ML17347A994

Semiannual Radioactive Effluent Release Rept Jul-Dec 1988. W/890302 Ltr

ML17347A994
Person / Time
Site:	Turkey Point
Issue date:	12/31/1988
From:	Conway W FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-89-75, NUDOCS 8903100271
Download: ML17347A994 (75)

Text

" ACCELERATED DISIBUTIOY DEMONSTR+ON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8903100271 DOC.DATE: 8872~b NOTARIZED: NO DOCKET g FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION CONWAY,W.F. Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"S al Radioactive Effluent Release Rept Jul-Dec 1988."

/890302 l r.

DISTRIBUTION ODE: 'IE48D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 5 EDISON,G 1 1 INTERNAL: AEOD/DSP/TPAB 1 1 ARM TECH ADV 1 1 NRR/DEST/PSB 8D 1 1 NI~gg3~~~PB 10 2 2 NUDOCS-ABSTRACT 1 1 G FIL 01 1 1 RGN2 DRSS/RPB 2 2 RGN2 ILE 02 1 1 EXTERNAL I BNL T CHLER i J 0 3 1 1 I EG&G S MPSON i F 2 2 LPDR 1 1 NRC PDR 1 1 A

D NOTE 'IO ALL "RIDS" RECIPIENIS'LEASE S

HELP US TO REDUCE HASTE! CXNX'ACI'HE DOCUMENI'ONIBOL DESK ROOM Pl-37 (EXT. 20079) %0 ELIHXKQ'E KKR NAME FKN DISQKBUTIGN LISTS FOR DOCUMENI'S YOU DON'T NEEDf TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 21

(i' P.O. Box14000, Juno Booch, FL 33408-0420 MARCH 2 1989 L-89-75 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Unit 3 and 4 Docket Nos. 50-250 and 50-251 Semi-Annual Radioactive Fffluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of July 1988 through December 1988 for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.4.

Should there be any questions regarding this information, please contact us.

Very truly yours,

~Pm<

gSenior Vice President Nuclear WFC/TCG/gp Attachment cc: Stewart D. Ebneter, Regional Administrator,, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company

TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JULY 1988 THROUGH DECEMBER 1988 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY 691231 pgp 490CK'0 5 000260 RN8/nid*C I:I R

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SUPPLEMENTAL INFORMATION JULY 1988 THROUGH DECEMBER 1988 1.0 Re lato Limits 1.1 Li uid Effluents a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentr6tion shall not exceed 2 x 10-4 pCi/ml.

b) The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluent released to unrestricted areas shall be limited, during any calendar quarter, to c1.5 mrem to the total body and to a5 mrem to any organ, and, during any calendar year, to c3 mrem to the total body and a10 mrem to any organ.

1.2 Gaseous Effiuents a) The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following.

Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin due to noble gases and less than or equal to 1500 mrem/yr to any organ due to I-131, I-133, tritium and for all radioactive materials in particulate form with half lives greater than 8 days.

b) The air dose per reactor to areas at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited, during any calendar quarter, to a5 mrad for gamma radiation and a10 mrad for beta radiation and, during any calendar year, to c10 mrad for gamma radiation and a20 mrad for beta radiation.

c) The dose per reactor to a member of the public, due to I-131, 1-133, tritium and to particulates with half-lives greater than 8 days in airborne effluents released to areas at and beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.

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OV/88 12/88 e 2.0 Maximum Permissible Concentrations The maximum permissible concentrations for liquid and airborne releases are described in Sections l.l-a and 1.2-a of this report.

The average energy of fission and activation gases in gaseous effluents is not applicable.

4.0 Measurements and A roximations of Total Radioactivi All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Regulatory Guide 1.21 was met or exceeded.

4.1 Li uid Hffluents Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2n gas flow proportional counter, The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases. Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system.

Monthly and quarterly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period of accumulation. The monthly composite was analyzed for tritium and gross alpha activity. Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2n gas flow proportional counter. The quarterly composite was analyzed for Sr-89/90 and Fe-55 by chemical separation.

All radioactivity concentrations determined from analysis of a pre-release composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period. 1 RNS/md*Cd:1 I

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07/88 - 12/88 Each batch of liquid effluent from the waste disposal system was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released in order to total the dissolved gases released.

4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and sporadic releases incidental to operation of the plant. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases, b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89/90 determination and gross alpha analysis, c) Absorption of halogen radionuclides on a charcoal filter

'1 and subsequent gamma-spectrum analysis, and d) Analysis of water vapor in a'as sample for tritium using liquid scintillation techniques.

All sporadic gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 by use of the plant vent process monitor recorder chart and the current calibration curve for the monitor.

Portions of the gas waste treatment system are shared by both units and generally all gas releases from the shared system are allocated on a 50/50 basis to each unit.

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OV/88 12/88 4.3 Estimate of Errors a) Sampling Error The error associatedJ with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been conservatively estimated to be collectively less than 2 1096.

b) Analytical Error'ur quarterly Q.C. cross-check program involves counting unknown samples provided by an independent external lab. The errors associated with our analysis of these unknown samples, and reported to us by the independent lab, were used as the basis for deriving the following analytical error terms.

Nuclide Maximum Error Liquid Gaseous t496 n NS/i>)d*C I: I

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07/88 12/88 5.0 BATCH RELEASES

'5.1 Liciuid Unit 3 Unit 4 a) Number of batch releases 2.06 E+02 2.06 E+02 b) Total time period of batch releases 1.96 E+04 1.96 E+04 Minutes c) Maximum time period for a batch releases 1.96 E+02 1.96 E+02 Minutes d) Average time period for a batch release 9.53 E+01 9.53 E+01 Minutes e) Minimum time period for a batch release 1.00 E+01 1.00 E+01 Minutes f) Average stream flow during period of 1.20 E+06 1.20 E+06 GP M release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 8.50 E+00 1.25 E+01 b) Total time period of batch releases 8.85 E+02 1.85 E+03'inutes c) Maximum time period for a batch release 2.40 E+02 2.40 E+02 Minutes d) Average time period for a batch release 1.04 E+02 1.47 E+02 Minutes e) Minimum time period for a batch release 1.00 E+00 1.00 E+00 Minutes 6.0 UNPLANNED RELEASES 6.1 Liciuid a) Number of releases b) Total activity releases 0.00 E+00 2.82 E-01 Curies 6.2 Gaseous a) Number of releases b) Total activity releases 0.00 E+00 0.00 E+00 Curies 6.3 See attachments (¹1) for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

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OV/88 12/88 V.O The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundry assumes a visitor was on-site at the "Red Barn" recreational area for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> a day, 2 days each week of the year, receiving exposure from both units at Turkey Point. The "Red Barn" is located approximately 0.39 miles NNE of the plant site. These dose calculations were made using historical meteorological data.

VISITOR DOSE SUMMATION JANUARY 1987 THROUGH DECEMBER 1987 UNITS 3 AND 4 Age Group: Adult Location: Red Barn Inhalation Bone 8.37 E-OV Liver 8.25 E-04 Thyroid 1.05 E-03 Kidney 8.25 E-04 Lung 8.25 E-04 GI-LLI 8.19 E-04 Total Body 8.19 E-04 NOBLE GAS EXPOSURE Gamma Air Dose 2.93 E-03 mRads Beta Air Dose 6.72 E-03 mRads 8.0 Offsite Dose Calculation Manual Revisions There were no ODCM revisions during this reporting period.

I 9.0 Solid Waste and Irratiated Fuel Shi ments No irradiated fuel shipments were made from the site. Common solid waste from Turkey Point Units 3 and 4 were shipped jointly. A summation of these shipments is given in Table 6 of this report.

10.0 Process Control Pro am Revisions See Attachment 3 e 11.0 C

S See ecial Re rts Attachment 2

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 3 TABLE 1 LIQUID EFFLUENTS SUMMATIONOF ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 1.75 E-01 6.91 E-02 al ha

2. Average diluted concentration during period pCi/ml 2.29 E-09 1.81 E-10 B. Tritium

1. Total Release Ci 1.38 E+02 5.50 E+01

2. Average diluted concentration during period pCi/ml 1.80 E-06 5.45 E-07 C. Dissolved and Entrained Gases

1. Total Release Ci 2.09 E-01 6.95 E-02

2. Average diluted concentration during period pCi/ml 2.73 E-09 6.88 E-10 D. Gross Alpha Radioactivity

1. Total Release Ci 1.12 E-07 <1.53 E-08+

E. Volume of Waste Released (prior to dilution) Liters 1.69 E+06 3.55 E+06 F. Volume of Dilution Water Used During Period Liters 7 65 Et10 1.01 E+11 MDA Value in pCi/ml 0

Approved by Date

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 3 TABLE 2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Continuous Mode Batch Mode Nucl ides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Ag-110m Ci 2.39 E-04 1.04 E-04 Co-5V Ci 1.75 E-06 Co-58 Ci 2.3V E-03 1.02 E-02 Co-60 Ci 1.48 E-01 7.10 E-03 Cr-51 Ci 1.19 E-03 1.73 E-03 Cs-134 Ci 2.03 E-04 1.23 E-03 Cs-136 Ci 2.13 E-03 5.15 E-03 Cs-137 Ci V.80 E-04 Fe-59 Ci 3.09 E-04 I-131 Ci 4.28 E-04 4.58 E-04 I-133 Ci 4.00 E-05 2.28 E-05 La-140 Ci 1.72 E-05 5.80 E-05 Mn-54 Ci 8.15 E-03 5.10 E-03 Mo-99 Ci 7.05 E-06 1.82 E-04 a-24 Ci 1.49 E-05 1.47 E-06 Nb-95 Ci 2.91 E-05 4.1V E-05 Ru-103 Ci 2.96 E-05 Sb-124 Ci 3.97 E-06 2.30 E-03 Sb-125 Ci 3.38 E-03 6.15 E-03 Zn-65 Ci 4.10 E-06 1.29 E-05 Zr-95 Ci 4.20 E-05 Ce-139 Ci 1.11 E-06 Ba-139 Ci 2.17 E-04 4.33 E-05 Sn-117m Ci 9.90 E-06 1.37 E-05 Sr-90 Ci 5.25 E-OS Fe-55 Ci 7.69 E-03 3.02 E-02 Sr-89 Ci 1.95 E-04 Unidentified Ci Total for Period Above Ci 1.75 E-01 6.91 E-02 Approved by Date RNS/md*C1:1

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 3 TABLE 2 (Continued)

LIQUID EFFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85 Ci 6.81 E-03 3.63 E-03 Kr-85m Ci 2.82 E-04 Xe-131m Ci 3.46 E-03 1.36 E-03 Xe-133 Ci 1.97 E-01 6.43 E-02 Xe-133 m Ci 1.19 E-03 1.24 E-04 Xe-135 Ci 1.88 E-04 1.05 E-04 Xe-135m Ci 2.34 E-06 1.38 E-05 Ci Total for Period Above Ci 2.09 E-01 6.95 E-02 LIQUID EFFLUENTS -DOSE SUMMATION JANUARY 1988 THROUGH DECEMBER 1988 UNlT 3 Age Group: Teenager Location: Cooling Canal Shoreline De ition Dose mRem  % of Annual Limit Total Body 8.14 E-03 2.71 E-01 Approved b Date Z-P RNS/md*C1: I

C FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 3 TABLE 3 GAS EFFLUENTS SUMMATIONOF ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release Ci 5.12 E+02 3.02 E+02

2. Average Release Rate for Period pCi/sec 6.44 E+01 3.79 E+01 B. Iodines

1. Total Iodine-131 Ci 1.17 E-03 5.94 E-04

2. Average Release Rate for Period pCi/sec 1.47 E-04 7.47 E-05'articulates

1. Particulates T - 1/2>8 Days Ci 5.12 E-OS 5.54 E-OS

2. Average Release Rate for Period pCi/sec 6.44 E-06 6.97 E-06

3. Gross Alpha Radioactvity Ci 1.87 E-08 (8.40 E-09*

D. Tritium

1. Total Release Ci 1.12 E+02 1.60 E+00

2. Average Release Rate for Period pCi/sec.. 1.41 E+01 2.01 E-01

• MDAValue in pCi/ml Approved by Date r

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 0 UNIT 3 TABLE 4 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases Ar-41 Ci 2.66 E-01 1.05 E-01 1.56 E-03 4.62 E-03 Kr-85 Ci 5.37 E-01 1.50 E-03 3.13 E-01 1.21 E-01 Kr-85m Ci 5.69 E-02 4.93 E-Ol 1.15 E-03 Kr-8V Ci V.25 E-03 1.57 E-06 Kr-88 Ci 2.49 E-02 Xe-131m Ci 1.06 E+01 9.95 E-03 4.60 E-01 5.9V E-01 Xe-133 Ci 4.59 E+02 2.73 E+02 2.89 E+01 2.15 E+01 Xe-133m Ci 1.31 E+00 1.65 E-03 1.9V E-01 1.52 E-01 Xe-135 Ci 1.00 E+01 5.43 E+00 5.64 E-02 1.79 E-01 Unidentified Ci Total for Period Above Ci 4.82 E+02 2.V9 E+02 2.99 E+01 2.26 E+01

2. Iodines I-131 Ci 5.15 E-04 5.10 E-04 I-133 Ci 3.V9 E-04 V.65 E-05 Br-82 2.78 E-04 7.80 E-06 Total for Ci Period Above 1.1V E-03 5.94 E-04 Approved by Date RNShnd*C1:1

I PLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 3 TABLE 4 (Continued)

GASEOUS EPFLUENTS Continuous Mode Nuclides Released Units Quarter 3 Quarter 4

3. Particulates Cr-51 Ci 1.24 E-05 Mn-54 Ci 2.62 E-06 Co-58 Ci 5.00 E-OV 1.84 E-05 Co-60 Ci 1.42 E-06 1.14 E-05 1-131 Ci 1.74 E-06 3.51 E-OV Cs-134 Ci 8.10 E-06 Cs-136 Ci 3.48 E-06 Cs-13 V Ci 2.03 E-05 1.28 E-05 Ba-140 Ci 1.30 E-OS Sr-89 Ci 6.50 E-11 Ci Unidentified Ci Total for Ci Period Above 5.12 E-05 5.54 B-OS Approved by Date aNS/(ndkCI:1 l

FLORIDA POWE TURKE LIGHT COMPANY INT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 0

UNIT 3 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body 2.40 E-04 1.80 E-03 6.38 E-02 V.17 E-04 1.52 E-03 1.52 E-03 1.63 E-03 Cow Milk Infant

- Fresh 1.3V E-05 1.84 E-03 . 1.82 .E-03 1.84 E-03 1.82 E-03 1.83 E-03 1.83 E-03 Fruit R Veg 1.97 E-05 1.97 E-05 1.97 E-05 1.97 E-05 1.97 E-.05 1.97 E-05 2.31 E-05 1.97 E-05 Ground Plane \

6.99 E-07 6.83 E-04 8.74 E-04 6.83 E-04 6.83 E-04 6.82 E-04 6.82 E-04 Inhalation-Adult Unit Totals (mRem) 2.74 E-04 4.34 E-03 6.65 E-02 3.26 E-03 4.04 E-03 4.05 E-03 2.31 E-05 4.16 E-03

% Annual Limit 2.74 E-03 4.34 E-02 6.65 E-01 3.26 E-02 4.04 E-02 4.05 E-02 2.31 E-04 4.16 E-02 DOSE NOBLE GASES Gamma Air Dose 8.71 E-03 mRad  % of Annual Limit 8.V1 E-02 %/Yr Beta Air Dose 2.47 E-02 mRad  % of Annual Limit 1.24 E-01 %/Yr Approved by Date

PLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 1 LIQUID EPPLUENTS SUMMATION OP ALL RELEASES Units Quarter 3 Quarter 4 A. Pission and Activation Products

1. Total Release (not including tritium, gases, Ci 1.75 E-01 6.91 E-02 al ha

2. Average diluted concentration during period pCi/ml 2.29 E-09 1.81 E-10 B. Tritium

1. Total Release Ci 1.38 E+02 5.50 E+01

2. Average diluted concentration during period pCi/ml 1.80 E-06 5.45 E-07

.C. Dissolved and Entrained Gases

1. Total Release Ci 2.09 E-01 6.95 E-02 Average diluted concentration during period pCi/ml 2.73 E-09 6.88 E-10 D. Gross Alpha Radioactivity

1. Total Release Ci 1.12 E-07 <1.53 E-08*

E. Volume of Waste Released (prior to dilution) Liters 1.69 E+06 3.55 E+06 F. Volume of Dilution Water Used During Period Liters 7.65 E+10 1.01 E+11

• MDAValue in pCi/ml Approved by Date RNS/md*Cd: I FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT.

JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 2 LIQUID EFFLUENTS Continuous Mode Batch Mode uclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Ag-110m Ci 2.39 E-04 1.04 E-04 Co-5V Ci 1.75 E-06 Co-58 Ci 2.37 E-03 1.02 E-02 Co-60 Ci'i 1.48 E-01 7.10 E-03 Cr-51 1.19 E-03 1.73 E-03 Cs-134 Ci 2.03 E-04 1.23 E-03 Cs-136 Ci 2.13 E-03 5.15 E-03 Cs-137 Ci 7.80 E-04 Fe-59 Ci 3.09 E-04 1-131 Ci 4.28 E-04 4.58 E-04 I-133 Ci 4.00 E-05 2.28 E-05

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La-140 Ci 1.72 E-05 5.80 E-OS Mn-54 Ci 8.15 E-03 5.10 E-03 Mo-99 Ci 7.05 E-06 1.82 E-04 a-24 Ci 1.49 E-05 1.47 E-06 Nb-95 Ci 2.91 E-OS 4.17 E-05 Ru-103 Ci 2.96 E-05 Sb-124 Ci 3.9V E-06 2.30 E-03 Sb-125 Ci 3.38 E-03 6.15 E-03 Zn-65 ,Ci 4.10 E-06 1.29 E-05 Zr-95 Ci 4.20 E-05 Ce-139 Ci 1.11 E-06 Ba-139 Ci 2.1V E-04 4.33 E-05 Sn-117 m ci 9.90 E-06 1.37 E-05 Sr-90 Ci 5.25 E-05 Fe-55 Ci 7.69 E-03 3.02 E-02 Sr-89 Ci 1.95 E-04 Unidentified Ci Total for Period Above Ci 1.75 E-01 6.91 E-02 Approved by Date RNS/md*C1: I I

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 2 (Continued)

LIQUID EFFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85 Ci 6.81 E-03 3.63 E-03 Kr-85m Ci 2.82 E-04 Xe-131m Ci 3.46 E-03 1.36 E-03 Xe-133 Ci 1.97 E-01 6.43 E-02 Xe-133m Ci 1.19 E-03 1.24 E-04 Xe-135 Ci 1.88 E-04 1.05 E-04 X3-135m Ci 2.34 E-06 1.38 E-OS Ci Total for Period Above Ci 2.09 E-01 6.95 E-02 LIQUID EFFLUENTS -DOSE SUMMATION JANUARY 1988 THROUGH DECEMBER 1988 UNIT 4 Age Group: Teenager Location: Cooling Canal Shoreline De sition Dose mRem  % of Annual Limit Total Body 8.14 E-03 2.71 E-01 Approved by Date I

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 3 GAS EFFLUENTS - SUMMATIONOF ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release Ci 5.73'+02 2.84 E+02

2. Average Release Rate for Period pCi/sec 7.21 E+01 3.57 E+01 B. Iodines

1. Total Iodine-131 Ci 1.17 E-03 5.94 E-04

2. Average Release Rate for Period pCi/sec 1.47 E-04 7.47'-05 Particulates

1. Particulates T 1/2>8 Days Ci 5.12 E-OS 5.54 E-05

2. Average Release Rate for Period pCi/sec 6.44 E-06 6.97 E-06

3. Gross Alpha Radioactvity Ci 1.87 E-08 <8.40 E-09*

D. Tritium

1. Total Release Ci 1.12 E+02 1.60 E+00

2. Average Release Rate for Period pCi/sec 1.41 E+01 2.01 E-01

• MDAValue in pCi/ml Approved by Date

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 4 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases Ar-41 Ci 2.66 E-01 1.05 E-01 3.96 E-01 Kr-85 Ci 5.37 E-01 1.50 E-03 3.13 E-01 1.12 E-01 Kr-85m Ci 5.69 E-02 4.93 E-01 4.20 E-02 Kr-87 C. 7.25 E-03 1.57 E-06 Kr-88 Ci 2.49 E-02 3.54 E-02 Xe-131m Ci 1.06 E+01 9.95 E-03 1.29 E+00 2.47 E-01 Xe-133 Ci 4.59 E+02 2.73 E+02 8.71 E+01 4.19 E+00 Xe-133m Ci 1.31 E+00 1.65 E-03, 7.80 E-01 4.87 E-02 Xe-135 Ci 1.00 E+01 5.43 E+00 9.3V E-01 6.34 E-02 Unidentified ,Ci Total for Period Above Ci 4.82 E+02 2.79 E+02 9.09 E+01 4.66 E+00

2. Iodines 1-131 Ci 5.15 E-04 5.10 E-04 1-133 Ci 3.79 E-04 V.65 E-05 Br-82 Ci 2.78 E-04 7.80 E-06 Total for Period Above Ci 1.17 E-03 5.94 E-04 Approved by Date RNS/md%'Cl:1 J

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT I , ~

SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 4 (Continued)

GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units Quarter 3 Quarter 4

3. Particulates Cr-51 Ci 1.24 E-OS Mn-54 Ci 2.62 E-06 Co-58 Ci 5.00 E-07 1.84 E-05 Co-60 Ci 1.42 E-06 1.14 E-05 I-131 Ci 1.74 E-06 3.51 E-07 Cs-134 Ci 8.10 E-06 Cs-136 Ci 3.48 E-06 Cs-137 Ci 2.03 E-OS 1.28 E-05 I Ba-140 Ci 1.30 E-05 Sr-89 Ci 6.50 E-11 Ci Ci Ci Ci Ci Unidentified Ci Total for Period Above Ci 5.12 E-05 5.54 E-OS Approved by Date I4NH/md'ACl:I I

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FLORIDA POWE TURK D LIGHT COMPANY NT PLANT SEMIAN AL REPORT JULY 1988 THROUGH DECEMBER 1988 0

UNIT 4 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body Cow Milk Infant 2.38 E-04 1.80 E-03 6.31 E-02 7.16 E-04 1.52 E-03 1.52 E-03 1.63 E-03 1.36 E-05 1.84 E-03 4.18 E-03 1.84 E-03 1.82 E-03 1.83 E-03 1.83 E-03 Fruit R Veg Fresh 1.96 E-05 1.96 E-05 1.96 E-05 1.96 E-05 1.96 E-0$ 1.96 E-05 2.29 E-05 1.96 E-OS Ground Plane Inhalation-Adult 6.94 E-07 6.83 E-04 8.72 E-04 1.83 E-04 6.83 E-04 6.82 E-04 6.82 E-04 Unit Totals (mRem) 2.72 E-04 4.34 E-03 6.82 E-02 3.26 E-03 4.04 E-03 4.05 E-03 2.29 E-05 4.16 E-03

% Annual Limit 2.72 E-03 4.34 E-02 6.82 E-01 3.26 E-02 4.04 E-02 4.05 E-02 2.29 E-04 4.16 E-02 DOSE NOBLE GASES Gamma Air Dose 1.38 E-02 mRad  % of Annual Lsmst 1.38 E-01 %/Yr Beta Air Dose 2.69 E-02 mRad  % of Annual Limit 1.35 E-01 %/Yr Approved b Dat RXS/mR*l 1'1

0 FLORIDA POMER 5 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1988 THROUGH DECEMBER 1988 UNITS 3 AND 4 TABLE 6 SOLID MASTE AND IRRADIATED FUEL SHIPNENTS A. SOLID MASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL TYPE OF WASTE UNIT 6 HO PERIOD %ERR a ~ Spent resin, filter, sludge m~ 2.36 EO evaporator bottoms, etc. Ci 1.49 E2 20

b. Dry compressable waste m 3.8 E1 (NOTE I) Ci 4.34 E-1 c~ Irradiated components, m 0.00 E-0 control rods, etc. Ci 0.00 E-0 20

d. Other non-compressable m'i 1.81 El metal waste (NOTE 2) 2.31 E-1

2. ESTINLTE OF MAJOR NUCLIDE COMPOSITION BY TYPE OF HASTE a ~ Co-60 54 Fe-55 17 Ni-63 9 Cs-137 9 Cs-134 3 I-131 3 Co-58 2 Sb-125 I tin-54 I

b. Co-60 56 C-14 14 Fe-55 12 Ni-63 10 H-3 3 Cs-137 1 Sb-125 1 Hn-54 1 c~

d. Co-60 51 Cs-137 31 Fe-55 8 Ag-110m 6 Ni-63 3 NN-54 1

.21-

3. SOLID HASTE DISPOSITION No. of Shipments Mode of Transporation Destination Sole use truck Barnwell, SC 10 (NOTE 3) Sole use truck Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS NONE 22.

FLORIDA POWER 5 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1988 THROUGH DECEMBER 1988 UNITS 3 AND 4 TABLE 6 SOLID WASTE SUPPLEMENT Waste Total (NOTE 4) (NOTE 5) (NOTE 6) R.G..1.21 (NOTE 7) Solidification or Classification Volume Total Principal Type of Category Type of Absorbent Agent Ft3 Curie Radionuclides Waste Container guantity Class A 1982.2 0.665 None PWR Compactable Non-Spec Strong, N/A and Non-campactable Trash Tight Package Class 8 83.4 149.0 Sr.90, Ni-63 PWR Ion l.a NRC Certified N/A Co-60. Cs-137 Exchange LSA > Type A Tl/2 ( 5 yr. Resins MSD/eb/07

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0 FLORIDA POWER 5 LIGHT COMPANY TURKEY POINT UNIT NOS. 3 th 4 TABLE 6 SEMI-ANNUAL REPORT JULY 1988 THROUGH DECEMBER 1988 NOTE 1: Dry Compressible Waste Volume indicates volume shipped to burial site following volume reduction by a waste processing facility.

Volume ~hipped to the waste processing facility was 2.71 E2 m .

NOTE 2: Other noncompressable metal waste indicates volume shipped to burial site following decontmination and. volume reduction by a waste processing facility. Volume shipped to the waste processing facility was 7.25 El m .

NOTE 3: Material transported to Oak Ridge, Tennessee, "was consigned to licensed processing facilities for volume reduction activities. The remaining material was transported by the processor to Barnwell, S.C. for burial.

NOTE 4 The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Units 3 8 4 are determined using a combination of qualitative and quantitive techniques.

In general, the Turkey Point Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/ll/83) for these determinations.

The most frequently used techniques for determining the total curie quantity in a package are the dose to curie methods and the (concentration) x (Volume or Mass) calculations. Where appropriate, engineering type activation analyses may be applied.

Since each of the above methodologies involves to some extent qualitative parameters, the total curie quantity is considered to be an estimate.

The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitters and periodic off-site analyses for difficult to measure isotopes.

The on-site analyses are performed either on a batch basis or on a routine basis using reasonably representative samples as appropriate for the waste type. Offiste analyses are used to establish scaling factors or other estimates for difficult to measure isotopes.

NOTE 5: "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .01 times the concentration of the nuclide listed in Table 1 or .Ol times the smallest concentration of that nuclide listed in Table 2 of 10CFR61.

1 NOTE 6: "Type of Waste" is generally specified as described in NUREG 0782, Draft Environment Impact Statement on 10CFR61 Requirements for Land Disposal of Radioactive Waste".

"Licensing NOTE 7: "Type of Container" refers to the transport package.

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ATTACHMENT 1 UNPLANNED RELEASES At approximately midnight on August 15, 1988 an unplanned release occurred when 3,166 gallons of water leaked from the Unit 4 Spent Fuel Pit (SFP) to the ground and canal system. Analysis of the Unit 4 SFP showed an activity level of 2.35 E-02 Co-60. Basing release calculations on this activity and the 3,166 gallons released yields a total of 2.819 E-01 Ci being discharged. A portion of this total was released to the canal system via the RCA storm drains while the remainder was clehned up under the direction of the Health Physics Department.

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ATTACHMENT2 SPECIAL REPORTS On December 3, 1988 the Unit 3 Spent Fuel Pit SPING-4 monitor was taken out of service for its 18 month Preventive Maintenance Program. At this time alternate sampling methods were initiated to ensure compliance with Technical Specification 3.9.2.d.

On December 5, 1988 the grab sample valves failed the leakrate test and were declared inoperable. With these valves out of service it was determined that representative sampling was no longer possible. Due to being unable to sample, the effluent release via the Unit 3 Spent Fuel Pit exhaust stack was terminated.

The valves which had failed the leak test are no longer manufactured. A Request for Engineering Assistance was submitted to replace these valves and rebuilding kits have been purchased for 'the interim. The repairs are in process at this time.

A2-1 RNH/md*Cd: l

FLORIDA POWER 5 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1988 THROUGH DECEMBER 1988 UNITS 3 AND 4 ATTACHMENT 3 Summary of the Revision to Florida, Power 8 Light Company Turkey Point Units 3 and 4 Operating Procedure 11550.48, Process and Control Program for Dewatering Radioactive Waste Liners.

~Pa e t Page 1 has been revised to show the date of PNSC review and Plant Manager's approval of the current revision and to update the list of effective pages.s" This change does not affect conformance of the dewatered waste to existing criteria.

~Pa e 2 In Section 3.2, the words "disposal site criteria" have been changed to "disposal site licenses". This more accurately reflects the regulatory basis for the authority to ,perform this proc'edure.

This is especially true for those disposal sites which have no published criteria.

This change does not affect conformance of the dewatered waste to" existing criteria.

In Section 3.3.3 the definition for a process control program has been- changed for grammatical enhancement only. No substantive change has been made to the definition.

This change does not affect conformance of'he dewatered waste to existing criteria.

~Pa e 3 The precautionary statement pertaining to solidification has been deleted. This procedure is directed specifically to dewatering of waste media.

This change does not affect conformance of the dewatered waste to existing criteria.

In Section 4.5.2 the words "conformance of dewatered bead resins" have been changed to "dewatered waste". This has been done to make the scope of this precautionary statement compatible with that of this procedure.

, This change does not affect conformance of the dewatered waste to existing criteria..

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PAGE 4 Page 4 has been revised for consistency in numbering and pagination only. No substantive changes have been made.

This changes does not affect conformance of the dewatered waste to existing criteria.

~Pa e 5 Section 7.1 has been revised for grammati cal enhancement only.

No substantive change has been made to this notification requirement.

This change does~ not affect conformance of the dewatered waste to existing criteria:

In Section 7.2 the words "Health Physics Supervisor or his designee" has been changed to "Radwaste Supervisor". This change in notification requirement has been made coincident with the creation of the Radwaste Supervisor position. The individual filling this management position is responsible for oversight of all solid waste processing.

This change does not affect conformance of the dewatered waste to existing criteria.

Pa e 6 Section 8.1 and 8.2 has been revised to disallow the use of a visual inspection of waste media to determine that the applicable freestanding liquid criteria has been met. This technique is no longer practiced at Turkey Point Units 3 and 4.

This change does not affect conformance of the dewatered waste to existing criteria.

Section 8.3 has been revised to specify the actual numerical limits for freestanding liquid in steel liners and high-integrity containers.

This change does not affect conformance of the dewatered waste to existing criteria.

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This proceduremay be aA'err o nv an 0 T 5.C (On The Spot Change) verify informeriun prior to use Date verified Initials FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4.

OPERATING PROCEDURE 11550.48 CONTROLLED DCCUME HEALTH PHYSICS PROCEDURE HP-48 JANUARY 5 1989

1. 0 Tt t1e: NO. ¹ PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS 2.0 A royal and List of Effective Pa es:

2. 1 ~Arova1:

Change Dated 1/5/89 Reviewed by Plant Nuclear Safety Committee: 89-004 and Approved by Plant Manager - Nuclear: 1/5/89

2. 2 Li st of Effective Pa es:

~Pa e Date ~Pa e Date ~Pa e Date 01/05/89 4 01/05/89 01/05/89 I

01/05/89 5 01/05/89 01/05/89 01/05/89 6 01/05/89 01/05/89 3.0 ~Pur ose:

The Turkey Point Process Control Program (PCP) impl ements requi rements of the Turkey Point 3 and 4 Technical Specifications and provides instructions for the removal of free standing water from liners containing radioactive bead resin, powdex resin, or charcoal.

3.1 Discussion

The PCP contains provisions to assure that dewatering of radioactive bead resin, powdex resin and charcoal results in a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 20 and of the low level radioactive waste disposal site. The Process Control Program includes in addition to this procedure, the following related documents:

3.1.1 Bead Dewatering Procedure for CNSI 14-195 or Smaller Liners; Chem Nuclear Procedure FO-OP-023.

3.1.2 CNSI Dewatering Containers Report Number CNSI-11118-01-P.

3.1.3 Dewatering procedure for the 24-inch diameter pressure demineralizing vessel containing ion-exchange resin CNSI No. FO-OP-004.

3. 1.4 CNSI Test Data, Engineering Project-11475 RTS 1898, 88-2985

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1/5/89 OPERATING PROCEDURE 11550.48, HP-48, PAGE 2 PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS

's I 3.1.5 Turkey Point HN-100 liner dewatering test report and correspondence dated February 4, 1981 3,1.6 Hittman Liner Dewatering Report No. I-843-3 3.1.7 Hittman Process Control Program for dewatering ion-exchange resin and activated charcoal filter media to 1/2 percent drainable liquid.

No. STD-P-04-002 3.1.8 Duratek Corporation Dewatering Test Results completed March 7, 1985.

3.1.9 TFC Nuclear Associates, Inc. NUHIC-1200(BR) Dewatering Procedure 3.1.10 Duratek Corporation Operating Procedure No. OP 3.10 for NuPac High Integrity Containet s.

s 3.1.11 Duratek -Corporation Dewatering Test Results completed September 16, 1985 3.1.12 CNSI Operating Procedure FO-OP-022; Ecodex Precoat/Powdex/Soka-Floc/Diatomaceous Earth Dewatering Procedure

3.2 Authority

'I The authority and responsibility to perform this

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procedure come from 10 10 CFR 61, Turkey Point Plant Units 3 and 4 Technical Specifications, disposal site licenses.

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3.3 Definitions

3.3.1 Dewatering

The process of removing "Free Standing" water from a final disposal package.

3.3.2 "Free Standing Water": Liquid which is no't retai'ned by the waste form.

3.3.3 Process Control Program (PCP): A program which contains the proves ons, based on full scale testing, to assure that dewatering of radioactive bead resin, powdered resin or charcoal results in a waste form with the properties that meet the requirements of 10 CFR 61 (as implemented by 10 CFR 20) and of the low level radioactive waste disposa1 ~site.

4.0 Precautions

4.1 Instructions used for the dewatering 'f liners which establish the conditions that must be met shall be based on full scale testing. This is to provide reasonable assurance that the dewatering will result in volumes of free standing water, at the time of disposal, within the limits of 10 CFR, Part 61 as implemented by 10 CFR 20 and of the low level radioactive waste disposal site.

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1/5/89 OPERATING PROCEDURE 11550.48, HP-48, PAGE 3 PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS DELETED 4.2 Class "B" and "C" radioactive waste (as determined by 10 CFR 61 and 0-HPA-040-Shipping and Receiving Radioactive Material) may be transferred to the disposal site in an approved High Integrity Container (HIC). No other containers may be used without PNSC approval.

4.3 Do not use High Integrity Containers - for radioactive material that could chemically or physically damage or otherwise exceed the allowable limits of the HIC..

4.4 All changes to Turkey Point Plant Process Control Program must be reviewed and approved by the PNSC before they become effective.

4.5 All changes to the Turkey Point Plant Process Control Program must be submitted t6 the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal must contain the following:

4.5.1 Sufficiently detailed information to support the rationale for the change.

4.5.2 A determination that the change did not reduce the overall con ormance of the dewatered waste to existing criteria for stabilized waste ~form.

4.5.3 Documentation of the fact that the change has been reviewed and found acceptable by the PNSC.

4.6 Disposal of radioactive bead resin is limited to the following containers:

4.6.1 CNSI Conical Bottom High Integrity Container Type PL6-80CR 4.6.2 CNSI Conical Bottom High Integrity Container Type PL14-195CR 4.6.3 HN 100 Steel Liner 4.6.4 CNSI 24-inch Diameter Pressure Demineralizer Liner 4.6.5 TFC Nuclear Associates, Inc. High Integrity Container Type NUHIC-1200(BR) 4.6.6 NuPac High Integrity Container EL-210

l I/5/89 OPERATING PROCEDURE 11550.48, HP-48, PAGE 4 PROCESS CONTROL PROGRN FOR DEWATERING RADIOACTIVE WASTE LINERS 4.7 Disposal of charcoal filter media fs limited to the following container:

4.7.1 HN 100 Steel Liner 4.7.2 TFC Nuclear Associates, Inc. High Intergrity Container Type NUHIC-1200(BR)

4. 7. 3 NuPac High-Integrity Container EL-210 4.8 Disposal 'of Condensate Polishing Resin is limited to the foll owing containers: V 4.8.1 CNSI Steel Liner L14-195 BTF with bottom drain 4.8.2 CNSI )teel Liner L14-195 BTFP with Powdex Dewatering Equipment

4. 9 Personnel performing dewatering procedure shoul d be aware that strong oxidizing agents such as nitric acid, when fn contact with organic ion-exchange material and in the presence of air, may produce a slightly degraded resin in an exothermic reaction, up to an explosion. The first indication of an exothermic reaction due to the presence of oxidizing agents is some fuming and a slight rise in temperature on the outside of the container. If this condition is found when dewatering a vessel, the immediate action to be taken is to refill the vessel with'ater. This will

, eliminate one of the ingredients necessary for the reaction (air) and will dissipate the majority of the. heat, returning the temperature of the vessel to ambient. This is a stable condition. Then your immediate supervisor must be notified.

5. 0 Responsibilities:

5.1 It is the responsibility of the Plant Manager to assure that all necessary procedures, equipment and support are provided to properly implement. the PCP.

5.2 It is the responsibility of the Health Physics Supervisor or his designee to assure that all liners will be dewatered in accordance with the PCP.

6. 0

References:

6.1 Turkey Point Units 3 and 4 Technical Specifications No. 3.9.3 6.2 Bead Dewatering Procedure for CNSI 14-195 or Smaller Liners; Chem Nuclear Procedure No. FO-OP-023 6.3 CNSI Dewatering Containers Report No. CNSI-11118-01-P 6.4 Dewatering Procedure for the 24-inch diameter pressure demineralizing vessel containing ion-exchange resin CNSI No. FO-OP-004 6.5 CSNI Test Data, Engineering Project - 11475

I I 1/5/89 OPERATING PROCEDURE 11550.48, HP-48, PAGE 5 PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS 6.6 Turkey Point HN-100 liner dewatering test report and correspondence dated February 4, 1981

6. 7 Hittman Liner Dewatering Report No. I-843-3 6.8 Hittman Process Control Program for dewatering ion-exchange resin and activated charcoal fi 1 ter medi a to 1/2 percent drai nabl e 1 i quid.

No. STD-P-04-002.

6.9 Health Physics Administrative Procedure, 0-HPA-040 "Shipping and Receiving.

Radioactive Material. " '

6. 10 49 CFR

6. 11 10 CFR 61

6. 12 OP-5333. 1 "WDS - Transfering Spent Storage Tank To Shielded Shipping Cask. "

6. 13 Duratek Corporation Dewatering Test Results completed March 7, 1985

6. 14 TFC Nuclear Associates, Inc. NUHIC-1200(BR) Dewatering Procedure

6. 15 Duratek Corporation Operating Procedure NO. OP-3. 10, for NuPac High Intergri ty Containers

6. 16 Duratek Corporation Dewatering Test Results completed September 16, 1985

6. 17 CNSI Operating Procedure FO-OP-022-Ecodex Pr ecoat/Powdex/ Solka-Floc/Diatomaceous Earth Dewatering Procedure

7. 0 Records and Notifications:

7.1 If it is suspected that the free standing water requirements may not have een met for any container shipped to, a disposal site, the Plant Manager and the Health Physics Supervisor shall be notified.

7.2 If the Process Control Procedures have not been followed or free standing water is suspected in the final shipping container in amounts greater than if allowed by regulations, the Radwaste Supervisor shall be notifed.

7.3 Completed copies of the below listed section(s), enclosure(s) and or attachment(s) constitute guality Assurance Records and shall be transmitted to Document Control and be retained for a minimum of 5 years in accordance with guality Assurance records requirements:

7.3. 1 Specification Container Shipping Release Form (HP-72C)

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7.3.2 Powdex Resin Liner Shipping Release Form (HP-72-L)

1/5/89 4 ~ OPERATING PROCEDURE 11550.48, HP-48, PAGE 6 PROCESS'ONTROL PROGRN FOR DEWATERING RADIOACTIVE WASTE LINERS 0 7.3.3 7.3.4 User Checklist Certification Container (HP-117) for High Statement Integrity Container (HP-115) for Disposal of Enviro-Safe High Integrity

7. 3. 5 CNSI Conical Bottom Enviro-Safe High Integrity Container Dewaterfng Completion Record to 1 percent FSW (HP-116) 7.3. 6 CNSI 24-inch Diameter Container Dewatering Record (HP-116. 1)

7. 3. 7 170 ft Liner Dewatering Record (HP-116.2) 7.3.8 NUHIC-120 Dewatering Record (HP-116. 3) 7.3.9 Duratek Dewatering Log (HP-116. 4)

7. 3. 10 Dewatering Completion Record (HP-116. 5) 7.3. 11 Powdex Resin Leak Check Record (HP-116. 6)

8. 0 Instructions:

8. 1 Dewaterin shall be performed in accordance with the applicable vendor proce ure or each liner or high integrity container.

8.2 If the dewatering is not performed in accordance with the vendor procedure the process shall be terminated. The package shall not be shipped for disposal until it is dewatered in accordance with the vendor procedure.

8.3 If the final waste form is found to be unacceptable (freestanding liquid in excess of 0. 5X of the waste volume for. steel liners or 1.0% for high integrity containers) processing and shipping shall be stopped until the procedures and/or dewatering equipment are corrected to prevent recurrance.

8. 4 Dewatering of Chem-Nucl ear Conical Bot tom High Integrity Container s (containing bead type ion-exchange resin) 8.4. 1 Chem Nuclear Conical Bottom High Integrity Containers containing bead type ion-exchange resin shall be dewatered in accordance with Chem Nuclear Systems, Inc. Procedure FO-OP-023, as amended.

8.4.2 Completion of the dewatering procedure shall be documented on Form HP-116, "Bead Dewatering Procedure

" for CNSI 14-195 or Smaller Liners.

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1!'5(89 OPERATING PROCEDURE 11550.48, HP-48, PAGE 7 PROCESS CONTROL PROGRN FOR DEWATERING RADIOACTIVE WASTE LINERS 8.4.3 High Integrity Containers shall be dewatered to <1$ free standing water.

8.5 Dewatering of Chem-Nuclear 24 inch Diameter Pressure Demineralizer Liner.

8. 5. 1 Chem Nuclear 24 inch Diameter Pressure Demineralizer Liners shall be dewatered in accordance with Chem Nuclear Procedure FO-OP-004, as amended.

8. 5.2 Completion of the dewatering procedure shall be documented on Form HP-116. 1 "CNSI 24 inch Diameter Pressure Demineralizer Containing Ion-Exchange Resins Dewatering Completion Record - . 5X, FSM. "

8. 6 Dewatering of Nuclear Packaging EL-210 High Integrity Containers Containing Bead Resins pnd Charcoal Filter Media

8. 6. 1 Dewaterfng of Nuclear Packaging EL-210 High Integrity Containers containing bead resins and charcoal filter media shall be performed in accordance with Duratek Corporation Operating Procedure OP-3. 10, as amended.

8. 6.2 Completion of the dewatering procedure shall be documented- on Form HP-116. 4, "Duratek Dewatering Log. "

8. 7 Dewatering of Chem Nuclear 14-195 BTFP Liners Containing Powdex Resin

8. 7.1 Chem Nuclear 14-195 BTFP Liners containing powdex resin shall be dewatered in accordance with Chem Nuclear Procedure FO-OP-022, as amended.

8. 7.2 Completion of the dewatering procedure shall be documented on Form HP-116. 5 "Dewatering Completion Record."

8.8 Packaging of Powdex Resin in Chem Nuclear 14-195 BTF Steel Liners with Bottom Drains 8.8. 1 Powdex resin to be packaged in Chem Nuclear 14-195 BTF Steel Liners shall be dewatered using the resin press at the condensate polisher ar ea 8.8.2 Health Physics shall monitor the transfer of resin to the burial liner to vert i fy the absence of free standing water.

8.8.3 Upon completion of filling, the liner shall be tilted approximately 10'ith the bottom drain at the low point.

8.8.4 Remove the bottom drain plug. Direct any leakage to an appropriate container.

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1/5/89 OPERATING PROCEDURE 11550.48, HP-48, PAGE 8 PROCESS CONTROL PROGRN FOR DEWATERING RADIOACTIVE WASTE LINERS 8.8. 5 Record the date and time of begfnfng the leak check on Form HP-116.6 "Powder Resin Leak Check Record. "

8.8. 6 Inspect the contafner at least every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for continued leakage. When inspection fndfcates that leakage has stopped, enter the date, time, and total collected volume of liquid on Form HP-116. 6 8.8. 7 Continue the leak check for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following the time noted fn

8. 10. 6. Collect any leakage during this period.

8.8.8 Upon completfon of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> leak check, record the date, time, and volume of liquid collected on Form HP-116.6 If the collected liquid volume fs less than 500 ml, the leak check is complete.

collected lfqufd volume fs greater than 500 ml, repeat 8.9.5 through If the 8.9.g; 8.8. 9 Prepare the liner for shipment by installing the drain plug and lid.

8.9 Dewaterfng of Hfttman HN 100 with bottom drain.

8.9.1 Upon completion of waste processing remove the liner from service.

8.9.2 Set in tipped configuration (Approx. 10'ith bottom drain at low point).

8.9. 3 Connect the dewatering line to the suction side of a positive displacement, air operated dfaphram pump and to the connection on the bottom drain of the Hittman Liner. Remove vent cap cover.

8.9.4 Start the dewatering pump and run at > 2 strokes per second for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Stop the pump after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

8.9.5 Let the liner stand for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.

8.9. 6 Obtain a container to collect discharge of pump.

CAUTION: Mater will be highly radioactive.

8.9. 7 Start the pump and collect discharge for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Before securing the pump, lift the suction hose to remove any trapped water in the line.

8.9.8 If collected water is greater than 500 ml, repeat Steps 8. 7. 5 thru

8. 7. 7 until less than 500 ml is collected.

8.9.9 If collected water is less than 500 ml, proceed to Step 8. 7. 10.

8.9. 10 Remove the dewatering line from the bottom drain and attach the line to the underdrain connection located on the top of the liner.

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T 1/5/89 OPERATING PROCEDURE 11550.48, HP-48, PAGE 9 PROCESS CONTROL PROGRN FOR DEWATERING RADIOACTIVE WASTE LINERS 8.9.11 Obtain a container to collect dfscharge of pump.

8.9.12 Run pump for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> collecting all pump dfscharge. Hefore securing the pump, 1 fne.

lift the suction hose to remove any trapped water fn the 8.9. 13 If collected water is greater than 500 ml, reconnect the suction hose to the bottom drain and repeat all Steps from 8. 7. 5 thru 8. 7. 12.

8.9. 14 If 'collected water fs less than 500 ml, proceed to Step 8.7.15. The final dewatering shall be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of shipping liner for disposal.

8.9. 15 Disconnect the dewatering line and ensure that the plug is secured in the bottom drain.

8.9. 16 Install'he vent cap covers and the top cover on the liner. Secure the liner for shipment.

8. 9. 17 Complete the 170 ft Liner Dewaterfng Record Form HP-116.2.

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