ML20247C525
| ML20247C525 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/31/1988 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17345A684 | List: |
| References | |
| NUDOCS 8905240494 | |
| Download: ML20247C525 (43) | |
Text
, - _ _ . _ - - - - - - - . _ _ _ _ _ _ _ _ _ _ _ - _ _ . -
e s
TURERY POINT PLANT UNITS 3 AND 4 SEMIANNUAL RADIOACTIVE EFFLUENT REIRASE REPOET JULY 1988 THROUGH DECEMBER 1988 1
9 SUBMFITED BY NUCLEAR CHEMurrRY DEPARTMENT TURREYPOurrPLANT FLORIDA POWER AND LIGHT COMPAMY l
1 l
8905240494 890519 PDR ADOCK 05000250
- R PDC RNS/md*Ct:1 l
FLORIDA POWER AND LIGHT COMPANY
' TURREY POINT UNIT 8 3 AND 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JULY 1988 THROUGH DECEMBER 1988 1.0 Reaulatory Limits 1.1 Llauld Effluents ,
a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentrations speelfled in 10CFR20, Appendix B, Table !!, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentention 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 radiometive materials in liquid effluent released to unrestricted areas shall be limited, during any calendar quarter, to s1.5 mrom to the total body and to s5 mrom to any organ, and, during any calendar year, to $3 mrom to the total body and sie mrom to any organ.
1.2 Gassous Effluents a) The dose rate due to radiomotive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the followings I Less than or equal to 500 mrom/yr to the total body and less than or equal to 3000 mrem /yr to the sida due to noble gases and less than or equal to 1500 mrem /yr to any organ due to I-131,1-133, tritium and for all radioactive materials la partleulate 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 gasse released in gaseous affluents shall be limited, during any calendar quarter, to 55 mrad for gamma radiation and s10 mrad for beta radiation and, during any calendar year, to sie mrad for gamma radiation and s20 mrod for beta radiation.
c) The dose per reactor to a member of the publie, due to I-131,1-133, tritium and to partleulates 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 meem to any organ during any calendar year.
O KNMAnd*C1:1 -1 i
07/88 - 12/88 c
2.0 asawimum Permissible centrations The maximum permissible concentrations for liquid and airborne releases are described in Sections 1.1-a and 1.2-a of this report.
3.8 Averase Energy The average energy of fission and activation gases in gaseous effluents is not applicable.
4.8 M - ;=cets --* A=ezimat% of Total mWivity All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Speelfication requirements. The minimum frequency of analysis as required by Regulatory Guide 1.21 was met or exceeded.
4.1 Limaid Effluents Aliquots of representative pre-release samples were either Isotopically analyzed for gamma emitting isotopes on a multichannel analyser, or evaporated and analysed for gross beta-gamma activity in a 2n gas flow proportional counter. , The effleiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopie 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 periodie sampling and analysis were used to conservatively determine if any radiometivity 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 St-89/90 and Fe-55 l 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.
l -
l' RNSAndeCl:1 ,
s 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 froms release of gas decay tanks, the instrument bleedline, containment purges, and sporadle releases incidental to operation of the plant. The techniques employed in determining the radioactivity in airborne releases ares a) Gamma spedtrum analysis for fission and activation gases, b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Se-89/90 determination and groes alpha analysis, c) Absorption of halogen radionuelldes on a charcoal filter and subsequent gamma-spectrum analysis, and d) Analysis of water vapor in a~ gas sample for tritium using liquid scintillation techniques.
All sporadie 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.
i r
e RNS/wdeCt:1 .
f
07/88 - 12/88 4.3 Estimate of Errors a) Sampling Error The error associated with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been conservatively estimated to be collectively less than i 10A b) Analytical Error Our quarterly Q.C. cross-check program involves counting unknown samples provided by an independent external lab. The errors associated with our analysis pf these unknown samples, and reported to us by the independent lab, were used asI the basis for deriving the following analytical error terms.
NuelndeTvos Avernate Error Maximum Error Liquid 13 % 19 %
Gaseous 13 % ,14%
i 1
l 1
1 e
e HNS/md *Cl .1 .
f
07/88 - 12/88 5.0 BATCH RELEASES i 5.1 Llauld E!IlLI Malli l
a) Number of batch releases 2.06 E+02 2.06 E+02 1 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 ytream flow during period of 1.20 E+06 1.20 E+06 GPM release of ef. fluent into a flowing stream 5.2 Gaseous a) Nu~mbe:* of batch releases 8.50 B+00 1.25 E+01 b) Total time period of batch releases 8.85 E+02 1.85 E+0S Minutes 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 1.00 E+00 Minutes e) Minimum time pe~riod for a batch release 1.00 E+00 6.0
- UNPLANNED RELEASES 6.1 Llauld a) Number of releases 0 1 b) Total activity releases 0.00 E+00 2.82 E-01 Curles 6.2 Gananas ~ .
a) Number of releases. 0 0 b) Total activity releases 0.00 E+00 0.00 E+00 Curies 6.3 See attachments (#1) fort a) A description of the event and equipment involved.
b) Cause(s) for the unplanned release.
t nNstmderI:n 1
1 07/88 - 12/88 7.0 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 /> .6 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 1988 THROUGH DECEMBER 1988 UNITS 3 AND 4
~
Age Group: Adult Location Red Barn ]
4 Inhalation -
Dose (mrem)
Bone -. .
8.37 E-07 .
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
' ~
-I~ + --NOBbE GAS-EKPOSURE- --
Gamma Air Dose ~
2.93 E-03 m Rads Beta' Air Dose ' 6.72 ~ E-03 mRads
~
8.0 Offsite Dose Calculitioni M~ariual R'e visions , ,
' ~ ~ ~ '
See A1tachment 4 9.0 Solid Waste and-lcratiated Fuel Shloments_ . . . .
l No irradiated fuel shipments were made from the site. Common solid waste from Turkey Point Units 3-and Owna shipped jointly.. A summation of these shipments is given in Table 6 of'Init report. ~ ~ ' ' ~
~
l 10.0 Process Control Program Revisions l
See Attachment 3 11.0 Special Reports See Attachment 2 KNShnd *Cl .l ,
k-._mm__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - . - . _ _ _ _
o- - - - .
SEMIANNUAL REPORT JULY 1988 THROUGH DECEMIE31988 UNIT 3 TABLE 1 LIQUID EFFI;UENTS - SUMatATIONCF ALL RELEARES
', Units Quarter 3 Quarter 4 A. Flasion and Activation Prodnets ... .,.
- 1. Total Release (not including tritium, gases' Cl 1.75 E-01 6.91' E-02 aloha)
- 2. Average diluted concentration during period pCl/ml 2.29 E-09 1.81 E-10 B. Tritium ' f.-
'~
5.50 E+01
~
- 1. Total Release _,
Cl - ' 1.38 ' E+02 . ,
- 2. Average diluted concentration during period-- pCl/ml 1.86 E-06 5.45 E-07 l C. Dissolved and-Entmined4ases - . -- . - - . . ,
- 1. Total Release Cl 2.09 E-01 6.95 E-02
- 2. Average diluted concentration during. period.- . --. _
pCl/mi 2.73 E-09 6.88 E-10
~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ '~~ ~ ~ ' ' ' -
D. Gross Alpha Radiometivity
- 1. Total Release . _ . . . _ _ . . _ . . . Cl .L12 E-07 <1.53 E-08*
E. Volume of Waste Ratamand (prior to dustion) Liters , ,1.89 E+06 3.55 E+06 F. Volume of Duutlos Water Used DuriWeriod- -- -
~~
" titors 7.85 E+10 1.01 E+11
'MDA Value in pCl/ml . . _. . _ .. ._
Approved by ]M2 I-
_ R .?
Dnte y _p _p -
t RNS/nd*Cl:1 -7*
/
~
SEMYNNUEItBE)lT JULY 1988 THROUGH DECEMBER 1988 UNrr3 TABLE 2
- LIQUID EFFLUENT 8 - SUMMATION OF ALL RELEASES Continuous Mode Batch Mode Units -
Nuelldes Released ;
Ag-110m C1 ----- - -- -
2.39 E-04 1.04 E-04 Co-57 Cl -
- - - - - - - - ---- 1.75 E-06 ----
Co-58 Cl ---- m 2.37 E-03 1.02 E-02 Co-60 C1 -----
1.48 E-01 7.10 E-03 Cr-51 Cl -----
~-
1.19 E-03 1;73 E-03 Cs-134 Cl ----- -- 2.03 E-04 1.23 E-03 Cs-136 Cl ,
- - - - 2.13 E-03 5.15 E-03 Cs-137 Cl
- - - - -- 7.80 E-04 -----
Fe-59 Cl - - - -
- ~~
3.09 E-04 I-131 Cl -----
- -~ - 4.28 E-04 4.58 E-04 I-133 Cl -----
~ ~4.00 E-05 - 2.28 E-05 La-140 Cl ---- -- 1.72 E-05 5.80 E-05 Mn-54 Cl - - - - 8.15 E-03 5.10 E-03 Mo-99 Cl 7.05 E-04 1.82 E-04 Na-24 Cl -- 1.49 E-05 1.47 E-06 Nb-95 C1 - - - - --- 2.91 E-05 4.17 E-05 Ru-103 Cl -- -- -- - 2.96 E-05 Sb-124 Cl ---- 3.97 E-OS 2.30 E-03 Sb-125 C1 -- -- 3.38 E-03 6.15 E-03 ,
Zn-65 Cl -. 4.10 E-04 1.29 E-05 Zr-95 Cl -- -- 4.20 E-05 Ce-139 Cl 1.11 E-08 -----
Ba-139 Cl -- -- 2.17 E-04 4.33 E-05 Sn-117 m Cl ---- 9.90 E-04 1.37 E-05 Sr-90 Cl ---- ---- 5.25 E-05 - - - -
Fe-55 Cl ----- -- -
7.69 E-03 3.02 E-02 Sr-89 Cl - -- -- ---- 1.95 E-04 Unidentified Cl Total for Period Above Cl ----- -- 1.75 E-01 6.91 E-02 7 Approved by JrZ-._1 E Date 2-J 1 -9 4 RNS/nJ*Ct:1 /
SEMIANNUAL REPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 3 TABLE 3 (Continued)
LIQUID EFFLUENTS Liquki Dissolved Gas ..
. Continuous Mode Batch Mode Nucildes Released Units -
Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85 C1 ---
6.81 E-03 3.63 E-03 Kr-85 m C1 2.82 E-04 Xe-131 m Cl ----
3.48 E-03 1.36 E-03 Xe-133 C1 -
1.97 E-01 6.43 E-02 Xe-133 m Cl . 1.19 E -1.24 E-04 Xe-135 Cl .; 1.88 E-04 1.05 E-04 Xe-135 m C1 2.34 E-08 1.38 E-05 Cl Total for Period Above Cl 2.09 E-01 6.95 E-02 LIQUID EFFLUENTS -DOSE 50MMA110N JANUARY 1988 THROUGH DECEMBER 1988
~ ~ ~ ' '
UNFF 3 Age Groups Teenager - -
Loestloos Coollag Canal -
Shorellos Decosition Does(mRemi % of Annual Limit Total Body -8.14 E-03 2.71 E-01 Approved bv M r Ss, Oak.
}
Date J-f-1M I
J itNS/md*CI:t ,
~
SEMTNNUAUREPOiti
. JULY 1988 THROUGH DECEMBES 1988 UNIT 3 TABLE 3 GAS EFFLUEN'IS- SU;2MATIDN OF ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products
- 1. Total Release Cl 5.12 E+02 3.02 E+02
- 2. Average Release Rate for Period pCl/see 6.44 E+01 3.79 E+01 j'
B. Iodines
~ '
- 1. Totallodine-131 Ci 1.17 E-03 5.94 E-04
- 2. Average Release Rate for Period pC1/see 1.47 E-04 7.47 E-05 C. Particulate .. - - . . . . . . . . . . . . , .. -
- 1. Partleulates T - 1/2>B Days Cl 5.12 E-05 5.54 E-05
- 2. Average Release Rate for Period pCl/see 6.44 E-06 6.97 E-06 f
- 3. Gross Alpha Radioactivity Cl 1.87 E-08 < 8.40 E-00*
D. Tritiuse _.._ , . . . . __
~
l
- 1. Total Release Cl 1.42 k+02 1.60 E+00
- 2. Average Release Rate for Period pCl/see.I 1.41 E401 2.01 E-01
- MDA Value in pCl/ml Approved by 1sL v_I '
/
Date y 3 ,,
t i
RNtWadeCl:1 ,
SRMIANNUAL REPORT JULY 1988 THROUGH DECEMLER 1988
- UNIT 3 TABLE 4 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 l Quarter 4
- 1. Flaston Games Ar-41 C1 2.68 E-01 1.05 E-01 1.56 E-03 4.62 E-03 Kr-85 Cl , 5.37 E-01 1.50 E-03 3.13 E-01 1.21 E-01 Kr-85 m C1'~ 5.69 E-02 4.93 E-01 1.15 E-03 Kr-87 Cl 7.25 E-03 1.57 E-06 Er-88 Cl 2.49 E-02 Xe-131m Cl 1.06 E+01 9.95 E-03 4.68 E-01 5.97 E-01 Xe-133 C1 4.59 E+02 2.73 E+02 2.99 E+01 2.15 E+01 Xe-133 m Cl 1.31 E+00 1.65 E-03 1.97 E-01 1.52 E-01 Xe-135 Cl - 1.00 E+01 5.43 E+00 5.84 E-02 1.79 E-01 Unidentified C1 - - -
Total for -- -
Period Above Cl 4.82 E+02 2.79 E+02 2.99 E+01 2.26 E+01
(
~ -
l
- 2. Iodines 1-131 Cl 5.15 E-04 5.10 E-04 I-133 C1 3.79 E-04 7.65 E-05 Br-82 2.78 E-04 7.80 E-04 Total for Cl Period Above 1.17 E-03 5.94 E-04 Approved by lyd - f- -- ' -
Date 1~2*1-19 O
KNs/mdect:1 .
~
TUiti[Ei ~ POINT PLANT SEMIANNUAL REPORT JULY 1988 THR@ UGH DECEMBER 1988 !
)
UNIT 3 TABLE 4 (Continued)
GASEOUS EFFLUEWTS
}
l Continuous Mode Nucildes Released Units Quarter 3 Quarter 4 a
- 3. Partleulates Cr-51 Cl 1.24 E-05
- Mn-54 C1 2.62 E-06 Co-58 f. Cl 5.00 E-07 1.84 E-05 Co-60 ;; Cl 1.42 E-04 1.14 E-05 I-131 Cl 1.74 E-06 3.51 E-07 Cs-134 Cl 8.10 E-06 Cs-136 Cl 3.48 E-06 Cs-137 C1 2.03 E-05 1.28 E-05 Ba-140 Cl 1.30 E-05 Sr-89 Cl 6.50 E-11 Cl l
Unidentified Cl Total for Cl Period Above 5.12 E-05 5.54 E-05 Approved by h A1=_
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- SEMIANNUAL REPORT JULY 1983 THROUGH DECEMBER 1933 UNrf 4 TABLE 1 LIQUID EFFLUENTS - SUMMATION OF AIL RELEASES Units Quarter 3 Quarter 4 A. Flaston and Activation Produets
- 1. Total Release (not including tritium, gases, Cl 1.75 E-01 6.91 E-02 alDha)
- 2. Average diluted concentration during period pCi/mi 2.29 E-09 1.81 E-10 l
B. Tritium -
1:
- 1. Total Release -
Cl 1.38 E+02 5.50 E+01
- 2. Average diluted concentration during period -
pCl/mi 1.80 E-06 5.45 E-07 C. Dissolved and Entrained Gases
- 1. Total Release ,
C1 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 Radiometivity
- 1. Total Release -- - ~
Cl 1.12 E <1.53 E-08*
L Volume of Waste,Relenest(prior to.dumtion) _ . Liters 1.69 E+08 3.55 E+06 F. Volume of Dilution Water Used During Period ~ ~
Liters 7.65 E+10 1.01 E+11
'MDA Value in pCl/mi - - - .
- -Approved by - J# -A_ .sp,
/
Date y ,y 3 g , ,
f RNShnd*Cl:1 .
_ _ - - - - _ - -__-------_------------_---_----_-.u____-
O CLOL.Ot3 0 UNO LJ C'!.p.XA> U SEMIANNUAL REPORT
. JULY 1988 THROUGH DECEMBER 1988 UNrt' 4 TABLE 2 LIQUID EFFLUENTS Continuous Mode Batch Mode Nudides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Ag-110 m Cl - -- - - - -
2.39 E-04 1.04 E-04 Co-57 Cl ,,
1.75 E-06 -----
Co-58 C1 ----- - - - -
2.37 E-03 1.02 E-02 Co-60 Cl. ----- ----- 1.48 E-01 7.10 E-03 Cc-51 Cl ----- -----
1.19 E-03 1.73 E-03 Cs-134 Cl ----- ---- 2.03 E-04 1.23 E-03 Cs-136 Cl ,
----- 2.13 E-03 5.15 E-03 Cs-137 Cl .,.
--- 7.80 E-04 -----
Fe-59 Cl -----
3.09 E-04 1-131 Cl ---- -- -
4.28 E-04 4.58 E-04 I-133 Cl -- - -- 4.00 E-05 2.28 E-05 La-140 Cl -- --
1.72 E-05 5.80 E-05 Mn-54 Cl - - - - --- 8.15 E-03 5.10 E-03 Mo-99 Cl ---- --
7.05 E-06 1.82 E-04 Na-24 C1 - - - - -- 1.49 E-05 1.47 E-06 Nb-95 Cl ----- 2.91 E-05 4.17 E-05 Ru-103 Cl ----- --- 2.96 E-05 Sb-124 .
C1 -- -- 3.97 E-06 2.30 E-03 Sb-125 Cl ---- ---- 3.38 E-03 6.15 E-03 Zn-65 C1 ---- -- 4.10 E-06 1.29 E-05 Zr-95 Cl -- - -- ~~ 4.20 E-05 Ce-139 Cl -- --
1.11 E-06 -----
^
Ba-139 C1 - - - - --- 2.17 E-04 4.33 E-05 Sn-117m Cl --- -- 9.90 E-06 1.37 E-05 Sr-90 Cl --- -- - 5.25 E-05 -----
Fe-55 C1 - - - - -- 7.69 E-03 3.02 E-02 Sr-89 Cl ----- ---- ----- 1.95 E-04 Unidentified Cl Total for Period Above Cl ---- --- 1.75 E-01 6.91 E-02 Approved by J.zz r L S2_ -
Date .2-2y-pq KNS/md*CI:n t
,a
. TUILKEI POINT PLINT SEMIANNUAL REPORT JULY 1988 TIIROUGli DECEMBER 1988 UNIT 4 TABLE 2 (Centinued)
LIQUID EFFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 ;
K r-85 C1 ----- -----
6.81 E-03 3.63 E-d3 K r-85 m Ci ----- -----
2.82 E-04 Xe-131 m 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 C1 -----
1.88 E-04 1.05 E-04 Xe-135 m C1 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 TIIROUGli DECEMBER 1988
. UNIT 4 -
Age Group: Teenager Location: Cooling Canal Shoreline Deposition Dose (m Rem) % of Annual Limit Total Body 8.14 - E-03 2.71- E-01 l
l -
l Approved by )MM -
L 7 . ..
Date ?'JO-f4 V
l l
l 1
l itNS/md
- Cl:1 i
~ _ - - -
SEMIANNUAL REPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 3 GAS EFFLUENTS - SUMMATIDN OF ALL RELEASES Units l Quarter 3 l Quarter 4 A. Flasion end Activation Products
- 1. Total Release Cl 5.73 E+02 2.84 E+01
- 2. Average Release Rate for Period pCl/see 7.21 E+01 3.57 E+01 B. Iodines ._
~ ' '
- 1. Totallodine-131 Cl 1.17 E-03 5.94 E-04 l
- 2. Average Release Rate.for Period. . .. pCl/see 1.47 E-04 7.47 E-05
~
C. Partleulates
~~~
- 1. Particulate T - 1/2>8' Days" ~ CI' 5.12 E-05 5.54 E-05 J
- 2. Average Release Rate for Period pCl/see 6.44 E-08 6.97 E-06
- 3. Gross Alpha Radioactivity . . . Cl 1.87 E-08 < 8.40 E-09*
~
D. Tritium .
- 1. Totrl Release Cl 1.12 B+02 1.60 E+00
- 2. Average Release Rate for Period pCl/see 1.41 E+01 2.01 E-01
- MDA Value in pCl/ml Approved by 1. A_'_
Date 9 _p4 l
wwm$ct:t B00EEG8 &Qo06] A 662M)o SEM1 ANNUAL REPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TATLE 4
. GASEOUS EFFLUENTS
. . Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Plaston Gases ~
Ar-41 Cl 2.66 E-01 1.05 E-01 3.96 E-01 ----
Kr-85 Cl 5.37 E-01 1.50 E-03 3.13 E-01 1.12 E-01 Kr-85 m Cl 5.69 E-02 4.93 E-01 4.20 E-02 Kr-87 Cl/ 7.25 E-03 1.57 E-06 Kr-88 Cl 2.49 E-02 3.54 E-02 ,
Xe-131 m Cl 1.06 E+01 9.95 E-03 1.29 E+00 2.47 E-01 Xe-133 -
Cl 4.59 E+02 2.73 E+02 8.71 E+01 4.19 E+00 Xe-133 m Cl 1.31 E+00 1.65 E-03 7.80 E-01 4.87 E-02 Xe-135 Cl 1.00 E+01 5.43 E+00 9.37 E-01 ' 6.34. E-02 Unidentified -
Cl __
i Total for - -.
Period Above Cl 4.82 E+02 2.79 E+02 9.09 E+01 4.66 E+00
- 2. Iodines 1-131 Cl 5.15 E-04 5.10 E-04 -
I-133 Cl 3.79 E-04 7.65 E-05 ----
Br-82 Cl 2.78 E-04 7.80 E-06 --
Total for -- -
Period Above Cl 1.17 E-03 5.94 E-04 Approved by J A _
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Date S - 2 3 -Pt O
KNS/md C1:1
_ _ ~- ---__ __
TURKEY POINT PLANT SEMIANNUAL REPORT
- ' JULY 1988 THROUGH DECEMBER 1988
- UNIT 4 TABLE 4 (Continued)
GASBOUS EFFLUENTS Continuous Mode Nuelldes Released . Units Quarter 3 Quarter 4
- 3. Partleulates Cr-51 Cl 1.24 'E-05 Mn-54 C1 2.82 E-06 -
Co-58 / Cl 5.00 E-07 1.84 E-05 Co-60
,- Cl 1.42 E-04 1.14 E-05 i
1-131 Cl 1.74 E-04 3.51 E-07 Cs-134 Cl 8.10 E-06 Cs-136 C1 3.48 E-06 Cs-137 C1 2.03 E-05 1.28 E-05 . ,
Ba-140 Cl 1.30 E-05 Sr-80 Cl 6.50 E-11 Cl Cl Cl Cl Cl Unidentified Cl Total for Period Above Cl 5.12 E-05 5.54 E-05 Approved by ler 27 f-Date m^-SY-#4 -
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SEMIAlgluAL REPORT JULY 1988 THROUGH DECEMER 1988 UNITS 3 AND 4 TABLE 6 l SOLID WASTE AND IRRADIATED FUEL SHIPENTS l
1 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL
- 1. TYPE OF WASTE UNIT 6 M0 PERIOD % ERR l'
- a. Spent resin, filter, sludge m8 2.36 EO evaporator bot, toms, etc. C1 1.49 E2 20
- b. Dry compressab1p waste m3 3.8 El (NOTE 1) C1 4.34 E-1
- c. Irradiated components, m8 0.00 E-0 control rods, etc. Ci 0.00 E-0 20
- d. Other non-compressible m8 1.81 El metal waste (NOTE 2) C1 2.31 E-1 2d
- 2. ESTIMTE OF MAJOR NUCLIDE CGF0SITI(Ni BY TYPE OF WASTE
Co-58 % 2 Sb-125 % 1 Mn-54 5 1
Ni-63 % 3 MN-54 % ,
1 0
- 21 -
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- 3. SOLID IdASTE DISPOSITI0lt No. of Shipments Mode of Transporatfon Destination 1 Sole use truck Barnwell, SC 10 (NOTE 3) Sole use truck Oak Ridge, TN IRRADIATED FUEL SHIPENTS NONE .
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FLORIDA POWER & LIGHT CO WANY TURREY POINT UNIT N05. 3 8 4 TA8tE 6 SEMI-AlWlUAL REPORT JULY 1988 THROUGH DECE!EER 1988
- NOTE 1: Dry Compressible Waste Volume indicates volume shipped to burial site following volume reduction by a waste processing facility.
Volume ghipped to the waste processing facility was 2.71 E2 m NOTE 2: Other ' noncompressable metal waste indicates volume shipped to burial site following decontamination and volume reduction by a waste processing facility. Volume shipped to the waste processing facility was 7.25 El m s'
NOTE 3: Material transported to Oak Ridge. Tennessee, was consigned to licensed Drocessing 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 radionuclides composition of solid waste shipped from the Turkey Point Units 3 & 4 are detemined using a combination of qualitative and quantitive techniques.
In general , the Turkey Point Plant follows the gutdelines ,
outlined in the Low Level Waste Licensing Branch Technical j
Position (BTP) on Radioactive Waste Classification (5/11/83) for these determinations.
The most frequently used techniques for determining the total curie quantity in a package are the dose to curia methods and the (concentration) x (Volume or Mass) calculations. Where appropriate, engineering type activation' analyses may be applied. I 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 l 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 l 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 i concentration of the nuclide listed in Table 1 or .01 times l the smallest concentration of that nuclide listed in Table 2 of 10CFR61.
1 24 ,
1 b
i NOTE 6: " Type of Waste" is generally specified as described in NUREG 0782, Draft Environment Impact Statement on 10CFR61 " Licensing Requirements for Land Disposal of Radioactive Waste".
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 3,168 gallons released yleids a total of 2.819 E-01 Cl being discharged. A portion of this total was released to the canal system via the RCA storm drains while the remainder was elskned up under the direction of the Health Physics Department. ..
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ ]
ATTACHMENT 2 I SPECIAL REPORTS l
i 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 ensum compliance with Technical Specification 3.9.2.d.
On December 5,1988 the grab sample valves failed the leakrate test and were declared inoperabl/. With these valves out of service it was determined that representative samplin'g 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 whleh had fa!!ed 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 RNWmd*Cl:1
FLORIDA P0ldER & LIGfT C0rANY TURKEY POINT PUWT
- SEMIAlpluAL REPORT JULY 1988 THROUGf DECEMBER 1988 UNITS 3 AND 4 ATTACMENT 3 Sumary of the Revision to Florida Power & Light Company Turkey Point Units 3 and 4 Operating Procedure 11550.48, Process and Control Program for Dewatering Radioactive Waste Liners.
Page 1 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. ~
L This change does riot affect confor1 nance of the dewatered waste to existing criteria.
Page 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 procedure.
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 gramatical enhancement only. No substantive i change has been made to the definition.
This change does not affect conferinance of the dewatered waste to existing criteria.
Page 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 i
make the scope of this precautionary statement compatible with that of this procedure.
This change does not affect confortnance of the dewatered waste l to existing criteria.
A3-1 '
l -
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. i 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.
Page 5 Section 7.1 has been revised for gramatical 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 "Radweste Supervisor". This change in notification requirement has been made coincident with the creation of the Radweste 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.
Paes 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.
RKR/eb/MTD/045/1 A3-2 9
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- - - . - _ - . _ - _ _ ~ _ _ _ . _ .
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, FLORIDA POWER AND LIGHT CG4PANY TURKEY POINT UNITS 3 AW 4 OPERATING PROCEDURE 11550.48 HEALTH PHYSICS PROCEDURE HP-48 NED DOCUMENT JANUARY 5. 1989
- {
NO. O
- 1. 0 Title _:
PROCESS CONTROL PROGRM FOR DEWATERING RADI0 ACTIVE WASTE LINERS
- 2. 0 Approval and List of Effective Pages:
2.1 Approval
Change Dated 1/5/89 Reviewed by Plant Nuclear Safety Committee: 89-004 i:
and Approved by Plant Manager - Nuclear: 1/5/89
- 2. 2 List of Effective Pages:
Page Date _Page Date ,P 3 Date 1 01/05/89 4 01/05/89 7 '01/05/89 2 01/05/89 5 01/05/89 8 .
01/05/89 3 01/05/89 6 01/05/89 9 01/05/89
- 3. 0
Purpose:
. The Turkey Point Process Control Program (PCP) implements requirements 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 Ofscussion
The PCP contains provisions to assure that dowatering 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 Progras includes in addition to this procedure, the following related documents:
r '
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 fon-exchange resin CNSI No. F0-0P-004.
3.1.4 CNSI Test Data, Engineering Pro,fect-11475 k.- ATS 1898, 88-2985 i
/m .
_L_______-________-_-___.
~
. PROCESS C0sT'iiON0GRAAldR DEW TER}NG"RADI0ldTIVE WISTE LINERS 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 l
3.1.7 Hittman Process Control Program for dewatering ion-exchange resin and 4 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 TFCNuclearAssociates,Inc.NUNIC-1200(8R)DewateringProcedure 3.1.10 Duratek Corporation Operating Procedure No. OP 3.10 for NuPac High Integr,ity Containers.
3.1.11 Durat'ek; Corporation Dewatering Test Results completed September 16, 1985 3.1.12 CNSI Operating Procedure F0-0P-022; Ecodex Precoat/Powdex/Soka-Floc / Diatomaceous Earth Dewatering Procedure
3.2 Authority
l The authority and responsibility to perform this procedure come from 10 un zu, 10 CFR 61 Turkey Point Plant Units 3 and 4 Technical Specifications, and disposal site licenses. l
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 not rdtai~ned by the waste form.
3.3.3 l Process Control Program (PCP): A program which contains the provisions, based on ful' 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 disposal site.
4.0 Precautions
4.1 Instructions used for the dowatering; of 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.
- f. ;
~
. PROCESS C0iTR60RdGR DDR DEski'iRlNG" RADIO 5&T}VE WISTE LINERS :
-b- DELETED 4.2 class '8" and "C" radioactive waste (as determined by 10 CFR 61 and 0-NP/
040-Shipping and Receiving Radioactive Materfal) may be transferred to tti disposal site in an approved High Integrity Container (NIC). No othe containers may be used without PNSC approval.
4.3 Do not use High Integrity Containers.for radioactive material that coul chemically or physically damage or otherwise exceed the allowable *11mits o the HIC.
4.4 All changes to Turkey Point Plant Process Control Program must be reviewe.
and approved by the PNSC before they become effective.
4.5 All changes to the Turkey Point Plant Process Control' Program must b submitted }4i the NRC in the Semiannual Radioactive Effluent Release Repor-l for the period in which the change (s) was made. This submittal must contali the followingi 4.5.1 Sufficiently detailed infomation to support- the rationale for ' the change.
4.5.2'l A determination that the change did not reduce the overal; conformance of the dewatered waste to existing . criteria for stabilized waste fom. l
[ i s .-
4.5.3 Documentation of the fact that the change has been reviewed and founc acceptable by the PNSC.
4.6 Disposal of radioactive bead resin is limited to the following containers:
4.6.1 CNSI Conical Botton High Integrity Container Type PL6-80CR 4.6.2 CNSI Conical Botton High Integrity Container 'Typei PL14-195CR 4.6.3 HN 100 Steel Liner .
4.6.4 CNSI 24-inch Diameter Pressure Dominera11rer Liner 4.6.5 TFC Nuclear Associates, Inc. High Integrity Container Type NllHIC-
[a.,} 1200(BR) 4.6.6 NuPac High Integrity Container EL-210 l
. OPERATING PROCEDURE 11550.48, HP-48, PAGE 4 7 -
, PROCESS CONTROL PROGRAM FOR DEWATERING RADI0 ACTIVE WASTE LINERS-4.7 Disposal of charcoal ffiter media is Ifatted to the following container:
- 4. 7.1 HN 100 Steel Lfner 4.7.2 TFC Nuclear Associates, Inc. Nfgh Intergrity Container Type NUNIC '
1200(BR)
- 4. 7. 3 NuPac High-Integrity Container EL-210 4.8 Disposal of Condensate Polishing Resin is limited to the following containers:
4.8.1 CNSI Steel Liner L14-195 BTF with bottom drain 4.8.2 CNSI fteel 1.tner L14-195 BTFP with Powdex Dewatering Equipment
- 4. 9 Personnel perfoming dowatering procedure should be aware that strong oxidizing agents such as nitric acid, when in contact with organic fon-exchange materiel and in the presence of afr, may produce a slightly I
degraded resic. ;n an exothermic reaction, up to an explosion. The first indication of an exothemic 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 famediate action to be taken is to refill the vessel with' water. This will eliminate one of the ingredients necessary for the reaction (af r) and will dissipate the majority of the heat, returning the temperature of the vessel l -
to ambient. This is a stable condition. Then your famedf ate 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 Phystes Supervisor or his designee to l assure that all liners will be dewatered in accordance with the PCP.
- 6. 0
References:
( 6.1 Turkey Point Units 3 and
- Technical Specifications No. 3.9.3
- 6. 2 Bead Dewatering Procedure for CNSI 14-195 or Smaller Liners; Chem Nuclear Procedure No.'F0-0P-023
- 6. 3 CNSI Dewatering Containers Report No. CNSI-11118-01-P
- 6. 4 Dewatering Procedure for the 24-inch diaseter pressure demineralizing vessel containing ton-exchange resin CNSI No. F0-0P-004
- 6. 5 CSNI Test Data, Engineering Project - 11475 l ,
0 l
i
. . OPERATING PROCEDURE 11550.48, HP-48, PAGE 5
. PROCESS CONTROL PROGRAM FOR DEWATERING RADI0 ACTIVE WASTE LINERS
- 6. 6 Turkey Potat HN-100 Ifner dowatering test report and correspondence' dated '
February 4,1981
- 6. 7 Hf ttman Liner Dewatering Report No. I-843-3 e
6.8 Hittman Process Control Program for dewatering fon-exchange resin ' and activated charcoal filter media to 1/2 percent drainable Ifquid.
No. STD-P-04-002.
- 6. 9 Health Physics Administrative Procedure, 0-NPA-040 " Shipping and Receiving '
Radioactive Material.'
6.10 49 CFR 6.11 10 CFR 61 -
f 6.12 OP-5333.1 "WDS - Transferring Spent Storage Tank To Shfelded Shfpping C'ask."
p 6.13 Duratek Corporation Dewatering Test Results completed March 7,1985 6.14 TFC Nuclear Associates, Inc. NUNIC-1200(8R) Dewatering Procedure
'6.15 Duratek Corporation ' Operating Procedure NO. OP-3.10, for NuPac Hfgh Intergrity Containers 6.16. Duratak Corporation Dewatering. Test Results completed September 16, 1985 6.17 CNSI Operating Procedure F0-0P-022-Ecodex Precoat/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
, been met for a container shipped to a disposal site, the Plant Manager and l l
the Health Phys es Supervisor shall be notified.
- 7. 2 If the Process Control Procedures have not been followed or if' free standing water is suspected in the final shipping container in amounts greater than allowed by regulations, the Radweste Supervisor shall be notifed. l
- 7. 3 Completed copies of the below listed section(s), enclosure (s) and or attachment (s) constitute Quality Assurance Records and shall be transmitted to Docusant Control and be retained for a minimum of 5 years in accordance with Qvality Assurance records requirements:
7.3.1 Specification Container Shipping Release Fom (HP-72C) 7.3.2 Powdex Resin Liner Shipping Release Form (HP-72-L)
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. OPERATING PROCEDURE 11550.48, HP-48, ' PAGE 6 -
,' " e
- PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS e 7. 3. 3 User Checklist for HIgh Integrity Container (HP-115) 7.3.4 Certification. Statement for Of sposal of Enviro-Safe High Integrf t).
Container (HP-117)
- 7. 3. 5 CNSI Conical Botton Enviro-Safe High Inte Completion Record to 1 percent FSW (HP-116)grity Container Dew
- 7. 3. 6 CNSI 24-inch Diameter Container Dewatering Record (HP-116.1)
- 7. 3. 7 170 ft3 Liner Dewatering Record (HP-116.2) 7.3.8 NUNIC-120 Dewatering Record (HP-116.3) 7.3.9 Durate'k Dewatering Log (HP-116.4) 7.3.10 DewaterkagCompletionRecord(HP-116.5)
~
7.3.11 Powdex Rarin Leak Check Record (HP-116.6)
- 8. 0 Instructions:
8.1 l Dewatering'shall be performed in accordance with the applicable vendor procacure for each liner or h1gh 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 a
disposal until it is dowatered in accordance with the vendor procedure.-
8.3 If the final waste form is found to be unacceptable (freestanding ifquid in excess of 0.5% of the waste volume . for steel if ners or 1.0% for high integrity containers) ' processing and shipping shall be stopped . untfl the procedures and/or dowatering equipment are ' cor*r ected to pre' vent-recurrance. l 8.4 Dewatering of Cham-Nuclear Conical Botton High Integrity Containers (containing bead type ton-exchange resin) 8.4.1 Chee Nuclear Conical Botton High Integrity Containers containing bead type fon-exchang resin shall be dewatere:f in accordance with Chem o Nuclear Systems, inc. Procedure F0-0P-023, as amended.
8.4.2 Completion of the dewatering procedure shall be documented on Form i l HP-116 " Bead Dewatering Procedure for CNS!14-195 or Smaller i
Liners."
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1/5/89 OPERATING PROCEDURE 11550.48, HP-48, PAGE 7 o PROCESS CONTROL PROGRAM FOR DEWATERING RADI0 ACTIVE WASTE LINERS 8.4.3 High Integrity Containers shall be dewatered to (11 free standing water.
8.5 Dewatering of Chan-Nuclear 24 inch Diameter Pressure Deaf neralizer Liner.
8.5.1 Chem Nuclear 24 inch Diameter Pressure Domineralizer Liners shall be!
l dewatered in accordance wf th Chen Nuclear Procedure FO-OP-004, as l
amended.
- 8. 5. 2 Completion of the dewatering procedure shall be documented on Form HP-116.1 "CNSI 24 inch Diameter Pressure Domineralizer Containing .
Ion-Exchange Resins Dewatering Completion Record
.5% FSW."
8.6 Dewatering of Nuclear Packaging EL-210 Nfgh Integrity Containers Containing Bead Resins And Charcoal Filter Medta 8.6.1 Dewatering of Nuclear Packaging EL-210 Hf gh Integrity Containers containing bead resins and charcoal filter media shall be perfonned 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 Cham Nuclear 14-195 BTFP Liners Containing Powdex Resin
- 8. 7.1 Chen Nuclear 14-195 8TFP Liners containing powdex resin shall be dewatered in accordance with Chen Nuclear Procedure FO-0P-022, as amended.
- 8. 7. 2 Completion of the dewatering procedure shall be documented on Form HP-116.5 "Dowatering Complet1 on 'acord."
8.8 Packaging of Powdex Resin in Chen Nuclear 14-195 STF Steel Lin'ers with Botton Orains 8.8.1 Powdex resin to be packaged in Chee Nuclear 14-195 BTF Steel Liners shall be dewatered using the resin press at the condensate polisher area f 8.8.2 Health Physics shall monitor the transfer of resin to the burial Ifner to vertify the absence of free standing water.
8.8.3 Upon completion of filling, the liner shall be tilted approximately i 10' with the bottom drain at the low point.
l l 8.8.4 Remove the bottom drain plug. Of ract any leakage to an approprf ate l container.
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PROCE$$ C0liTl000iOGRFidit bEWkTERING"RA010idTIfWh5TE LINERS 8.8.5 Record the date and time'of begining the leak check on Fors HP-11@
" Powder Resin Leak Check Record."
8.8. 6 Ins met the container at least every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for continuc leatage. Wien inspection indicates that leakage has stopped, entC the date, time, and total collected volume of liquid on Form HP-116.I L
8.8.7 Continue the leak check f tr 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following the t.'me noted
- 0 8.10.6. Collect any leakage during this period.
8.8.8 Upon completion 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, aa volume of liquid collected on Form HP-116.6 If the collected liquS volume is less than 500 al. the leak check is complete. . If tb collected liquid volume is greater than 500 al, repeat 8.9.5 throug
- 8. 9 4,;
8.8.9 prepare'the Ifner for shipment by installing the drain plug and lid.
l 8.9 Dewatering of Hittman HN 100 with bottom drain.
l 8.9.1 Upon completion of waste processing remove the Ifner from service.
8.9.2 Set in tipped coni'guration (Approx. 10* with bottom drain at 1s point).
g--- 8.9.3 Connect the dowatering Ifne to the suction side of a positiv(
displacement, air operated diaphram pump and to the connection on th:
I 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 2(
hours. 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: Water 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
,N the pump, lift the suction hose to remove any trapped water in thc s ,, . line.
8.9.8 If collected water is greater than 500 al, repeat Steps 8.7.5 thR 8.7.7 until less than 500 m1 is collected.
8.9.9 If collected water is less than 500 al, proceed to Step 8. 7.10.
8.9.10 Remove the dewatering ifne from the bottom drain and attach the linc to the underdrain connection located on the top of the liner.
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4 4 s e em eeeep e en ep esp eg>9 4ese ee de e e we *
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. OPERATING PROCEDURE 11550048, HP-48, PAGE 9 PROCESS CONTROL PROGRAM FOR DEWATERING RADI0 ACTIVE WASTE LINERS 8.9.11 Obtain a container to collect dischar9e 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 discharge. Before securing the line.puep, lift the suction hose to remove arty trapped water in the 8.9.13 If collected water is greater than 500 al, 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 is less than 500 m1, 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~ dowatering line and ensure that the plug is secured in theppttomdrain.
8.9.16 Install"the vent cap covers and the top cover on the liner. Secure i the Ifner for shipment.
3 8.9.17 Complete the 170 ft Liner Dewatering Record Fors HP-116.2.
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, s ATTACHMENT 4 1
On August 10, 1988 the Offsite Dose Calculation Manual was revised to include requirements for an annual review. This periodic review is intended to meet the requirements of Section 6.8.2 of the Turkey Point Technical Specifications. No changes to the calculational methods contained in the Offsite Dose Calculation Manual were instituted during this period.
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, YOR GASEOVS ANIiLIQUID EFFLUENT 7 LO- Introduction 1 1.1 ODCM Review and Approval 1 1.1.1 Responsibility for Review' 1 1.1.2 Documentation of Reviews la 1.1.3 Institution of Changes la 1.1.4 Submittal of Changes . la 2.0 Liquid Effluent 2 2.1 Itadioactivity Concentration In Liquid Waste 2 2.2 Radioactivity Concentration in Water at the Restricted 2 Area Boundary 2.2.1 Aqueous Concentration 2 2.2.2 Batch Release > ,, , y 3 7
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- n *~r 2.2.3 Continuous Release 3M j 4 2.3 ' Cumulative Dose Method of Establishing Alarm and Trip Setpoints ff f@
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2.4 2.4.1 Setpoint for a Batch Release '
7 2.4.2 Setpoint for a Continuous Release T._ ,
7 2.5 Projected Dose .
5 8 Figure 2.1 Liquid Effluent System 9 3.0 Gaseous Effluent 10 3.1 Introduction 10 3.2 Radioactivity in Gaseous Effluent f 10 f
3.3 Dose Rate Due to Gaseous Effluent f}
$j 11 3.3.1 Total Body Dose Rate Qi 12 3.3.2 Skin Dose Rate i h! 12 3.3.3 H-3,1-131,1-133, and Particulate Dose Rate ll M '
13 3.4 Dose - Noble Gases 14 3.4.1 Noble Gas Gamma Radiation Dose 15 3.4.2 Noble Gas Beta Radiation Dose 16 3.5 Dose Due to lodine, Tritium, and Particulate in Gaseous Effluents 17 3.5.1 Determining the Quentity of Iodine, Teltium and Particulate 17 j 3.5.2 Calculating the Dose Due to lodine, Tritium and Particulate 18 3.6 Effluent Noble Gas Monitor Alarm Setpoint 21 3.6.1 Se'. point Based on Dose Rate 22 i 3.6.2 Setpoint Based on Concentration 23 3.7 Project Dose for Gaseous Effluents 24 Figure 3.1 Gaseous Effluent Systems 25 !
Figure 3.2 Locations at Which Doses Due to Airborne Effluents 26 from the Turkey Point Plant are Calculated A4-2
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i ATTACHMENT 4
, OFFSITE DOSE CALCULATION MANUAL FOR GASEOUS AND LIQUID EFFLUENT 4
1 1.0 Introduction 1 This Manual describes ac,ceptable methods of calculating radioactivity concentrations in the environment and the potential resultant doses
- offsite** that are associated with liquid and gasecus effluents from the Turkey Point Nuclear Plant. The radioactivity concentrations and dose estimates are used to demonstrate compliance with Technical Specifications required by 10 CPR 50.36. The methodology stated in this Manual is acceptable for use in demonstrating operational' compliance with 10 CFR 20.106,10 CFR 50 Appendix I, and 40 CFR 190. Only the dose attributable to the Turkey Point Units 3 and 4 is considered in demonstrating compliance with 40 CFR 190 since no other nuclear facility exists within 50 miles of the Plant.
Monthly calculations are made to guide the management of station effluents and to verify that potential radioactivity concentrations and doses offsite satisfy the Technical Specifications. The receptor is described such that the exposure of any
>p>3 resident near the plant is unlikely to be underestimated. Even more conservative conditions (e.g. location and/or exposure pathways expected to yield higher computer
}-4 } viO I: og o doses) than appropriate for the maximally exposed person may be assumed when calculating the concentration or dose.
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r- r-Monthly calculations made to assure that air dose and dose commitment specifications are not exceeded are based on atmospheric dispersion and deposition of r/
gaseous effluents derived from reference meteorological conditions.*** Calculations made to assess the radioactive noble gas does to air are based on the location offsite y
3 that could be occupied by a person where the maximu n air dose is expected.
Calculations of dose committed from radioactive releases over extended time (3 and 12 months) are also made for the purpose of verifying compliance with regulatory limits on offsite dose. For these calculations the receptor is selected on the basis of the combination of applicable exposure pathways identified in the land use census and g g the maximum ground level X/Q at a residence, or on the basis of more conservative
> > conditions such that the dose to any resident near the Plant is unlikely to be M M underestimated.
t J ODCM Review and Aporoval h 1.1 1.1.1 Responsibility for._Revley l
The Chemistry Department Supervisor or his designee shall perform a review of the ODCM annually.
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- Dose is commonly used to mean personal dose equivalent commitment.
- Offsite means outside the exclusion area.
- Reference meteorological conditions are annual averaged conditions during years 1976
, and 1977.
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ATTACHMENT 4 I 4
OFFSITE DOSE CALCULATION MANUAL
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FOR GASEOUS AND LIQUID EFFLUENT 1.1.2 Documentation of Reviewal Following the performance of the annual review required by Section i 1.1.1, the individual performing the review shall submit a report for PNSC approval. This report should contain the following information a
- 1. A copy o! the ODCM with any requested changes.
- 2. Information necessary to support the rationale for the requested changes.
- 3. A determination that the requested changes will not reduce the -
2 accuracy or reliability of dose calculations or setpoint g;M %3 3
5 E: o 38 determinations.
fh f 1.1.3 Institution of Chanrad Changes to the ODCM shall become effective upon review and acceptance by the PNSC.
g [ 1.1.4 Submittal of Changend
{ Changes to the ODCM and any supporting documentation shall be submitted to the NRC in the Semi-Annual Radioactive Effluent Release Report for the period in which the changes were made effective.
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