL DOSE (MREM) FOR TOTAL BODY 6.31E-03 1.50E+00 4.?lE-01 TOTAL DOSE (MRDi) FOR THYROID 4.79E-03 5.00E+00 9.58E-02 TOTAL DOSE (MR8M) FOR KIDNEY 5.09E-03 5.00E+00 1.02E-01 TOTAL DOSE (MRDi) FOR LUNG 4.45E-03 5.00E+00 8.90E-02 i
TMAL DOSE (MRDi) FOR GI-LLI 6.81E-02 5.00E+00 1.36E+00 l
l UNIT 1, QUARTER 2 OF 1988 WTAL DOSE (MRD1) FOR DONE 5.31E-03 5.00E+00 1.06E-01
]
TOTAL DOSE (MRDi) FOR LIVER 2.06E-02 5.00E+00 4.12E-01 WTAL DOSE (MREM) FOR TMAL BODY 1.88E-02 1.50E+00 1.25E+00 TMAL DOSE (MRai) FOR THYROID 1.46E-02 5.00E+00 2.92E-01 NIAL DOSE (MREM) FOR KIDNEY 1.61E-02 5.00E+00 3.22E-01 TMAL DOSE (MRDi) FOR LUNG l.4'iE-02 5.00E+00 2.94E-01 TOTAL DOSE (MRDi) EOR GI-LLI 4.248-02 5.00E+00 8.48E-01 i
UNIT 1, TOTALS FOR 1988 WTAL DOSE (MRDi) FOR BONE 6.96E-03 1.00E+01 6.96E-02 TOTAL DOSE (MRDi) FOR LIVER 2.76E-02 1.00E+01 2.76E-01 i
TOTAL DOSE (MREM) FOR TMAL BODY 2.51E-02 3.00E+P0 8.37E-01 TOTAL DOSE (MRDi) FOR THYROID 1.94E-02 1.00E+01 1.94E-01
]
TOTAL DOSE (MRDi) FOR KIDNEY 2.12E-02 1.00E+01 2.12E-01 TOTAL DOSE (MRDi) FOR LUNG 1.92E-02 1.00E+01 1.92E-01 d
TMAL DOSE (MRD1) FOR GI-LLI 1.llE-01 1.00E+01 1.11E+00 1
Based on Technical Specification 3.11.1.2 which restricts dose to the whole body to less i
than or equal to 1.5 mrem per quarter and 3.0 mrem per year. Dose restriction to any l
l organ is less than or equal to 5 mrem per quarter and 10 mrem par year.
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Year 1988 LIQUID CLMU[ATIVE DOSE StPHutY TABLE 2 t
A.
Fission & Activation Products Quarter 1 Quarter 2 Total (not including H-3, 1.
Total Release - gases, alpha) Ci 1.24E-01 6.04E-02 1.84E-01 2.
Maxinum Organ Dose (mrem) 6.38E-02 2.83E-02 9.21E-02 l
3.
Organ Dose Limit (mrem) 5.00E+00 5.03E+00 1.00E+01 l
l 4.
% of Limit 1.28E+00 5.66E-01 9.21E-01 B.
Tritium 1.
Total Release Ci 3.90E+01 1.66E+02 2.04E+02
(
2.
Maxinum Organ Dose (mrem) 4.26E-03 1.41E-02 1.84E-02 3.
Organ Dose Limit (mrem) 5.00E+00 5.00E+00 1.00E+01 I
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% of Limit 8.52E-02 2.82E-01 1.84E-01 i
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This table is included to show the correlation between curies released and the associated calculated mxinum organ dose. Wolf Creek 00CM methodology is used to calculate the mximum i
organ dose which assumes that an individual drinks the water and eats fish from the discharge
(
point. Technical Specification 3.11.1.2 organ dose limits are used.
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Year 1988 REPORP OF RADIOACTIVE EFFLUFRPS: AIRDORNE Quarter Quarter Unit 1
2 A.
Fission & Activation Gases 1.
Total Release Ci 4.44E+02 1.06E+02 _
2.
Average release rate for period uCi/sec 2.29E+02 1.08E+02 3.
Percent of Tech 11 cal Specification Limits 2.26E-01 1.23E-01 B.
Iodines 1.
Total Iodine-13;.
Ci 4.04E-06 0.00E+00 2.
Average release rate for p3riod uCi/sec 5.14E-07 0.00E+00 3.
Percent of Technical Specification Limits 4.04E-04 0.00E+00 C.
Particulates 1.
Particulates with half-lives > 8 days Ci 3.18E-06 0.00E+00 2.
Average release rate for period uCi/sec 4.04E-07 0.00E+00 3.
Percent of Technical Specification Limits 2.24E-05 0.00E+00 4.
Gross Alpha radioactivity Ci 0.00E+00 8.05E-08 D.
Tritium 1.
Total Release Ci 1.51E+01 9.62E+01 2.
Average release rate for parimi uCi/sec 1.97E+00 1.33E+01 3.
Percent of Technical Specification Limits 1.44E-01 9.15E-01 The percent of Technical Specification Limits for fission and activation gases is calculated using the foll& ding enthodology:
% of Technical Specification Limit = (Quarterly Total Gamns Airdose)(103),
5 mrad The parcent of Technical Specification Limits for Iodine is calculated using the following nuthalo1&Jy:
% of Technical Specification Limit = (Total Curies of Iodine-131) (100) 1 curie Page 7 of 22 j
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e The pe,rcent of Technical Specification Limits for particulates is calculated using the following nuthodology:
% of Technical Specification Limit = (Highest Organ Dose due to Particulates)(100) 7.5 mrem The IIarcent of Technical Specification Limits for tritium is calculated using the following methodology:
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% of Technical Specification Limit = (Highest Organ Dose due to H-3) (100) 7.5 mrem This type of nuthodology is used since the Wolf Creek Technical Specifications tie releases to doses rather than Curie release rates.
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l Year 1988 GME00S EFFLUENTS Continuous Mode Batch Mode
]
NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1
2 1
2 i
]
1.
Fission arxl Activation Gases 1
j Ar-41 Ci 0.00E+00 4.33E-01 5.76E-02 3.51E-01 i
i Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 1.57E-01
(
Kr-85M Ci 0.00E+00 7.56E-01 0.00E+00 9.30E-03 t
Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 1.09E+00 0.00E+00 8.28E-03
(
Xe-131M Ci 0.00E+00 0.00E+00 3.71E+00 2.39E-01 Xo-133 Ci 7.80E+01 7.79E+01 3.51E+02 1.63E+01 4
I Xo-133M Ci 2.00E+00 0.00E+00 5.52E+00 1.24E-01 i
i Xo-135 Ci 1.39E-01 8.62E+00 3.31E+00 8.80E-02 Xo-135M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
(
Total Ci 8.02E+01 8.88E+01 3.64E+02 1.73E+01 j
i 2.
Halogens (G1seous)
)
l I-131 Ci 4.04E-06
<2.59E-04
<1.12E-05
<2.68E-07 I-133 Ci
<2.46E-9
<2.59E-02
<l.12E-03
<2.68E-05 i
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I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
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l Br-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Total Ci 4.04E-06 0.00E+00 0.00E+00 0.00E+00 l
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j Note: Less than values are calculated using the lower limit of detection (LLD) values obtained at Wolf Creek Generatirvj Station rtultiplied by 1
the volum of air disclurged duriry) the respectivo quarter.
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r-Year 1988 GASEOUS !!FFLUDfPS Continuous Mode Batch Mode NUCLIDES Quarter Quarter Quarter Quarter RELEASED Unit 1
2 1
2 3.
Particulates-Co-58 Ci 3.lGE-06
<2.59E-03
<1.12E-04
<2.68E-06 H-3 Ci 1.50E+01 9.60E+01 1.10E-01 2.04E-01 Co-60 Ci
<2.46E-03
<2.59E-03
<l.12E-04
<2.68E-06 1
Mn-54 Ci
<2.46E-03
<2.59E-03
<1.12E-04
<2.68E-06 l
Fe-59 Ci
<2.46E-03
<2.59E-03
<l.12E-04
<2.68E-06 ll
}
Zn-65 Ci
<.2. 4 6E-03
<2.59E-03
<1.12E-04
<2.688-06 Mo-99 Ci
<2.46E-03
<2.59E-03
<1.12E-04
<2.68E-06 Cs-134 Ci
<2.46E-03
<2.59E-03
<l.12E-04
<2.68E-06 Cs-137 Ci
<2.46E-03
<2.59E-03
<l.12E-04
<2.68E-06 4
Ce-141 Ci
<2.46E-03
<2.59E-03
<l.12E-04
<2.68E-06 j
Ce-144 Ci
<2.46E-03
<2.59E-03
<l.12E-04
<2.68E-06 Sr-89 Ci
<2.46E-03
<2.59E-03
<l.12E <2.68E-06 Sr-90 Ci
<2.46M-03
<2.59E-03
<l.12E-04
<2.68E-06 i
}
Gross Alpha Ci
<2.46E-03 8.05E-08
<l.12E-04
<2.68E-06 i
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i Notel Loss than values are calculated using the lower limit of detection (LLD) values obtained at Wolf Creek Goterating Station nultiplied by tho volunn of air dischargM during the respectivo quarter.
Note On two occasions snull quantities of gross alpha were indicated on the unit vent particulate filters.
It is beloived that paint j
fums contributed to these positive indications.
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Page 10 of 22 I
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_, _ - - _ _ _. _ _. _. _ -.. _ - -.. _ _ - - _ _ _ -. _.. - ~ - - _ - ~. _ - - _, - - -
Year 1988 GASB00S CtMKATIVE DOSE SlffRRY Table 1
_____y_______________
TECHNICE SPECIFICATION
% OF QUARTER 1 0F 1988 LIMIT LIMIT l
DOSE FROM RADIOIODINES, PARTICULATES, AND TRITIUM AT CONTROLLING IDCATION:
TOTAL DOSE. (MRDi) FOR BONE 7.69E-06 7.50E+00 1.03E-04 TOTAL DOLE (MRDi) FOR LIVER 1.08E-02 7.50E+00 1.44E-01 l
TOTAL DOSE (MRDi) FOR TOTAL DODY 1.08E-02 7.50E+00 1.44E-01 TOTAL DOSE (MREM) MR 'IHYROID 1.31E-02 7.50E+00 1.75E-01 TOTAL DOSE (MRDi) FOR KIDNEY 1.08E-02 7.50E+00 1.44E-01
'IVTAL DOSE (MRDi) FOR LUNG 1.08E-02 7.50E+00 1.44E-01 TOTAL DOSE (MRDi) MR GI-LLI 1.08E-02 7.50E+00 1.44E-01 i
QUARTER 2 OF 1988 DOSE FROM RADI0 IODINES, PARTICULATES, AND TRITIUM AT CONTROLLING UEATION:
l
' TOTAL DOSE (MRDi) FOR BONE 0.00E+00 7.50E+00 0.00E+00 t
TOTAL DOSE (MRDi) FOR LIVER 6.86E-02 7.50E+00 9.15E-01 TOTAL DOSE (MRD1) FOR TOTAL BODY 6.86E-02 7.50E+00 9.15E-01 TOTAL DOSE (MRDi) FOR THYROID 6.86E-02 7.50E+00 9.15E-01 TOTAL DOSE (MRDi) FOR KIDNEY 6.86E-02 7.50E+00 9.15E-01 TOTAL DOSE (MREM) FOR LUNG 6.86E-02 7.50E+00 9.15E-01
'IUTAL DOSE (MRDi) FOR GI-LLI 6.86E-02 7.50E+00 9.15E-01 i
TOTALS MR 1988 DOSE FROM RADIOIODINES, PARTICULATES, AND TRITIUM AT CONTROLLING LOCATION
'IOTAL DOSE (MRD1) FOR BONE 7.69E-06 1.50E+01 5.13E-05 l
TOTAL DOSE (MRD1) MR LIVER 7.94E-02 1.50E+01 5.29E-01 TOTAL DOSE (MRD4) FOR TOTAL BODY 7.94E-02 1.50E+01 5.29E-01 TOTAL DOSE (MRDi) FOR THYROID 8.17E-02 1.50E+01 5.45E-01 TOTAL DOSE (MRDi) FOR KIDNEY 7.94E-02 1.50E+01 5.29E-01 TOTAL DOSE (MRD1) FOR LUNG 7.94E-02 l.50E+01 5.29E-01 TOTAL DOSE (MRDi) FOR GI-LLI 7.94E-02
.. 50E+01 5.29E-01 l
i 1.
Based on Wolf Creek Technical Specification 3.11.2.3 which restricts dose during any calender quarter to less than or equal to 7.5 mrem to any organ and during any calender year to less than or equal to 15 mrem to any organ.
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Year 1988 r
~
GASEOUS CtMRATIVE DOSE SCMRRY f
TABLE 2 A.
Fission & Activation Gases Quarter 1 Quarter 2 Total 1.
Total Release (Ci) 4.44E+02 1.06E+02 5.50E+02 2.
Total Gams Airdose (mrad) 1.13E-02 6.16E-03 1.75E-02 3.
Gams Airdose Limit (mrad) 5.00E+00 5.00E+00 1.00E+01 4.
% of Limit 2.26E-01 1.23E-01 1.75E-01
)
B.
Particulates 1.
Total Particulates (Ci) 3.18E-06 0.03E+00 3.18E-06 1
2.
Maxinum Organ Doso (mrem) 1.68E-06 0.00E-00 1.68E-06_
3.
Organ Doso Limit (mrem) 7.50E+00 7.50E+00 1.50E+01 4.
% of Limit 2.24E-05 0.00E+00 1.12E-05 l
i C.
Tritium l
4 1.
Total Release (Ci) 1.51E+01 9.62E+01 1.11E+02 2.
Maximum Organ Dose (mrem) 1.08E-02 6.86E-02 7.94E-02 3.
Organ Dose Limit (mrem) 7.50E+03 7.50E+03 1.50E+01 4.
% of Limit 1.44E-01 9.15E-01 5.29E-01 I
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D.
Iodine j
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1.
Total I-131 (Ci) 4.04E-06 0.00E+00 4.04E-06 i
{
2.
Maxinum Organ Dose (mrem) 2.31E-03 0.00E+00 2.31E-03 l
i 3.
Organ Doso Limit (mrem) 7.50E+00 7.50E+00 1.50E+01
[
4.
% of Limit 3.08E-02 0.00E+00 1.54E-02 1
These values differ from the "Report of Radioactive Effluents Airborne" table since this value in hised on dose and not one (1) curio.
j This table is included to show the correlaticas between curies released and the associated calculated miximum organ doso. The rMxinum organ dose is calculated using Wolf Creek 0001
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methcdology which assums that an individual actually residos at the rolosso point. Technical Specification 3.11.2.3 organ doso limits are used.
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SIETION II Supplanental Information Facility: Wolf Creek Generating Station License thrnber: NPF-42 1.
Regulatory Limits A.
For liquid waste effluents A.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Colunn 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entraimd ngble gases, the concentration shall be limited to 2 x 10 microcurie /ml total activity.
A.2 The dose or dose comnitment to a MDiBER OF THE RIBLIC fran radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall b3 limited:
a.
During any calendar quarter to less than or equal to 1.5 mrens to the whole body aM to less than or equal to 5 mrems to any organ, and b.
During any calendar year to less than or equal to 3 mrens to the whole body and to less than or equal to 10 mrems to any organ.
B. For gaseous waste effluents B.1 The dose rate due to radioactive materials releast.d in gaseous effluents from the site to areas at and beyond the SITE BOUT 0ARY shall be limited to the following:
a.
For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and b.
For Iodine-131 and 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to 1500 mrems/yr to any organ.
B.2 'Ihe air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyoM the SITE BOUNDARY shall be limitcd to the follwing:
a.
During any calendar quarters tass than or equal to 5 mrads for gamna radiation aM less than or equal to 10 mrada for beta radiation, and b.
Durinj any calendar yean Less than or equal to 10 mrada for garana radiation aM less than or equal to 20 mrads for beta radiation.
D.3 The dose from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous of fluents released, from each unit, to areas at and beyoM the SITE SCUNDARY shs11 b3 limited to the followiny:
Page 13 of 22
l
[
a.
During any calendar quarter:
Less than or equal to l
l 7.5 mrems to any organ, and b.
During any calendar year:
Less than or equal to 15 1
mrems to any organ.
l 2.
Maximum Permissible Concentrations Water - covered in section 1.A.
l Air - covered in section 1.B.
i i
3.
Average energy of fission and activation gaseous effluents is not f
1 applicable.
j 4.
Measurenents and Approxinutions of Total Radioactivity 4
A.
Liquid Effluents l
1 i
i LIQUID RELEASE SAMPLING METHOD OF TYPE OF ACTIVITY f
l TYPE FREQUECY ANALYSIS ANALYSIS
(
l
[
h
- 1. Batch Waste P.H.A.
Principal Gama t
I Tanks Each 9atch Enniters Release P
j P.H.A.
I-131 i
i
- a. Waste 3
Monitor P
Dissolved and Tank One Batch /M P.H.A.
Entrained Gases (Ga:mn Emitters) l
- b. Secondary l
l Liquid P
L.S.
Waste Each Batch i
y j
Monitor G.F.P.
Gross Alpha a
Tank l
P O.S.L.
Sr-89, Sr-90 Each Batch O.S.L.
Fe-55 I
I I
P = prior to each batch j
1 i
M = monthly
{
P.H.A. = ga:mn spectrum pulse height analysis using a High Purity Cernunium detector.
i l
t j
Page 14 of 22 i
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o.
L.S. = liquid scintillation l
G.F.P. = Gas Flow Proportional counting l
0.S.L. = performd by an Offsite Laboratory There were no continuous radioactive waste effluents for this reporting period.
B.
Gaseous Waste Effluents j
l SAMPLING METHOO OF TYPE OF GASEOUS, RELEASE TYPE FRECOEtCY ANALYSIS ACTIVITY ANALYSIS 7
P Each Tank P.H.A.
Principal Gama Waste Gas Decay Tank Grab Sa@le Emitters P
Principal Gama Containment Purge or Each Purge P.H.A.
Emitters Vent Grab Sanple Gas Bubbler and L.S.
H-3 (oxide)
Principal Gama
[
Unit Vent M
P.H.A.
Emitters Grab Sanplo Gas Bubbler and L.S.
H-3 (oxide) i Radwaste Building M
P.H.A.
Principal Gama l
Vent Grab Sanple Emitters I
l All Release Types as I-131 listed above Continuous P.H.A.
I-133 P.H.A.
[
Continuous Particulate Principal Guma l
Sam le Emitters I
G.F.P.
I Continuous Particulate Gross Alpha Composite Sample O.S.L.
j Composite Sr-89, Sr-90 i
Continuous Particulate Sanple C.
A conservative error of +30% has been estimated. This l
includes volustric masiirenunt device, flow masurement device and analytical errors.
1 Page 15 of 22 t
I
e 5.
Batch Releases There were thirty (30) gaseous intch releases during the report period. The longest gaseous batch release took 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, the shortest occurred over a fourty-eight (48) minute interval. The average release took 18.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with a total gaseous batch release tima of 547 hours0.00633 days <br />0.152 hours <br />9.044312e-4 weeks <br />2.081335e-4 months <br />.
There were 119 liquid batch releases during the report period. The longest liquid batch release took 221 minutes while the shortest took only 38 minutes. The average release tima for the liquid batch releases was 81.2 minutes. Total release time for all 119 liquid batch releases was 161 hours0.00186 days <br />0.0447 hours <br />2.662037e-4 weeks <br />6.12605e-5 months <br />.
6.
Abnormal Releases a.
There were no abnorml liquid or gaseous releases for this report period.
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Page 16 of 22
l i
EFFLUENF AIO WASTE DISPOSAL S!!M1 ANNUAL REPORT (1988) t SOLID WASTE SHIRGNFS A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated I
fuel)
L
- 1. Type of waste Unit 6-month Est. Total Period Error %
- a. Spent resins, filter sludges, m3*
10.23E+00 i
evaporator bottans, etc.
Ci 1.27E+03 2.50E+01
,_3*
1.76E+01 1
- b. Dry compressible waste, m
contaminated equip. etc.
Ci 1.80E-01 2.50E+01
- c. Irradiated components, m3*
0.0JE+00 control rods, etc.
Ci 0.03E+00 0.00E+00
- d. Other (describe) m3*
0.00C'JJ Ci 0.00E+00 0.00E+00 m3* = cubic meters l
- 2. Estimte of mjor nuclide conposition (by type of waste)
[
a.
Co-58 4.44E+01 Fe-55 2.64E+01 Co-60 1.68E+01 l
Mn-54 4.87E+00 Cr-51 2.65E+00 Fe-59 3
1.04E+00 i
Nb-95 9.87E-01 Zr-95 1
7.36E-01 Ni-63 4.66E-01 Ce-144 3.67E-01 j
- 3. 2 0E-01 i
H-3 2.03E-01 I
j Cs-137 4
1.41E-01 l
f Sr-89 1.01E-01 j
Mf=181 1
8.60E-02 1
Sn-113 5.60E-02 l
C-14 4
2.80E-02 1
Sr-90 1.69E-04 l
l b.
Fo-55 3.34E+01 i
Co-58 3.23P.+01 l
Co-60 2.15E+01 l
4 Mn-54 4.77E+0J Co-57 3.15E+00 l
Fe-59 1
2.51E+00 j
]
Cr-51 2.25E+00 j
C-14 7.50E-02 l
1 Pago 17 of 22 l
1 h
. _,. - - _ _ - -. _ _ _ =. _.. ~
I l
- c. None
- d. None
- 3. Solid Waste Disposition Number of Shipnents Mode of Tracarat ation Destination 3
TrOE ~
Ba rtra' ell, South Carolirn 1
Truck Beatty, Nevada
- 4. Class of Solid Waste a.
Class A b.
Class A c.
Not applicable d.
Not applicable
- 5. Type of Container a.
LSA (Strong, tight) b.
LSA (Strong, tight) c.
Not applicable d.
Not applicable
- 6. Solidification Agent a.
Not applicable b.
Not applicable c.
Not applicable d.
Not applicable B.
IRRADIATED FUEL SHIPME!TTS (Disposition)
There were no irradiated fuel shipments during this reporting period.
i l
Page 18 of 22
t O
SECTION III Additional Information 1.
Unplanned Releases There were no unplanned releases during this report period.
2.
Process Control Program Revision four (4) to the Wolf Creek Process Control Program (PCP) was issued on August 27, 1986. This was a general revision aM was included in the Semiannual Rsdiological Effluent Release Report Number 4, covering the priod from July 1,1986 through December 31, 1986. There have been two temporary changes to the PCP since Revision 4 was issued.
The first change was dated December 5,1986, aM was insdvertently omitted from the Semiannual Radiological Ef fluent Release Report Nanber 4, aM is therefore being reported herein. The secoM change to the PCP discussed in this report is dated March 10, 1988. A ccrnplete copy of the PCP Revision 4 is included with this report as Attachment 1.
The first change to the PCP, dated December 5,1986, changed section 4.1.2 in its entirety to read "Chem-Nuclear Systems, INC. performance of resin dewatering will be performd in accordance with an NRC approved Topical Report. NUS performance of solidification aM filter encapsulation will be N rformed in accordance with an NRC approved Process Control Program." This change was inplemented to provide a more accurete representation of vendor programs used. W e overall conformance of the solidified waste product to existD.7 criteria is not reduced by this PCP change. We channe only nams the specific veMor and which function the vendor performs.
The secoM change to the PCP, dat<3d March 10, 1988, added section 4.2 as follows:
4.2 WCGS Processing 4.2.1 WCGS waste shall bo processed for shipTent in accordance with NRC, DOT, aM state burial requiremnts.
4.2.2 Wen solidification, resin dewatering or filter encapsulation is done oy FCGS, it shall tu done in accordance with the latest revision of an NRC approved veMor process control program or topleal report where applicable.
This change was implemented te include provisions for WCGS personnel to use veMor approved processes. The change did not reduce the overall conformnce of the colidified prMuct as the sa.te equipment was used that a vendor would use. The asm acceptance criteria was adhered to for a finished product.
I Page 19 of 22
3.
Of fsite Dose Calculation Manual (ODCM)
There wrie no changes to the ODCM during this report period.
4.
Major Changes to Liquid, Gaseous or Solid Radwaste Systems A permanent change to the Liquid Radwaste System which altered the capacity of haMling Radioactive vastes was reviewed and found acceptable by th3 Plant Safety Review Comittee on November 4,1986.
Becausa this change was not reparted previously, it is being reported herein.
Plant Modification Request (PMR) 01594 installs an additional cross-i tie between the Boron Recycle System (HE) aM the Liquid Radwaste System (10). Relevant drawings from PtiR 01594 are included with this repart as Attachment 2.
1 a.
This trodification does not involve any safety-related systems an3 I
has no impset on any safety aspects of the plant. Therefore, it does not involve an unreviewed safety question.
1 b.
This modification allows the floor drain tanks aM the waste
)
holdup tank to be processed through the Secon3ary Waste System (liF) ovaporator while the Liquid Radwaste System is processinj waste from the Boron Recycle System. The increased flexibility from this modification optimizes the liquid Radioactive waste proces ing.
We radwaste crystallizer (rated at 30 gpm) is essentially a i
specially designed forced circulation evaporator consistin3 of a I
vapor body, recirculation pipa, large recirculation pop, and two l
pass vertical heater, ror K GS, three inorganic salts can be crystallized. These are sodium sulfate (Na SO ), amonium sulfate 2 4 conedn)trating of either a nulfido)m. The desiga concept includes
>SO ) and boric acid (H BO
((R1 4
3 ponent mixture of Na3SO S0, H B0 oranyoneofthesesaltscombinedwithffo,or (Mt )2 3
3 3 3 l
drain wadte to 50% by weight total solids, l
l i
l l
Page 20 of 22
Another plant has ande this change, and is currently concentrating with the !!F evaporator up to 25 gpm without boric acid (40-45%
total solids), which is nnre than double the output from the Im evaporator at ICGS. This change would therefore allw 5 CGS to maximize (by doublin]) the annunt of concentrated waste loaded into a 55 gallon drum and at the saw tinn allws ICNOC to optimize the successful boric acid solidification.
This change allws the floor drain tanks and the waste holdup tank liquid radwaste feed to be processed through a nore suitable Inconel 625 tubing mtorial (which is a superior nuterial in terms of resistance to pitting and stress corrosion crackin) in enviroments where a high chloride concentration and low pH exists for extended pariods of time) as compared to Incoloy 825 that is used in the evaporator packages.
By allwing the HF evaporator to process what is normally 10 feed, the te evaporator package could then be used interchangeably with the llE evaporator to concentrate reusable boric acia. @is would provide radwaste operators a greater degree of flexibility within the Boron Recycle System by having an operable alternate package for the HE (15gpm) evaporator, c.
We additional cross-tie is a two inch pipe and valve that connects the supply side of Boron Recycle System valve V-158 ard the Liquid Radvaste System, downstream of valve V-053.
(See ).
Because the original design allwed the secondary waste evaporator to be used to process the water from the floor drain tanks:
d.
We nnlification does not change the predicted releases of Radioactive mterials.
e.
The modif. cation does not change the expected mximrn exposures.
f.
The modification does not change the predicted release of Radioactive nuterials.
g.
The nullfication does not change the exposure to plant operating p3rsonnel.
Page 21 of 22
5.
Land Use Census There were no new locations for dose calculations ides.cified during this report p2riod.
6.
Radioactiv.. Shipnents There were four shipments of Radioactive radwaste during this report patiod. Three shipnents were to Barnwell, South Carolim, and one shipnunt was to Beatty, Nevada.
7.
Inoperability of Airborne Effluent Monitoring Instrumentation On July 1,1988, the Unit Vent System Noble Gas Radiation Monitor, Gt RE-21B, had been out of service for thirty days. Therefore, the following informtion is included in the Semiannual Radioactive Effluent Release Report in accordance with Technical Specification (T/S) 3.3.3.11.
On June 1, 1988, at approxi m tely 0840 CDT, GT RE-21B was removed from service for scheduled nuintenance activities. The licensed operations personnel entered T/S 3.3.3.11, Action Statenent b, end inititated 12.. hour grab samples as required for GT RE-21B. On June 2, 1988, the scheduled maintenance activities were completed, but because GT RE-21B failed its retest, the nonitor was not returned to service.
As a result of the retest failure, troubleshooting activitics were l
cerducted on June 3,1988. Diagnostics on GP R5-21B indicated a programmble read-only memory (PROM) chip failure. A spare set of PROM chips were installed but indicated a different PROM chip failure. Additional troubleshooting was then coMucted to verify d
that the failure was in the PROM chips. Because additional spare sets of PROM chips were not available on site, a purchase order was initiated on June 9,1988, to obtain the PROM chips from the vendor.
'Ihe vendor was contacted to expedite the shipmnt of the replacenunt chips needed to restore GT RE-21B to operable status. Followin3 receipt of the PROM chips, ruintemnce and testing were completed ard GP RE-219 was returned to service on July 8,1988.
1 Page 22 of 22 j
l i
1 e
1 l
l l
l AWAONENT 1 i
l EM @M EMM I
l
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1 l
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I t
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1 1
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1 1
W C H P-Cf2-O'4 -O'l PIGURE 9 - TEMPORARY PROCEDURE CHANGE FORM Tracking No. MA MAJOR Q MAJOR SPECIAL SCOPE PROCEDURE NUMBER AND 1 RENT rey SI N
%2
/$V M PROCEDURE TITLE:
44 //;pt (4-er7 REASON FOR CHANGE:
/
///M5I4W' hY & d4 d 4 2 /) LW h CHANGE:
/
/
_. i.
~
Valid Until y///g oE mgW SAFETY EVALUATION SCREENING Does this procedure f.hange or revision involve 1)
Yes No
/
A change to the facility or procedures from their description in the USAR?
(2)
Yes No
/ A change to a test or experiment not desceibed in the USAR?
(3)
Yes No / A change that affects Nuclear Safety in a way not previously evaluated in the USAR?
/ A change to the Technical Specifications or (4)
Yes No a reduction of the.aargin of safety as in the Technical Specification?
/, defined An Environmental Question?
(5)
Yes No (6)
Yes No
/ A Technical Specification Surveillance Requirement'r (7)
Yes No A'previously made committment?
(5) is yes, this If the answer to any one of questions (1) change Form shall be routed to the Supervisor Results Engineering for a safety / environmental evaluation per ADM 91-922.
If the answer to question (6) is yes, this Change Form shall be routed to the Surveillance coordinator for evaluation.
If the answer to question (7) is yes, this Change shall be routed to the Superintendent of Regulatory, Quality and Administrative Services for evalution.
If the answers to above questions are no, the normal approval p ces may proceed.
s Ajn Date Jfhsk[
Prepared By
/$/ s
[lk Approval _
Datt Cognizant Group SulMrvisor 3 '/8 '#
l Call Superintendent 8/
d Date
(
ate J*N Y g
PSRC Approval Recommenda o
Plant Manager U
ADM 07-100 Rev. d 0C30 S W BS Page 23 of 30 J
p. e @ 0 m Ot2 390- 3-CO298802PM i
3C o
l 4.2 WCGS Processing 4.2.1 WCG8 waste shall be processed for shipaqnt la QCC0fdtn00 With NRO, BOT, and state burial requirements.
4 2.2 When solidification, resin dewatering or filter 3
with the latest revision of an NRC approved vendor pro control program or topical report where applicable, m
4 PIGURE 5 WOLF CREEK NUCLEAR OPERATING CORPORATION PSRC SERIAL REVIEW SHEET Document Number / Revision (if applicable)
Md N8 -0 2-
/dY Document Title tes3 1 dve I hve. mm Procedure classification (if applicable):
Major /Maj. Spec. Scope Minor / Minor Spec. Scope NNSR
~
gio O
Superintendent of Operations Date Superintendent of Technical Support Date Chemist Date Health Physicist Date I&C Supervisor na Date l
Reactor Engineering Supervisor
/
Date Superintendent of Maintenance
- Dat d[
Superintendent of Plant Support fd-
' Dat J./o ~##
^# Dbe 3-/o fg Results Engineering Supervisor..
m/wr W/
Superintendent of Regulatory, gglity and Administratise Servides
/Ar Date Quality Engineering Date (As required per 6.7.1)
O */O Approved:
Date PSKC/ Chairman A
I i
ADM 07-100 Rev. 33 Page 19 of 31 i
- a-
~
R fcW"V-/ '
FIGURE IS Tracking No. HA M
TEMPORARY PROCEDURE CHANGE FORM MAJOR Q HAJOR SPECIAL SCOPE PROCEDURE NUMBER AND CURRENT REVISION:
WCHP-02 Rev. 4 PROCEDURE' TIT LE:
19 CFR 59.59 NUCLEAR SAFETY EVALUATION (Refer to ADM 91-972 for specific guidelines)
The procedure revision or change to'which this evaluation is applicable represents:
1)
Yes No XX A change to the facility or procedures from their description in the FSAR?
(2)
Yes No XX A change to a test or experiment not described in the FSAR?
(3)
Yes Jo XX A change that affects Nuclear Safety in'a way not previously evaluated in the FSAR?
(4)
Yes No XX A change to the Technical Specifications or a reduction of the margin of safety as defined in the Technical Specifications.
(S)
Yes No XX Does an Environmental Question exist?
(
If the answer to any of th< above. questions is "Yes", this Change Form shall be forwarded to the Results Engineering Supervisor or Supervisor Environmental Management for completion of a i
safety / environmental evaluation per ADM 91-922.
If the answers to all of the above are no, no unreviewed safety / environmental question exists.
REASON FOR CHANGE: More accurate representation of vendor programs used.
CHANGE: Change section 4.1.2 in its entirity to read "Chem-Nuclear Systems, Inc.
rurformance ot resin dewatering will te periormed in accordance with an NFC i
approved Tcpical Report.
NUS performance of solidification and fil ter encaceulation will te ferformed in accordance with an NRC approved Process Control Precram Valid Until Revision 5 is issued.
Prepared By bhw C, O... I ;
Date 12 4 y6
- Approval,
,Da te 42-Y-W
/
Cognizant Group Supervi_sor a --
g
\\
Call Superintendent 7-,
} '
)d Date /2[V/[4 PSRC Approval Recommen M
, J, Date /[-TM
. vv Plant Manager o
7 i ADM 97-199 Rev. b Page 24 of 3.1
]
O On FIGURE 6 WOLF CREEK GENEtATING STATION PSRC SERIAL REVIEW SHEET l
Document Number / Revision (i f applica ble)
W CNh-61
/h Document Title 9teun 6bt P=,m U
l Procedure Classi fication (i f applicable):
l Major /Maj. Spec. Scope Minor / Minor Spec. Scope NNSR Superinten nt of Operations Date
- / [I s
\\
f Superinten e.c o f,Te qical Support /
Date i
Chemist 3
Date 4 t-fs Da te _ / J.- T- /5 Health rhysicist 2
V I&C Supervisor Date f
)
[
Reactor Engineering Supervisor
/)
f Date
' ~ '
I I l Superintendent of Maintenance l
Date Superintendent of Plant Support Date Results Engineering Supervisor Date Superintendent of Regulatory, Quality and Administrative Services Date Quality Assurance Date (As c
're per 6.7.1)
Approved:
Date IE-EM PSRC Cha(rman ADM 07-100
('
Rev. 28 Page 19 of 30
(ABM o7-407eev ai 3ROCESS CON-RO_.
3ROGRAV arv.
Rtvis t u REtetD sy hus 3
RELEASED FOR USE SJ. f-es 4
GENERAL REVISON NNE KANSAS GAS & ELECTRIC COMPANY WOLF CREEK GENERATING STATION
~
DOC M NT NUMB.ER REV.
WC 3-02 4
'?
e e
WJLF CREEK GENERATING STATION PROCESS CCNTROL PROGPM Revision 4 Classification: Major 1/
AJ0V W
PRCPAldD BY
~2Au. s DATE j..-
fu'h &
eMas INDEPENDENT REVIEW DATE RAL-r M rc.
COGPGZn.v g P SUPERVISOR DATE C
m+#11 a.ma RESPONSI8T.E 3UPEhlt3ryt APPROVAL DATE YAn Nba 1.u Ji, PSRC APPROVAL RDXeNINDATIOg DATE
/4 Aff i ^:
L e n s<
euwr amata AreRovu.
f an QUALITY ASSURATE DAE i
Rev.'4 6/86
J TABLE OF CONTENTS P+
PAGE NO.
TITLE PAGE i
TABLE OF CONTENTS 11 1.0 SCOPE l-1 4
1 1.1 PURPOSE l-1 i
1.2 APPLICABILITY l-1
2.0 REFERENCES
AND DEFINITIONS 1-1 p
r
2.1 REFERENCES
1-1 2.2 DEFINITIONS 1-2 l
3.0 SYSTEM DESCRIPTION' l-2 t
3.1 SOLIDIFICATION SYSTEM DESCRIPTION 1-2 i
3.2 PROCESS PARAMETERS 1-3 3.3 DETAILED SYSTEM DESCRIPTION 1-5 3.4 SYSTEM CONTROL l-17 3.5 SOLIDIFICATION SAMPLE VERIFICATION 1-26 I
3.6 PRIMARY CONCENTRATES VERIFICATION 1-28 3.7 SOLIDIFICATION OF SPENT ION EXCHANGE RESIN 1-29 3.8 SECONDARY CONCENTRATES / SPENT RESIN VERIFICATION 1-30 j
3.9 SYSTEM INTERFACING l-31 j
3.10 CORRECTIVE ACTIONS 1-32 l
4.0 ADDITIONAL PROCESSING l-32 q
i 4.1 VENDOR PROCESSING l-32 J
5.0 FILTER DISPOSAL IN HIC *S 1-33 l
5.1 ADMINISTRATIVE CONTROLS 1-33 5.2 FILTER DESCRIPTION AND TRANSFER l-33 i
5.3 HIGH INTEGRITY CONTAINER DESCRIPTION 1-34 5.4 FILTER TREATMENT METHOD l-34 I
5.5 FILTER TREATMENT DETERMINATION 1-35 APPENDIX At CONCENTRATES SOLIDIFICATION WORKSHEET l-36 APPENDIX B RESIN SOLIDIFICATION WORKSHEET l-39 APPENDIX C FILTER CARTRIDGE DISPOSAL DATA l-42 APPENDIX D CERTIFICATION OF COMPATIBILITY l-43 i
11 Rev. 4 6/86
't 1
1.0 SCOPE 1.1 PURPOSE m e purpose of this process control program is to provide reasonable assurance that the final processed products produced at Wolf Creek Generating Station (WCGS) meet or exceed all federal, state and burial site requirements pertaining to the solidification, transportation and disposal of low-level radioactive waste (LIM).
1.2 APPLICABILITY tis process contrel program is applicable to all solidification evolutions involving the installed cement solidification system at WCGS.
%is process control program acknowledges the potential use of mobile vendor processing including solidification, resin 4
dewatering and filter encapsulation.
Wis process control program also applies to filter disposal in high integrity containers (HIC's).
2.9 REFERDCES AND DEFINITIONS 2.1 REFERDCES
2.1.1 NURD3-9800
Standard Review Plan Section 11.2 Liquid Waste Management Systems
2.1.2 NURD3-9600
Standard Review Plan Section 11.4 Solid Waste Management Systems 2.1.3 Branch Technical Position 11-3, "Design Guidance for Solid Radioactive Waste Management Systems Installed in Light Water Cooled Nuclear Power Reactor Plants" 2.1.4 lEFR29, "Standards for Protection against Radiation" 2.1.5 19CFR61, "Licensing Requirements for Lard Disposal of Radioactive Waste" 2.1.6 19CFR71, "Packaging of Radioactive Material for Transport and Transportation of Radimetive Materials urder Certain conditions" 2.1.7 NURD3-0472, Revision 3, "Stardard Radiological Effluent Technical Specifications for Pressurized Water Reactors" 2.1.8 USmc Branch Technical Position on Waste Forro, May 11, 1983 Rev. 4 1-1 6/86
2.1.9 Stock Equipment Company, Equipment Manual (s) for the Wolf l
Creek Generating Station's Installed Cement Solidification System; M-135 series.
I 2.1.10 Reg. Guide 1.143 Rev. O, Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-cooled Nuclear Power Plants.
2.2 DEFINITIONS 2.2.1 Free Standing Liquid (FSL) - is water which is not l
chemically or mechanically combined with the solidifica-tion binder. Solidified products which meet FSL criteria of the applicable disposal f acility shall be termed a dry product.
2.2.2 Free Standing Water (FSW) - is defined as that water which is present above a settled bed of resin in the decant tank.
The percent free standing water is the volume percentage of the total volume of waste represented by this free standing water, prior to solidification.
2.2.3 Structural Stability - The ability of *.he solidified product or processed waste package to withstand the expected disposal conditions, such as weight of soil overburden, the presence in the burial environment of moisture and microbial activity, and internal factors such as radiation effects and chemical changes. Structural stability can be provided by the waste form itself, processing the vaste to a stable form, or placing the i
vaste in a disposable container that provides stability after disposal.
2.2.4 High Integrity Container (HIC) - A package designed to i
provide for structural stability and prevent the egress of its contents under burial conditions for a period of 300 years.
2.2.5 Batch - The final recirculated volume prior to injection into the solidification system.
3.0 SYSTEh DESCRIPTION 3.1 SOLIDIFICATION SYSTEM DESCRIPTION The installed cement solidification system is designed to solidify the three primary waste streams generated at VCGS:
boric acid concentrates, sodium sulfate concentrates and spent bead resins.
The system consists of three major subsystems:
3.1.1 Cement storage and filling systems which include the bulk storage silo, day tank and required support equipment.
Rev. 4 1-2 6/86
1 1
o e
1 l
3.1.2 Drum conveying system which includes the necessary equipment to locate the drums at the cement filling station and to safely move the cement loaded drums to the radwaste druening station.
f 3.1.3 Decanting station which includes the necessary controls and monitoring devices required to deliver properly decanted resin slurries to the radwaste drumming station.
l 3.2 PROCESS PARAMETERS 3.2.1 PROCESS DESCRIPTION l
Prior to the first soldification of a particular type of radioactive vaste in a full-size container, process con-trol verification test (s) will be performed. The purpose of the verification test (s) vill be to determine the proper quantities of cement, and additives required to be placed in each 55-gallon drum. The verification test (s) will also indicate the required amount of pH additive required to be added to the vaste tank to insure the proper pH is obtained.
Once a satisf actory verification test has been performed, j
the radwaste operator vill begin the solidification l
evolution. The required quantities of additives will be l
place 3 in the 55-gallon drus prior to placing the container on the drum conveying system.
Once the additives have been placed in the container, the container vill be placed on the drum conveying system and moved to the cement fill station, where the required quantity of Portiand Type III cement will be placed in the drum. A mixiag weight will be placed in the drum following concrete addition.
The drum conveying system will then move the cement-filled drum to the loaded drum storage area.
The installed overhead crane system will trensfer the cement-filled drum to the radvaste fill station where the wet radioactive waste vill be metered into the drum. The j
drum will then be placed in the drum tumbler and tumbled for the required time.
3.2.1.1 Binder l
The solidification binder used in the installed solidtfication system is Portland Type III hydraulic cement.
Rev. 4 l
1-3 6/86 1
e 3.2.1.2 Calcium Hydroxide (Lim): C3(OH)
A predetermined quantity of calcitrn hydroxide is added to the influent waste stream for; 1) initial pH adjustmnt, 2) to react with the boric acid to form insoluble calciarn etaborate salts to prevent boron from retarding the hydration of the cemnt, ard 3) to act as a divalent cation depletir>3 agent for lon exchange resins.
3.2.1.3 Calcium oiloride: CaCly calcitn chloride is aMed to the solidification birder to accelerate the hydration of the coment.
3.2.1.4 Lithium Hydroxid: LioH'2H o y
Lithium hydroxide is added to the influent waste strmm as required to insure the firal pH will be at least 10.5.
3.2.2 WASTE DOUNDARY CONDITIONS In order for radioactive waste solidified with Portland cemnt to met the stability requiramnts, certain bourdary conditions must be achieved.
3.2.2.1 g 1
The waste stream pH affects the ability of the cemnt to hydrate. The solidification process at WIS ircorporates the addition of calcita hydroxide ard lithium hydroxick for initial and finsi pH control acMitives, respectively.
3.2.2.2 Boric Acid Boric acid affects the ability of the comnt to properly solidify the waste stream by providing an acidic enviroment. The boron present in the waste stream also affects the hydration process i
of the biMer. The solidification pro:ess at i
W:GS incorporates the use of calcium hydroxide (Ca(OH)2) to react with boron to form insoluble l
calcium mtaborate salts.
3.2.2.3 Sodium Sulfate l
The presence of scdiun sulfate in the waste strewn can cause a flash set of the solidification biMer producing excessive heat from the hydration of the cemnt binder.
l Rev. 4 1
1-4 6/86
3.2.2.4 Bead Resin When solidifying depis+ed bead ::;in, care must be taken to insure the active cation sites have been neutralized to prevent removal of divalent or trivalent ions from the cement /vaste slurry.
1 3.2.2.5
- 011, Waste stream containing greater than 2% oil will be solidified with an acceptable oil solidification binder and process control program for the solidification of oil waste.
3.3 DETAILED SYSTEM DESCRIPTION 3.3.1 CEMENT STORACE SYSTEM DESCRIPTION The STOCK solid radvaste system for WCCS begins with a cement filling system for onsite storage of large quantities of cement as well as the control equipment and instrumentation to accurately transfer measured quantf. ties of cement to standard 55-gallon drums. Although the entire cement filling process is carried out in safe areas of the plant, the equipment has been precision engineered l
for dust-free operation so that no cement dust will enter the plant atmosphere or cause deposits on the outside surface of the drums which might subsequently become 3
contaminated.
l The entire cement filling system is operated from its own control console located adjacent to the cement filling station and the conveyor system. Controls, monitoring devices and alarm indicators have been centralized in this location for ease of operation and to keep the operator informed of system status and operation.
Incoming ceuent is transferred into the storage silo utilizing the fluidizing equipment and blowers mounted on the cement delivery truck.
Cement is again fluidized and transferred in small increments on operator command to the inside cement filling station day tank as neaded. Mounted above the day tank is a duet collection system interconnected to the day tank, the drum feeder assembly fill nossle and to the storage silo to maintain vacuum conditions and dust containment at all times.
Standard 55-gallon drums from a clean storage area enter the cement filling station on a STOCK roller conveyor and l
are individually positioned beneath the cement fill nostle. A predeterrtned amount of cement is placed into each drum by the action or a screw feeder located at the Rev. 4 1-5 6/86
day tank discharge hopper. The weight of cement per drum is determined in accordance with the process sample verification which is performed on each batch of radioactive vaste to be processed.
Once a drum has been filled with cement and sealed, it is conveyed to the drum staging area for pickup by the bridge crane. The crane may transfer the drum either to a drum storage area or to the drum processing enclosure where the decanting and drumming equipment remotely apply measured quantities or specified proportions of radioactive slurries and concentrates.
An air compressor system is included in the cement filling system and is housed in an environmentally-controlled room located at the base of the storage silo to provide process air free of oil and water contaminants. STOCK-supplied transfer piping supplies air to the pneumatic conveyor, the fluidizing jets in both the silo discharge zone and in the day tank discharge hopper, the automatic filter cleaning equipment in the dust collection system, the bell-type shut-of f valve in the cement fill nozzle orifice and to the air-oil cylinder operating the drum scale plat f o rm.
The cemeat filling system performs a number of related functions :
inspection of drums and caps for damage and proper thread line, long-term storage of large quantities of cement under controlled conditions, application of the specified quantity of cement and the mixing weight to the drum, recording of drum tare weight and filled weight and drum sealing.
It is recommended that a drum control number be assigned to each drum and recorded, and that a label or stencil be applied to the drum head in this safe location.
Numbering vill facilitate positive identification for
.I subsequent procees contro11 therefore, the labels or stencils used should be of sufficient size and contrast to permit viewing by means of the traveling bridge crane grab TV and surveillance cameras located a considerable distance above the drum storage area. The cement filling systen has been provided with the f ollowing systems and components.
3.3.1.1 cement storage Silo The cement storage silo is of cylindrical construction with a dished head and conical discharge section, fabricated from 1/4" ASTM A-283-C steel.
Double-velded construction I
1 Rev. 4 1-6 6/86
throughout assures dust-tight integrity and vacuum maintenance.
Storage capacity is 1,530 cubic feet of cement.
The silo is filled from self-unloading delivery trucks through a 4" diameter fill line. The fill line includes a clean-out port at its highest elevation and is connected to a discharge box centered on the top of the silo. The discharge box allows the cement to fall evenly incide the tank during filling.
Also located at the top of the silo is an inspection manhole and a 5" diameter vent line which is connected to the dust collection systen i
located on the cement filling station day tank.
l Access to the top of the silo is provided by a I
hand ladder with safety cage and a maintenance l
platform with perimeter railing--all designed and I
constructed to OSRA standards.
Cement is discharged f rom the bottom of the silo to a pneumatic conveying system. The pneumatic conveying system is mounted to the inlet chute.
The pneumatic conveying system connects to the cement silo via a dust-tight inlet chute and c manually-operated shut-off valve. The sides of the discharge cone of the silo directly above the shut-off valve are sloped at a 500 angle from horizontal. Ten automatically controlled air fluidizing nosales are installed in the perimeter of the discharge cone to prevent packing of the cement powder.
3.3.1.2 Si' fressure Reitef Valve A mechanical pressure relief valve is mounted at the top of the silo to prevent possible pressurization c' the silo.
It is set to open at 10" of water and, through a limit switch, energises a red alarm.
3.3.1.3 Silo High-level Controls i
l The cement storage silo is equipped with a sonic l
high-level sensor loccted at the normally filled l
1evel of the silo. When activated by abnormally l
high cement levels, the control energizes two red l
lights located at the cement filling station electrical console and located on the exterior vall of the silo.
l Rev. 4 1-7 6/86
The high-level control also activates an audible alarm located at the top of the silo.
During normal filling of the silo, placing the ON/0FF switch to the ON position will energize two green lights located on the exterior side wall of the silo and in the rear of the cement filling station console.
Placing the ON/0FF switch into ON position also energizes the dust collector.
3.3.1.4 Silo cement Level Indicator A mechanical level indicator is provided for monitoring the amount of cement remaining in the silo.
l A 4-figure digital readout located in the air compressor room displays in tenths of feet the l
1evel of cement remaining in the silo.
l 3.3.1.5 Silo Fluidizing System Transfer of cement from the storage silo to the air conveyor equipment is facilitated by an air fluidizing system. The air fluidizing system consists of an air filter with automatic drain, an accumulator tank for air storage, a pulsator l
motor with cycle timer and ten fluidizing 1
nostles. The nosales are deployed at various levels around the perimeter of the silo discharge cone.
l l
All nozzles are connected by a common manifold to a pulsator solenoid valve located next to the silo discharge cone downstream of the accumulator tank. The cement conveying system controls are interlocked to the fluidizing system, permitting i
a pulsate.r motor and cycle timer to open for I
several brief intervals before the sti 2 of each i
conveying cycle. Short bursts of high pressure I
air through the fluidizing nosales aerate the cement in the discharge cone area of the silo facilitating its passage to the cement chute for j
controlled application to the fluidizing vessel.
3.3.1.6 Air Compressor System j
An air compressor system is installed in a separate room attached to the base of the cement storage silo to supply process air to the cement filling system. The pneumatie equipment is an j
independent and self-contained system including Rev. 4 1-8 6/86
o all necessary components to provide the required delivery of air for the cement filling system free of any oil or water contamination. The air system is equipped with two air compressors, coalescing filters, air dryers and pressure regulators.
3.3.2 CEMENT FILLING SYSTDI The cement filling system includes all the equipment necessary to transfer cement from the storage silo into the drum. The four principal items of equipment aret an air conveyor unit to transfer cement to the day tank, the day tank, a screw feeder assembly which precisely meters the appiteaton of cement into each drum and a dust collector assembly designed to remove the cement dust generated at each point in the process.
3.3.2.1 Air Conveyor System An air conveyor system is utilized to transfer cement from the cement storage silo to the cement day tank. The system has an operating capacity l
of transferring 150 lbs/1.5 minutes. Compressed I
air at 80-100 psi (30 ScrM) is required to l
operate the system.
l l
Cement in the silo discharge cone is fluidized by I
the continuous application of high pressure air.
l This allows the cement to drop into the I
fluidizing vessel of the air conveyor system l
without packing. Once the fluidizing vessel is l
filled with cement, unregulated air at 80-100 psi is introduced into the vessel. The unregulated i
air aerates the cement and causes the pressure in j
the vessel to increase. When pressure in the fluidizing vessal reaches 15 psi, the unregulated air is stopped.
Regulated air then forces the aerated cement from the fluidizing vessel into the transfer line.
The transfer line is connected to the day tank. The regulated air
(
forces the cement in the transfer line into the l
l day tank.
The conveying cycle is complete when the transfer line is empty.
3.3.2.1.1 Air conveyor Booster Jet The air conveyor discharge piping into the day tank contains a pneumatic booster jet to impart additional l
accelerating force and mixing action Rev. 4 1-9 6/86 t
i l
l
a l
g I
to the cement flow. Air application l
to the booster jet is regulated at the l
pneumatic control panel by an air l
service valve.
3.3.2.1.2 Conveying Fault Timer l
The conveying fault timer is included l
to automatically stop the conveying process if a batch of cement is not i
completely evacuated from the fluidising vessel to the day tank within a specified interval.
3.3.2.2 Cement Filling Station Day Tank The day tank of the cement filling station is located inside the radwaste building and is designed to hold suf ficient cement for one day's operation. The tank has a net storage capacity of 50 cubic feet. The air conveyor system is capable of filling the day tank in 1.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
The day tank is rectangular in shape with all l
four sides tapered sharply into an integral discharge hopper. The entire assembly is fabricated from 1/4" ASnt A-283-C teel utilizing double-welded construction for str.ngth and dust-tight integrity. The tank itself and equipment mounted thereon is accessible by a welded steel service ladder and a bar-grating maintenance platform surrounded by OSHA specified double handrailing.
Fluidized cement from the air conveyor enters the I
day tank through a discharge box which distributes the cement evenly inside the tank.
l l
The day tank is equipped with a mechanical I
pressure-reitef valve. The pressure-relief valve l
is set to open at 10 inches of water to prevent the possible over pressurization of the day tank.
A sonic high-level sensor located at the normally filled level of the day tank provides indication of day tank level. The day tank has sufficient capacity to complete the transfer of a batch of i
cement should the high-level set point be reached during transfer. The day tank is equipped with an interlock to prevent the transfer of cement to the day tank once the day tank high-level alarm i
has been reached.
i Rev. 4 l
1-10 6/86 l
l
o The transferring of cement from the day tank to the drum screw feeder assembly is facilitated by four fluidizing nozzles located in the wall of the discharge hopper. The nozzles are connected by a common manifold to a solenoid valve and the compressed air supply.
3.3.2.3 Screw Feeder Assembly The screw feeder assembly is used to transfer cement from the day tank discharge hopper to the fill nczzle. The fill nozzle is placed inside the 55-gallon drum. The screw feeder consists of a tapered, rolled, steel screw driven at 25.7 rpm. This provides a cement delivery rate of 110 cubic feet per hour.
The screw feeder discharges to a vertical exit hopper. The drum fill nozzle is attached to the base of the exit hopper. The walls of the exit hopper are installed at a steep angle to prevent the accumulation of cement in the exit hopper.
l 3.3.2.4 Dust Collection System A Torit filter cartridge-type dust collector is installed with the cement filling system to i
provide vacuum conditions within the system and to eliminate area contamination from airborne cement dust. The dust collection equipment is mounted to the top of the day tank for direct I
dust collection from the day tank but, is also interconnected throughout the cement filling system. The dust collection system takes a suction on the cement filling system at the following points:
a.
Cement silo, b,
Silo fluidizing vessel, and c.
Exit hopper.
Air is drawn in by the system vent fan threugh nine filter cartridges housed within the dust collector.
Dust is captured on the exterior surface of the elements while filtered air passes j
out through the filters to the exhaust dischacge port and into the radwaste building ventilating j
system. The capaetty of the ventilation system at the dust collector is 1,000 SCTH @ 6" H 0.
2 Rev. 4 1-11 6/86 l
s e
The f11ter elements are alternately cleaned in i
groups of three.
Each group of filters is equipped with a solenoid valve and will admit high pressure air to the center of the filter elemente. At ten-second intervals a pulse of low-volume, high-pressure air is directed into the center of the selected elements. The dislodged dust falls into the day tank where it i
is utilized for drum filling.
The dust collector is electrically interlocked to operate automatically whenever any of the i
following operations are initiated:
a.
Drum Filling - by moving console selector switch SS57 to either the AUTOMATIC or MANUAL drum fill position.
b.
Storage Silo Filling - by moving selector switch SS28 at the silo to the ON position.
c.
Cement Conveying to the Day Tank - by l
depressing the AIR START pushbutton at the I
electrical console.
j 3.3.3 DRUM CONVEYING SYSTEM i
The drum conveying system consists of the roller conveyor l
i used to transport drums through the cement filling station area and the integral lift assembly and scale platform which raise the drums to the cement fill nosale for
- filling, i
3.3.3.1 Roller Conveyor l
The roller conveyor is divided into four distinct 1
(
sections. The first section is a flat drum staging area seven feet in length for drum inspection, numbering and cap removal. The second section is the scale platform and drun lift area which hydraulically elevates one drum i
at a tima for filling and weighing. The third i
section is a long, flat receiving area for inserting the sixing weight and replacing the cap. The fourth section is a floating storage area approximately 22 feet in length for conveying filled drums to the traveling bridge J
crane pickup point. The length of the storage i
area is designed to hold enough profilled drums i
for one day's nors.a1 needs.
1 l
)
Rev. 4 1-12 6/86
)
i
All individual rollers in the conveyor are provided with dust-proof sealed bearings. Five brake rollers are spaced throughout the storage area of the conveyor.
3.3.3.2 Scale Platform A scale platform is installed for weighing individual drums.
It is located beneath the elevating section of the roller conveyor. It consists of three 500-pound espacity load cells.
The outputs of the three celle are added by the load cell summing junction in the electrical console and the total is displayed on one of two LED-type, three-figure digital readouts on the electrical console. The readout labeled DRUM TARE displays the weight of the empty drum when the scale platform is in its lowered position.
This tare weight is retained in a memory circuit of the electronic weighing system. The readout labeled DRUM NET displays the continuously changing net weight of cement as it is being injected into a drum.
When the desired net weight of cement is reached and the feed screw is deactivated, the operator will depress the CLEAR TARE pushbutton on the electrical console. This allows the tare weight to be a led to the net veight of cement. This is the net weight of the drum.
3.3.3.3 Mixing Weights The mixing weight is a reinforcing bar bent at 2
its midpoint to an angle of approximately 120 degrees. At least one mixing weight vill be inserted into each drum at the cement filling station af ter the cement has been metered into the drum. While the drum is tumbled, the weight (s) imparts mixing action to its contents in the drunning operation.
3.3.4 CEMENT FILLING STATION CONTROLS The electrical control console contains all controis for operating the cement filling station. The controls and instrumentation are located at various points in the console and are listed below by area.
3.3.4.1 Console Control Panel The aperations and control panel is mounted on the desk top of the control console. The I
Rev. 4 1-13 6/86
operations and control panel contains the following system indications.
3.3.4.1.1 Control on/Off The two position selector switch energizes the complete cement filling station and all control circuitry.
3.3.4.1.2 Main Tank High Level A red indicator light informs the operator of high cement level in the main storage silo.
Input is provided by the silo high-level sensor.
3.3.4.1.3 Day Tank liigh Level A red indicator light informs the operator of high cement level in the day tank.
Input is provided by the day tank high-level sensor. In a high-level condition, cement conveying i
to the day tank vill cease as soon as the current cycle is completed.
3.3.4.1.4 Emergency Stop A red pushbutton immediately de-energizes the cement filling station contr?1 cftcuitry including any l
operations in progress.
3.3.4.1.5 Air Compressor l
A red pushbutton energizes the control and power circuits to the air compressor system, including the desiccant dryers and electric drain trap. The pushbutton vill light the red AIR COMPRESSOR indicator light on l
the concrol panel.
3.3.4.1.o Vent yan A red pushbutton energines the control and power circuits to the dust collector system ventilation fan.
Operation of the dust collector system is automatic whenever drum filling operations are initiated or when cement is being loade4 into the storage silo or transferred to the day Rev. 4 1-14 6/86 1
I o
I
{
tank. However, this pushbutton is T.rovided to e:able the operator to activate the dust collection systen independently as needed. The pushbutton will light the red VENT FAN indicator light on the control panel.
r r
l 3.3.4.1.7 Teed Screw Running A red indicator light infor1es the operator that the day tank feed screw conveyor is operating.
Input is l
provided by the DRUN FILL PERMIT pushbutton located on the right side well of the console.
f 3.3.4.1.8 Air Conveyor On/Off The two position selector switch energizes the complete air conveyor
[
procest and circuitry.
3.3.4.1.9 Air Start A black pushbutton starts the air i
conveyor transferring cement. The
[
process will continue untti the day l
tank high-level is reached or $573 is turned off.
l i
3.3.4.1.10 Scale Zero A black pushbutton enablea the
[
l operator to recalibrate the platforu scale af ter each drum tilling operation.
i 3.3.4.1.11 Cleer Tate A black pushbutton releases the drum's i
l tare weight Iroe storage in the l
electronic assory c)rcuit and adds it s
j to the net weight of the cement in the I
drva. The total weight is then displayed as DRLM TARE weight.
3.3.4.1.12 Fluidi 4 %, Tank i
A black pushbutton opens a solenoid l
valve permitting air injection iuto Rev. 4
[
1-15 6/86 l
s the day tank discharge hopper. This promotes cement flow to the feed screw and will centinue as long as PB100 is depressed.
3.3.4.1.13 conveying A red indicator light informs the operator that a batch of cement has been fluidized in the air conveyor and is en route to the day tank.
Input is provided by the fluidizer vessel pressure switch.
3.3.4.1.14 Auto / Manual Fill Drum A spring-return toggle switch enables the operator to selectively fill drums with cement by setting the desired weight on the thumbwheel switch or by visually monitoring the weight as it appeers on the DRUM NET readout.
3.3.4.1.15 Drum Raise / Lower A spring-return toggle switch is provided to raise and lower the drum i
en the scale platform. The switch lever must be held in the appropriate position for the control to be energized. Automatic circuitry j
prevents overtravel in either direction.
3.3.4.1.16 Drum Tare An LED-type digital readout displays the empty weight of a drum moved into position on the scale platform.
3.3.4.1.17 Drum Net An LED-type digital readout displays
[
the net weight of cement in the drum as it is being filled. When filling is complete and the CLEAR TARE pushbutton is depressed, this weight is blanked and the combined weig of the cement end the drum weights.
displayed at the DRUM TARE display.
i l
Rev. 4 1-16 6/86
.~.,
s 3.3.4.1.18 Set Net Weight A thumbwheel switch is provided to permit the operator to program into the electronic weighing system the required amount of cement to be added to the drum.
In the manual drum filling mode,_this switch is not utilized.
3.3.4.1.19 Drum Fill Permit A pushbutton located alone near the top of the right side of the electrical console enables the operator to initiate the drum filling operation, an long as the scale platform has been completely raised.
3.4 SYSTEM CONTROL 3.4.1 SYSTEM CONTROL PANEL The system control console As a free-standing, desk-type enclosure for single unit control of the overhead traveling bridge crane, the decanting station, the cement drumming station and the operations section for radwaste feed system control of tanks, pumps and valves.
All control and indication devices required for remote l
operation of the STOCK traveling bridge crane, decanting /
l drumming stations, and the spent resin / evaporator bottoms tanks and associated system valves and pumps are located on the vertical front face and operator's writing table of the console. The control console consists of three modularized sections, each approximately 24" wide, which comprise the operational controls of the radwaste system.
The drum processing control section contains a graphics display panel of the system and all manual switches and visual indicators for operating the decanting / drumming stations. An annunciator panel, process selection panel, status display and control panel and operations panel comprise the control sector for this section of the control console.
Located in the bridge crane control ocction are the TV monitors with their control units ccaveniently grouped for l
operator surveillance while operating the crane. Spring loaded, toggle-type control handles are provided to l
Rev. 4 1-17 6/86
operate the crane, in addition to a crane control panel with indicators and controls for grab elevation, crane operation / status, lighting, grab operation / status and crane /TV circuit selection.
The control section contains an annunciator panel, meter panel, tank / pump status display and control panel and valve operations panel'for spent resins and evaporator bottoms waste control.
Removable front panels and hinged doors on the lower front and entire rear of the console provide for easy access to equipment for maintenance and replacement. A graphics i
display panel provides.a visual process flow schematic for j
the decanting and drumming stations.
i 3.4.1.1 Process Selection Panel The process selection panel is positioned below the graphics display. The process selection panel contains the following control and instrumentation:
Evaporator Bottoms Waste Operations Select, a.
b.
Decant Tank Gallons 530 gallons full
- range, Machinery Air psig 150 psig full range c.
(PI2),
d.
Flush Water psig 100 psig full range (PII),
e.
Evaporator Bottoms Primary Feed Temp 0F 2400F.
full range, and f.
Evaporator Bottoms Secondary Feed Temp 0F-full range.
3.4.1.2 Status Display and Co,ntrol Panel The status display and control panel is below the process selection panel and contains digital readout displays which serve as both status displays and controls.
The following readouts are functionally grouped on the status display and control psnelt a.
Evaporator Bottoms / Chemical Waste Metering Pump Gallonn - Indicates the total number of gallons of waste material metered into a i
Rev. 4 1-18 6/86
e drum. The readout it displayed in half-y gallon increments to correspond to the delivery rate of the metering pump.
2 1st Count /2nd Count - A paif of'thumbwheel b.
switches are provided with which to select the amount of waste, in gallons, to be metered into the drum. The switches can be used in three different combinations:
IST C00NT only, 2ND COUNT only, or IST COUNT and 2ND COUNT combination for double filling..
Each switch is set to the nearest half gallon increment. Also, both the decent metering pump and evaporator bottons/ chemical waste metering pump can be set tc fill a drum simultaneously or in any 1st and 2nd count.
combinations, such as setting the 1st fill from the decant t. ink and the 2nd fill from the evaporator bottoms metering pump.
c.
Drumming Station On/Off - A separate two-positic) selector switch is used as an ON/0FF 1
stitch to energize the relay logic for the drumming station controls.
d.
Drum or Tank Radiation Level / Roentgens Per Hour - The 1,000R radiation monitor consists of a scintillator detector and its associsted 4
electronics and display package. The system is designed as a dual-channel system with an operating range of 1,000R to 10 mr.
A three-position selector switch, with DRUM RADIATION /0FF/ TANK RADIATION clockwise indicators is p*ovided to display the radiation signal from either the decant tank or the drumming station scale, via the radiation level display.
Drum Gross Weight /Lbs. - A readout provides e.
the weight of a processed drum via an i
electronic weighing system.
I f.
Zero Scale - A black zero scale push button is providad to reset the drum gross neight display to zero before or after weighing a drum.
3.4.1.3 Operations Panel The operations Janel is positioned immediately below the status display and control panel and mounted on the desk top of the control console.
Rev. 4 1-19 6/86 1
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The operations panel contains pushbuttons or pushbutton/ indicator light combinations for additione.1 operator-controlled functions.
The operations panel contains the following controls and instrumentation:
3.4.1.3.1 Flush Drum Fill Line Energizes valve operators to open the proper valves to allow flush water through the decant metering pump, decant to drum fill Jine and the slurry filling nozzle to clean the i
line.
3.4.1.3.2 Flush Evaporator Bottoms / Chemical Waste Feed Line Energizes valve operators to open the proper valves to allow flush water through the evaporator bottoms metering pump end into the select evaporator bottens waste fe2d line.
The chemical wast.e feed line is flushed independent of the evaporator bottoms metering pump.
3.4.1.3.3 Enclosure Washdown Energises valve operators and a rotating spray drive motor to allow flush water through a revolving manifold to clean the inside of the drum processing enclosure.
3.4.1.3.4 Drum Wa:hdown Energizes valve operators to open proper valves to allow flush water through a manifold within the drum processing enclosure to wash down the exterior surfaces of a drum. The washdown can be energized when the drum is either tumbling or at rest.
3.4.1.3.5 Auto On Energizes the automatic mode of the drum processing cycle. Assuming all conditions are satisfied, the drum will proceed through h complete cycle automatically.
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Rev. 4 1-20 6/86
3.4.1.3.6 Hatch Open Energizes a solenoid valve which causes a pneumatic actuator to raise the drum processing enclosure hatch cover to the fully open position.
3.4.1.3.7 Manual Advance Permits step-by-step advancement through the drum processing cycle rather than automatic advancement.
3.4.1.3.8 Hatch Closed Energizes a solenoid valve which causes the same actuator to lower the drum processing enclosure hatch cover to the fully closed position. 'The light indicates that the hatch is fully closed.
3.4.1.3.9 Skip Operation Depressing the red SKIP OPERATION push button will cause the drumming sequence programmer to cycle through the steps in the automatic cycle without the equipment actually performing the operation. The lights on the right side of the graphic display panel will flash on as the programmer cycles through each step in the automatic sequence, letting the operator know which steps are being
'uy passed.
The programmer will continue to cycle until the buttons are released. Drum processing may be continued from any point in the sequence as long as the permissives are satisfied.
3.4.1.3.10 Energency Stop De-energizes the drumming cycle circuit immediately. This button is independent of the decanting operation.
3.4.1.4 Graphics Display A graphics display panel, located below the annunciator panel on the left vertical section of the control console, represents the decanting and Rev. 4 1-21 6/86
=.
t v
drumming stations, with associated interconnecting piping, valves, pumps and equipment. The symbols on the left represent the decanting station, with the decant tank, mixer, decant arm and decant pump. Red lights indicate mixer running, arm movement up or down, decant pump running, and high-or low-level tank status. The circle under the tank represents the decint metering pump with a piston in the center and four valves which can be opened in various cembinations of oper.ed or closed depending upon the mode of operation and direction of flow through the. pump. The pump port valves light (red) when open, turn off when closed. The pump piston will light (amber) when intake is complete and turn off upon discharge. The pump valve and piston lights visually indicate that the pump is in op. ration and show which valves and lines are in use. The shut-off valves, for flush / spray lines and for tank feed loops, have red (open) and green (closed) indicating lights, which.are operated from valve actuator limit switches, to give positive indication of valve position. The metering pump and process valving along with the piping flow indications (amber), verify to the operator which process lines are in use for a particular station operation.
The symbols at the center of the mimic represent the drumming statioa, showing the drunning enclosure and evaporator bottoms metering pump, along with associated piping and valves. In addition to ths valve, pump and flow indicators, there are two rotational arrows in the center of the drum symbol which light (red), af ter each revolution of the DRUM TUMBLE cycle, gf,ving positive indication that the drum is being tumbled.
On the right side of the mimic is a vertical row of indicator lights that identifies each sequence of the drumming operation cycle. The drumming cycle is initiated and completed at the Load Position sequence. During the drumming operation, the operator knows the status and position of the drum by referencing the glowing (amber) indicator light, which identifies the drumming cycle sequence occurring. The indicator lights provide greater flexibility in operation
)
by allowing the operator to change from the automatic mode to MANUAL ADVANCE at any stage in the sequence or to skip sequences, for, example, advancing the step prograsser to the CLAMP 2nd i
Rev. 4 1-22 6/86
l step from the CAP / TUMBLE POSITION for a contaminated drum washdown, and returning the i
operation to the automatic mode to complete the drumming cycle. The drumming cycle sequence.
indicator lights also serve as a troubleshooting aid by indicating which sequence the drumming cycle was in when a fault trip occurs, thus allowing the operator to manually reset the sequence programmer at the desired step for restarting the drumming operation.
3.4.1.5 Annunciator Panel Annunciator windows above the graphics display panel provide the following fault or status indication to the radwaste operatort a.
demineralizer water pressure, b.
machinery air pressure, c.
decant tank high-level, d.
select feed loop valve, e.
motor overload tripped, f.
drum process cycle complete, g.
no cap in drum, h.
no fill selection (gallons of fill),
- i. drum overfill, J.
drum process fault, and k.
evaporator bottoms feed line temperature high.
3.4.3 DECANTING STATION CONTROLS I
The decanting station is functionally controlled by tie operator from the control console decanting and drumming section by means of selector switches and pushbuttons, with indicators and indicator lights supplementing the controls. Controls and monitoring devices have been provided to allow for ease of operation and to inform the operator of station status and operation.
Rev. 4 1-23 6/86
.i The decanting station has been provided with the STOCK solid radwaste system to accurately decant' slurries prior to drum filling. This station is a compact assembly of components attached to both sides of'a 12" thick steel shield wall. Mounted on the maintenance side of the sh!. eld wall are all motors, pneumatic valves, actuators and as many of the gear reducers as is practical. On the prc:ess side of the wall are the decanting tank and the-pumping ends of the metering and decanting pumps.
Incoming waste slurries are transferred from the liquid radwaste system storage tanks to the decanting tank through the piping aanifold.
During this filling operation, the decant tank mixer is automatically operated to ensure that the slurry is a uniform mixture. Upon a
completion of the filling operation, an automatic flush 4
operation is initiated to flush the fill line to the decant tank and the feed line back to the liquid system 1
i storage tank. Af ter this flush operation has been J
completed, the slurry is allowed to settle for a predetermined period of time. This settling time allows for the separation of solids and water to a uniform level bed-of-solids.
1 Once this settling period has elapsed, the water level and l
water-solid interface level ars +curately measured with sensors mounted nn the decanting arm and STOCK designed 1
solid state eqe.pment. These readings sie dfaplayed on the control console and inform the o e;atoc in to whether s
excess water is to be removed or if water is to be added to the decant tank.
This is done in accordance with the process control program in order to achieve the correct solid / water ratio consistent with the pretested solidification formula for the waste stream. Excess water is removed with decanting equipment and returned to the liquid radwaste system storage tanks by means of a specially designed decanting punp. This minimizes the amount of water requiring disposal.
After the decant tank has been prepared with the correct solid / water ratio, the mixer is then automatically started and operated for a predetermined period of time to ensure that the slurry is again uniform. While the slurry is being mixed, the operator is then able to record the radiation level of the slurry to be processed with the radiation detector provided with the decanting station.
The STOCK metering pump is used to transfer the prepared decant tank slurry to the drumming station for drum processing. The pump and its associated controls allow the operator to program accurate pump quantities to be Rev. 4 1-24 6/86
e processed in each drum. Once programmed,~the pumping operation becomes part of the automatic processing cycle at the drumming station. The metering pump is also used-for transferring decant tank contents back to the vaste stream storage tank.
3.4.4 DRUMMING STATION CONTROLS All controls for operation of the drumming station are located immediately adjacent to the decanting station controls. A single selector switch on the front face of the control console energizes the drumming station control circuits. Complete monitoring of operation of the drumming station can be accomplished by watching the graphics display panel while the drumming station is in use. The operator has the option of drumming 'either decanted wastes or concentrator wastes as well as any corbination of the two.
The drumming station is a compact assembly of components' i
to drum radioactive slurrf es and solutions in 55-gallon drums with cement solidif a tation binder. For safety in operation and for maintenance, the equipment is attached to both sides of a 12-inch thick steel shield wall. On the safe side of the wall are mounted all motors, pneumatic valves, actuators and as many of the gear reducers as is practical. On the hot side of the wall are the pumping ends of the metering pump and the drum processing enclosure. The 12-inch thick steel shield wall provides the equivalent of 39 inches of concrete shielding, allowing personnel to be present on the safe side of the wall during operation for maintenance or for other purposes.
The drumming station is remotely operated from the console which is provided with the control station.
Controls and q
monitoring devices have been provided to allow automatic or manual operation and to inform the operator of station status and operation.
j The drumming station allows drums to be filled with either j
evaporator concentrates or resin slurries. Prior to drumming operations process control verification tests are performed in accordance with the requirements of the process control program. Once a satisfactory verification sample has been performed, the required quantity of waste is programmed into the waste meter pump controls. The metering pump will automatically transfer the required l
quantity of waste to the disposal container.
4 Rev. 4 l
1-25 6/86 s
o Disposable containers which have been prefilled with concrete at the cement filling station are transferred to the drum positioning platform inside the drum processing enclosure. Once the drum is inside the drum processing enclosure, the station operator shuts the drum processing enclosure hatch isolating the drum processing enclosure from the station's environment.
With the metering pumps and the appropriate feed controls setup for the correct quantity of waste (s), drum processing can then be initiated. The movement of the drum through the drumming station cycle is automatic, once l
the drum has been loaded into the drum processing enclosure and the hatch has been closed. The drum is uncapped, filled, recapped, clamped, tumbled and unclamped. This operational sequence may be repeated in the automatic cycle to permit the drum to be filled twice.
Upon completion of the automatic process cycle, the drum is returned to the load / unload position within the drum processing enclosure. The operator then initiates remote opening of the hatch and lowers the crane's drus grab into the enclosure. The drum grab is equipped with a downward viewing camera, which allows the operator to inspect the drum.
After the operator has verified that the top head of the drum is free from contamination, he then raises it out of the drum processing enclosure and pocitions it upon the scale platform. Once the drum has been releaced, the drum's weight and radiation level are then measured and recorded.
Displays for these functions are provided at the control console and provide valuable information as to the decay pit and location at which the drum should be stored.
'.5 SOLIDIFICATION SAMPLE VERIFICATION i
3.5.1 RECIRCULATION OF WASTE STREAMS 3.5.1.1 Prior to sampling radioactive vaste hold up tanks l
for process control sample verification, each tank shall be recirculated until a representative sample can be obtained.
1 3.5.1.2 No waste should be added to or removed from a batch tank af ter sampling has been performed.
Should waste be adied or removed from the tank prior to completing the solidification of the tank, solidification activities will be secured and the tank placed in the recirculation mode until representative samples are obtained.
Rev. 4 1-26 6/86
J ^
r 3.5.1.3 The radioactive waste tank shall remain in the recirculation mode durirag actual solidification operations.
3.5.2 VERIFICATION SAMPLE REQUIREMENTS 3.5.2.1 Solidification sample verification will be performed on each batch of each type radioactive waste until star.dard cement-to-waste ratios have been developed and proven to produce acceptable products on a minimum of ten consecutive batches.
3.5.2.2 Once the standard ratios have been proven to produce acceptable solidified products for ten consecutive batches of each type radioactive waste, solidification sample verification requirements will be decreased to at least once every tenth batch of each type of radioactive waste.
3.5.2.3 Should any solidification verification sample prove to produce unsatisfactory solidified products, solidification verification sampling requirements will be increased to every batch of each typa radioactive waste until the criteria of Step 3.5.2.1 are met.
3.5.3 WASTE IDENTIFICATION 3.5.3.1 Each verification sample shall be analyzed for the following minimum characteristics:
3.5.3.1.1 011 per procedure CHM-02-450.
3.5s3.1.2 pH per procedure CHM-02-230.
3.5.3.1.3 Temperature pei,
. tre CHM-02-230.
3.5.3.1.4 Boron content per procedure CRM-02-052 or sodium sulfate per procedures 01M-02-075 and/or CHM-02-110.
3.5.3.1.5 Isotopic analysis per procedure CHH-03-021.
3.5.3.2 The results of each sample verification will be recorded on the appropriate sample worksheets.
3.5.3.3 Wastes shall be classified and curie content determined per procedures HPH 09-501 and HPB 09-502, respec*.'vely, or by NRC approved computer software.
Each package shall be identified in 4
i Rev. 4 1-27 6/86
s accordance with applicable NRC and DOT regulations for packaging and transportation of low-level radioactive waste.
3.5.4 SOLIDIFICATION SM4PLE ACCEPTANCE CRITERIA 3.5.4.1 Visual inspection of the end product after solidification must indicate a free standing, monolithic structure which meets the free standing water criteria of the appliciable low level radioactive waste disposal facility.
3.5.4.2 The end product must resist penetration when probed with a spatula or comparable firm object.
3.5.5 SOLIDIFICATION SAMPLE VERIFICATION DOCUMENTATION 3.5.5.1 Calculate and record all required information on either the concentrates solidification work sheet or the resin solidification worksheet.
3.5.5.2 The Radwaste Coordinator or his designee shall inspect and verify the results of each sample verification.
3.6 PRIMARY CONCENTRATES VERIFICATION 3.6.1 Based on the sample analysis, determine the quantities of 4
calcium hydroxide, calciuu chloride, and lithium hydroxide required for satisfactory solidification. Record these quantities on the concentrates solidification worksheet.
3.6.2 Ensure the temperature of the concentrate sample is at least 160 F.
Record the temperature on the solidification sample verification worksheet.
3.6.3 Transfer the waste stream to the disposable container.
Measure and record pH.
3.6.4 Add the required quantity of calcium hydroxide to the waste sample. Mix for five minutes.
3.6.5 Measure and record pH.
If pH is less than 10.5+.5 add LiOHa2H 0 increments of 2 grams until pH is greater than 2
10.5.
NOTE:
Because of the difference in the quantity of heat of hydration released in the test sample and the full scale solidification, the test sample will not demonstrate the quantity of hardness of' the full scale sample.
3.6.6 Mix sample for approximately 1 minute.
Rev. 4 1 6/86
e 3.6.7 Record sample weight and volume on the solidification sample verification form.
3.6.8 Place a lid on the disposable beaker and allow to stand for a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 130 F in e. convection oven.
3.6.9 Inspect each sample for free standing water and product integrity. Record sample results on the solidification sample verification form.
3.6.10 If the solidification sample is satisf actory, determine the quantities of waste, thumb wheel settings, cement, calcium chloride, and lithium hydroxide to be placed in each 55 gallon drum and the quantity of calcium hydroxide to be placed in the batch tank by performing the calculations described in Section D of the concentrates solidification sample verification form.
3.6.11 If the solidification aample is not satisfactory, adjust the waster binder ratio (Formula B.2) downward in
{
increments of.5 until a satisfactory sample verification is obtained.
3.6.12 Perform Step 3.6.10.
3.6.13 Ferform full scale solidification in accordance with the system operating procedure using the boundary parameters recorded in Section D of the concentrates solidification sample verification form.
3.7 SOLIDIFICATION OF SPENT ION EXCH ANGE RESIN NOTE: If radiation levels do not permit the verification testing of the actual depleted resin, depleted non-radioactive resin may be used.
3.7.1 Determine pH, boron content, and resin to water ratio of the resin stream to be solidified and record results on the resin solidification worksheet.
3.7.2 Based on sample analysis results, determine the quantities of cement, calcium chloride, and lithium hydroxide required to obtain a satisfactory solidification. Record these quantities on the resin solidification worksheet.
I 3.7.3 Transfer the required quantity of waste to a disposable i
container.
3.7.4 Heasure and record waste stream temperature.
3.7.5 Add the required quantity of calcium hydroxide to the waste stream. Mix for 5 minutes prior to adding the waste to the disposable container.
Rev. 4 1-29 6/86
3.7.6 Measure and record pH.- IfpHislessthan10.515, add lithium hydroxide to the resin waste stream to increase pH to at least 10.5.
Record the additional LiOH 2H O 2
required to increase pH to at least 10.5.
3.7.7 Transfer the required quantities of cement and calcium chloride to the disposable container.
3.7.8 Mix sample for.1 minute.
3.7.9 Record waste sample final pH on the resin solidification worksheet.
t 3.7.10 Record weight and volume of the waste sample on the resin solidification worksheet.
3.7.11 Place a lid on the disposable beaker and allow to stand for a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 130 7 in an convection oven.
3.7.12 Inspect each sample for free standing water and product integrity. Record sample results on the resin solidification worksheet.
3.7.13 If the solidification sample is satisfactory, determine the quantities of cement, calcium hydroxide, calcium chloride, lithium hydroxide and waste to be placed in each 55 gallon drum or batch tank by performing the calculations described in section D of the resin solidification worksheet.
3.7.14 If the solidification sample is not satisfactory, adjust the waster binder ratio (Formula B.2) downward in increments of.5 until a satisfactory sample verification is obtained.
3.7.15 Perform Step 3.7.13.
3.7.16 Calculate the quantities of waste, thumb wheel settings, cement, calcium hydroxide, lithium hydroxide and calcium chloride required for each container.
j i
3.7.17 Perform full scale solidification in accordauce with the system operating procedure using the boundry parameters recorded in Section D of the solidification sample i
verification form.
1 3.8 SECONDARY CONCENTRATES AND SECONDARY SPENT RISIN VERIFICATION 3.8.1 Secondary concentrates and secondary system spent resins will be processed through the bulk waste disposal station. This waste will not be solidified in the in-plant solidification system.
I Rev. 4 1-30 6/86 f
3.8.2 Secondary spent resin will be discharged through the secondary bulk waste disposal station to 55 gallon drums.
Secondary resins will be dewatered in the 55 gallon d rums. The dewatered resins will be transported to a sanitary landfill for disposal. Sluice water will be returned to the clean floor drains.
3.8.3 Should secondary spent resins exceed the activity levels for unrestricted release, they will be processei in accordance with Section 3.7.
3.9 SYSTEM INTERFACING 3.9.1 The installed solidification system interfaces with the liquid radioactive waste system, solid radwaste decanting station, chemical drains, reactor make up water system, and the radwaste building ventilation system.
3.9.2 Liquid wastes are transferred from the primary evaporator bottoms tank, chemical drain tank, or the secondary evaporator bottoms tanks by installed pumps. All piping used to transfer the concentrates to the solid radwaste drumming station and for recirculation of the bottoms tanks is heat traced to prevent crystallization of the concentrates prior to reaching the solid radwaste drumming station. The solid radwaste drumming station also receives liquid waste from the chemici drain tank.
3.9.3 The primary and secondary bottoms tanks and the chemical drain tanks are equipped with recirculation capability to insure satisfactory samples may be obtained and analyzed.
3.9.4 The installed resin sluicing system transfers spent resin and depleted charcoal to the spent resin storage tanks (primary and secondary).
Resin slurries are then transferred to the solid radwaste decanting station. The solidification system operator can maintain the required amount of liquid in the resin slurry and decant and transfer all excess liquid to the spent resin hold up tanks.
3.9.5 All exhaust from the decanting station and the solid radwaste drumming station is processed by the radwaste building venti 11ation system.
3.9.6 The reactor make up water system is used to wash down and decontaminate processed drums as necessary to remove external contamination from the drums due to spillage.
1 3.9.7 The installed bulk waste disposal station provides l
necessary interface support for mobile vendor processing systems; the discharge header includes primary / secondary Rev. 4 i
1-31 6/86
w resins and concentrates supply; the return header provides a return route for decanted water resulting from resin slurries. Both lines are tied into the reactor makeup water (RMW) system for backflushing capability.
3.10 CORRECTIVE ACTIONS 3.10.1 At predetermined intervals a portion of the solidified containers will be inverted and allowed to stand for a period of time. Each of these containers will then be inspected for free standing water. The results of each inspeccion shall be recorded. Should any container be found to exhibit free standing water greater than the FSW criteria established by the low level radioactive waste disposal facility, the following actions shall be taken:
3.10.1.1 Secure solidification activities until new solidification ratios can be determined and proven.
3.10.1.2 Inspect all available containers from the same batch of radioactive vaste solidified using the formulas which provided the unsatisf actory results.
3.10.2 Drums that exhibit free standing water shall either be dewatered or reprocessed by determining the quantity of water and adding proper quantities of cement and additive chemicals as required by a sample verification test.
4.0 ADDITIONAL PROCESSING 4.1 VENDOR PROCESSING 4.1.1 In the event that WCGS requires vendor processing capacity, KG&E shall use vendor processing to ensure that LLW produced at WCGS is efficiently processed for shipment in accordance with KRC, DOT and state burial requirements.
4.1.2 When vendor solidification, resin dewatering, or filter encapsulation services are used at WCGS the latest revision of the NRC approved vendor process control program shall govern the applicable LLW processing whenever this service is in use.
4.1.3 Low-level radioactive waste processed by vendor systems shall be certified as complying with the f ree standing liquid requirements for licensed shallow land disposal sites.
Rev. 4 1-32 6/86
.s 5.0 FILTER DISPOSAL IN HIGH INTEGRITY CONTAINERS (HIC'S) 5.1. ADMINISTRATIVE CONTROLS 5.1.1 Filter cartridges produced at WCGS that are'in excess of 1 uCi/cc specific activity containing radionuclides with half-lives greater than five years shall either be encapsulated in accordance with step,4.1.2 or disposed of.
in approved high integrity containers (HIC's).
5.1.2 When HIC's are used at WCCS for filter ' cartridge disposal, each polyethylene HIC ordered shall be pre-foamed on its interior to preclude any container damage during packaging handling and transportation to a burial facility. Metal alloy HIC's will not require interior pre-foaming.
5.1.3 Filter packaging and disposal shall be.done in conformance with the latest state-approved certificate of. compliance.
WCGS shall obtain the C of C onsite prior to any waste i
processing.
i 5.1.4 KG6E shall insure that the maximum allowable f ree standing.
liquid in a high integrity container is less than one half percent (0.5%) of the waste volume.
5.1.5 Qualified test data supporting compliance with the free-standing liquid requirements in 10CFR61 for.the WCGS filter disposal method are contained in Appendix C.
Vendor certification statements for mechanical filter cartridge compatibility with identified HIC's are j
contained in Appendix D.
i 5.2 FILTER DESCRIPTION AND TRANSFER l
5.2.1 Spent filter cartridges that normally require disposal at L
WCGS are Pall-Trinity cartridge filters. The Pall-Trinity cartridge filter contains fiber filter media rigidly enclosed in a stainless steel mesh cylinder housing. The plant Pall-Trinity seal water injection filters are 2-3/4"
{
(inches) in diameter and 19-1/4" (inches) long; the remaining plant Pall-Trinity filters are 6" in diameter I
and 16-1/2" long.
5.2.2 The spent filters are first valved out of service, then vented and drained by the 'une of remote valve operators.
l The filter housing is unbolted and opened using long handled tools. The filtera ar6 then removed manually using a long handled hook or remotely using a shielded filter transfer cask (FTC) depending on radiation levels.
i i
I Rev. 4 1-33 6/86 i
v v
5.2.3 he filters are then transported to storage and placed into a high integrity container (HIC) if the estim ted activity is equal to or greater than 1 ri/cc of isotopes with half-lives greater than five years averaged over the volum of the filter.
5.2.4 Other filter cartridge types utilized at WCGS include de-sludging Cuno type cartridge filters (2" in diameter by 14-3/4" long); respirator trailer and ultrasonic turbulator Cuno type cartridge filter (2" dia. by 10" long); and a respirator trailer Gelman Acroflow II cartridge filter (2" dia. by 10" long;. W ese filters are changed out nanually and placed in plastic bags or other suitable container and transported for placunent in a HIC, if the f11ters are determined to contain in excess of 1 uCi/cc of isotopes with greater than five year half-lives.
5.2.5 Spent cartridge filters produced at ES shall be classified according to 10CFR61 and have curie content determined per procedures HPH 09-501 arxl HPH 09-502, respectively, or by NRC approved conputer sof tware.
5.3 HIGH IRTEGRITY CONTAINER DESCRIPTION 5.3.1 Spent filter eartridges produced at WOGS are placed into two different types of HIC's. The first type is constructed of polyethylene:
the second type is constructed of a metal alloy (Ferrallura 255). Both containers have undergone full scale testing and are designed to conply with the structural stability requiremnts of 10CFR61.56.
5.3.2 HIC's used for filter cartridge disposal at WCGS have been certified as being resistant to the identiff ed filter cartridges and their contents, including the water absorbing agents.
Refer to Appendix D for certification of ccrnpatibility statements between WCGS filter types and i
identified HIC's.
5.4 FILTER TREAMDTP METHOD 5.4.1 Prior to the addition of the filters to the HIC, the bottom of the container is filled with approximately 6" of ver Iculite or Aquaset agent. Following each filter addition, a mininum of one gallon of vermiculite or one-half gallon of Aguaset is also added to the HIC. We amount of agent added has been determimd to provide a conservative amount of absorbent to assure at least twice the amount necessary to remve residual filter liquids within the HIC.
i Rev. 4 l-34 6/86 4
o 5.5 FILTER TREATMENT DETERMINATION 5.5.1 The previously described treatment method was determined to be adequate to meet regulations and burial ground requirements by measurements made at WCCS.
Each type of filter was weighed dry then immersed overnight in water.
The filters were then removed and weighed to determine the maximum water retention (the results are contained in Appendix C).
5.5.2 The Vermiculite and Aquaset agents were tested to determine the quantity required to absorb a known amount of liquid. The ratio was determined to be 2.5 parts Vermiculite to one part water. For Aquaset, this ratio was determined to be one part Aquaset to one part water.
5.5.3 Since the maximum amount of water that could conserva-i tively be estimated to be present in a filter at WCGS is 627 ad, the required amount of Vermiculite would be 1568 al, or 627 al for Aquaset.
Since the burial facilities dictate that twice the amount of absorbent required to fully absorb liquids be added, 3136 al of Vermiculite or 1254 al of Aquaset should be added. Therefore, a one gallon (3785 mi) addition of Vermiculite, or a one-half j
gallon (1893 ml) addition of Aquaset, for each filter packaged is a conservative amount to assure package free standing liquid restrictions are met. The preplaced 6" of absorbent is for conservatism.
i 0
Rev. 4 1-35 6/86
r APPENDIX A: CONCENTRATE SOLIDIFICATION WORKSHEET l
A.
Waste Identification Boron Content ppa.
Test i pH Waste Type i Tempe rature OF Tank Id i Oil (% by volume) i i
DATE CH EMISTRY B.
Sample Preparation l.
Waste Sample Volume (Vgs) 200 al 2.
Waste Sample Volume to Cement Volume Ratio Waste Volume (Vys) 0.75 or
]
Cement Volume (VCS)
I l
3.
Weight of Cement (WCS) "
I XVWS x 0.93 ga =
cm i
0.75 or al Step B.2 4
Weight of Calcium Hydroxide (Lime)-Ca(OH)2 ppm Boron x 3.64 x 10-4 =
gm Ca(OH)2 s
5.
Weight of Lithium Hydroxide-LiOH 2H O 2
200 ml of Waste (Vgs) x 0.083 =
16.6 - gm LiOH 2H O 2
I 6.
Weight of Calcium Chloride-CaCl2 l
j (WCS) l l
gas cement X 0.04 =
zu CaCl2 i
i l
7.
pH following Addition pH L
i l
Page 1 of 3 i
4 Rev. 4 1-36 6/86 1
.1
9.
8.
Additions 1 LiOHsH O rsquirsd to incrossa pH to 10.515 a
2 gm Lial H O 2
9.
Total Weight of Lithium (WL) required gm LiOH H O 2
/ 16.6 =
11.
Final Product Volume (Vyp) ml 12.
Final Product Weight (Wyp) gm C.
Solidification Sample Results 1.
Free Liquid (Free Standing H O) al 2
2.
General Appearance 3.
Test Acceptable Cyes C No
/
Shift Chemist Date 4
Radwaste Operator Review
/
Date 5.
Coments D.
Full Scale Solidification 1.
Volume of Container (Vc) ft3 gal.
2.
Useful Volume (Vu) ft3 gal.
3.
Waste Volume to Cement Volune Ratio (Waste to Binder Ratio) 0.75 or Fron Step B.2 4
Vaste Volume (Vy) in gallons.
Vws (free B.1 in mi.) = 200 al.
Vyp (from B.10 in m1.) =
al.
Vg (from D.2 in gal.) =
gal.
(Vws/Vyp) X Vg =
Waste Volume in Ca11ons (Vg)
Page 2 of 3 Rev. 4 1-37 6/86
5.
Weight of cement Vg (from D.4 in gal.)
gal.
i WC"YW X 7.75 lb/ gal. =
lbs. cement 0.75 or D.3 j
6.
Line--Ca(04)2 liters ppm Boron X 1.853 X Vw (gal) X 3.785 gal lb
=
4.536 X 105 mg/lb 7
Lithium Hydroxide LiCH H O (weight in pounds) 2 Vw gal X 0.6926 X Lithium Ratio (B.10) =
lbs.
8.
CaCl2 (weight in pounds)
WC (1b) X 0.04 =
pounds of CaC12 9.
THUMBWHEEL SETTINGS NOTEt Gallons = Pounds /(7.75 lbs per gal.)
(Container Volume x 0.95) - VCEMENT = First Thumb Wheel Setting a.
First Thumb Wheel Setting Gallons b.
(VWASTE - VFIRST THUMB WHEEL SETTING) = Second Thumb Wheel Setting Second Thumb Wheel Setting Gallons 10.
Operation Verified Thumb Wheel Setting
/
Operator Date 4
a.
Waste Container Id f*s 11.
a.
Prepared by Radwaste Operator Radwaste Operator Date b.
Reviewed by Operations Radwaste Coordinator Operations Radwaste Coordinator Date Page 3 of 3 Rev. 4 1-38 6/86
f*
u APPENDIX B:
RESIN SOLIDIFICATION WORKSHEET A.
Wast.e Identification
% Resin Slurry Volume of Resin X 100% =
% Resin-Test #
Total Volume Boron Content ppm Boron-Batch #
pH pH-Waste Type Tempe rature 07. Tank Id #
011(% by volume)
DATE OiEMISTRY B.
Sample Preparation 1.
Waste Sample Volume (Vys) [ Volume of Resin] = 100 ml 2.
Waste Volume to Cement Volume Ratio Waste Volume (Vus) 0.43 or
=
Cement Vold'5e (VCS) 3.
Weight of Cement (WCS) "
I XVWS x 0.93 ga =
gm 0.43 or el Step B.2 d
4 Weight of Calcium Hydroxide (Lime)-Ca(OH)2 l
ppm Boron x 3.64x10-4 =
grams of Ca(OH)2 5.
Weight of Calcium chloride-CaC12 WCS Weight of cement x 0.04 =
gm CaC12 6.
pH following time Addition pH 7.
Final Product Volune (Vpp) a1 8.
Final Product Weight (Wpp) gas Page 1 of 3 Rev. 4 1-39 6/86
C.
Solidification Sanple Results
' l. : Free Liquid (Free Standing water)'
t ml 2.
General Appearance 3.
Test Acceptable [Yes Q No
/
Shift Chemist Date 4.
Radwaste Operator Review
/
Date 5.
Coments D.
Full l Scale _' Solidification 3
1.
Volume of Container (V )
ft gal.
C 2.
Useful volume (v )
ft gal.
g 3.
Waste volume to Canent Volume Ratiot (Waste to Binder Ratio) 9.43 or From Step B.2 4.
Waste Volume (V ) in gallons.
g Waste Volume (V ) ml g
X Useful Volume (V ) =
Waste Volume U
Final Volume (VFP) ml gallons 5.
Weight of Caent (W )
C V X 7.75 lb/ gal =
lbs. cement g
0.43 or D.3 6.
Weight of Lime-Ca(OH)2 ppn Boron X 1.546 X 10-5 XVg (gal) =
pounds of lime 7.
Weight of Calcium 011oride-CaC1 2
Weight of Canent (W ) in pounds X 9.04 =
pounds of CaC1 C
2 Page 2 of 3 Rev. 4 1-49 6/86
~
.,o.
8.
THUMB WHEEL SETTINCS (a)
(Container Volume x 0.95). Volume
- First Thumb Wheel' l
CEMENT Setting'(gallons)
First Thumb Wheel Setting gallons (b) Volume Waste (V ). Volume
-Sec nd Thumb
.l' l
g FIRSTTHUMBWHEE1.SETTIU0eelSetting j
l Second T1amb Wheel Setting gallons t
9.
(a) Operation.erified Thumb Wheel Setting
/
l Operator Date
]
. (b) Waste Container Id s's i
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10.
(a)
Prepared by Radwaste Operator l
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l Radvaste Operator Date e
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(b) Reviewed by Operations Radwaste Coordinator L
i Ope. rations Radwaste Coordinator Date i
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APPENDfX C:
FILTER CARTRIDGE DISPOSAL DATA TEST ELEMENTS:
- 1) Chemistry department Metier PC 2000 digital weighing scale used for all data weight measurements.
- 2) Data was gathered for both size (large and small) Pall trinity cartridge filters, Cuno type filter cartridges, and a Gelman filter cartridge that may be generated at WCGS.
PALL TRINITY FILTER TEST DATA:
a.
Filter size (large) 6" x 15-1/4"
=
Large filter dry weight 3.15 Kg Large filter wet weight 3.75 Kg
=
Weight of retained water 0.60 Kg
=
Volume of retained water 600 mi b.
Filter size (small) 2-3/4" x 17-1/4"
=
Small filter dry weight 0.75 Kg
=
Small filter wet weight 1.00 Kg
=
Weight of retained water 0.25 Kg
=
Volume of retained water 250 ml
=
DE-SLUDGING FILTER TEST DATA:
a.
Filter size (Cuno type) 2" x 14-3/4"
=
Filter dry weight 0.316 Kg
=
Filter vet weight 0.943 Kg
=
Weight of retained water 0.627 Kg a
Volume of retained water 627 ml
=
RESPIRATOR TRAILER / ULTRASONIC TURBULATOR FILTER:
a.
Filter size (Ceno type) 1" x 10"
=
Filter dry weight 0.294 Kg
=
Filter wet weight 0.739 Kg
=
Weight of retained water 0.445 Kg
=
Volume of retained water 445 ml
=
RESPIRATOR TRAILER FILTER:
a.
Filter size (Celnsn Acroflow II) =
2"*x 10" Filter dry weight 0.287 Kg
=
Filter wet weight 0.453 Kg
=
Weight of retained water 0.166 Kg
=
Volume of retained water 166 al o
Page 1 uf 1 1-42 Rev. 4 6/86
t APPENDIX D: CERTIFICATION OF COMPATABILITY j
I i
.1 hug 9st Jsse 18. 1986
.a e w
m Mr. Les E. Paulsee reasse Ces and tiestric Costeer P.O. Se 200 Wichtte, teases 67201 i
Referesses t$LO 86 071 ft 42530/42526 Sent NIC/ Filter Certridge Ceepetittlier Stateseet j
Dear Mr. Feeleost j
NePet Services hee retteved the seteriste of teostruttles sed j
descripttese provided for the cettridge filtere predeced at WCGl.
4 We fled these filters to be sespettble with our e es p e e t 's tevitelley Nigh lategetty Centateers sed eer tetereellt fossed Pe17etheless Nigh !stegrity Cettelsers. Use of testateere 67 i
WCCS east be to coefersease with the respettive Certificate of Ceepiteese eed reforested Weres Procedures and User's Getdes for these costateers.
1 1 have e?.se eetlesed terrest copies of the State Certif ttetes of Cospiteete f or ett u!C's se have 1steseed for shellev tead terial.
1 4
VePet Servteos appresistes the opportsatts to to of see wite to j
WCCS set we leek ferverd to eer teettened rotationehtp.
Stacerett,
$ _ lnl _-
4t, 1
4 1
Check Fe11 haver Customer Services Diretter I
Rette i
State Cetttitestes of Ceepittate for MIC f
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1 J
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~*--- - - - ~
wesee., seser,e..e.e.se,e,..e,,,,.
1 i
j Page 1 of 5 4
1 43 Rev, 4 6/86
..-,-. -.. - -., n.. -,n -..-
..,-.-n,---
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F
.PPENDIX D:
CERTIFICATION Ol' COMPATABILITY 1 CHEM NUCLEAR SYSTEMS.INC.
to-s 6 -s P-; 4 4 g eosata.se a.secmmasis June 27, 1986 Mr. Lon Paulson Ransas Cas a-d Electric Corpany P. O. Box 20; wichita., Kans.s 67201 Dear Mr. Pa41 sons Please be advised that Chem-Nuclear Systems, Inc. has performed testing to demon trate the capability of Chem-Nuclear Systems, Inc.
high integrity containers to re:sive filter cartridges provided the internal surfaces of the high integrity container are protected with polyurethane foam.
The saax.aum weight of a single filter that can be placed in the container is eighty pounds.
This testing demonstrates the effectiveness of the foam cushioned container to withstand the impact of placing the filters in the container. The user retains responsibility to insure that the filters placed in the container are placed with care to insure that the container is not damaged by the loading rtocess.
Yours truly,
' Ets N s
Samuel D. Pearson, P.E.
Manager, Liner Operations SDP/cae
.aw mm.ve
,wr Page 2 of 5 1 44 Rev. 4 6/86 l
e' e
APPENDIX D:
CERTIFICATION OF COMPATABILITY O
Hllsam Eidow
@N*
$mYn refer to:
HN.3948 5
July 25, 1996 Mr. Vayne Caul.
R.adweste Regineer Kansas Cas & Electrie Company Meritage Park Nuclear Sutletag P.O. Dez 206 Vichita, Kanese 47202 Subj ect: Un,0f Westinghouse Mittaan Nueleer Incorporated RADLCES For Filter Storage And Burtal har Mr. Caul:
Westingh*use Mittaan's SADt4E line of high integetry containers (NIC's) een accept filter media that meet the ertteria set in the enclosed standard STD.D.03 009. Revisten 10, of our Users Manual. I have encies 4 an uncontrolled sepy for your reference. N !!1ters you have desertbed meet this ertteria, theuld you have any guestten, you can refer to this procedure er give se a call
/
at the above number.
I have also enelesed a copy of our Certif tsate Of Ceepitance for each of the IMLOKs.
Thank vw fe'r your tatorest in our sc Los produe Itne, sincerete, e
mn Doug J sr. treject tastneer DJ:jd incle ute.
Page 3 of 5 1 45 Rev. 4 6/86
APPENDIX D:
CERTIFICATION OF COMPATABILITY NUS COAPOAATIONPAOCESS SE AVICES 1
l July 1). 1966 PS-se-0263-L12 l
Mr. Lon E. Paulson Kansas Gas and Slectric Company 201 N. Market Street j
Wichita, Kansas 61201-020s Dear Ron In response. to your June 11. 1986 lettere kUS Process Services does have high intecrity containers (NIC's) which can be used for disposal of the tilter cartridges produced at the bolt Creek Ceneratino station. Those HIC's are produced by Irc kuclear Associates. Inc. and they are licensed f or use at the Barnwell radioactive waste disposal site. A copy of the stato certificate of compliance and a tlyer describino the NIC are enclosed for your review.
In addition to the 1FC HIC, NUS Procesa Services of fers a (11ter encapsulation liner. This liner encapsulates the filters with coment and is acceptable at the Barnwell and Richland burial sites. This liner also serves as a self shleid and can be used ter spent tilter storace when the filter oeneratino rete is low.
hUS Process Services is also in the process et licensino a new NIC that will meet the burial recuirements at all waste disposal d
sites. he sepect to have that HIC available early in 1901 he have several methods available for disposino of your certridae tilters and we stand ready to provide the best one for your particular situation.
sincegely.
1 Recan E. bolt Director.
haste Management Services cca Mike Isom Gerry Mott halt Hipsher Enclosures 1) DHEC C of C for h!C
- 2) HUMIC 120 flyer i
REV/ dab A maw Co tact =s, meso ccesA s c asso, cacasase assa Page 4 of 5 1 46 Rev. 4 6/86
^'
APPENDIX D:
CERTIFICATION OF COMPATABILITY e.R[-
TFC Nuclear Associates,Inc.
e i.,,o o.,e ese i
w e., -,o esosr
, sos, rrea st, July 14 1986
/
Mr. Wayne Gaut l
e, tansas Cae and Electric Company 201 Market Street P.O. Boa 208 t
Vichita, teases 67201
Subject:
Rish'!ategrity Coateiners Dest Mr. Gault 1
la response to Mi. Loa E. Paulson's letter if 6/11/86 this as to certify that all TFC High lateartty Contateers are compatible with the mechanical filter cartridges prodsced by VCGS. as Listed in the above referenced letter.
Eastosed also please find one(1) copy of our Certificate of Compliance
=tth the state of South Caroline Department of Health and Eastressental Centrol, providtag approval for burial at t
Baravell. South Carottaa.
Shoule you require any additional information, please contact se.
q i
I Very truir your
/
h
- Chando, r.
President JJC/cd l
Enclosures l
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PACKAGE PDL-532 W M-12HEo2 2
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CHANGE NOTICE
""""""* 8M. Al,;t ZONE : D - 2.
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W4JLF CREEK NUCLEAR OPERATING CORPORATION Bart D. Wrthers Prwoont and Ctwet Docutive Omcer August 29, 1988 WM 88-C211 I
U. S. Nuclear Regulatory Commission ATTN: Doc uraen t Control Desk Mail Station PI-137 Washington, D. C. 20555
Subject:
Docket No. 50-4 82 :
Sem). annual Radiological Effluent Release Report Gentlemen Attached is the Wolf Creek Generating Station Semiannual xadiological Effluent Release Report covering the period from January 1,
- 1988, through June 30, 1988.
This report is submitted pursuant to section 6.9.1.7 of the Wolf Creek Generating Station, Unit No. 1, Technical Specifications.
Very truly yours,
)
-J Bart D. Withers President and Chief Executive Of ficer B DW/j ad Attachment cc B. L. Bartlett (NRC), w/a D. D. Chamberlain (NRC), w/a R. D. Martin (NRC), w/a P. W. O'Connor ( NRC), </a (2) e PO. Box 411 I Burnngton, KS 66839 / Phone: (J16) 364431 An tu owerw*y tw wucvet
_ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ - _ - _.