ML17215A789: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(One intermediate revision by the same user not shown)
Line 2: Line 2:
| number = ML17215A789
| number = ML17215A789
| issue date = 12/31/1984
| issue date = 12/31/1984
| title = Combined Semiannual Radioactive Effluent Release Rept, Jul-Dec 1984.
| title = Combined Semiannual Radioactive Effluent Release Rept, Jul-Dec 1984
| author name =  
| author name =  
| author affiliation = FLORIDA POWER & LIGHT CO.
| author affiliation = FLORIDA POWER & LIGHT CO.
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:r'e                         , REGULATORY 1NFORNATION DISTRIBUTION SYSTEM                       g fP ~tt ~.
{{#Wiki_filter:r'e i ~
i~
mr
mr ACCESSION NOP:850320057d                 DuCeDATE:     84/12/31       NOTARIZED:     NO FACI<:50-335 St Lucie~lantF Uni t p F orida
, REGULATORY 1NFORNATION DISTRIBUTION SYSTEM gfP ~tt ~.
                              ~                            1   1          Power   5   Light Co,         05000335 50-589 St. LucJe Plant-,Unit 2, Florida Power                     8   Light Co.         05000589 AUTH.frAlrE               AUT4OR AFFILIATIOrf F or i da Power 1                  R Light Co ~
ACCESSION NOP:850320057d DuCeDATE: 84/12/31 NOTARIZED:
REC I P NAHEr
NO FACI<:50-335 St
                ~                  REC IP Ir N I AF F IL I'ATION SUSJECT:     "Combinedl Sem.iannua.r Radioactive           Effluent Release Rept, Ju-l--Dec, 198(."
~ Lucie~lantF Uni t 1 p F
DISTRIBUTION COOL:: IE25L             COPIES RECEIVED:LTR             ENCL P
1 orida Power 5 Light Co, 05000335 50-589 St.
SIZEa TITLE: Periodic Environ             monitoring Rept (50         DKT) Annual/Semiannua>/Effluent/
LucJe Plant-,Unit2, Florida Power 8 Light Co.
NOTES:                                                                                             05000335 OL:02/01/76 0500038'St OL:04/06/83 RFC IPIE.NT             COPIES              RE.C IP IENT            COPIES I 0 CODE/4At'E           LT TP. ENCL        lD CODE/NAHE            LTTR ENCL NRR OR83       BC   04                       NRR ORB3      BC  Ott INTERNAL: ACRS                   1>                       AEQD I E F ILK.           01                       NRR/DV/EEB         08
05000589 AUTH.frAlrE AUT4OR AFFILIATIOrf F
                                    '
1 or i da Power R Light Co ~
NRR~          I        fit                    NRR/DSI/METB
REC I P ~ NAHEr REC IP Ir NI AF F ILI'ATION SUSJECT:
                        /              10                        RGN2/DRSS/EPRPB f<      DANI/NIB EXTERNAL: LPDR                                             NRC   PDR         02 TOTAL NUMBER OF COPIES           REVUIRED: LTTR               ENCL     26
"Combinedl Sem.iannua.r Radioactive Effluent Release
: Rept, Ju-l--Dec, 198(."
DISTRIBUTION COOL::
IE25L COPIES RECEIVED:LTR ENCL P
SIZEa TITLE: Periodic Environ monitoring Rept (50 DKT) Annual/Semiannua>/Effluent/
NOTES: OL:02/01/76 OL:04/06/83 05000335 0500038'St RFC IPIE.NT I 0 CODE/4At'E NRR OR83 BC 04 INTERNAL: ACRS 1>
I E F ILK.
01 NRR~
I fit
/
10 f<
DANI/NIB COPIES LT TP.
ENCL RE.C IP IENT lD CODE/NAHE NRR ORB3 BC Ott AEQD NRR/DV/EEB 08 NRR/DSI/METB RGN2/DRSS/EPRPB COPIES LTTR ENCL EXTERNAL: LPDR NRC PDR 02 TOTAL NUMBER OF COPIES REVUIRED:
LTTR ENCL 26


FLORIDA P(NER & LIGHT QMPAHY SR ~ LUCIE PLANT UNIT NO   I & 2 LICENSE NO     DPR-67 & NPF-16 CABINED SEHI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD Jul   1, 1984   THROUGH   December 31, 1984 8503200578 841231 PDR ADQCK 05000335 R
FLORIDA P(NER
& LIGHT QMPAHY SR ~ LUCIE PLANT UNIT NO I & 2 LICENSE NO DPR-67
& NPF-16 CABINED SEHI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD Jul 1,
1984 THROUGH December 31, 1984 8503200578 841231 PDR ADQCK 05000335 R


~        DESCRIPTION JULY 1, 1984 VISITOR DOSE ASSESSMENT....
FLORIDA POWER
PROCESS CONTROL PROGRAM REVISIONS.
& LIGHT COMPANY ET.
GAS ANALYZER INOPERABLE REPORT.
LUOIE UNII NO. I E
LIQUID EFFLUENT:
2 SEMIANNUAL REPORT JULY 1, 1984 THROUGH DECEMBER 31 1984 TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION.oo ~ oo ~ ~ ol VISITOR DOSE ASSESSMENT....
UNIT UNIT lo FLORIDA POWER ET. LUOIE UNII NO.
~...
                                          ~
~...
                                                  ~ ~
~..............
THROUGH
~. ~....
                                                        ~
~. ~.5 OFFSITE DOSE CALCULATION MANUAL REVISIONS.........
os
~.. ~.......5 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS'
                                                                &
~ ~.
SEMIANNUAL REPORT TABLE OF CONTENTS EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION.oo ~ oo
~ ~.
                                            ... ... ..............
~ ~.
OFFSITE DOSE CALCULATION MANUAL REVISIONS.........
~ ~ ~. ~.5 PROCESS CONTROL PROGRAM REVISIONS. ~
SOLID WASTE AND IRRADIATED FUEL
os~
                                                  ~       ~
~
SHIPMENTS' LIGHT COMPANY
.os~
                                                                .....     ~
.. ~. ~...
                                                      ........ .... .. . . .
~ ~ ~. ~ 5 GAS ANALYZER INOPERABLE REPORT.
                                                                      ~
~ ~........
SU&fATION OF ALL RELEASES; NUCLIDE SUMMATION BY QUARTER, DOSE SUMMATION
~....
                  ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~.. ~. ~. ~. ~ ~ ~ ~ ~ o6 LIQUID EFFLUENT:
2o..o....oooo..o..oo..oooooooo.oo.ooo.o.oo.ll-l4 GASEOUS EFFLUENT SUMMATION OF ALL RELEASES, I
SU&fATION OF ALL RELEASES; NUCLIDE SUMMATION BY QUARTER, DOSE SUMMATION UNIT lo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
DECEMBER 31
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
                                                                            .os
. ~ ~ ~ ~ ~ ~ ~ 7-10 UNIT 2o..o....oooo..o..oo..oooooooo.oo.ooo.o.oo.ll-l4 GASEOUS EFFLUENT SUMMATION OF ALL RELEASES, NUCLIDE SUMMATION BY QUARTER, DOSE SUMMATION UNIT 1 ~ ~ ~ ~
                                                                        .... . . .
~
                                                                                ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
                                                                                ~
~ o ~
                                                              ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~
E 2
~ ~
                                                                                      ~ ~
~ ~ ~
                                                                                          ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15 17 UNIT 2o.........o.oooooo......o.o...o.ooooo.oo..18-20 SOLID WASTE SHIPMENT SUMMATIONoo ~.....
                                                                                          ~
~...........
                                                                                            .
~......21-22 PROCESS CONTROL PROGRAM PAGE REVISIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ o.ATTACHMENT A
                                                                                      .. . ...
                                                                                      ~
                                                                                        .
                                                                                          ~
                                                                                            ~
                                                                                              ~
                                                                                              ~ ~
                                                                                              ~
                                                                                                ~
1984
                                                                                                .... . .5
                                                                                            .. .......5
                                                                                                ~
                                                                                                    ~ ~ ~
                                                                                                          ~
                                                                                                      ~ ~ ~
                                                                                                            .
                                                                                                    ~ ~ ~ ~ ~
                                                                                            ~ ~ ~ ~ ~ ~ ~
NUCLIDE SUMMATION BY QUARTER, DOSE SUMMATION PAGE
                                                                                                            ~ ~
                                                                                                              ~
                                                                                                              ~
ol
                                                                                                                .5
                                                                                                              .~5 7-10 o6 UNIT 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~   15 17 UNIT 2o.........o.oooooo......o.o...o.ooooo.oo..18-20 SOLID WASTE SHIPMENT         SUMMATIONoo ~             ..... ...........
                                                              ~                        ~ ......21-22 PROCESS CONTROL PROGRAM PAGE REVISIONS.                         ~ ~ ~ ~ ~ ~ ~ ~ ~   o.ATTACHMENT A


Page 1 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION
Page 1
: 1. Regulatory Limits 1 ~1 For Liquid Waste Effluents a ~   The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble'gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10 micro curies/ml total activity.
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION 1.
: b. The dose or dose   commitment to a MEMBER OF THE PUBLIC             from radioactive materials in liquid effluents released,         from each reactor unit, to UNRESTRICTED AREAS shall be limited to-'uring any calendar quarter to   < 1.5 mrems to the total             body and to < 5 mrems to any organ, and During any calendar year to     < 3 mrems to the total body             and to < 10 mrems to any organ.
Regulatory Limits 1 ~ 1 For Liquid Waste Effluents a ~
1.2 For Gaseous Waste Effluents:
The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble'gases.
: a. The dose   rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site shall be limited to:
For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10 micro curies/ml total activity.
For Noble Gases:   < 500 mrems/yr   to the total body             and
b.
                                        < 3000 mrems/yr   to the skin, and For Iodine-131, Iodine-133,     Tritium, and all   radionuclides in particulate form with half-lives greater       than           8 days:
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to-'uring any calendar quarter to < 1.5 mrems to the total body and to
                    < 1500 mrems/yr to any organ.
< 5 mrems to any organ, and During any calendar year to
* b. The air dose due to noble gases released in   gaseous   effluents from each reactor   unit, to areas at and beyond the SITE               BOUNDARY shall be limited to the following:
< 3 mrems to the total body and to
During any calendar quarter, to < 5 mrad for gamma radiation and 10 mrad for beta radiation and, during any calendar year to <
< 10 mrems to any organ.
10 mrad for gamma radiation and < 20 mrad for beta radiation.
1.2 For Gaseous Waste Effluents:
* c     The dose   to a MEMBQt OF THE PUBLIC   from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form, with half-lives ) 8 days in gaseous effluents released, from each reactor unit to areas at an8 beyond the SQTE BOUNDARY, shall be limited to the following:
a.
During any calendar quarter to < 7.5 mrem to any organ, and during any calendar year to < 15 mrem to any organ.
The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site shall be limited to:
* The calculated doses contained in a semi-annual report shall not apply to any STS LCO. The reported values are based on =actual release conditions instead of historical conditions that the STS LCO dose calculations are based on         The STS LCO dose limits are therefore included in Item 1 of the report, for information only.
For Noble Gases:
< 500 mrems/yr to the total body and
< 3000 mrems/yr to the skin, and For Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
< 1500 mrems/yr to any organ.
* b.
The air dose due to noble gases released in gaseous effluents from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
During any calendar quarter, to < 5 mrad for gamma radiation and 10 mrad for beta radiation and, during any calendar year to 10 mrad for gamma radiation and
< 20 mrad for beta radiation.
c The dose to a MEMBQt OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form, with half-lives ) 8 days in gaseous effluents released, from each reactor unit to areas at an8 beyond the SQTE BOUNDARY, shall be limited to the following:
During any calendar quarter to
< 7.5 mrem to any organ, and during any calendar year to
< 15 mrem to any organ.
* The calculated doses contained in a semi-annual report shall not apply to any STS LCO.
The reported values are based on =actual release conditions instead of historical conditions that the STS LCO dose calculations are based on The STS LCO dose limits are therefore included in Item 1 of the report, for information only.


Page 2 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION continued)
Page 2
: 2. Maximum Permissible Concentrations WATER:     As per 10 CFR Part 20, Appendix B, Table II, Column 2, except for entrained or dissolved noble gases as described in 1 ~ 1.a of this report.
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION continued) 2.
AIR:       Release   concentrations are limited to dose rate limits described in 1.2.a   of this report.
Maximum Permissible Concentrations WATER:
3 ~ Average energy of     fission   and activation   gases   in gaseous   effluents is not applicable.
As per 10 CFR Part 20, Appendix B, Table II, Column 2, except for entrained or dissolved noble gases as described in 1 ~ 1.a of this report.
4~ Measurements   and Approximations     of Total Radioactivity A summary   of liquid effluent accounting methods is described in Table 3,1.
AIR:
A summary   of gaseous effluent accounting methods is described in Table 3.2.
Release concentrations are limited to dose rate limits described in 1.2.a of this report.
4 ' Estimate of Errors
3 ~
: a. Sampling Error The error associated with volume measureaant devices, flow measuring devices, etc. based on calibration data and design tolerances has been conservatively estimated collectively to be less than + 10%.
Average energy of fission and activation gases in gaseous effluents is not applicable.
: b. Analytical Error for Nuclides
4 ~
                    ~Te               ~Avera e         Maximum Liquid              +9%             +30%
Measurements and Approximations of Total Radioactivity A summary of liquid effluent accounting methods is described in Table 3,1.
Gaseous            +10%           +35%
A summary of gaseous effluent accounting methods is described in Table 3.2.
TABLE 3 ~ 1 RADIOACTIVE LI UID EFFLUENT SAMPLING AND ANALYSIS LIQUID         SAMPLING               TYPE OF                 METHOD OF SOURCE        FRE UENCY                ANALYSIS                ANALYSIS Each Batch     Princi al   Gamma   Emitters           .r .a.
4 '
Monitor         Monthly                                           L.S.
Estimate of Errors a.
Tank        Com osite             Gross Al ha                 G  F,P, Releases        Quar ter ly            SR-907 SR-89                   C S ~
Sampling Error The error associated with volume measureaant
Com osite                FE-55 Continuous                  No   continuous   activity releases Releases                        for this re ortin       eriod Boric Acid Evaporator condensate         is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to liquid waste effluent totals.
: devices, flow measuring
p.h.a. gamma spectrum pulse       height analysis using Lithium Germanium detectors.       All peaks   are identified   and quantified L.S.     Liquid Scintillation Counting C.ST     Chemical Separation G.F.PE   Gas Plow Proportional Counting
: devices, etc.
based on calibration data and design tolerances has been conservatively estimated collectively to be less than + 10%.
b.
Analytical Error for Nuclides
~Te Liquid Gaseous
~Avera e
+9%
+10%
Maximum
+30%
+35%
TABLE 3 ~ 1 RADIOACTIVE LI UID EFFLUENT SAMPLING AND ANALYSIS LIQUID SOURCE SAMPLING FRE UENCY TYPE OF ANALYSIS Each Batch Princi al Gamma Emitters METHOD OF ANALYSIS
.r.a.
Monitor Tank Releases Continuous Releases Monthly Com osite Quar terly Com osite Gross Al ha SR-907 SR-89 FE-55 No continuous activity releases for this re ortin eriod L.S.
G F,P, C
S ~
Boric Acid Evaporator condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to liquid waste effluent totals.
p.h.a.
gamma spectrum pulse height analysis using Lithium Germanium detectors.
All peaks are identified and quantified L.S.
Liquid Scintillation Counting C.ST Chemical Separation G.F.PE Gas Plow Proportional Counting


Page 3 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 4.1 Measurements       and Approximations     of Total Radioactivity   (continued)
Page 3
F 1.b     (continued)
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 4.1 Measurements and Approximations of Total Radioactivity (continued)
TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS           SAMPLING               TYPE OF         METHOD OF SOURCE            FRE UENCY              ANALYSIS          ANALYSIS Waste gas                                Principal            (G)
F 1.b (continued)
Decay Tank          Each Tank              Gamma Releases                                  Emit ters            .h.a.
TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SOURCE Waste gas Decay Tank Releases Con tainme nt Purge Releases Plant Vent SAMPLING FRE UENCY Each Tank Each Purge Weekly Monthly Composite (Particulates)
Con tainme  nt                        Principal Gamma          (G)
Quarterly Composite (Particulates)
Purge          Each Purge              Emitters              .h.a.
TYPE OF ANALYSIS Principal Gamma Emitters Principal Gamma Emitters H-3 Principal Gamma Emitters H-3 Gross Alpha SR-90 SR-89 METHOD OF ANALYSIS (G)
Releases                                    H-3                L S Principal Gamma      (G, C, P)-
.h.a.
Weekly              Emit ters            .h.a.
(G)
H-3                L,Si Monthly                Gross            P-GFP Plant            Composite              Alpha Vent        (Particulates)
.h.a.
Quarterly                SR-90              C S Composite                SR-89 (Particulates)
L S (G, C, P)-
G             Gaseous   Grab Sample C              Charcoal   Filter Sample P              Particulate Filter Sample L  S ~        Liquid Scintillation Counting C S  ~        Chemical Separation p.h.a        Gamma   spectrum pulse height analysis using Lithium Germanium detectors,       All peaks are identified and quantified G FOP          Gas Flow Proportional Counting
.h.a.
L,Si P-GFP C S G
C P
L S ~
C S ~
p.h.a G FOP Gaseous Grab Sample Charcoal Filter Sample Particulate Filter Sample Liquid Scintillation Counting Chemical Separation Gamma spectrum pulse height analysis using Lithium Germanium detectors, All peaks are identified and quantified Gas Flow Proportional Counting


Page   4 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT NO. 1 & 2 SEMIANNUAL REPORT July 1,   1984   THROUGH   December 31   1984 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 5~ Batch Releases
Page 4
: 5. 1 Liquid UNIT  1  UNIT 2
FLORIDA POWER 6 LIGHT COMPANY ST.
: a. Number of batch releases:                               22.5    22. 5
LUCIE UNIT NO.
: b. Total time period of batch releases:                     9941
1
                                                                          ~c)~      MINJTES
& 2 SEMIANNUAL REPORT July 1, 1984 THROUGH December 31 1984 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 5 ~
: c. Maximum time period for a batch release:                 660      660    MINUTES
Batch Releases
: d. Average time period for a batch release:                 442      442      MINUTES e   Minimum time period for a batch release:               287     287     MINUTES f ~ Average stream flow during periods of release of effluent into a flowing stream.         8.18E05   ~~8I~      GPM ALL LIQUID RELEASES   ARE SlMMARIZED   IN TABLES 5.2 Gaseous
: 5. 1 Liquid a.
: a. Number   of batch releases:                             16        39
Number of batch releases:
: b. Total time period for batch releases:                 ~5        12119    MINUTES c, Maximum time period for a batch release:                 1514    2145    MINUTES
b.
: d. Average time period for batch releases:                           311    MINUTES
Total time period of batch releases:
: e. Minimum time period for a batch release:                   8       30   MINUTES ALL GASEOUS WASTE RELEASES ARE SlHMARIZED IN TABLES
c.
: 6. Unplanned Releases 6.1 Liquid a   Number   of releases:                                               0
Maximum time period for a batch release:
: b. Total activity releases:                                           0   CURIE S 6.2 Gaseous
d.
: a. Number   of releases:                                               0
Average time period for a batch release:
: b. Total activity released:                                           0    CURIE S 6.3 See attachments     (if applicable) for:
e Minimum time period for a batch release:
: a. A description of the event     and equipment involved b   Cause(s)   for the unplanned release
UNIT 1 22.5 9941 660 442 287 UNIT 2
: c. Actions taken to prevent a recurrence, d   Consequences of the unplanned release.
: 22. 5
~c)~ MINJTES 660 MINUTES 442 MINUTES 287 MINUTES f ~
Average stream flow during periods of release of effluent into a flowing stream.
8.18E05 ALL LIQUID RELEASES ARE SlMMARIZED IN TABLES 5.2 Gaseous
~~8I~ GPM a.
Number of batch releases:
b.
Total time period for batch releases:
c, Maximum time period for a batch release:
d.
Average time period for batch releases:
e.
Minimum time period for a batch release:
16
~5 1514 8
39 12119 MINUTES 2145 MINUTES 311 MINUTES 30 MINUTES ALL GASEOUS WASTE RELEASES ARE SlHMARIZED IN TABLES 6.
Unplanned Releases 6.1 Liquid a
Number of releases:
b.
Total activity releases:
0 0
CURIES 6.2 Gaseous a.
Number of releases:
b.
Total activity released:
6.3 See attachments (if applicable) for:
a.
A description of the event and equipment involved b
Cause(s) for the unplanned release c.
Actions taken to prevent a recurrence, d
Consequences of the unplanned release.
0 0
CURIE S


Page 5 FLORIDA POWER     & LIGHT COMPANY ST. LUCIE UNIT NO. 1 & 2 SEMIANNUAL REPORT JULY 1. 1984     THROUGH     DECEMBER   31, 1984 EFFLUENT AND WASTE DISPOSAL -'SUPPLEMENTAL INF01UVTION (continued) 7 ~ Assessment         of radiation dose from radioactive effluents to the GENERAL PUBLIC due to their activities inside the site boundary assume the visitor was onsite for 40 hours, at an average distance of 0.3 Kilometers in the worst dispersion direction, and received exposure from each of the two reactor units on the St. Lucie Site.
Page 5
VISITOR       DOSE RESULTS FOR CALENDAR YEAR         1984 WERE:
FLORIDA POWER
GASEOUS   PARTICULATES & IODINE EXPOSURE                         NOBLE GAS EXPOSURE ORGAN                  DOSE    (mrem)          Gamma   Air Dose   4.6E-2 mrads Bone                    5 'E-5                  Beta   Air Dose     9.2E-2 mrads Liver                  8.5E-4 Thyroid                1.9E-2 Kidney'ung 3.6E-4 7.7E-4 GI-LLI                7.9E-4 Total Body             8.2E-4
& LIGHT COMPANY ST.
: 8. Offsite   Dose       Calculation Manual Revisions:
LUCIE UNIT NO.
No changes were issued to the ODCM during the period July   1, 1984 December 31, 1984.
1
: 9. Solid Waste and Irradiated Fuel Shi ments No     irradiated fuel shipments were made from the site. Common solid waste from St. Lucie Units 1 and 2 were shipped )ointly. A summation of these shipments is given in Table 3.9 of this report.
& 2 SEMIANNUAL REPORT JULY 1.
: 10. Process   Control Pro ram Revisions Revisions 03 and 04 were implemented during this reporting period. The revised revisions are included in Attachment-A of this report with explanations provided.
1984 THROUGH DECEMBER 31, 1984 EFFLUENT AND WASTE DISPOSAL -'SUPPLEMENTAL INF01UVTION (continued) 7 ~
Assessment of radiation dose from radioactive effluents to the GENERAL PUBLIC due to their activities inside the site boundary assume the visitor was onsite for 40 hours, at an average distance of 0.3 Kilometers in the worst dispersion direction, and received exposure from each of the two reactor units on the St. Lucie Site.
VISITOR DOSE RESULTS FOR CALENDAR YEAR 1984 WERE:
ORGAN Bone DOSE (mrem) 5'E-5 Liver 8.5E-4 GASEOUS PARTICULATES & IODINE EXPOSURE NOBLE GAS EXPOSURE Gamma Air Dose 4.6E-2 mrads Beta Air Dose 9.2E-2 mrads Thyroid Kidney'ung GI-LLI 1.9E-2 3.6E-4 7.7E-4 7.9E-4 8.
Total Body 8.2E-4 Offsite Dose Calculation Manual Revisions:
No changes were issued to the ODCM during the period July 1, 1984 December 31, 1984.
9.
Solid Waste and Irradiated Fuel Shi ments No irradiated fuel shipments were made from the site.
Common solid waste from St. Lucie Units 1 and 2 were shipped )ointly.
A summation of these shipments is given in Table 3.9 of this report.
10.
Process Control Pro ram Revisions Revisions 03 and 04 were implemented during this reporting period.
The revised revisions are included in Attachment-A of this report with explanations provided.


Page 6 ll. Waste Gas Deca     Tank Ex losive Gas Monitorin S stem Ino erable Unit No. 1 This information is provided pursuant to St. Lucie, Unit No.     1 Technical Specification 3.3.3.10.b The oxygen monitors   required by St. Lucie Unit No. 1 Technical Specifications 3.3.3.10   were inoperable from October 25, 1984 until December 6, 1984. This condition   resulted in less than the minimum number of channels operable required by   Table 3.3-13 in excess of the time permitted by Table 3.3-13 for the Waste Gas Decay Tank Explosive Gas Monitoring System.
Page 6
The cause   of the inoperability was due primarily to excessive amounts of moisture in the system which resulted in the failure of the oxygen detectors.
ll.
A number   of factors contributed to the delay in returning the Waste Gas Decay Tank Explosive Gas Monitoring System to operable status.     During the investigation of the instrument failures     it was determined that additional maintenance would be required in order to restore the system reliability. This additional maintenance involved replacing a pump and eliminating suspected system leakage. Some of-the required spare parts to repair the system were not initially available on site. This contributed to the delay in restoring the system's operability. The remaining time is attributed to the extensive system maintenance which proved to be necessary to achieve the desired reliability.
Waste Gas Deca Tank Ex losive Gas Monitorin S stem Ino erable Unit No.
The St. Lucie P1ant is conducting an evaluation of the system's design and operation with an objective to preclude similar failures in the future. In addition, to avoid delays in system maintenance the quantity of spare parts to be stocked has been increased.
1 This information is provided pursuant to St. Lucie, Unit No.
1 Technical Specification 3.3.3.10.b The oxygen monitors required by St. Lucie Unit No.
1 Technical Specifications 3.3.3.10 were inoperable from October 25, 1984 until December 6, 1984.
This condition resulted in less than the minimum number of channels operable required by Table 3.3-13 in excess of the time permitted by Table 3.3-13 for the Waste Gas Decay Tank Explosive Gas Monitoring System.
The cause of the inoperability was due primarily to excessive amounts of moisture in the system which resulted in the failure of the oxygen detectors.
A number of factors contributed to the delay in returning the Waste Gas Decay Tank Explosive Gas Monitoring System to operable status.
During the investigation of the instrument failures it was determined that additional maintenance would be required in order to restore the system reliability.
This additional maintenance involved replacing a pump and eliminating suspected system leakage.
Some of-the required spare parts to repair the system were not initially available on site.
This contributed to the delay in restoring the system's operability.
The remaining time is attributed to the extensive system maintenance which proved to be necessary to achieve the desired reliability.
The St. Lucie P1ant is conducting an evaluation of the system's design and operation with an objective to preclude similar failures in the future.
In
: addition, to avoid delays in system maintenance the quantity of spare parts to be stocked has been increased.
During the period of time that the explosive gas monitoring system was inoperable, the conditions of Technical Specification 3.11.2.5 were maintained by monitoring oxygen'n the on service waste gas decay tank with the lab gas partitioner in accordance with Table 3.3-13, ACTION 5, of Technical Specification 3.3.3.10.
During the period of time that the explosive gas monitoring system was inoperable, the conditions of Technical Specification 3.11.2.5 were maintained by monitoring oxygen'n the on service waste gas decay tank with the lab gas partitioner in accordance with Table 3.3-13, ACTION 5, of Technical Specification 3.3.3.10.


Page   7 FLORIDA   POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 1 SEMIANNUAL REPORT July 1, 1984     THROUGH December 31   1984 TABLE 3 '-1 LIQUID EFFLUENTS   - SUMMATION OF ALL RELEASES U         E
Page 7
)A, Fission and Activation Products
FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 1
: 1. Total Release (not including                                       8. 84E-01
SEMIANNUAL REPORT July 1, 1984 THROUGH December 31 1984 TABLE 3'-1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES U
: 4. 20E-01 tritium, gases, alpha)                   CI
E
: 2. Average diluted concentration durin eriod                             uCI/ml   1.51E-08       4.89E-08     I B. Tritium 1~   Total Release                             CI    5 95E401        1. OOE402 2~   Average diluted concentration durin   eriod                         uCI/ml  2.14E-06 CD Dissolved and Entrained Gases 1~   Total release                             CI     3.72E-01     . 9.07E-Ol
)A, Fission and Activation Products 1.
: 2. Average diluted concentration durin eriod                            uCI/ml   1.34E-OB   . 5.38E-08 D. Gross Alpha  Radioactivity 1.'otal    Release                            CI E. Volume   of Waste Released                                           1.60E+06
Total Release (not including tritium, gases, alpha) 2.
( rior to dilution)                         Liters    1.13E406 F. Volume of Dilution Water Used Durin Period                           Liters   1.40Et10       1.69E+10
Average diluted concentration durin eriod B.
Tritium CI uCI/ml
: 4. 20E-01 1.51E-08
: 8. 84E-01 4.89E-08 I
1 ~
Total Release 2 ~
Average diluted concentration durin eriod CD Dissolved and Entrained Gases 1 ~
Total release 2.
Average diluted concentration durin eriod D.
Gross Alpha Radioactivity 1.'otal Release CI 5 95E401
: 1. OOE402 uCI/ml 2.14E-06 CI 3.72E-01 9.07E-Ol uCI/ml 1.34E-OB 5.38E-08 CI E.
Volume of Waste Released
( rior to dilution)
F.
Volume of Dilution Water Used Durin Period Liters 1.13E406 Liters 1.40Et10 1.60E+06 1.69E+10


Page FLORIDA     POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO. 1 SEMIANNUAL REPORT July 1,     1984         THRoUGH Oecember   31, 1934 TABLE   3.4-1 LIQUID EFFLUENTS CONTINUOUS MODE                BATCH MODE NUCLIDES RELEASED     UNIT QUARTER             QUARTER       UARTER I     QUARTER fk Na-24           cz         0               0       5.65E-04      6.80E-03 CR-51           CI         0               0       2.77E-04      7.90E-03 MN-54           CI         0               0       2.63E-03      1.43E-02 MN-56       I   cz Co-57           CI         0               0 Co-58           CI                   I     o                     1.35E-01 Co-60           Cz I     0               0       6.15E-02      3.03E-02 Fe-59           Cz         0               0       1. 5E-  2      9.35E-03 Fe-55       I   CI I     0                       2.36E-02      5.45E-02 SN-113       I   CI Sb-122           cz         0         I     0       1.86E-03       1.46E-02 Sb-124          CI        0                0                      1. 61E-03 W-187            Cz        0                0                      2.47E-04 N -239           cz         0 I-131           Cz         0                       1.88E-01      1.30E-01 cz                                                I2.57E-05 0'-132 0               0 I-133         I CI I     0               0       2. 13E-02      1.94E-02 I-134           Cz         0               0 I-135           cz         0               0       2.62E-04        2.30E-03 Rb-88           CI         0               0                     5. 5 -04 zr-95           Cz         0               0       9.65E-05      1.37E-03 Nb-95           cz         0               0       2.36E-04      3.49E-03 ZR-97           cz         0               0
Page FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO.
                  'I Nb-97           Cz         0               0 Mo-99           cz         0               0 Tc-994               I     0               0       1. 36E-03      2.47E-03 Cs-130           cz   I     0               0                     2.01E-03 Sb-125           czl       0               0       1.85E-03       1.57E-02 Cs-134        I  CI        0                      I3.65E-02       1.54E-01
1 SEMIANNUAL REPORT July 1, 1984 THRoUGH Oecember 31, 1934 TABLE 3.4-1 LIQUID EFFLUENTS CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER QUARTER BATCH MODE UARTER I QUARTER fk Na-24 cz 0
0 CR-51 CI 0
0 MN-54 CI 0
0 MN-56 I cz Co-57 CI 0
0 Co-58 CI I
o Co-60 Cz I
0 0
Fe-59 Cz 0
0 Fe-55 I CI I
0 SN-113 I CI Sb-122 cz 0
I 0
Sb-124 CI 0
0 W-187 Cz 0
0 5.65E-04 2.77E-04 2.63E-03 6.15E-02
: 1. 5E-2 2.36E-02 1.86E-03 6.80E-03 7.90E-03 1.43E-02 1.35E-01 3.03E-02 9.35E-03 5.45E-02 1.46E-02
: 1. 61E-03 2.47E-04 N -239 cz 0
I-131 Cz 0
0'-132 cz 0
0 I-133 I CI I
0 0
I-134 Cz 0
0 I-135 cz 0
0 Rb-88 CI 0
0 zr-95 Cz 0
0 Nb-95 cz 0
0 ZR-97 cz 0
0 Nb-97 Cz 0
0 Mo-99 cz 0
0 Tc-994 'I I 0
0 Cs-130 cz I
0 0
Sb-125 czl 0
0 Cs-134 I CI 0
1.88E-01
: 2. 13E-02 2.62E-04 9.65E-05 2.36E-04
: 1. 36E-03 1.85E-03 I3.65E-02 1.30E-01 I2.57E-05 1.94E-02 2.30E-03 5.
5 -04 1.37E-03 3.49E-03 2.47E-03 2.01E-03 1.57E-02 1.54E-01


Page FLORIDA POWER, & LIGHT COMPANY ST ~ LUCIE UNIT NO. 1 SEMIANNUAL REPORT Jul   1, 1984       THROUGH December 31   1984 TABLE 3   '-1 LIQUID EFFLUENTS (continued)
Page FLORIDA POWER, & LIGHT COMPANY ST ~ LUCIE UNIT NO.
CONTINUOUS MODE                 BATCH MODE NUCLIDES RELEASED     UNIT   QUARTER   t     UARTER 84     UARTEk 8       UARTER t4 )
1 SEMIANNUAL REPORT Jul 1,
Cs-136          CI                        0       1.48E-03       1.53E-02 Cs-137          CI                        0       7.50E-02       2.55E-01 Ba-140        I  CI                        0       8.10E-04       1.14E-03 La-140          CI                        0       8.55E-05       5.95E-03 Sr-89            CI                        0       1.22E-02       5.90E-03 Sr-90            CI                        0       3.39E-04       2.35E-04 Y-90             CI                                 3.39E-04       2.35E-04 UNIDENTIFIED        CI TOTAL FOR PERIOD ABOVE       CI                         0       4.20E-01       8.84E-01 N.-41         I CI                                 7.60E-05       9. 15E-04 KR-85            CI XE-131M          CI                                  1.76E-03       2.92E-02 XE-133        I  CI                                  3. 56E-01     8. 55E-01 XE-13 3M        CI                                  5. 40E-03     9. 95E-03 XE-135        I  CI                                  8.55E-03       1.23E-02 KR-85M          CI XE-138          CI                                  0             0 mTAL FOR                                              3.72E-01       9.07E-01 PERIOD ABOVE        CI NOTE:   If no value is entered for     a   nuclide, the value equals zero Curies.
1984 THROUGH December 31 1984 TABLE 3'-1 LIQUID EFFLUENTS (continued)
CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT Cs-136 CI Cs-137 CI Ba-140 I CI La-140 CI Sr-89 CI Sr-90 CI QUARTER t UARTER 84 UARTEk 8 UARTER t4
)
0 1.48E-03 1.53E-02 0
7.50E-02 2.55E-01 0
8.10E-04 1.14E-03 0
8.55E-05 5.95E-03 0
1.22E-02 5.90E-03 0
3.39E-04 2.35E-04 Y-90 UNIDENTIFIED CI CI 3.39E-04 2.35E-04 TOTAL FOR PERIOD ABOVE CI 0
4.20E-01 8.84E-01 N.-41 KR-85 XE-131M XE-133 XE-13 3M XE-135 KR-85M XE-138 mTAL FOR PERIOD ABOVE I CI CI CI I CI CI I CI CI CI CI 7.60E-05
: 9. 15E-04 1.76E-03 2.92E-02
: 3. 56E-01
: 8. 55E-01
: 5. 40E-03
: 9. 95E-03 8.55E-03 1.23E-02 0
0 3.72E-01 9.07E-01 NOTE: If no value is entered for a nuclide, the value equals zero Curies.


Page 10 FLORIDA POWER   & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMIANNUAL REPORT Janua     1, 1984   THROUGH     December 31, 1984 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION Age Group:     Adult                 Location.'ny Adult Exposure Interval:   From Janua     1, 1984   through     December 31, 1984 FISH   & SHELLFISH             CALENDAR YEAR PATHWAY TO                       DOSE ORGAN                      (mrem)
Page 10 FLORIDA POWER
Bone                        1.24   E-l Liver                      4 ~ 60 E-1 Thyroid                    2.30   E-1 Kidney                      1.78   E-2 Lung                        4.59   E-l GI-LLI                      4.41   E-l T. Body                    1.56   E-l
& LIGHT COMPANY ST.
LUCIE UNIT NO.
1 SEMIANNUAL REPORT Janua 1,
1984 THROUGH December 31, 1984 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION Age Group:
Adult Location.'ny Adult Exposure Interval:
From Janua 1,
1984 through December 31, 1984 FISH & SHELLFISH CALENDAR YEAR PATHWAY TO ORGAN Bone Liver Thyroid Kidney Lung GI-LLI T. Body DOSE (mrem) 1.24 E-l 4 ~ 60 E-1 2.30 E-1 1.78 E-2 4.59 E-l 4.41 E-l 1.56 E-l


Page 11 FLORIDA   POWER & LIGHT COHPANY ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT July 1,   1984         THROUGHOecember 31, 1984 TABLE 3.3-2 LIQUID EFFLUENTS SlMMATION OF ALL RELEASES NUCL DES RELEASED                   UN T  QUARTER    3    QUARTER    4 A.,Fission   and Activation Products
Page 11 FLORIDA POWER
: 1. Total Release (not including tritium, gases, alpha)                   CI   4.20E-01       8.84E-01
& LIGHT COHPANY ST ~ LUCIE UNIT NO.
      *
2 SEMIANNUAL REPORT July 1, 1984 THROUGHOecember 31, 1984 TABLE 3.3-2 LIQUID EFFLUENTS SlMMATION OF ALL RELEASES NUCL DES RELEASED A.,Fission and Activation Products UN T QUARTER 3
: 2. Average diluted concentration durin    eriod                          ucI/ml  1. 51E-08     4. 89E-08 B. Tritium 1   Total Release                             CI     5. 95E+01     1.00E~02
QUARTER 4
: 2. Average diluted concentration durin eriod                              ucI/ml   2.14E-06     5.93E-06 C. Dissolved and Entrained      ases
1.
: 1. Total release                               CI     3.72E-01     9.07E-01 2~   Average diluted concentration                               I durin   eriod                           ucZ/ml   1.34E-08     5.38E-08 D. Gross Alpha Radioactivity 1~   Total Release                             CI     0             0 E. Volume of Waste Released (prior to dilution)                           Liters  1.13E+06      1.60E>06 F. Volume o Dilution Water Used Durin Period                           Liters   1. 40E+10     1. 69E110
Total Release (not including tritium, gases, alpha) 2.
* Average diluted concentration durin eriod B.
Tritium CI ucI/ml 4.20E-01 8.84E-01
: 1. 51E-08
: 4. 89E-08 1
Total Release 2.
Average diluted concentration durin eriod C.
Dissolved and Entrained ases CI
: 5. 95E+01 1.00E~02 ucI/ml 2.14E-06 5.93E-06 1.
Total release CI 3.72E-01 9.07E-01 2 ~
Average diluted concentration durin eriod ucZ/ml 1.34E-08 5.38E-08 I
D.
Gross Alpha Radioactivity 1 ~
Total Release CI 0
0 E.
Volume of Waste Released (prior to dilution)
F.
Volume o Dilution Water Used Durin Period Liters Liters 1.13E+06
: 1. 40E+10 1.60E>06
: 1. 69E110


Page FLORIDA POWER 6 LIGHT C(MPANY ST ~ LUCIE UNIT NO 2 SEMIANNUAL REPORT July 1,     1984       THROUGH December 31, 1984 TABLE 3 '-2 LIQUID EFFLUENTS NUCLIDES RELEASED Na-24 (R-51 UNIT CI CI 0,
FLORIDA POWER 6
CONTINUOUS MODE QUARTER 0
LIGHT C(MPANY ST ~ LUCIE UNIT NO 2
UARTEK 0
SEMIANNUAL REPORT July 1, 1984 THROUGH December 31, 1984 TABLE 3'-2 LIQUID EFFLUENTS Page CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER UARTEK BATCH MODE UARTEK UARTEK Na-24 CI (R-51 CI MN-54 I cz MN-56 CI Co-57 I cz cz Co-60 CI
0 5.65E-O BATCH MODE UARTEK        UARTEK 6.80E-03 MN-54        I  cz                                                      -  2 MN-56            CI Co-57        I  cz cz                                  1.43E-02 Co-60            CI                                  6.15E-02     3.03E-02
.Fe-59 cz I
    .Fe-59            cz  I                              1. 15E-02     9.35E-03 Fe-55           CI                                 2 '6E-02       5.45E-02 SN-113           CI                                 0            0 Sb-122           cz I                               1. 86E-03     1. 46E-02 Sb-124          CI                                  0             1.61E-03 W-187,          CI                                  0             2.47E-04 N -239          CI                                  0             0 I-131            CI                                  1.88E-01     1.30E-01 I-132            cz  I                              0             2.57E-05 I-133            CI          0                      2. 13E-02     1.94E-02 I-134            CI                                  0             0 I-135            CI                  I    0         2.62E-04     2.30E-03 Rb-88            CI                                  0             5. 15E-04 zr-95            CI                                  9.65E-05     1.37E-03 Nb-95            cz  I                              2.36E-04     3.49E-03 zR-97            CI                                  0             0 Nb-97            CI                                  0             0 Mo-99            cz  I                              0           '0 Tc-99M        I  CI                                  1.36E-03     2.47E-03 Cs-138          CI                                  0             2. 01E-03 Sb-125          CI                                                1.57E-02 Cs-134.          CI                                  3.65E-02     1.54E-01
0, 0
0 0
5.65E-O 6.80E-03 2
1.43E-02 6.15E-02 3.03E-02
: 1. 15E-02 9.35E-03 Fe-55 CI 2 '6E-02 5.45E-02 SN-113 CI Sb-122 cz I
Sb-124 CI W-187, CI N -239 CI I-131 CI I-132 cz I
I-133 CI I-134 CI I-135 CI Rb-88 CI zr-95 CI Nb-95 cz I
zR-97 CI Nb-97 CI Mo-99 cz I
Tc-99M I CI Cs-138 CI Sb-125 CI Cs-134.
CI 0
I 0
0 0
: 1. 86E-03
: 1. 46E-02 0
1.61E-03 0
2.47E-04 0
0 1.88E-01 1.30E-01 0
2.57E-05
: 2. 13E-02 1.94E-02 0
0 2.62E-04 2.30E-03 0
: 5. 15E-04 9.65E-05 1.37E-03 2.36E-04 3.49E-03 0
0 0
0 0
'0 1.36E-03 2.47E-03 0
: 2. 01E-03 1.57E-02 3.65E-02 1.54E-01


Page FLORIDA   POWER 6   LIGHT COMPANY ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT July 1,     1984         THR0UGH December   31, 1984 TABLE 3   '-2 LIQUID EFFLUENTS (continued)
Page FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO.
CONTINUOUS MODE                  BATCH MODE NUCLIDES RELEASED       UNIT   QUARTER   fi'UARTER           QUARTEK 0     QUARTER   /h I Cs-136            CI          0        I    0        1.48E-03       1.53E-02 Cs-137            CI                                    7.50E-02       2.55E-01 Ba-140           CI         0               0         8. 10E-04     1. 14E-03 La-140           CI         0               0         8.55E-05       5.95E-03 Sr-89            CI         0               0         1.22E-02       5.90E-03 Sr-90             CI                                   3.39E-04       2.35E-04 Y-90             CI                                   3.39E-04       2.35E-04 UNIDENTIFIED        CI TOTAL FOR                                                                8.84E-01 PERIOD "ABOVE        CI                                    4. 20E-01 I       AR-.41           CI         0                         7.60E-05       9. 15E-04 I
2 SEMIANNUAL REPORT July 1, 1984 THR0UGH December 31, 1984 TABLE 3'-2 LIQUID EFFLUENTS (continued)
KR-85            CII        0                      Jo              0             I I        XE-131M          CI   I      0                         1. 76E-03     2. 92E-02 I        XE-133        )  CI          0                        3.56E-01       8.55E-Ol l        XE-13 3M         C I        0                 0       5.40E-03       9.95E-03 l        XE-135         j CI         0                         8.55E-03       1.23E-02     I I
NUCLIDES RELEASED UNIT Cs-136 CI Cs-137 CI CONTINUOUS MODE QUARTER fi'UARTER 0
KR-85M            CI                                    0             0             I XE-138           CI TOTAL FOR PERIOD ABOVE         CI                                   3. 72E-01     9.07E-01 NOZE:   If no   value is entered for a nuclide, the value equals zero Curies.
I 0
BATCH MODE QUARTEK 0 QUARTER
/h I
1.48E-03 1.53E-02 7.50E-02 2.55E-01 Ba-140 CI 0
0
: 8. 10E-04
: 1. 14E-03 La-140 Sr-89 CI 0
0 8.55E-05 5.95E-03 CI 0
0 1.22E-02 5.90E-03 Sr-90 CI 3.39E-04 2.35E-04 Y-90 UNIDENTIFIED TOTAL FOR PERIOD "ABOVE CI CI CI 3.39E-04
: 4. 20E-01 2.35E-04 8.84E-01 I
I I
I l
l I
AR-.41 CI 0
7.60E-05
: 9. 15E-04 XE-131M CI I
0 XE-133
) CI 0
: 1. 76E-03
: 2. 92E-02 3.56E-01 8.55E-Ol XE-13 3M CI 0
0 5.40E-03 9.95E-03 XE-135 j CI 0
KR-85M CI 8.55E-03 1.23E-02 I
0 0
I KR-85 CII 0
Jo 0
I XE-138 TOTAL FOR PERIOD ABOVE CI CI
: 3. 72E-01 9.07E-01 NOZE: If no value is entered for a nuclide, the value equals zero Curies.


page l4 FLORIDA POWER & LI8GHT COMPANY ST. LUCIE UNIT NO, 2 SEMIANNUAL REPORT Januar   1, 1984     THROUGH     December 31, 1984 TABLE   3.5-2 LIQUID EFFLUENTS DOSE SUMMATION Age Group:   Adult                 Location:     Any Adult Exposure Interval:   From   Januar   1, 1984     through 'ecember     31, 1984 FISH & SHELLFISH             CALENDAR YEAR PATHWAY TO                       DOSE ORGAN                        (mrem)
page l4 FLORIDA POWER
Bone                         1.24   E-l Liver                        4.60   E-1 Thyroid                      2.30   E-1 Kidney                        1.78 E-2 Lung                          4.59   E-1 GI-LLI                        4.41   E-l T. Body                      1.56   E-l
& LI8GHT COMPANY ST.
LUCIE UNIT NO, 2
SEMIANNUAL REPORT Januar 1,
1984 THROUGH December 31, 1984 TABLE 3.5-2 LIQUID EFFLUENTS DOSE SUMMATION Age Group:
Adult Location:
Any Adult Exposure Interval:
From Januar 1,
1984 through 'ecember 31, 1984 FISH & SHELLFISH CALENDAR YEAR PATHWAY TO ORGAN DOSE (mrem)
Bone Liver Thyroid Kidney Lung GI-LLI T. Body 1.24 E-l 4.60 E-1 2.30 E-1 1.78 E-2 4.59 E-1 4.41 E-l 1.56 E-l


Page   15 FLORIDA POMER & LIGHT C(MPANY ST ~ LUCIE UNIT NO, 1 SEMIANNUAL REPORT 98             " ~0b TABLE 3.6-1 GASEOUS EFFLUENTS   - SlHMATION OF ALL RELEASES NUCLIDES RELEASED                 UN IT          QUARTER 3 QUARTER     4 )
Page 15 FLORIDA POMER
)A. Fission and Activation   Gases
& LIGHT C(MPANY ST ~ LUCIE UNIT NO, 1
: 1. Total Release                       I   CI   1         60E<04   1.59E~04 2.02E403            2.00E&03 2~  Avera e Release Rate  for Period      CI/
SEMIANNUAL REPORT 98
BE Iodines
" ~0b TABLE 3.6-1 GASEOUS EFFLUENTS - SlHMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 3
: 1. Total Iodine-131                         CI   1.93E-01           3.00E-02 Avera e Release Rate   for Period     ucI/sec                     3. 7E-03 2.
QUARTER 4
C, Particulates 1 ~ Particulates T-1/2 0 8 Days       )
)
CI   1.81E-03'.
)A.
2.27E-04      I E-0    2.86E-05 Average Release Rate   for Period   )
Fission and Activation Gases 1.
ucI/sec
Total Release 2 ~
: 3. Gross Alpha Radioactivity                 CI   1.07E-12           3. 32E-21 D Tritium E+02 1~   Total Release                           CI
Avera e Release Rate for Period I
: 2. Avera e Release Rate   for Period     uCI/sec 3.47Et01           5.49E+01
CI 1 60E<04 CI/
2.02E403 1.59E~04 2.00E&03 BE Iodines 1.
Total Iodine-131 CI 1.93E-01 2.
Avera e Release Rate for Period ucI/sec C,
Particulates 1 ~
Particulates T-1/2 0 8 Days
)
CI 1.81E-03'.
Average Release Rate for Period
) ucI/sec E-0 3.
Gross Alpha Radioactivity CI 1.07E-12 3.00E-02
: 3. 7E-03 2.27E-04 I
2.86E-05
: 3. 32E-21 D
Tritium 1 ~
Total Release CI E+02 2.
Avera e Release Rate for Period uCI/sec 3.47Et01 5.49E+01


Page 16 FLORIDA   POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 1 SEMIANNUAL REPORT TABLE 3.7-1 GASEOUS EFFLUENTS CONTINUOUS MODE              BATCH MODE NUCLIDES RELEASED   UNIT QUARTER         QUARTM         UARTEK        UARTER 1 ~   FISSION GASES AR-41     CI GI   0                           5.1E0          5. OE KR-85M    CI   1. 85E402     2.20E402 KR-87      CI   5.92E+01       6.1 f401
Page 16 FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 1
: 2. Ei01       l. Et0 XE-131M    CI   3.61E001       8.57E 00    2.99E 00      4.05E&01 XE-13 3    Cr   1.3 E<0       1.1 E+0           E+
SEMIANNUAL REPORT TABLE 3.7-1 GASEOUS EFFLUENTS CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER QUARTM 1 ~
XE-133M    CI    8.28f<01      4.4 Et01     1.83E 0 XE-135      CI    1.70EH03      1.76E+03     4.07ft02      l. 9E  0 XE-135M    GI                  l. 11 XE-13      CI    0 TOTAL FOR PERIOD ABOVE    CI    1. 55E i04    1.35Ei04    5.36E&02       2.43ft03 2~   IODINES I-131         CI    1.93E-01      3.00E-02 I-13 3       CI I-1 5       CI TOTAL FOR PERIOD ABOVE   CI   6. 13E-01     1. 09E-01
FISSION GASES BATCH MODE UARTEK UARTER AR-41 KR-85M KR-87 XE-131M XE-13 3 XE-133M XE-135 XE-135M XE-13 TOTAL FOR PERIOD ABOVE CI 8.28f<01 CI 1.70EH03 GI CI 0
    ~   PARTICULATES Co-58       CI    0 Co-60       CI SR-90       CI    0 Y- 0       GI   0 GI I-133      CI   4.12E-03       1.04E-04 GI   0 TOTAL FOR PERIOD ABOVE    CI   5.93E-03       3.31E-04
CI
: 1. 55E i04 CI GI 0
CI
: 1. 85E402 CI 5.92E+01 2.
Ei01 CI 3.61E001 Cr 1.3 E<0 2.20E402 6.1 f401 l.
Et0 8.57E 00 1.1 E+0 4.4 Et01 1.76E+03 l.
11 1.35Ei04 5.1E0 2.99E 00 E+
1.83E 0
4.07ft02 5.36E&02 5.
OE 4.05E&01 l.
9E 0
2.43ft03 2 ~
IODINES I-131 I-13 3 I-1 5 TOTAL FOR PERIOD ABOVE CI CI CI CI 1.93E-01 3.00E-02
: 6. 13E-01
: 1. 09E-01
~
PARTICULATES Co-58 Co-60 CI 0
CI SR-90 Y- 0 I-133 TOTAL FOR PERIOD ABOVE CI 0
GI 0
GI CI 4.12E-03 1.04E-04 GI 0
CI 5.93E-03 3.31E-04


FLORIDA POWER     & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMIANNUAL REPORT Table 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION         QUARTER 8   NA AGE GROUP:     INFANT         EXPOSURE INTRVAL: FROM Janua           1, 1984   THROUGH   December 31, 1984 BONE            LIVER            THYROID              KIDNEY          LUNG            GI-LII      T. BODY PATHWAY                 (mrem)          (mrem)            (mr em)              (mrem)        (mrem)            (mrem)        (mrem)
FLORIDA POWER
Ground Plane (A)           0                  0                  0                0              0                0      9.5  E-4 Grass-Cow-Milk (B)         1.42 E-2       2.28 E-2             5.43 EO          6.80 E-3       5.8 E-3      6.53 E-3       1.56 E-2 Inhalation (A)         2.14 E-4      4.38 E-3           8.30 E-2            1.89 E-3       4.1 E-3      4 ~ 12 E-3    4.22 E-3 TOTAL               1.44 E-2       2 ~ 72 E-2           5 '1   EO       8.69 E-3         9.9 E-3       1.07 E-2       2.08 E-2 (A)   SECTOR:     WEST       RANGE:   1.78 miles         B)     COW/GOAT     SECTOR:   WNW       RANGE:   Default, 4.25 miles QUARTER                   CALENDAR YEAR (ABOVE TIME INTERVAL)                     (mrad)
& LIGHT COMPANY ST.
NOBLE GASES                        (mr ad)
LUCIE UNIT NO.
Gamma  Air Dose                          NA                        3.05 E-1 Beta  Air Dose                                                      6.24 E-l Sector:  West                    Range:    1.78 miles Note:   The dose values above were         calculated using actual meteorological data during the specified time interval with MET data reduced as per Reg. Guide 1.111, March 1976.
1 SEMIANNUAL REPORT Table 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION QUARTER 8 NA AGE GROUP:
INFANT EXPOSURE INTRVAL:
FROM Janua 1, 1984 THROUGH December 31, 1984 PATHWAY Ground Plane (A)
Grass-Cow-Milk (B)
Inhalation (A)
BONE (mrem) 0 1.42 E-2 2.14 E-4 LIVER (mrem) 0 2.28 E-2 4.38 E-3 THYROID (mrem) 0 5.43 EO 8.30 E-2 KIDNEY (mrem) 0 6.80 E-3 1.89 E-3 LUNG (mrem) 0 5.8 E-3 4.1 E-3 GI-LII (mrem) 0 6.53 E-3 4 ~ 12 E-3 T.
BODY (mrem) 9.5 E-4 1.56 E-2 4.22 E-3 TOTAL 1.44 E-2 2 ~ 72 E-2 5'1 EO 8.69 E-3 9.9 E-3 1.07 E-2 2.08 E-2 (A)
SECTOR:
WEST RANGE:
1.78 miles B)
COW/GOAT SECTOR:
WNW RANGE:
Default, 4.25 miles NOBLE GASES Gamma Air Dose Beta Air Dose Sector:
West QUARTER (ABOVE TIME INTERVAL)
(mrad)
NA Range:
1.78 miles CALENDAR YEAR (mrad) 3.05 E-1 6.24 E-l Note:
The dose values above were calculated using actual meteorological data during the specified time interval with MET data reduced as per Reg. Guide 1.111, March 1976.


Page   le FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 2 SEMIANNUAL REPORT July 1 1984       THROUGH December 31   1984 TABLE 3 6-2 GASEOUS EFFLUENTS SlMHATION OF ALL RELEASES NUCLIDES RELEASED                 UN ZT   QUARTER     QUARTER A. Fission and Activation   Gases 1~   Total Release                           CI     1.84'3
Page le FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 2
: 2. Avera e Release Rate   for Period     ucI/sec 2.31E+02   3.20E<02 (B Iodines 1~ Total Iodine-131                         cz     7. 61E-03 2. 36E-01     (
SEMIANNUAL REPORT July 1
2~   Avera e Release Rate   for Period     ucI/sec 9 '7E-04   2 '7E-02 C Particulates 1 ~ Particulates T-1/2 > 8 Days         (
1984 THROUGH December 31 1984 TABLE 3 6-2 GASEOUS EFFLUENTS SlMHATION OF ALL RELEASES NUCLIDES RELEASED UN ZT QUARTER QUARTER A.
cz     6.5$ E-05 2.34E-04 2    Average Release Rate  for Period    (
Fission and Activation Gases 1 ~
ucZ/sec 8.29E-06   2.94E-05 3 ~  Gross Al ha  Radioactivit                cz     4 '8E-21   8 '0E-21 D. Tritium 1   Total Release                           cz     6.96E+01   1.64E>02 2~   Avera e Release Rate   for Period     ucz/sec
Total Release CI 1.84'3 2.
Avera e Release Rate for Period ucI/sec 2.31E+02 3.20E<02 (B
Iodines 1 ~
Total Iodine-131 cz
: 7. 61E-03
: 2. 36E-01
(
2 ~
Avera e Release Rate for Period ucI/sec 9 '7E-04 2 '7E-02 C
Particulates 1 ~
Particulates T-1/2 > 8 Days 2
Average Release Rate for Period 3 ~
Gross Al ha Radioactivit
(
cz 6.5$ E-05 2.34E-04
( ucZ/sec 8.29E-06 2.94E-05 cz 4 '8E-21 8 '0E-21 D.
Tritium 1
Total Release cz 6.96E+01 1.64E>02 2 ~
Avera e Release Rate for Period ucz/sec


Page SEMIANNUAL REPORT TABLE 3.7-2
FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO.
                                              " D~
2 SEMIANNUAL REPORT "D~
FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO. 2 GASEOUS EFFLUENTS CONTINUOUS MODE            BATCH MODE NUCLIDES RELEASED   UNIT   QUART         QUART M    UARTER         UART EK 1 ~   FISSION GASES AR-41     CI                                            1. E 4.00E-O CI  1. 79E+01      9.28E 00  9.48E-02      9.74E-O CI CI XE-131M      CI   0 XE-1        CI   1.53E+03        .28E+03 XE-1        CI  5.39E 0 XE-135      CI  1.71E+02       1.20E 02 XE-1324      CI XE-138      cr TOTAL FOR PERIOD ABOVE    CI  1.73E<03       1.42E003 1. 18E+02     8.98E   2 2     IODINES I-131         CI I-13         CI   1.90E-02      6.98 -02 CI TOTAL FOR PERIOD ABOVE    CI   2.66E-02       3.06E-01 3 ~   PARTICULATES Co-58       CI Co-60       CI SR-90       CI Y-90       CI CI   6.59 -   5 CI CI OT      0 PERIOD ABOVE    CI  6.59E-05       2.34E-04
TABLE 3.7-2 GASEOUS EFFLUENTS Page CONTINUOUS MODE NUCLIDES RELEASED UNIT QUART QUARTM BATCH MODE UARTER UARTEK 1 ~
FISSION GASES AR-41 XE-131M XE-1 XE-1 XE-135 XE-1324 XE-138 TOTAL FOR PERIOD ABOVE CI CI CI CI CI CI CI CI CI cr CI
: 1. 79E+01 0
1.53E+03 5.39E 0
1.71E+02 1.73E<03 9.28E 00
.28E+03 1.20E 02 1.42E003 9.48E-02
: 1. 18E+02 1.
E 4.00E-O 9.74E-O 8.98E 2
2 IODINES I-131 I-13 TOTAL FOR PERIOD ABOVE CI CI 1.90E-02 CI CI 2.66E-02 6.98 -02 3.06E-01 3 ~
PARTICULATES Co-58 Co-60 CI CI SR-90 Y-90 OT 0
PERIOD ABOVE CI CI CI CI CI CI 6.59 -
5 6.59E-05 2.34E-04


FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT Table 3.8-2 GASEOUS EFFLUENTS DOSE SUMMATION         QUARTER //   NA AGE GROUP:         INFANT     EXPOSURE INTRVAL: FROM Janua           1, 1984   THROUGH December 31, 1984 BONE          LIVER          THYROID          KIDNEY            LUNG          GI-LII        To BODY PATHWAY                         (mrem)        (mrem)          (mrcm)            (mrem)          (mrem)          (mrem)        (mrem)
FLORIDA POWER
Ground Plane   (A)                     0                0              0                0                0              0  4.78 E-4 Grass-Cow-Milk (B)                 1.51 E-2       2.00 E-2         5.78 E-O         5.4 E-3          2.10 E-3       2.79 E-3      1 ~ 25 E-2 Inhalation (A)                 1.41 E-4      1.64 E-3         5.51 E-2        6.83 E-4         1.47 E-3      1.48 E-3      1 '0   E-3 TOTAL                       1.52 E-2, 2.16     E-2         5.84 E-0         6. 1 E-3         3.57 E-3       4.27 E-3     1.46 E-2 (A)   SECTOR:   WEST               RANGE:   1.78 miles     B)   COW/GOAT     SECTOR:     WNW       RANGE:   Default, 4.25 miles QUARTER                 CALENDAR YEAR (ABOVE TIME INTERVAL)               (mrad)
& LIGHT COMPANY ST. LUCIE UNIT NO.
NOBLE GASES                              (mr ad)
2 SEMIANNUAL REPORT Table 3.8-2 GASEOUS EFFLUENTS DOSE SUMMATION QUARTER //
Gamma  Air Dose                                                        6.29 E-2 Beta  Air                                                              1.24 E-1 Dose'ector:
NA AGE GROUP:
West                        Range:    1.78 miles NOTE:  The dose values above were             calculated using actual meteorological data during the specified time           interval with   MET data reduced as per Reg. Guide 1.111, March 1976.
INFANT EXPOSURE INTRVAL:
FROM Janua 1, 1984 THROUGH December 31, 1984 PATHWAY Ground Plane (A)
Grass-Cow-Milk (B)
Inhalation (A)
BONE (mrem) 0 1.51 E-2 1.41 E-4 LIVER (mrem) 0 2.00 E-2 1.64 E-3 THYROID (mrcm) 0 5.78 E-O 5.51 E-2 KIDNEY (mrem) 0 5.4 E-3 6.83 E-4 LUNG (mrem) 0 2.10 E-3 1.47 E-3 GI-LII (mrem) 0 2.79 E-3 1.48 E-3 To BODY (mrem) 4.78 E-4 1 ~ 25 E-2 1'0 E-3 TOTAL 1.52 E-2, 2.16 E-2 5.84 E-0
: 6. 1 E-3 3.57 E-3 4.27 E-3 1.46 E-2 (A)
SECTOR:
WEST RANGE:
1.78 miles B)
COW/GOAT SECTOR:
WNW RANGE:
Default, 4.25 miles NOBLE GASES Gamma Air Dose Beta Air Dose'ector:
West QUARTER (ABOVE TIME INTERVAL)
(mrad)
Range:
1.78 miles CALENDAR YEAR (mrad) 6.29 E-2 1.24 E-1 NOTE:
The dose values above were calculated using actual meteorological data during the specified time interval with MET data reduced as per Reg.
Guide 1.111, March 1976.


Page  21 FLORIDA POWER 6 LIGHT COMPANY ET. LUCIE UNIT NO. I & 2 EENIANNUAL REPORT July 1, 1984     THROUGH December 31, 1984 TABLE 3 "
FLORIDA POWER 6 LIGHT COMPANY ET. LUCIE UNIT NO. I &
COMBINED SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A     SOLID WASTE SHIPPED OFFSITE FOR BURIAL         OR DISPOSAL   (Not irradiated   fuel) 6-month      Es t. Total
2 EENIANNUAL REPORT July 1, 1984 THROUGH December 31, 1984 TABLE 3 "
: 1. T   e of waste                             Unit        Pe riod        Error, X
COMBINED SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Page 21 A
: a. Spent resins, filter sludges           m3    t 1.2E1 2.0E1 I             eva orator bottoms, etc.               Ci       7.0E2
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1.
: b. Dry compressible waste;           l   >>      )
T e of waste a.
6.6E2 l
Spent resins, filter sludges I
2.0E1 l            contaminated equip, etc.               Ci      3.9E1
eva orator bottoms, etc.
: c. Irradiated components, I
6-month Es t. Total Unit Pe riod
control rods, etc.                     Ci
: Error, X
: d. Other (describe)                   I   m3 Ci
m3 t 1.2E1 Ci 7.0E2 2.0E1 b.
: 2. Estimate of major composition (by type of waste) a       Co 60 Co - 58 Fe--   55 3.0E1 Cs  - 134                                    1.4E1
Dry compressible waste; l
: b.       H-3                                           2.4E1 Co-                                           2.9E1 S--
contaminated equip, etc.
S I   - 131                                     4.1EO
c.
: 3. Solid Waste Disposition Number   of Shi ments         Mode of Trans ortation                 Destination 10                   SOLE USE TRUCK                         BARNWELL, S CN 12                    SOLE USE TRUCK                        RICHLAND, WASH ~
Irradiated components, I
BE   IRRADIATED FUEL SHIPMENTS       (Disposition)
control rods, etc.
Number   of Shi ments         Mode of Trans ortation                 Destination
d.
Other (describe) l
) 6.6E2 Ci 3.9E1 Ci I
m3 Ci l
2.0E1 2.
Estimate of major composition (by type of waste) a Co 60 Co - 58 Fe--
55 Cs - 134 3.0E1 1.4E1 b.
H-3 Co-S--
S I
- 131 2.4E1 2.9E1 4.1EO 3.
Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 10 12 SOLE USE TRUCK SOLE USE TRUCK BARNWELL, S CN RICHLAND, WASH ~
BE IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shi ments Mode of Trans ortation Destination


FLORIDA POWER 5 LIGHT COHPANY ST. LUCIE UNIT NOS. I AND 2 EERIARRRIIL REPOSER JULY   I, 1984 THROUGH DECEMBER   31, 1984 Solid Waste Supplement Total   Total Note I                                 Type Note 3 Type  "    4    Solidification Waste         Volume  Curie        Principal "                    of              R. G. 1.21 of                    Agent Classification Cu-Ft  ~oaottt      Radionuclides                  Waste            ~Cate or Container          or Absorbent Class A        22,272    11.27      None                            PWR  Trash            l.b Non-Specification       None Strong Tight Pkg.
FLORIDA POWER 5 LIGHT COHPANY ST.
Class A            780  25.04      63NI 90Sr      137C5            PWR  Trash            l.b  NRC Certified           None LSA > Type A Class 8           195   3.188     63Ni   90Sr p 137Cs           PWR Trash             l.b NRC Certi fied         Hone LSA > Type A Class 8            195  278.61      14C  60Co    63Ni            PWR  Ion-              l.a. NRC Certified           None 90Sr                            Exchange Resins            LSA > Type A Class 8           121   4.817     60Co 63Ni       90Sr           PWR  Filters          I.a. NRC  Certified          None 131Cs                                                       Type 8 Class C            121  417.12      14C   60()
LUCIE UNIT NOS. I AND 2 EERIARRRIIL REPOSER JULY I, 1984 THROUGH DECEMBER 31, 1984 Solid Waste Supplement Waste Classification Class A
1 63Ni            PWR lon-             l.a. NRC Certified           None 90sr,      Cs                  Exchange Resins,            Type 8
Class A
Total Volume Cu-Ft 22,272 780 Total Note I Curie
~oaottt 11.27 25.04 Principal "
Radionuclides None 63NI 90Sr 137C5 Type Note 3
of Waste PWR Trash PWR Trash R.
G. 1.21
~Cate or l.b l.b Type "
4 of Container Non-Specification Strong Tight Pkg.
NRC Certified LSA > Type A
Solidification Agent or Absorbent None None Class 8
Class 8
195 195 3.188 278.61 63Ni 90Sr p
137Cs 14C 60Co 63Ni 90Sr PWR Trash PWR Ion-Exchange Resins l.b l.a.
NRC Certi fied LSA > Type A NRC Certified LSA > Type A Hone None Class 8
Class C
121 121 4.817 417.12 60Co 63Ni 90Sr 131Cs 14C 60()
63Ni
: 90sr, 1
Cs PWR Filters PWR lon-Exchange
: Resins, I.a.
l.a.
NRC Certified Type 8 NRC Certified Type 8 None None


Pace 23 FLORIDA POWER 5 LIGHT COMPANY ST. LUCIE UNIT NOS. 1 AND 2 SEMIANNUAL REPOSER JULY 1, 1984 THROUGH DECEMBER     31, 1984 TABLE 3.9 Cont.
Pace 23 FLORIDA POWER 5 LIGHT COMPANY ST.
Solid Waste Supplement Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Luci e Plant are determined using a combination of qualitative and quantitative techniques. In general, the St.
LUCIE UNIT NOS.
1 AND 2 SEMIANNUAL REPOSER JULY 1, 1984 THROUGH DECEMBER 31, 1984 TABLE 3.9 Cont.
Solid Waste Supplement Note 1:
The total curie quantity and radionuclide composition of solid waste shipped from the St. Luci e Plant are determined using a combination of qualitative and quantitative techniques.
In general, the St.
Lucie Plant follows the guidelines outlined in the Low-Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/11/83) for these determinations.
Lucie Plant follows the guidelines outlined in the Low-Level Waste Licensing Branch Technical 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-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 most frequently used techniques for determining the total curie quantity in a package are the dose-to-curie methods and the (Concentration)
The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitter s, and periodic offsite analyses for other radionuclides. The onsite analyses are performed either on a batch basis or on a routi,ne basis using reasonably representative samples as appropriate for the waste type. Offsite analyses are used to a~tab/ash scaling factors or other estimates for radi onucl ides such as   H, C Tc   129I   TRU   1Pu t 242Cm 63Ni R
X (Volume or Mass) calculations.
5 Fe.
Where appropriate, engineering type activation analyses may be applied.
and Note 2: "Principal Radionuclides" refers to those radionuclides contained in the waste in concentrations greater than .Ol times the concentration of that nuclide listed in Table 1 or .01 times the smallest concentration of that nuclide listed in Table 2 of 10CFR61.
Since each of the above methodologies involves to some extent qualitative parameters, the total curie quantity is considered to be an estimate.
Note 3: "Type of Waste" is generally specified as described in NUREG 0782, Draft Environmental Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste".
The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitter s, and periodic offsite analyses for other radionuclides.
Note 4: "Type of Container"   refers to the transport package.
The onsite analyses are performed either on a batch basis or on a routi,ne basis using reasonably representative samples as appropriate for the waste type.
Offsite analyses are used to a~tab/ash scaling factors or other estimates for radi onucl ides such as H,
C Tc 129I TRU 1Pu 242Cm 63Ni R
t and 5 Fe.
Note 2:
"Principal Radionuclides" refers to those radionuclides contained in the waste in concentrations greater than.Ol times the concentration of that nuclide listed in Table 1 or.01 times the smallest concentration of that nuclide listed in Table 2 of 10CFR61.
Note 3:
"Type of Waste" is generally specified as described in NUREG 0782, Draft Environmental Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste".
Note 4:
"Type of Container" refers to the transport package.


FLORIDA POWER 6 LIGHT COMPANY ST. LOUIE UNIT NO. I S 2 SEMIANNUAL REPORT ATTACHMENT' CHANGES TO PROCESS   CONTROL PROGRAM DURING PERIOD JULY   1, 1984 THROUGH DECEMBER 31, 1984 A. 1. Paragraphs 3.1, 3.2.2, 3.2.3, 3.4.1, 3.4.3, 3.4.5, 3.4.8, 4.2, 5.3 and 6.4 of Revision 3 add to the process control program the waste form classification item per the implementation of 10 CFR, part 61 and 10 CFR 20,311.
FLORIDA POWER 6 LIGHT COMPANY ST.
: 2. Paragraphs 3.2.1.B and 3.2.1.C of Revision 4 make CNSI project num-bers consistent with references listed in 6.2 and 6.3.
LOUIE UNIT NO. I S 2
: 3. Paragraph 6.1 of Revision 4 changed the Dewatering procedure to   ~
SEMIANNUAL REPORT ATTACHMENT' CHANGES TO PROCESS CONTROL PROGRAM DURING PERIOD JULY 1, 1984 THROUGH DECEMBER 31, 1984 A.
Chem-nuclear Bead Dewatering procedure for CNSI 14-195 or smaller liners   FO-OP-023.
1.
B. The above changes   were administrative changes and did not reduce the overall conformance of the dewatered bead resin to existing criteria for radioactive wastes.
Paragraphs 3.1, 3.2.2, 3.2.3, 3.4.1, 3.4.3, 3.4.5, 3.4.8, 4.2, 5.3 and 6.4 of Revision 3 add to the process control program the waste form classification item per the implementation of 10 CFR, part 61 and 10 CFR 20,311.
C. Documentation of the review and acceptance of the changes by   FRG is on the cover sheet of the attached procedure.
2.
Paragraphs 3.2.1.B and 3.2.1.C of Revision 4 make CNSI project num-bers consistent with references listed in 6.2 and 6.3.
3.
Paragraph 6.1 of Revision 4 changed the Dewatering procedure to
~
Chem-nuclear Bead Dewatering procedure for CNSI 14-195 or smaller liners FO-OP-023.
B.
The above changes were administrative changes and did not reduce the overall conformance of the dewatered bead resin to existing criteria for radioactive wastes.
C.
Documentation of the review and acceptance of the changes by FRG is on the cover sheet of the attached procedure.


Page   1   of 5 FLORIDA POWER & LIGHT COMPANY ST+ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025 REVISION 4
Page 1 of 5 FLORIDA POWER
~ ~o TETLrE:
& LIGHT COMPANY ST+ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025 REVISION 4
iNEGRMQiai GND                    use, controlled. Before PROCESS CONTROL PROGRAM                                   ent is not 2EO   REVIEW AND APPROVAL:                             'f >n formabon with a cont venfy Reviewed by   Facility   Review Group                                 December 28      1982 Approved by       J. H Barrow (for)       Plant Manager           December     28, 1982 Revision   4 Reviewed by F R G                                             <>4        iSd    4
~ ~o TETLrE:
    .Approved by                                   ant Manager                     3     19 3,0   SCOPE:
PROCESS CONTROL PROGRAM 2EO REVIEW AND APPROVAL:
3~1 Purpose The St ~ Lucie Plant Process Control Program (PCP) implements the requirements of the St, Lucie Plant Technical Specifications for both units       Specifically, the PCP applies to waste form classification of all radioactive waste destined for land burial in accordance with 10 CFR 20,311, dewatering of bead resins for disposal, and solidification, encapsulation, or absorption vendor supplied processes for liquid radioactive waste 3+2 Discussion
Reviewed by Facility Review Group Approved by J.
                                'R4 I~   The PCP contains provisions to assure that dewatering of bead resins 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 procedures:
H Barrow (for) iNEGRMQiai GND ent is not controlled. Before use, a cont venfy >n
A     St ~ Lucie Plant Operating Procedure No, 0520023, "Dewatering Radioactive Bead Resins" ~
'f formabon with December 28 1982 Plant Manager December 28, 1982 Revision 4 Reviewed by F R G
BE   CHEM-NUCLEAR SYSTEMS,   IN'est     procedure for Dewatering Conical Bottom Demineralizers and Resin Liners - Project Noo 11118 C     CHEM-NUCLEAR SYSTEMS,   IN'ab     Record Sheet for Conical Bottom Demineralizers and Resin Liners >> Prospect No, 11118.                       /R4 2, Vendor supplied processes     for solidification, encapsulation, or absorption of liquid radioactive waste is handled under a topical report which the vendor has submitted to the Nuclear Regulatory Commission for approval or under an N,R,C approved process control program. Controlled copies of appropriate vendor procedures for these processes must be used to assure provision under the topical report are met ~
.Approved by ant Manager
<>4 iSd 4 3
19 3,0 SCOPE:
3 ~ 1 Purpose The St ~ Lucie Plant Process Control Program (PCP) implements the requirements of the St, Lucie Plant Technical Specifications for both units Specifically, the PCP applies to waste form classification of all radioactive waste destined for land burial in accordance with 10 CFR 20,311, dewatering of bead resins for
: disposal, and solidification, encapsulation, or absorption vendor supplied processes for liquid radioactive waste 3+2 Discussion I ~
The PCP contains provisions to assure that dewatering of bead resins 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 procedures:
A St ~ Lucie Plant Operating Procedure No, 0520023, "Dewatering Radioactive Bead Resins"
~
BE CHEM-NUCLEAR SYSTEMS, IN'est procedure for Dewatering Conical Bottom Demineralizers and Resin Liners - Project Noo 11118'R4 C
CHEM-NUCLEAR SYSTEMS, IN'ab Record Sheet for Conical Bottom Demineralizers and Resin Liners >> Prospect No, 11118.
/R4 2,
Vendor supplied processes for solidification, encapsulation, or absorption of liquid radioactive waste is handled under a
topical report which the vendor has submitted to the Nuclear Regulatory Commission for approval or under an N,R,C approved process control program.
Controlled copies of appropriate vendor procedures for these processes must be used to assure provision under the topical report are met ~


Page 2  of 5 ST, LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS   CONTROL PROGRAM 3eO SCOPE:   (continued) 3 2 Discussion:     (continu'ed) 3~   All radioactive     waste shiped for land burial must beet the requirements of 10      CFR 20 311  regarding waste form classification and packaging This is implemented through procedure HP-47, "Classification of Radioactive Waste'aterial for Lend Disposal" ~
ST, LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM Page 2 of 5
3.3  Authority The  authority    and  responsibility to perform the requirements of this procedure come from 10 CFR 20, 10 CFR 61, St Lucie Plant Unit            1 Technical Specifications, St ~ . Lucie Plant Unit 2 Technical Specifications, and from disposal site criteria, 3,4  Definitions 1    Abso tion - The process of absorbing          liquid radioactive  waste mater a s onto an absorbent material, a  final disposal    package which contains  radioactive bead  resins material within cement-like material, such that the final product is a free-standing monolith 4    "Free Standin " Water      -  Liquid which is not retained  by the waste orm, 5~  Solidification      - The  process of solidifying liquid radioactive waste material      in cement-like material, such that the final product is    a  free<<standing monolith 6    Process  Coritiol Pro am (PCP) - The Process Control Program s      conta n t e provisions, based on full scale testing, to assure that dewatering of radioactive bead resins 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 at the time of disposal 7    Visual Ins ection  The direct observation of the bead resins uring t e ent re period of resin transfer as they are packaged in the final disposal container 8    Waste Form    Classification    - Classification of radioactive  waste
3eO SCOPE:
(continued) 3 2 Discussion:
(continu'ed) 3 ~ All radioactive waste shiped for land burial must beet the


Page 3 of 5 ST, LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025,       REVISION 4 PROCESS  CONTROL PROGRAM 4+0  PRECAUTIONS:
requirements of 10 CFR 20 311 regarding waste form classification and packaging This is implemented through procedure HP-47, "Classification of Radioactive Waste'aterial for Lend Disposal" ~
4 1 Process Control Procedures used for the dewatering of radioactive bead resins that establish the conditions that must be met shall be based on   full scale testing, This is to provide reasonable assurance that the dewatering of the resin and disposal container will  result in volumes of free standing water, at the time of disposal, within the limits of 10CFR, Part 61 as implemented by 10CPR20 and of the low level radioactive waste disposal site, 4+2  Vendor supplied    solidification, encapsulation,  and  absorption processes shall be NRC approved or under a topical report which has been submitted to NRC fgor approval        Procedures which are to be used must be controlled per the vendor's gA program, 4+3  In lieu of dewatering performed as per the Process Control Procedures,    a visual inspection of the bead resin as    it is transferred and of the final disposal container after loading may be performed    if conditions permit, This inspection must be conducted in a manner that will assure that the free standing liquids will meet shipping, transportation and disposal site requirements, 4,4  All changes    to the St ~ Lucie Plant Process Control Program must be reviewed and approved by the      Facility Review Group before they become    effective 4i5  All changes to the St, Lucie Plant Process Control Program must be submitted to 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:
3.3 Authority The authority and responsibility to perform the requirements of this procedure come from 10 CFR 20, 10 CFR 61, St Lucie Plant Unit 1
1 ~  Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information, 2,  A  determination that the change did not reduce the overall conformance of the dewatered bead resins to existing criteria for solid wastes'
Technical Specifications, St ~
            ~  Documentation of the fact that the change has been reviewed and found acceptable by the Pacility Review Group 5+0 RESPONSIBILITIES:
. Lucie Plant Unit 2 Technical Specifications, and from disposal site criteria, 3,4 Definitions 1
5~1  It is  the rdsponsibility of the Plan't Manager to assure that all necessary procedures, equipment and support are provided to properly implement the PCS 5+2  It is the responsibility of the Health Physics Supervisor or his designee to assure that the radioactive bead resin will be dewatered in accordance with the PCP 5+3  It is the responsibility of the Health Physics Supervisor or his designee to assure that radioactive waste material is classified        in accordance with the PCP
Abso tion -
The process of absorbing liquid radioactive waste mater a s onto an absorbent
: material, a final disposal package which contains radioactive bead resins material within cement-like material, such that the final product is a free-standing monolith 4
"Free Standin
" Water -
Liquid which is not retained by the waste
: orm, 5 ~
Solidification - The process of solidifying liquid radioactive waste material in cement-like material, such that the final product is a free<<standing monolith 6
Process Coritiol Pro am (PCP) -
The Process Control Program s
conta n t e provisions, based on full scale testing, to assure that dewatering of radioactive bead resins 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 at the time of disposal 7
Visual Ins ection The direct observation of the bead resins uring t e ent re period of resin transfer as they are packaged in the final disposal container 8
Waste Form Classification - Classification of radioactive waste


6+0 7+0
ST, LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM Page 3 of 5 4+0 PRECAUTIONS:
4 1
Process Control Procedures used for the dewatering of radioactive bead resins that establish the conditions that must be met shall be based on full scale testing, This is to provide reasonable assurance that the dewatering of the resin and disposal container will result in volumes of free standing water, at the time of disposal, within the limits of 10CFR, Part 61 as implemented by 10CPR20 and of the low level radioactive waste disposal site, 4+2 Vendor supplied solidification, encapsulation, and absorption processes shall be NRC approved or under a topical report which has been submitted to NRC fgor approval Procedures which are to be used must be controlled per the vendor's gA program, 4+3 In lieu of dewatering performed as per the Process Control Procedures, a visual inspection of the bead resin as it is transferred and of the final disposal container after loading may be performed if conditions permit, This inspection must be conducted in a manner that will assure that the free standing liquids will meet shipping, transportation and disposal site requirements, 4,4 All changes to the St ~ Lucie Plant Process Control Program must be reviewed and approved by the Facility Review Group before they become effective 4i5 All changes to the St, Lucie Plant Process Control Program must be submitted to 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:
1 ~
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information, 2,
A determination that the change did not reduce the overall conformance of the dewatered bead resins to existing criteria for solid wastes'
~
Documentation of the fact that the change has been reviewed and found acceptable by the Pacility Review Group 5+0 RESPONSIBILITIES:
5 ~ 1 It is the rdsponsibility of the Plan't Manager to assure that all necessary procedures, equipment and support are provided to properly implement the PCS 5+2 It is the responsibility of the Health Physics Supervisor or his designee to assure that the radioactive bead resin will be dewatered in accordance with the PCP 5+3 It is the responsibility of the Health Physics Supervisor or his designee to assure that radioactive waste material is classified in accordance with the PCP
 
ST LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM Page 4 of 5
6+0


==REFERENCES:==
==REFERENCES:==
6,1 Bead Dewatering Procedure for CNSI 14-195 or smaller liners-FO-OP-023'R4 6'
Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners, Prospect No, 11118 6i3 Test Procedure for Dewatering Conical 'Bottom Demineralizers and Resin Liners, Prospect No, 11118 '
4 Health Physics Procedure, HP-47, "Classification of Radioactive Waste Material for Land Disposal" ~
7+0 RECORDS AND NOTIFICATIONS:
7' Records shall be as per St, Lucie Plant Operating Procedure No
: 0520023, "Dewatering Radioactive Bead Resins" ~
7,2 Notifications 1
If it is suspected that the free standing water requirements may not be met for any container of radioactive bead resin shipped to a disposal site, notify the Plant Manager and the Health
'hysics Supervisor.
2 ~ If the process control procedures have not been followed or if free standing water may be present in the final shipping container of bead resin in amounts greater than allowed by regulations, notify the Health Physics Supervisor or his
: designee,


6,1 6 '
ST>> LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM Page 5 of 5
Bead FO-OP-023  'R4          ST PROCESS Dewatering Procedure LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, CONTROL PROGRAM for CNSI 14-195 REVISION 4 or smaller Lab Record Sheet for Conical Bottom Demineralizers Prospect No, 11118 liners-and Resin 6i3 Test Procedure for Dewatering Conical 'Bottom Demineralizers and 4
8' INSTRUCTIONS:
Resin Liners, Prospect No, 11118 '
8,1 Dewatered radioactive bead resins:
Health Physics Procedure, HP-47, "Classification of Radioactive Waste RECORDS AND Material for Land Disposal" ~
1 Dispose of dewatered radioactive bead resins is limited to the following containers for which full scale dewatering tests have been conducted:
NOTIFICATIONS:
A CNSI Conical Bottom EnviroSAPE'High Integrity Container-PL6-80CR>>
Page 4 Liners, of 5 7 '  Records  shall  be as per St, Lucie Plant Operating Procedure   No 0520023,   "Dewatering Radioactive Bead Resins" ~
B CNSI Conical Bottom EnviroSAPE'High Integrity Container-PL14-195CR>>
7,2  Notifications 1        it If is suspected that the free standing water requirements may not be met for any container of radioactive bead resin shipped to a disposal site, notify the Plant Manager and the Health Supervisor.                                            'hysics 2~  If the process control procedures have not been followed or     if free standing water may be present in the final shipping container of bead resin in amounts greater than allowed by regulations, notify the Health Physics Supervisor or his designee,
C,'NSI Conical Bottom EnviroSAPE'High Integrity Container-PL8-1 20CR>>
2, Dewater the container as per St>> Lucie Plant Operating Procedure No
: 0520023, "Dewatering of Radioactive Bead Resins" ~
3 ~
In lieu of dewatering, radioactive bead resin may be shipped for disposal in a different container, provided the radiological and regulatory conditions permit, if a visual inspection of the resin during transfer and of final shipping container after loading can be conducted in a manner that will assure that the free standing, liquid volume present wilL meet shipping,'ransportation, and disposal site requirements, 4,
With dewatering not meeting disposal site, shipping, and transportation requirements, suspend shipment of the inadequately dewatered bead resin and correct the process control program, the applicable procedures(s),
and/or the dewatering system as necessary to prevent recurrence, 5 ~
With dewatering not performed in accordance with the PCP:
(1) if the dewatered bead resin has not already been shipped for disposal, verify each container to ensure that it meets burial ground, shipping and transportation requirements and/or (2) take appropriate administrative action to prevent recurrence 6 ~
Close the container as per the manufacturer's instructions' Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with vendor approved procedures' All radioactive waste material packaged and destined for land disposal shall conform to the requirements of 10 CPR 20,311 as implemented by procedure HP-47'f waste form classification exceeds Class C or packaging does not meet the requirements of the waste form class, the Health Physics Supervisor shall be notified and shipment shall not be made,


Page 5 of 5 ST>> LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025,        REVISION 4 PROCESS    CONTROL PROGRAM 8 ' INSTRUCTIONS:
O N tNFONMATION ON t.y ll d. Before uses t'ot controlled, B fore uses verify in o rination with a contro e
8,1  Dewatered  radioactive  bead  resins:
FLORIDA POWER tE LIGHT COMPANY ST ~ LVCIE PLANT ARtINISTRATIVE PROCEDURE NEtBER 0520025 REVISION 3 1,0 EXELE:
1  Dispose of dewatered radioactive bead resins is limited to the following containers for which full scale dewatering tests have been conducted:
PROCESS CONTROL PROGRAM 2 SO REVIEW AND APPROVAL:
A    CNSI Conical Bottom EnviroSAPE' High        Integrity Container-PL6-80CR>>
Pag OAYI EOCr~A/'
B  CNSI Conical Bottom EnviroSAPE' High        Integrity Container-PL14-195CR>>
g <~a~o SY$
C,'NSI    Conical Bottom EnviroSAPE' High        Integrity Container-PL8-1 20CR>>
coMp~~~Ppgy.:
2,  Dewater the container as per St>> Lucie Plant Operating Procedure No  0520023, "Dewatering of Radioactive Bead Resins" ~
IIII~
3~  In lieu of dewatering, radioactive bead resin may be shipped for disposal in a different container, provided the radiological and regulatory conditions permit,        if a visual inspection of the resin during transfer and of final shipping container after loading can be conducted in a manner that will assure that the free standing, liquid volume present wilL meet and disposal site requirements,    shipping,'ransportation, 4,  With dewatering not meeting disposal site, shipping, and transportation requirements, suspend shipment of the inadequately dewatered bead resin and correct the process control program, the applicable procedures(s), and/or the dewatering system as necessary to prevent recurrence, 5~  With dewatering not performed in accordance with the PCP:
Reviewed by Facility Review Group Approved by J
(1) if  the dewatered bead resin has not already been shipped for it        meets burial disposal, verify each container to ensure that ground, shipping  and  transportation  requirements                        and/or  (2) take appropriate administrative action to prevent recurrence 6~  Close the container as per the manufacturer's        instructions'
H. Barrow (for)
      '  Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with vendor approved procedures'
Plant 'Manager December 28, 1982 December 28, 1982 Revisioa 3 Reviewed by F R G Approved by 3,0 SCOPE:
      '  All radioactive
Plant Manager 1
                                              'f waste material packaged and destined for land disposal shall conform to the requirements of 10 CPR 20,311 as implemented by procedure HP-47            waste form classification exceeds Class C or packaging does not meet the requirements of the waste form class, the Health Physics Supervisor shall be notified and shipment shall not be made,
1I Sh' j&j 3.1 Purpose The St Lucie Plant Process Control Program (PCP) implements the requirements of the St Lucie Plant Technical Specifications for botn
 
: units, Specifically, the PCP applies to waste form classification of all radioactive waste destined for land burial in accordance with 10 CFR 20'11, dewatering of bead resins for disposal, aad solidification, encapsulation, or absorption vendor supplied processes for liquid radioactive waste~
ATION        ON t.y O N tNFONMcontrolled,                                                                  Pag t 'ot B fore uses ll d. Before contro  e
3 2 Discussion 1,
                '            with a verify in o rination FLORIDA POWER tE LIGHT COMPANY ST ~ LVCIE PLANT ARtINISTRATIVE PROCEDURE NEtBER 0520025 OAYI
The PCP contains provisions to assure tnat dewatering of bead resins results ia a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 20 and of tae low level radioactive waste disposal site The Process Control Program includes in addition to this procedure the following related procedures:
                                                                                                      ~A/     '
A St Lucie Plant Operating Procedure No
                                                                                                    ~
: 0520023, "Qewateriag Radioactive Bead Resias"
REVISION 3                          EOCr g <~a~o 1,0    EXELE:                                                                        SY$
~
PROCESS    CONTROL PROGRAM                                                    coMp~~~Ppgy.:
B QKN-NUCLEAR SYST&fS, INC Test procedure for Dewateriag Conical Bottom Demiaeralizers and kesin Liners - Project, No
IIII 2 SO    REVIEW AND APPROVAL:
: 11118, 10/05/81 C
Reviewed by     Facility     Review Group                               December 28, 1982 Approved by           J   H. Barrow     (for)       Plant 'Manager     December 28, 1982 Revisioa     3 Reviewed     by F R G Approved by                                           Plant Manager 3,0     SCOPE:
QQ8-NUCLEAR SYSTEMS, INC Lab Record Sheet for Conical ttottom Demiaeralizers and Resin Liners - Project No. 11118; 10/01/81.
3.1   Purpose The St     Lucie Plant Process Control Program (PCP) implements the requirements of the St Lucie Plant Technical Specifications for botn units, Specifically, the PCP applies to waste form classification of 1I Sh' j&j                    all radioactive waste destined for land burial in accordance with 1
2 ~
10 CFR 20 '11, dewatering of bead resins for disposal, aad solidification, encapsulation, or absorption vendor supplied processes for liquid radioactive           waste~
Vendor supplied processes for solidification, encapsulation, or absorption of liquid radioactive waste is handled under a topical I
3 2   Discussion 1,   The PCP contains       provisions to assure tnat dewatering of bead resins results ia a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 20 and of tae low level radioactive waste disposal site               The Process Control Program includes in addition to this procedure the following related procedures:
report which the vendor has submitted to the Nuclear Regulatory Commission for approval or uader aa N.R.C approved process coatrol program Controlled copies of appropriate vendor procedures for these processes must be used to assure provision under the topical.
A   St Lucie Plant Operating Procedure No 0520023, "Qewateriag Radioactive Bead Resias" ~
B     QKN-NUCLEAR SYST&fS, INC Test procedure for Dewateriag Conical Bottom Demiaeralizers and kesin Liners - Project, No 11118, 10/05/81 C   QQ8-NUCLEAR SYSTEMS, INC Lab Record Sheet for Conical ttottom Demiaeralizers and Resin Liners - Project No. 11118; 10/01/81.
2~   Vendor supplied processes           for solidification, encapsulation, or absorption of liquid radioactive waste         I is handled under a topical report which the       vendor   has submitted to the Nuclear Regulatory Commission for approval or uader aa N.R.C approved process coatrol program       Controlled copies of appropriate vendor procedures for these processes must be used to assure provision under the topical.
report are met~
report are met~


Page   2- of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUNSK8. 0520025,             REVISION   3 PROCES   S CONTROL PROGRAM 3 0 SCOPE:   (ccaciaued) sion'(continued) 3 2 3  'll Discus radioactive waste shiped for land burial must beet the requirements of 10 CFR 20,311 regarding waste form classification and packaging     This is implemented through procedure HP-47, "Classification of Radioactive Waste 8aterial for Land Disposal"           /RS 3 3   Authority The authority   and responsibility to perform the requirements of this procedure come from     10 CFR 20, 10 CFR 61, St Lucie Plant Unit   1 Technical Specifications, St Lucie Plant Unit 2 Technical Specifications, and from disposal site criteria 3 4   Definitions materials onto an absorbent material                                       /R3.
Page 2-of 5
2~   Dewaterin - The process of removing "free standing" water from a inal disposal package which contains radioactive bead resins, material within cement"like material, such that the final product is a freemtanding monolith 4   "Free Standin " Water - Liquid which is not retained by the waste orms 5~   Solidification   - The   process of solidifying liquid radioactive waste material in cement-like material, such that the final product is a free-standing monolith.                                               /R3 6~   Process Control Pro ram (PCP)     - The Process Control Program shall contain the provisions, based on full scale testing, to assure that dewatering of:radioactive bead resins 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 at the time of disposal, 7   Visual Ins ection The direct observation of the bead resins during the entire period of resin transfer as they are packaged in the final disposal container.
ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUNSK8. 0520025, REVISION 3
8~   Waste Form Classification - Classification of radioactive waste material based upon the concentrations of radionuclides identified.       /RS 4~0 PRECAUTIONS:
PROCES S CONTROL PROGRAM 3 0 SCOPE:
4 1 'rocess Control     Procedures used for the dewatering of radioactive bead resins that establish. the conditions that must be met shall be based on full scale testing This is to provide reasonable assurance that the dewatering of the resin and disposal container will result in volumes of free standing water, at the time of disposal, within the limits of 10CFR," Part 61 as implemented by 10CFR20'and of the low level radioactive waste disposal site
(ccaciaued) 3 2 Discus sion'(continued) 3 'llradioactive waste shiped for land burial must beet the requirements of 10 CFR 20,311 regarding waste form classification and packaging This is implemented through procedure HP-47, "Classification of Radioactive Waste 8aterial for Land Disposal"
/RS 3 3 Authority The authority and responsibility to perform the requirements of this procedure come from 10 CFR 20, 10 CFR 61, St Lucie Plant Unit 1
Technical Specifications, St Lucie Plant Unit 2 Technical Specifications, and from disposal site criteria 3 4 Definitions materials onto an absorbent material 2 ~
Dewaterin -
The process of removing "free standing" water from a inal disposal package which contains radioactive bead resins, material within cement"like material, such that the final product is a freemtanding monolith 4
"Free Standin " Water - Liquid which is not retained by the waste orms 5 ~
Solidification - The process of solidifying liquid radioactive waste material in cement-like material, such that the final product is a free-standing monolith.
6~
Process Control Pro ram (PCP) -
The Process Control Program shall contain the provisions, based on full scale testing, to assure that dewatering of:radioactive bead resins 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 at the time of disposal, 7
Visual Ins ection The direct observation of the bead resins during the entire period of resin transfer as they are packaged in the final disposal container.
8 ~
Waste Form Classification -
Classification of radioactive waste material based upon the concentrations of radionuclides identified.
/R3.
/R3
/RS 4~0 PRECAUTIONS:
4 1 'rocess Control Procedures used for the dewatering of radioactive bead resins that establish. the conditions that must be met shall be based on full scale testing This is to provide reasonable assurance that the dewatering of the resin and disposal container will result in volumes of free standing water, at the time of disposal, within the limits of 10CFR," Part 61 as implemented by 10CFR20'and of the low level radioactive waste disposal site


Page 3 of 5 ST LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025,             REVISION 3 PROCESS   CONTROL PROGRAM 4 0 PRECAUTIONS-     (continued) 4~2 Vendor supplied solidification, encapsulation, and absorption processes shaLL be NRC approved or uncover a topical report which has been submitted to NRC         approval. Procedures which are to be used est be controlled per t e vendor 's Qk program                                   /R3 4 3 In lieu of dewatering performed. as per the Process Control Procedures, a visual inspection of the bead resin as it is transferred and of the final disposal container after loading may be perforaad if conditions permit This inspection must be conducted in a manner that will assure that the free standing liquids will meet shipping, transportation and disposal site requirements 4 4 All changes to     the St, Lucie Plant Process Control Program est be reviewed and approved by the Facility Review Group before they become ef fective i 4 5 All changes to the St Lucie Plant Process Control Program axxst be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal
Page 3 of 5
        'must contain the     following:
ST LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 3
1     Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information, 2~   A determination that the change did not reduce the overall conformance of the dewatered bead resins to existing criteria   for solid wastes, 3 . Documentation of the fact that the change has been reviewed and found acceptable by the Facility Review Group 5rO RESPONSIBILITIES:
PROCESS CONTROL PROGRAM 4 0 PRECAUTIONS-(continued) 4~2 Vendor supplied solidification, encapsulation, and absorption processes shaLL be NRC approved or uncover a topical report which has been submitted to NRC approval.
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 ~
Procedures which are to be used est be controlled per t e vendor 's Qk program
5,2 It is   the responsibility of the Health Physics Supervisor or his designee to assure that the radioactive bead resin will be dewatered     in accordance with the PCP ~
/R3 4 3 In lieu of dewatering performed. as per the Process Control Procedures, a visual inspection of the bead resin as it is transferred and of the final disposal container after loading may be perforaad if conditions permit This inspection must be conducted in a manner that will assure that the free standing liquids will meet shipping, transportation and disposal site requirements 4 4 All changes to the St, Lucie Plant Process Control Program est be reviewed and approved by the Facility Review Group before they become effective i 4 5 All changes to the St Lucie Plant Process Control Program axxst be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made.
5.3 It is   the responsibility of the Health Physics Supervisor or his in designee to assure that radioactive waste material is classified accordance with the PCP.                                                     /R3
This submittal
'must contain the following:
1 Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information, 2 ~
A determination that the change did not reduce the overall conformance of the dewatered bead resins to existing criteria for solid wastes, 3
Documentation of the fact that the change has been reviewed and found acceptable by the Facility Review Group 5rO 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 the radioactive bead resin will be dewatered in accordance with the PCP ~
5.3 It is the responsibility of the Health Physics Supervisor or his designee to assure that radioactive waste material is classified in accordance with the PCP.
/R3


Page 4   of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION               3 PROCESS         CONTROL PROGRAM 6 e0
Page 4 of 5
ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 3
PROCESS CONTROL PROGRAM 6 e0


==REFERENCES:==
==REFERENCES:==
6~1 Dewatering Procedure for CNSI Conical-Bottom EnviroSAPE'High Integrity Containers (containing bead-type ion exchange resin) 1X free standing water - FOWP-003 6,2 Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners',
Prospect No, 11118 6 3 Test Procedure for Dewatering Conical Bortom Demineralizers and Kesin Linexs, Pro)ect No~
11118',4 Health Physics Pxocedure, HP-47, "Classification of Radioactive Waste Material for Land Disposal"',
/R3 7,0 RECORDS AND NOTIPICATIONS:
7,1 Records shall be as per St. Lucie Plant Operating Procedure No
: 0520023, "Dewatering Radioactive Bead Resins" ~
'7 2 Notifications 1 ~ If it, is suspected that the free standing water requirements may not be met for any container of xadioactive bead resin shipped to a disposal site, notify the Plant Manager and the Health Physics Supervisor~
2 ~ If the. process control procedures have not been followed or if free standing water may be present in the final shipping container of bead resin in amounts greater than allowed by regulations, notify the Health Physics Supervisor or his designee,


6~1  Dewatering Procedure for CNSI Conical-Bottom EnviroSAPE' High Integrity Containers (containing bead-type ion exchange resin)      1X free standing water - FOWP-003 6,2  Lab Record Sheet for Conical Bottom Demineralizers    and Resin  Liners',
Page 5 of 5
Prospect No, 11118 6 3  Test Procedure for Dewatering Conical Bortom Demineralizers and Kesin Linexs, Pro)ect No~    11118',4 Health Physics Pxocedure, HP-47, "Classification of Radioactive Waste Material for Land Disposal"',                                                    /R3 7,0  RECORDS AND  NOTIPICATIONS:
ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, dEVISION 3
7,1  Records shall be as per St. Lucie Plant Operating Procedure      No 0520023, "Dewatering Radioactive Bead Resins" ~
PROCESS CONTROL'ROGRAM 8 o0 INSTRUCTIONS:
    '7 2  Notifications 1~  If it, is suspected that the free standing water requirements may not be met for any container of xadioactive bead resin shipped to      a disposal site, notify the Plant Manager and the Health Physics Supervisor~
8 1
2~  If the. process  control procedures have not been followed or if free standing water    may be present in the final shipping container of bead resin in amounts greater than allowed by regulations, notify the Health Physics Supervisor or his designee,
Dewatered radioactive bead resins:
 
1 ~
Page 5 of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025,                 dEVISION     3 PROCESS     CONTROL'ROGRAM 8 o0 INSTRUCTIONS:
Dispose of dewatered radioactive bead resins is limited to the following containers for which full scale dewatering tests have been. conducted:
8 1   Dewatered     radioactive bead resins:
A CNSI Conical Bottom EnviroSAPE'High Integrity Container-PL6-80(Ro B
1 ~   Dispose   of dewatered radioactive bead resins is limited to the following containers for which full scale dewatering tests have been. conducted:
CNSI Conical Bottom EnviroSAPE~ High Integrity Container-PL14-195' CNSI Conical Bottom EnviroSAPE~ High Integrity Container-PL8-120(Ri 2i Dewater the container as per St, Lucie Plant Operating Procedure No
A   CNSI Conical Bottom EnviroSAPE' High     Integrity Container-PL6-80(Ro B   CNSI Conical Bottom EnviroSAPE~ High Integrity Container-PL14-195' CNSI Conical Bottom EnviroSAPE~ High Integrity Container-PL8-120(Ri 2i Dewater the container         as per St, Lucie Plant Operating Procedure 0520023, "Dewatering of Radioactive Bead Resins",
: 0520023, "Dewatering of Radioactive Bead Resins",
* No 3>>     In lieu of dewatering, radioactive bead resin may be shipped for disposal in a different container, provided the radiological and regulatory conditions permit,     if a visual inspection of the resin during transfer and of final shipping container after loading can be conducted in a manner that will assure that the free standing liquid volume present will meet shipping, transportation, and disposal site requirements 4,     With dewatering not meeting disposal     site,'hipping,   and transportation requireients, suspend shipment of the inadequately dewatered bead resin and correct the process control program, the applicable procedures(s),, and/or the dewatering system as necessary to prevent recurrence 5     With dewatering not performed in accordance wich the PCP:
3>> In lieu of dewatering, radioactive bead resin may be shipped for disposal in a different container, provided the radiological and regulatory conditions permit, if a visual inspection of the resin during transfer and of final shipping container after loading can be conducted in a manner that willassure that the free standing liquid volume present will meet shipping, transportation, and disposal site requirements 4,
(1) if the dewatered bead resin has not already, been shipped for it  meets burial
With dewatering not meeting disposal site,'hipping, and transportation requireients, suspend shipment of the inadequately dewatered bead resin and correct the process control program, the applicable procedures(s),,
                ~
and/or the dewatering system as necessary to prevent recurrence 5
disposal, verify each container to ensure that ground, shipping and transportation requirements and/or (2) take appropriate administrative action to prevent, recurrence.
With dewatering not performed in accordance wich the PCP:
6i Close the container       aa per the manufacturer 's instructions 8 2   Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with vendor approved procedures~
(1) if the dewatered bead resin has not already, been shipped for
8 3 All radioactive waste material packaged and destined for land disposal
~ disposal, verify each container to ensure that it meets burial ground, shipping and transportation requirements and/or (2) take appropriate administrative action to prevent, recurrence.
          =sha11 conform to the requireuents of 10 CHL 20i311 as implemented by procedure HP-47 ~       If waste form classification exceeds Class 0 or packaging does not meet, the requirements of the waste form. class, the Health Physics Supervisor shall be notified'and shipment shall not be made}}
6i Close the container aa per the manufacturer 's instructions 8 2 Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with vendor approved procedures~
8 3 All radioactive waste material packaged and destined for land disposal
=sha11 conform to the requireuents of 10 CHL 20i311 as implemented by procedure HP-47 ~ If waste form classification exceeds Class 0 or packaging does not meet, the requirements of the waste form.class, the Health Physics Supervisor shall be notified'and shipment shall not be made}}

Latest revision as of 15:13, 8 January 2025

Combined Semiannual Radioactive Effluent Release Rept, Jul-Dec 1984
ML17215A789
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 12/31/1984
From:
FLORIDA POWER & LIGHT CO.
To:
References
NUDOCS 8503200578
Download: ML17215A789 (37)


Text

{{#Wiki_filter:r'e i ~ mr , REGULATORY 1NFORNATION DISTRIBUTION SYSTEM gfP ~tt ~. ACCESSION NOP:850320057d DuCeDATE: 84/12/31 NOTARIZED: NO FACI<:50-335 St ~ Lucie~lantF Uni t 1 p F 1 orida Power 5 Light Co, 05000335 50-589 St. LucJe Plant-,Unit2, Florida Power 8 Light Co. 05000589 AUTH.frAlrE AUT4OR AFFILIATIOrf F 1 or i da Power R Light Co ~ REC I P ~ NAHEr REC IP Ir NI AF F ILI'ATION SUSJECT: "Combinedl Sem.iannua.r Radioactive Effluent Release

Rept, Ju-l--Dec, 198(."

DISTRIBUTION COOL:: IE25L COPIES RECEIVED:LTR ENCL P SIZEa TITLE: Periodic Environ monitoring Rept (50 DKT) Annual/Semiannua>/Effluent/ NOTES: OL:02/01/76 OL:04/06/83 05000335 0500038'St RFC IPIE.NT I 0 CODE/4At'E NRR OR83 BC 04 INTERNAL: ACRS 1> I E F ILK. 01 NRR~ I fit / 10 f< DANI/NIB COPIES LT TP. ENCL RE.C IP IENT lD CODE/NAHE NRR ORB3 BC Ott AEQD NRR/DV/EEB 08 NRR/DSI/METB RGN2/DRSS/EPRPB COPIES LTTR ENCL EXTERNAL: LPDR NRC PDR 02 TOTAL NUMBER OF COPIES REVUIRED: LTTR ENCL 26

FLORIDA P(NER & LIGHT QMPAHY SR ~ LUCIE PLANT UNIT NO I & 2 LICENSE NO DPR-67 & NPF-16 CABINED SEHI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD Jul 1, 1984 THROUGH December 31, 1984 8503200578 841231 PDR ADQCK 05000335 R

FLORIDA POWER & LIGHT COMPANY ET. LUOIE UNII NO. I E 2 SEMIANNUAL REPORT JULY 1, 1984 THROUGH DECEMBER 31 1984 TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION.oo ~ oo ~ ~ ol VISITOR DOSE ASSESSMENT.... ~... ~... ~.............. ~. ~.... ~. ~.5 OFFSITE DOSE CALCULATION MANUAL REVISIONS......... ~.. ~.......5 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS' ~ ~. ~ ~. ~ ~. ~ ~ ~. ~.5 PROCESS CONTROL PROGRAM REVISIONS. ~ os~ ~ .os~ .. ~. ~... ~ ~ ~. ~ 5 GAS ANALYZER INOPERABLE REPORT. ~ ~........ ~.... ~.. ~. ~. ~. ~ ~ ~ ~ ~ o6 LIQUID EFFLUENT: SU&fATION OF ALL RELEASES; NUCLIDE SUMMATION BY QUARTER, DOSE SUMMATION UNIT lo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ 7-10 UNIT 2o..o....oooo..o..oo..oooooooo.oo.ooo.o.oo.ll-l4 GASEOUS EFFLUENT SUMMATION OF ALL RELEASES, NUCLIDE SUMMATION BY QUARTER, DOSE SUMMATION UNIT 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15 17 UNIT 2o.........o.oooooo......o.o...o.ooooo.oo..18-20 SOLID WASTE SHIPMENT SUMMATIONoo ~..... ~........... ~......21-22 PROCESS CONTROL PROGRAM PAGE REVISIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ o.ATTACHMENT A

Page 1 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION 1. Regulatory Limits 1 ~ 1 For Liquid Waste Effluents a ~ The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble'gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10 micro curies/ml total activity. b. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to-'uring any calendar quarter to < 1.5 mrems to the total body and to < 5 mrems to any organ, and During any calendar year to < 3 mrems to the total body and to < 10 mrems to any organ. 1.2 For Gaseous Waste Effluents: a. The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site shall be limited to: For Noble Gases: < 500 mrems/yr to the total body and < 3000 mrems/yr to the skin, and For Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days: < 1500 mrems/yr to any organ.

  • b.

The air dose due to noble gases released in gaseous effluents from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following: During any calendar quarter, to < 5 mrad for gamma radiation and 10 mrad for beta radiation and, during any calendar year to 10 mrad for gamma radiation and < 20 mrad for beta radiation. c The dose to a MEMBQt OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form, with half-lives ) 8 days in gaseous effluents released, from each reactor unit to areas at an8 beyond the SQTE BOUNDARY, shall be limited to the following: During any calendar quarter to < 7.5 mrem to any organ, and during any calendar year to < 15 mrem to any organ.

  • The calculated doses contained in a semi-annual report shall not apply to any STS LCO.

The reported values are based on =actual release conditions instead of historical conditions that the STS LCO dose calculations are based on The STS LCO dose limits are therefore included in Item 1 of the report, for information only.

Page 2 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION continued) 2. Maximum Permissible Concentrations WATER: As per 10 CFR Part 20, Appendix B, Table II, Column 2, except for entrained or dissolved noble gases as described in 1 ~ 1.a of this report. AIR: Release concentrations are limited to dose rate limits described in 1.2.a of this report. 3 ~ Average energy of fission and activation gases in gaseous effluents is not applicable. 4 ~ Measurements and Approximations of Total Radioactivity A summary of liquid effluent accounting methods is described in Table 3,1. A summary of gaseous effluent accounting methods is described in Table 3.2. 4 ' Estimate of Errors a. Sampling Error The error associated with volume measureaant

devices, flow measuring
devices, etc.

based on calibration data and design tolerances has been conservatively estimated collectively to be less than + 10%. b. Analytical Error for Nuclides ~Te Liquid Gaseous ~Avera e +9% +10% Maximum +30% +35% TABLE 3 ~ 1 RADIOACTIVE LI UID EFFLUENT SAMPLING AND ANALYSIS LIQUID SOURCE SAMPLING FRE UENCY TYPE OF ANALYSIS Each Batch Princi al Gamma Emitters METHOD OF ANALYSIS .r.a. Monitor Tank Releases Continuous Releases Monthly Com osite Quar terly Com osite Gross Al ha SR-907 SR-89 FE-55 No continuous activity releases for this re ortin eriod L.S. G F,P, C S ~ Boric Acid Evaporator condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to liquid waste effluent totals. p.h.a. gamma spectrum pulse height analysis using Lithium Germanium detectors. All peaks are identified and quantified L.S. Liquid Scintillation Counting C.ST Chemical Separation G.F.PE Gas Plow Proportional Counting

Page 3 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 4.1 Measurements and Approximations of Total Radioactivity (continued) F 1.b (continued) TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SOURCE Waste gas Decay Tank Releases Con tainme nt Purge Releases Plant Vent SAMPLING FRE UENCY Each Tank Each Purge Weekly Monthly Composite (Particulates) Quarterly Composite (Particulates) TYPE OF ANALYSIS Principal Gamma Emitters Principal Gamma Emitters H-3 Principal Gamma Emitters H-3 Gross Alpha SR-90 SR-89 METHOD OF ANALYSIS (G) .h.a. (G) .h.a. L S (G, C, P)- .h.a. L,Si P-GFP C S G C P L S ~ C S ~ p.h.a G FOP Gaseous Grab Sample Charcoal Filter Sample Particulate Filter Sample Liquid Scintillation Counting Chemical Separation Gamma spectrum pulse height analysis using Lithium Germanium detectors, All peaks are identified and quantified Gas Flow Proportional Counting

Page 4 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT NO. 1 & 2 SEMIANNUAL REPORT July 1, 1984 THROUGH December 31 1984 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 5 ~ Batch Releases

5. 1 Liquid a.

Number of batch releases: b. Total time period of batch releases: c. Maximum time period for a batch release: d. Average time period for a batch release: e Minimum time period for a batch release: UNIT 1 22.5 9941 660 442 287 UNIT 2

22. 5

~c)~ MINJTES 660 MINUTES 442 MINUTES 287 MINUTES f ~ Average stream flow during periods of release of effluent into a flowing stream. 8.18E05 ALL LIQUID RELEASES ARE SlMMARIZED IN TABLES 5.2 Gaseous ~~8I~ GPM a. Number of batch releases: b. Total time period for batch releases: c, Maximum time period for a batch release: d. Average time period for batch releases: e. Minimum time period for a batch release: 16 ~5 1514 8 39 12119 MINUTES 2145 MINUTES 311 MINUTES 30 MINUTES ALL GASEOUS WASTE RELEASES ARE SlHMARIZED IN TABLES 6. Unplanned Releases 6.1 Liquid a Number of releases: b. Total activity releases: 0 0 CURIES 6.2 Gaseous a. Number of releases: b. Total activity released: 6.3 See attachments (if applicable) for: a. A description of the event and equipment involved b Cause(s) for the unplanned release c. Actions taken to prevent a recurrence, d Consequences of the unplanned release. 0 0 CURIE S

Page 5 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 & 2 SEMIANNUAL REPORT JULY 1. 1984 THROUGH DECEMBER 31, 1984 EFFLUENT AND WASTE DISPOSAL -'SUPPLEMENTAL INF01UVTION (continued) 7 ~ Assessment of radiation dose from radioactive effluents to the GENERAL PUBLIC due to their activities inside the site boundary assume the visitor was onsite for 40 hours, at an average distance of 0.3 Kilometers in the worst dispersion direction, and received exposure from each of the two reactor units on the St. Lucie Site. VISITOR DOSE RESULTS FOR CALENDAR YEAR 1984 WERE: ORGAN Bone DOSE (mrem) 5'E-5 Liver 8.5E-4 GASEOUS PARTICULATES & IODINE EXPOSURE NOBLE GAS EXPOSURE Gamma Air Dose 4.6E-2 mrads Beta Air Dose 9.2E-2 mrads Thyroid Kidney'ung GI-LLI 1.9E-2 3.6E-4 7.7E-4 7.9E-4 8. Total Body 8.2E-4 Offsite Dose Calculation Manual Revisions: No changes were issued to the ODCM during the period July 1, 1984 December 31, 1984. 9. Solid Waste and Irradiated Fuel Shi ments No irradiated fuel shipments were made from the site. Common solid waste from St. Lucie Units 1 and 2 were shipped )ointly. A summation of these shipments is given in Table 3.9 of this report. 10. Process Control Pro ram Revisions Revisions 03 and 04 were implemented during this reporting period. The revised revisions are included in Attachment-A of this report with explanations provided.

Page 6 ll. Waste Gas Deca Tank Ex losive Gas Monitorin S stem Ino erable Unit No. 1 This information is provided pursuant to St. Lucie, Unit No. 1 Technical Specification 3.3.3.10.b The oxygen monitors required by St. Lucie Unit No. 1 Technical Specifications 3.3.3.10 were inoperable from October 25, 1984 until December 6, 1984. This condition resulted in less than the minimum number of channels operable required by Table 3.3-13 in excess of the time permitted by Table 3.3-13 for the Waste Gas Decay Tank Explosive Gas Monitoring System. The cause of the inoperability was due primarily to excessive amounts of moisture in the system which resulted in the failure of the oxygen detectors. A number of factors contributed to the delay in returning the Waste Gas Decay Tank Explosive Gas Monitoring System to operable status. During the investigation of the instrument failures it was determined that additional maintenance would be required in order to restore the system reliability. This additional maintenance involved replacing a pump and eliminating suspected system leakage. Some of-the required spare parts to repair the system were not initially available on site. This contributed to the delay in restoring the system's operability. The remaining time is attributed to the extensive system maintenance which proved to be necessary to achieve the desired reliability. The St. Lucie P1ant is conducting an evaluation of the system's design and operation with an objective to preclude similar failures in the future. In

addition, to avoid delays in system maintenance the quantity of spare parts to be stocked has been increased.

During the period of time that the explosive gas monitoring system was inoperable, the conditions of Technical Specification 3.11.2.5 were maintained by monitoring oxygen'n the on service waste gas decay tank with the lab gas partitioner in accordance with Table 3.3-13, ACTION 5, of Technical Specification 3.3.3.10.

Page 7 FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 1 SEMIANNUAL REPORT July 1, 1984 THROUGH December 31 1984 TABLE 3'-1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES U E )A, Fission and Activation Products 1. Total Release (not including tritium, gases, alpha) 2. Average diluted concentration durin eriod B. Tritium CI uCI/ml

4. 20E-01 1.51E-08
8. 84E-01 4.89E-08 I

1 ~ Total Release 2 ~ Average diluted concentration durin eriod CD Dissolved and Entrained Gases 1 ~ Total release 2. Average diluted concentration durin eriod D. Gross Alpha Radioactivity 1.'otal Release CI 5 95E401

1. OOE402 uCI/ml 2.14E-06 CI 3.72E-01 9.07E-Ol uCI/ml 1.34E-OB 5.38E-08 CI E.

Volume of Waste Released ( rior to dilution) F. Volume of Dilution Water Used Durin Period Liters 1.13E406 Liters 1.40Et10 1.60E+06 1.69E+10

Page FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO. 1 SEMIANNUAL REPORT July 1, 1984 THRoUGH Oecember 31, 1934 TABLE 3.4-1 LIQUID EFFLUENTS CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER QUARTER BATCH MODE UARTER I QUARTER fk Na-24 cz 0 0 CR-51 CI 0 0 MN-54 CI 0 0 MN-56 I cz Co-57 CI 0 0 Co-58 CI I o Co-60 Cz I 0 0 Fe-59 Cz 0 0 Fe-55 I CI I 0 SN-113 I CI Sb-122 cz 0 I 0 Sb-124 CI 0 0 W-187 Cz 0 0 5.65E-04 2.77E-04 2.63E-03 6.15E-02

1. 5E-2 2.36E-02 1.86E-03 6.80E-03 7.90E-03 1.43E-02 1.35E-01 3.03E-02 9.35E-03 5.45E-02 1.46E-02
1. 61E-03 2.47E-04 N -239 cz 0

I-131 Cz 0 0'-132 cz 0 0 I-133 I CI I 0 0 I-134 Cz 0 0 I-135 cz 0 0 Rb-88 CI 0 0 zr-95 Cz 0 0 Nb-95 cz 0 0 ZR-97 cz 0 0 Nb-97 Cz 0 0 Mo-99 cz 0 0 Tc-994 'I I 0 0 Cs-130 cz I 0 0 Sb-125 czl 0 0 Cs-134 I CI 0 1.88E-01

2. 13E-02 2.62E-04 9.65E-05 2.36E-04
1. 36E-03 1.85E-03 I3.65E-02 1.30E-01 I2.57E-05 1.94E-02 2.30E-03 5.

5 -04 1.37E-03 3.49E-03 2.47E-03 2.01E-03 1.57E-02 1.54E-01

Page FLORIDA POWER, & LIGHT COMPANY ST ~ LUCIE UNIT NO. 1 SEMIANNUAL REPORT Jul 1, 1984 THROUGH December 31 1984 TABLE 3'-1 LIQUID EFFLUENTS (continued) CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT Cs-136 CI Cs-137 CI Ba-140 I CI La-140 CI Sr-89 CI Sr-90 CI QUARTER t UARTER 84 UARTEk 8 UARTER t4 ) 0 1.48E-03 1.53E-02 0 7.50E-02 2.55E-01 0 8.10E-04 1.14E-03 0 8.55E-05 5.95E-03 0 1.22E-02 5.90E-03 0 3.39E-04 2.35E-04 Y-90 UNIDENTIFIED CI CI 3.39E-04 2.35E-04 TOTAL FOR PERIOD ABOVE CI 0 4.20E-01 8.84E-01 N.-41 KR-85 XE-131M XE-133 XE-13 3M XE-135 KR-85M XE-138 mTAL FOR PERIOD ABOVE I CI CI CI I CI CI I CI CI CI CI 7.60E-05

9. 15E-04 1.76E-03 2.92E-02
3. 56E-01
8. 55E-01
5. 40E-03
9. 95E-03 8.55E-03 1.23E-02 0

0 3.72E-01 9.07E-01 NOTE: If no value is entered for a nuclide, the value equals zero Curies.

Page 10 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMIANNUAL REPORT Janua 1, 1984 THROUGH December 31, 1984 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION Age Group: Adult Location.'ny Adult Exposure Interval: From Janua 1, 1984 through December 31, 1984 FISH & SHELLFISH CALENDAR YEAR PATHWAY TO ORGAN Bone Liver Thyroid Kidney Lung GI-LLI T. Body DOSE (mrem) 1.24 E-l 4 ~ 60 E-1 2.30 E-1 1.78 E-2 4.59 E-l 4.41 E-l 1.56 E-l

Page 11 FLORIDA POWER & LIGHT COHPANY ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT July 1, 1984 THROUGHOecember 31, 1984 TABLE 3.3-2 LIQUID EFFLUENTS SlMMATION OF ALL RELEASES NUCL DES RELEASED A.,Fission and Activation Products UN T QUARTER 3 QUARTER 4 1. Total Release (not including tritium, gases, alpha) 2.

  • Average diluted concentration durin eriod B.

Tritium CI ucI/ml 4.20E-01 8.84E-01

1. 51E-08
4. 89E-08 1

Total Release 2. Average diluted concentration durin eriod C. Dissolved and Entrained ases CI

5. 95E+01 1.00E~02 ucI/ml 2.14E-06 5.93E-06 1.

Total release CI 3.72E-01 9.07E-01 2 ~ Average diluted concentration durin eriod ucZ/ml 1.34E-08 5.38E-08 I D. Gross Alpha Radioactivity 1 ~ Total Release CI 0 0 E. Volume of Waste Released (prior to dilution) F. Volume o Dilution Water Used Durin Period Liters Liters 1.13E+06

1. 40E+10 1.60E>06
1. 69E110

FLORIDA POWER 6 LIGHT C(MPANY ST ~ LUCIE UNIT NO 2 SEMIANNUAL REPORT July 1, 1984 THROUGH December 31, 1984 TABLE 3'-2 LIQUID EFFLUENTS Page CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER UARTEK BATCH MODE UARTEK UARTEK Na-24 CI (R-51 CI MN-54 I cz MN-56 CI Co-57 I cz cz Co-60 CI .Fe-59 cz I 0, 0 0 0 5.65E-O 6.80E-03 2 1.43E-02 6.15E-02 3.03E-02

1. 15E-02 9.35E-03 Fe-55 CI 2 '6E-02 5.45E-02 SN-113 CI Sb-122 cz I

Sb-124 CI W-187, CI N -239 CI I-131 CI I-132 cz I I-133 CI I-134 CI I-135 CI Rb-88 CI zr-95 CI Nb-95 cz I zR-97 CI Nb-97 CI Mo-99 cz I Tc-99M I CI Cs-138 CI Sb-125 CI Cs-134. CI 0 I 0 0 0

1. 86E-03
1. 46E-02 0

1.61E-03 0 2.47E-04 0 0 1.88E-01 1.30E-01 0 2.57E-05

2. 13E-02 1.94E-02 0

0 2.62E-04 2.30E-03 0

5. 15E-04 9.65E-05 1.37E-03 2.36E-04 3.49E-03 0

0 0 0 0 '0 1.36E-03 2.47E-03 0

2. 01E-03 1.57E-02 3.65E-02 1.54E-01

Page FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT July 1, 1984 THR0UGH December 31, 1984 TABLE 3'-2 LIQUID EFFLUENTS (continued) NUCLIDES RELEASED UNIT Cs-136 CI Cs-137 CI CONTINUOUS MODE QUARTER fi'UARTER 0 I 0 BATCH MODE QUARTEK 0 QUARTER /h I 1.48E-03 1.53E-02 7.50E-02 2.55E-01 Ba-140 CI 0 0

8. 10E-04
1. 14E-03 La-140 Sr-89 CI 0

0 8.55E-05 5.95E-03 CI 0 0 1.22E-02 5.90E-03 Sr-90 CI 3.39E-04 2.35E-04 Y-90 UNIDENTIFIED TOTAL FOR PERIOD "ABOVE CI CI CI 3.39E-04

4. 20E-01 2.35E-04 8.84E-01 I

I I I l l I AR-.41 CI 0 7.60E-05

9. 15E-04 XE-131M CI I

0 XE-133 ) CI 0

1. 76E-03
2. 92E-02 3.56E-01 8.55E-Ol XE-13 3M CI 0

0 5.40E-03 9.95E-03 XE-135 j CI 0 KR-85M CI 8.55E-03 1.23E-02 I 0 0 I KR-85 CII 0 Jo 0 I XE-138 TOTAL FOR PERIOD ABOVE CI CI

3. 72E-01 9.07E-01 NOZE: If no value is entered for a nuclide, the value equals zero Curies.

page l4 FLORIDA POWER & LI8GHT COMPANY ST. LUCIE UNIT NO, 2 SEMIANNUAL REPORT Januar 1, 1984 THROUGH December 31, 1984 TABLE 3.5-2 LIQUID EFFLUENTS DOSE SUMMATION Age Group: Adult Location: Any Adult Exposure Interval: From Januar 1, 1984 through 'ecember 31, 1984 FISH & SHELLFISH CALENDAR YEAR PATHWAY TO ORGAN DOSE (mrem) Bone Liver Thyroid Kidney Lung GI-LLI T. Body 1.24 E-l 4.60 E-1 2.30 E-1 1.78 E-2 4.59 E-1 4.41 E-l 1.56 E-l

Page 15 FLORIDA POMER & LIGHT C(MPANY ST ~ LUCIE UNIT NO, 1 SEMIANNUAL REPORT 98 " ~0b TABLE 3.6-1 GASEOUS EFFLUENTS - SlHMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 3 QUARTER 4 ) )A. Fission and Activation Gases 1. Total Release 2 ~ Avera e Release Rate for Period I CI 1 60E<04 CI/ 2.02E403 1.59E~04 2.00E&03 BE Iodines 1. Total Iodine-131 CI 1.93E-01 2. Avera e Release Rate for Period ucI/sec C, Particulates 1 ~ Particulates T-1/2 0 8 Days ) CI 1.81E-03'. Average Release Rate for Period ) ucI/sec E-0 3. Gross Alpha Radioactivity CI 1.07E-12 3.00E-02

3. 7E-03 2.27E-04 I

2.86E-05

3. 32E-21 D

Tritium 1 ~ Total Release CI E+02 2. Avera e Release Rate for Period uCI/sec 3.47Et01 5.49E+01

Page 16 FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 1 SEMIANNUAL REPORT TABLE 3.7-1 GASEOUS EFFLUENTS CONTINUOUS MODE NUCLIDES RELEASED UNIT QUARTER QUARTM 1 ~ FISSION GASES BATCH MODE UARTEK UARTER AR-41 KR-85M KR-87 XE-131M XE-13 3 XE-133M XE-135 XE-135M XE-13 TOTAL FOR PERIOD ABOVE CI 8.28f<01 CI 1.70EH03 GI CI 0 CI

1. 55E i04 CI GI 0

CI

1. 85E402 CI 5.92E+01 2.

Ei01 CI 3.61E001 Cr 1.3 E<0 2.20E402 6.1 f401 l. Et0 8.57E 00 1.1 E+0 4.4 Et01 1.76E+03 l. 11 1.35Ei04 5.1E0 2.99E 00 E+ 1.83E 0 4.07ft02 5.36E&02 5. OE 4.05E&01 l. 9E 0 2.43ft03 2 ~ IODINES I-131 I-13 3 I-1 5 TOTAL FOR PERIOD ABOVE CI CI CI CI 1.93E-01 3.00E-02

6. 13E-01
1. 09E-01

~ PARTICULATES Co-58 Co-60 CI 0 CI SR-90 Y- 0 I-133 TOTAL FOR PERIOD ABOVE CI 0 GI 0 GI CI 4.12E-03 1.04E-04 GI 0 CI 5.93E-03 3.31E-04

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMIANNUAL REPORT Table 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION QUARTER 8 NA AGE GROUP: INFANT EXPOSURE INTRVAL: FROM Janua 1, 1984 THROUGH December 31, 1984 PATHWAY Ground Plane (A) Grass-Cow-Milk (B) Inhalation (A) BONE (mrem) 0 1.42 E-2 2.14 E-4 LIVER (mrem) 0 2.28 E-2 4.38 E-3 THYROID (mrem) 0 5.43 EO 8.30 E-2 KIDNEY (mrem) 0 6.80 E-3 1.89 E-3 LUNG (mrem) 0 5.8 E-3 4.1 E-3 GI-LII (mrem) 0 6.53 E-3 4 ~ 12 E-3 T. BODY (mrem) 9.5 E-4 1.56 E-2 4.22 E-3 TOTAL 1.44 E-2 2 ~ 72 E-2 5'1 EO 8.69 E-3 9.9 E-3 1.07 E-2 2.08 E-2 (A) SECTOR: WEST RANGE: 1.78 miles B) COW/GOAT SECTOR: WNW RANGE: Default, 4.25 miles NOBLE GASES Gamma Air Dose Beta Air Dose Sector: West QUARTER (ABOVE TIME INTERVAL) (mrad) NA Range: 1.78 miles CALENDAR YEAR (mrad) 3.05 E-1 6.24 E-l Note: The dose values above were calculated using actual meteorological data during the specified time interval with MET data reduced as per Reg. Guide 1.111, March 1976.

Page le FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 2 SEMIANNUAL REPORT July 1 1984 THROUGH December 31 1984 TABLE 3 6-2 GASEOUS EFFLUENTS SlMHATION OF ALL RELEASES NUCLIDES RELEASED UN ZT QUARTER QUARTER A. Fission and Activation Gases 1 ~ Total Release CI 1.84'3 2. Avera e Release Rate for Period ucI/sec 2.31E+02 3.20E<02 (B Iodines 1 ~ Total Iodine-131 cz

7. 61E-03
2. 36E-01

( 2 ~ Avera e Release Rate for Period ucI/sec 9 '7E-04 2 '7E-02 C Particulates 1 ~ Particulates T-1/2 > 8 Days 2 Average Release Rate for Period 3 ~ Gross Al ha Radioactivit ( cz 6.5$ E-05 2.34E-04 ( ucZ/sec 8.29E-06 2.94E-05 cz 4 '8E-21 8 '0E-21 D. Tritium 1 Total Release cz 6.96E+01 1.64E>02 2 ~ Avera e Release Rate for Period ucz/sec

FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT "D~ TABLE 3.7-2 GASEOUS EFFLUENTS Page CONTINUOUS MODE NUCLIDES RELEASED UNIT QUART QUARTM BATCH MODE UARTER UARTEK 1 ~ FISSION GASES AR-41 XE-131M XE-1 XE-1 XE-135 XE-1324 XE-138 TOTAL FOR PERIOD ABOVE CI CI CI CI CI CI CI CI CI cr CI

1. 79E+01 0

1.53E+03 5.39E 0 1.71E+02 1.73E<03 9.28E 00 .28E+03 1.20E 02 1.42E003 9.48E-02

1. 18E+02 1.

E 4.00E-O 9.74E-O 8.98E 2 2 IODINES I-131 I-13 TOTAL FOR PERIOD ABOVE CI CI 1.90E-02 CI CI 2.66E-02 6.98 -02 3.06E-01 3 ~ PARTICULATES Co-58 Co-60 CI CI SR-90 Y-90 OT 0 PERIOD ABOVE CI CI CI CI CI CI 6.59 - 5 6.59E-05 2.34E-04

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT Table 3.8-2 GASEOUS EFFLUENTS DOSE SUMMATION QUARTER // NA AGE GROUP: INFANT EXPOSURE INTRVAL: FROM Janua 1, 1984 THROUGH December 31, 1984 PATHWAY Ground Plane (A) Grass-Cow-Milk (B) Inhalation (A) BONE (mrem) 0 1.51 E-2 1.41 E-4 LIVER (mrem) 0 2.00 E-2 1.64 E-3 THYROID (mrcm) 0 5.78 E-O 5.51 E-2 KIDNEY (mrem) 0 5.4 E-3 6.83 E-4 LUNG (mrem) 0 2.10 E-3 1.47 E-3 GI-LII (mrem) 0 2.79 E-3 1.48 E-3 To BODY (mrem) 4.78 E-4 1 ~ 25 E-2 1'0 E-3 TOTAL 1.52 E-2, 2.16 E-2 5.84 E-0

6. 1 E-3 3.57 E-3 4.27 E-3 1.46 E-2 (A)

SECTOR: WEST RANGE: 1.78 miles B) COW/GOAT SECTOR: WNW RANGE: Default, 4.25 miles NOBLE GASES Gamma Air Dose Beta Air Dose'ector: West QUARTER (ABOVE TIME INTERVAL) (mrad) Range: 1.78 miles CALENDAR YEAR (mrad) 6.29 E-2 1.24 E-1 NOTE: The dose values above were calculated using actual meteorological data during the specified time interval with MET data reduced as per Reg. Guide 1.111, March 1976.

FLORIDA POWER 6 LIGHT COMPANY ET. LUCIE UNIT NO. I & 2 EENIANNUAL REPORT July 1, 1984 THROUGH December 31, 1984 TABLE 3 " COMBINED SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Page 21 A SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1. T e of waste a. Spent resins, filter sludges I eva orator bottoms, etc. 6-month Es t. Total Unit Pe riod

Error, X

m3 t 1.2E1 Ci 7.0E2 2.0E1 b. Dry compressible waste; l contaminated equip, etc. c. Irradiated components, I control rods, etc. d. Other (describe) l ) 6.6E2 Ci 3.9E1 Ci I m3 Ci l 2.0E1 2. Estimate of major composition (by type of waste) a Co 60 Co - 58 Fe-- 55 Cs - 134 3.0E1 1.4E1 b. H-3 Co-S-- S I - 131 2.4E1 2.9E1 4.1EO 3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 10 12 SOLE USE TRUCK SOLE USE TRUCK BARNWELL, S CN RICHLAND, WASH ~ BE IRRADIATED FUEL SHIPMENTS (Disposition) Number of Shi ments Mode of Trans ortation Destination

FLORIDA POWER 5 LIGHT COHPANY ST. LUCIE UNIT NOS. I AND 2 EERIARRRIIL REPOSER JULY I, 1984 THROUGH DECEMBER 31, 1984 Solid Waste Supplement Waste Classification Class A Class A Total Volume Cu-Ft 22,272 780 Total Note I Curie ~oaottt 11.27 25.04 Principal " Radionuclides None 63NI 90Sr 137C5 Type Note 3 of Waste PWR Trash PWR Trash R. G. 1.21 ~Cate or l.b l.b Type " 4 of Container Non-Specification Strong Tight Pkg. NRC Certified LSA > Type A Solidification Agent or Absorbent None None Class 8 Class 8 195 195 3.188 278.61 63Ni 90Sr p 137Cs 14C 60Co 63Ni 90Sr PWR Trash PWR Ion-Exchange Resins l.b l.a. NRC Certi fied LSA > Type A NRC Certified LSA > Type A Hone None Class 8 Class C 121 121 4.817 417.12 60Co 63Ni 90Sr 131Cs 14C 60() 63Ni

90sr, 1

Cs PWR Filters PWR lon-Exchange

Resins, I.a.

l.a. NRC Certified Type 8 NRC Certified Type 8 None None

Pace 23 FLORIDA POWER 5 LIGHT COMPANY ST. LUCIE UNIT NOS. 1 AND 2 SEMIANNUAL REPOSER JULY 1, 1984 THROUGH DECEMBER 31, 1984 TABLE 3.9 Cont. Solid Waste Supplement Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Luci e Plant are determined using a combination of qualitative and quantitative techniques. In general, the St. Lucie Plant follows the guidelines outlined in the Low-Level Waste Licensing Branch Technical 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-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 emitter s, and periodic offsite analyses for other radionuclides. The onsite analyses are performed either on a batch basis or on a routi,ne basis using reasonably representative samples as appropriate for the waste type. Offsite analyses are used to a~tab/ash scaling factors or other estimates for radi onucl ides such as H, C Tc 129I TRU 1Pu 242Cm 63Ni R t and 5 Fe. Note 2: "Principal Radionuclides" refers to those radionuclides contained in the waste in concentrations greater than.Ol times the concentration of that nuclide listed in Table 1 or.01 times the smallest concentration of that nuclide listed in Table 2 of 10CFR61. Note 3: "Type of Waste" is generally specified as described in NUREG 0782, Draft Environmental Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste". Note 4: "Type of Container" refers to the transport package.

FLORIDA POWER 6 LIGHT COMPANY ST. LOUIE UNIT NO. I S 2 SEMIANNUAL REPORT ATTACHMENT' CHANGES TO PROCESS CONTROL PROGRAM DURING PERIOD JULY 1, 1984 THROUGH DECEMBER 31, 1984 A. 1. Paragraphs 3.1, 3.2.2, 3.2.3, 3.4.1, 3.4.3, 3.4.5, 3.4.8, 4.2, 5.3 and 6.4 of Revision 3 add to the process control program the waste form classification item per the implementation of 10 CFR, part 61 and 10 CFR 20,311. 2. Paragraphs 3.2.1.B and 3.2.1.C of Revision 4 make CNSI project num-bers consistent with references listed in 6.2 and 6.3. 3. Paragraph 6.1 of Revision 4 changed the Dewatering procedure to ~ Chem-nuclear Bead Dewatering procedure for CNSI 14-195 or smaller liners FO-OP-023. B. The above changes were administrative changes and did not reduce the overall conformance of the dewatered bead resin to existing criteria for radioactive wastes. C. Documentation of the review and acceptance of the changes by FRG is on the cover sheet of the attached procedure.

Page 1 of 5 FLORIDA POWER & LIGHT COMPANY ST+ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025 REVISION 4 ~ ~o TETLrE: PROCESS CONTROL PROGRAM 2EO REVIEW AND APPROVAL: Reviewed by Facility Review Group Approved by J. H Barrow (for) iNEGRMQiai GND ent is not controlled. Before use, a cont venfy >n 'f formabon with December 28 1982 Plant Manager December 28, 1982 Revision 4 Reviewed by F R G .Approved by ant Manager <>4 iSd 4 3 19 3,0 SCOPE: 3 ~ 1 Purpose The St ~ Lucie Plant Process Control Program (PCP) implements the requirements of the St, Lucie Plant Technical Specifications for both units Specifically, the PCP applies to waste form classification of all radioactive waste destined for land burial in accordance with 10 CFR 20,311, dewatering of bead resins for

disposal, and solidification, encapsulation, or absorption vendor supplied processes for liquid radioactive waste 3+2 Discussion I ~

The PCP contains provisions to assure that dewatering of bead resins 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 procedures: A St ~ Lucie Plant Operating Procedure No, 0520023, "Dewatering Radioactive Bead Resins" ~ BE CHEM-NUCLEAR SYSTEMS, IN'est procedure for Dewatering Conical Bottom Demineralizers and Resin Liners - Project Noo 11118'R4 C CHEM-NUCLEAR SYSTEMS, IN'ab Record Sheet for Conical Bottom Demineralizers and Resin Liners >> Prospect No, 11118. /R4 2, Vendor supplied processes for solidification, encapsulation, or absorption of liquid radioactive waste is handled under a topical report which the vendor has submitted to the Nuclear Regulatory Commission for approval or under an N,R,C approved process control program. Controlled copies of appropriate vendor procedures for these processes must be used to assure provision under the topical report are met ~

ST, LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM Page 2 of 5 3eO SCOPE: (continued) 3 2 Discussion: (continu'ed) 3 ~ All radioactive waste shiped for land burial must beet the

requirements of 10 CFR 20 311 regarding waste form classification and packaging This is implemented through procedure HP-47, "Classification of Radioactive Waste'aterial for Lend Disposal" ~ 3.3 Authority The authority and responsibility to perform the requirements of this procedure come from 10 CFR 20, 10 CFR 61, St Lucie Plant Unit 1 Technical Specifications, St ~ . Lucie Plant Unit 2 Technical Specifications, and from disposal site criteria, 3,4 Definitions 1 Abso tion - The process of absorbing liquid radioactive waste mater a s onto an absorbent

material, a final disposal package which contains radioactive bead resins material within cement-like material, such that the final product is a free-standing monolith 4

"Free Standin " Water - Liquid which is not retained by the waste

orm, 5 ~

Solidification - The process of solidifying liquid radioactive waste material in cement-like material, such that the final product is a free<<standing monolith 6 Process Coritiol Pro am (PCP) - The Process Control Program s conta n t e provisions, based on full scale testing, to assure that dewatering of radioactive bead resins 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 at the time of disposal 7 Visual Ins ection The direct observation of the bead resins uring t e ent re period of resin transfer as they are packaged in the final disposal container 8 Waste Form Classification - Classification of radioactive waste

ST, LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM Page 3 of 5 4+0 PRECAUTIONS: 4 1 Process Control Procedures used for the dewatering of radioactive bead resins that establish the conditions that must be met shall be based on full scale testing, This is to provide reasonable assurance that the dewatering of the resin and disposal container will result in volumes of free standing water, at the time of disposal, within the limits of 10CFR, Part 61 as implemented by 10CPR20 and of the low level radioactive waste disposal site, 4+2 Vendor supplied solidification, encapsulation, and absorption processes shall be NRC approved or under a topical report which has been submitted to NRC fgor approval Procedures which are to be used must be controlled per the vendor's gA program, 4+3 In lieu of dewatering performed as per the Process Control Procedures, a visual inspection of the bead resin as it is transferred and of the final disposal container after loading may be performed if conditions permit, This inspection must be conducted in a manner that will assure that the free standing liquids will meet shipping, transportation and disposal site requirements, 4,4 All changes to the St ~ Lucie Plant Process Control Program must be reviewed and approved by the Facility Review Group before they become effective 4i5 All changes to the St, Lucie Plant Process Control Program must be submitted to 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: 1 ~ Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information, 2, A determination that the change did not reduce the overall conformance of the dewatered bead resins to existing criteria for solid wastes' ~ Documentation of the fact that the change has been reviewed and found acceptable by the Pacility Review Group 5+0 RESPONSIBILITIES: 5 ~ 1 It is the rdsponsibility of the Plan't Manager to assure that all necessary procedures, equipment and support are provided to properly implement the PCS 5+2 It is the responsibility of the Health Physics Supervisor or his designee to assure that the radioactive bead resin will be dewatered in accordance with the PCP 5+3 It is the responsibility of the Health Physics Supervisor or his designee to assure that radioactive waste material is classified in accordance with the PCP

ST LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM Page 4 of 5 6+0

REFERENCES:

6,1 Bead Dewatering Procedure for CNSI 14-195 or smaller liners-FO-OP-023'R4 6' Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners, Prospect No, 11118 6i3 Test Procedure for Dewatering Conical 'Bottom Demineralizers and Resin Liners, Prospect No, 11118 ' 4 Health Physics Procedure, HP-47, "Classification of Radioactive Waste Material for Land Disposal" ~ 7+0 RECORDS AND NOTIFICATIONS: 7' Records shall be as per St, Lucie Plant Operating Procedure No

0520023, "Dewatering Radioactive Bead Resins" ~

7,2 Notifications 1 If it is suspected that the free standing water requirements may not be met for any container of radioactive bead resin shipped to a disposal site, notify the Plant Manager and the Health 'hysics Supervisor. 2 ~ If the process control procedures have not been followed or if free standing water may be present in the final shipping container of bead resin in amounts greater than allowed by regulations, notify the Health Physics Supervisor or his

designee,

ST>> LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM Page 5 of 5 8' INSTRUCTIONS: 8,1 Dewatered radioactive bead resins: 1 Dispose of dewatered radioactive bead resins is limited to the following containers for which full scale dewatering tests have been conducted: A CNSI Conical Bottom EnviroSAPE'High Integrity Container-PL6-80CR>> B CNSI Conical Bottom EnviroSAPE'High Integrity Container-PL14-195CR>> C,'NSI Conical Bottom EnviroSAPE'High Integrity Container-PL8-1 20CR>> 2, Dewater the container as per St>> Lucie Plant Operating Procedure No

0520023, "Dewatering of Radioactive Bead Resins" ~

3 ~ In lieu of dewatering, radioactive bead resin may be shipped for disposal in a different container, provided the radiological and regulatory conditions permit, if a visual inspection of the resin during transfer and of final shipping container after loading can be conducted in a manner that will assure that the free standing, liquid volume present wilL meet shipping,'ransportation, and disposal site requirements, 4, With dewatering not meeting disposal site, shipping, and transportation requirements, suspend shipment of the inadequately dewatered bead resin and correct the process control program, the applicable procedures(s), and/or the dewatering system as necessary to prevent recurrence, 5 ~ With dewatering not performed in accordance with the PCP: (1) if the dewatered bead resin has not already been shipped for disposal, verify each container to ensure that it meets burial ground, shipping and transportation requirements and/or (2) take appropriate administrative action to prevent recurrence 6 ~ Close the container as per the manufacturer's instructions' Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with vendor approved procedures' All radioactive waste material packaged and destined for land disposal shall conform to the requirements of 10 CPR 20,311 as implemented by procedure HP-47'f waste form classification exceeds Class C or packaging does not meet the requirements of the waste form class, the Health Physics Supervisor shall be notified and shipment shall not be made,

O N tNFONMATION ON t.y ll d. Before uses t'ot controlled, B fore uses verify in o rination with a contro e FLORIDA POWER tE LIGHT COMPANY ST ~ LVCIE PLANT ARtINISTRATIVE PROCEDURE NEtBER 0520025 REVISION 3 1,0 EXELE: PROCESS CONTROL PROGRAM 2 SO REVIEW AND APPROVAL: Pag OAYI EOCr~A/' g <~a~o SY$ coMp~~~Ppgy.: IIII~ Reviewed by Facility Review Group Approved by J H. Barrow (for) Plant 'Manager December 28, 1982 December 28, 1982 Revisioa 3 Reviewed by F R G Approved by 3,0 SCOPE: Plant Manager 1 1I Sh' j&j 3.1 Purpose The St Lucie Plant Process Control Program (PCP) implements the requirements of the St Lucie Plant Technical Specifications for botn

units, Specifically, the PCP applies to waste form classification of all radioactive waste destined for land burial in accordance with 10 CFR 20'11, dewatering of bead resins for disposal, aad solidification, encapsulation, or absorption vendor supplied processes for liquid radioactive waste~

3 2 Discussion 1, The PCP contains provisions to assure tnat dewatering of bead resins results ia a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 20 and of tae low level radioactive waste disposal site The Process Control Program includes in addition to this procedure the following related procedures: A St Lucie Plant Operating Procedure No

0520023, "Qewateriag Radioactive Bead Resias"

~ B QKN-NUCLEAR SYST&fS, INC Test procedure for Dewateriag Conical Bottom Demiaeralizers and kesin Liners - Project, No

11118, 10/05/81 C

QQ8-NUCLEAR SYSTEMS, INC Lab Record Sheet for Conical ttottom Demiaeralizers and Resin Liners - Project No. 11118; 10/01/81. 2 ~ Vendor supplied processes for solidification, encapsulation, or absorption of liquid radioactive waste is handled under a topical I report which the vendor has submitted to the Nuclear Regulatory Commission for approval or uader aa N.R.C approved process coatrol program Controlled copies of appropriate vendor procedures for these processes must be used to assure provision under the topical. report are met~

Page 2-of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUNSK8. 0520025, REVISION 3 PROCES S CONTROL PROGRAM 3 0 SCOPE: (ccaciaued) 3 2 Discus sion'(continued) 3 'llradioactive waste shiped for land burial must beet the requirements of 10 CFR 20,311 regarding waste form classification and packaging This is implemented through procedure HP-47, "Classification of Radioactive Waste 8aterial for Land Disposal" /RS 3 3 Authority The authority and responsibility to perform the requirements of this procedure come from 10 CFR 20, 10 CFR 61, St Lucie Plant Unit 1 Technical Specifications, St Lucie Plant Unit 2 Technical Specifications, and from disposal site criteria 3 4 Definitions materials onto an absorbent material 2 ~ Dewaterin - The process of removing "free standing" water from a inal disposal package which contains radioactive bead resins, material within cement"like material, such that the final product is a freemtanding monolith 4 "Free Standin " Water - Liquid which is not retained by the waste orms 5 ~ Solidification - The process of solidifying liquid radioactive waste material in cement-like material, such that the final product is a free-standing monolith. 6~ Process Control Pro ram (PCP) - The Process Control Program shall contain the provisions, based on full scale testing, to assure that dewatering of:radioactive bead resins 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 at the time of disposal, 7 Visual Ins ection The direct observation of the bead resins during the entire period of resin transfer as they are packaged in the final disposal container. 8 ~ Waste Form Classification - Classification of radioactive waste material based upon the concentrations of radionuclides identified. /R3. /R3 /RS 4~0 PRECAUTIONS: 4 1 'rocess Control Procedures used for the dewatering of radioactive bead resins that establish. the conditions that must be met shall be based on full scale testing This is to provide reasonable assurance that the dewatering of the resin and disposal container will result in volumes of free standing water, at the time of disposal, within the limits of 10CFR," Part 61 as implemented by 10CFR20'and of the low level radioactive waste disposal site

Page 3 of 5 ST LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 3 PROCESS CONTROL PROGRAM 4 0 PRECAUTIONS-(continued) 4~2 Vendor supplied solidification, encapsulation, and absorption processes shaLL be NRC approved or uncover a topical report which has been submitted to NRC approval. Procedures which are to be used est be controlled per t e vendor 's Qk program /R3 4 3 In lieu of dewatering performed. as per the Process Control Procedures, a visual inspection of the bead resin as it is transferred and of the final disposal container after loading may be perforaad if conditions permit This inspection must be conducted in a manner that will assure that the free standing liquids will meet shipping, transportation and disposal site requirements 4 4 All changes to the St, Lucie Plant Process Control Program est be reviewed and approved by the Facility Review Group before they become effective i 4 5 All changes to the St Lucie Plant Process Control Program axxst be submitted to 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: 1 Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information, 2 ~ A determination that the change did not reduce the overall conformance of the dewatered bead resins to existing criteria for solid wastes, 3 Documentation of the fact that the change has been reviewed and found acceptable by the Facility Review Group 5rO 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 the radioactive bead resin will be dewatered in accordance with the PCP ~ 5.3 It is the responsibility of the Health Physics Supervisor or his designee to assure that radioactive waste material is classified in accordance with the PCP. /R3

Page 4 of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 3 PROCESS CONTROL PROGRAM 6 e0

REFERENCES:

6~1 Dewatering Procedure for CNSI Conical-Bottom EnviroSAPE'High Integrity Containers (containing bead-type ion exchange resin) 1X free standing water - FOWP-003 6,2 Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners', Prospect No, 11118 6 3 Test Procedure for Dewatering Conical Bortom Demineralizers and Kesin Linexs, Pro)ect No~ 11118',4 Health Physics Pxocedure, HP-47, "Classification of Radioactive Waste Material for Land Disposal"', /R3 7,0 RECORDS AND NOTIPICATIONS: 7,1 Records shall be as per St. Lucie Plant Operating Procedure No

0520023, "Dewatering Radioactive Bead Resins" ~

'7 2 Notifications 1 ~ If it, is suspected that the free standing water requirements may not be met for any container of xadioactive bead resin shipped to a disposal site, notify the Plant Manager and the Health Physics Supervisor~ 2 ~ If the. process control procedures have not been followed or if free standing water may be present in the final shipping container of bead resin in amounts greater than allowed by regulations, notify the Health Physics Supervisor or his designee,

Page 5 of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, dEVISION 3 PROCESS CONTROL'ROGRAM 8 o0 INSTRUCTIONS: 8 1 Dewatered radioactive bead resins: 1 ~ Dispose of dewatered radioactive bead resins is limited to the following containers for which full scale dewatering tests have been. conducted: A CNSI Conical Bottom EnviroSAPE'High Integrity Container-PL6-80(Ro B CNSI Conical Bottom EnviroSAPE~ High Integrity Container-PL14-195' CNSI Conical Bottom EnviroSAPE~ High Integrity Container-PL8-120(Ri 2i Dewater the container as per St, Lucie Plant Operating Procedure No

0520023, "Dewatering of Radioactive Bead Resins",

3>> In lieu of dewatering, radioactive bead resin may be shipped for disposal in a different container, provided the radiological and regulatory conditions permit, if a visual inspection of the resin during transfer and of final shipping container after loading can be conducted in a manner that willassure that the free standing liquid volume present will meet shipping, transportation, and disposal site requirements 4, With dewatering not meeting disposal site,'hipping, and transportation requireients, suspend shipment of the inadequately dewatered bead resin and correct the process control program, the applicable procedures(s),, and/or the dewatering system as necessary to prevent recurrence 5 With dewatering not performed in accordance wich the PCP: (1) if the dewatered bead resin has not already, been shipped for ~ disposal, verify each container to ensure that it meets burial ground, shipping and transportation requirements and/or (2) take appropriate administrative action to prevent, recurrence. 6i Close the container aa per the manufacturer 's instructions 8 2 Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with vendor approved procedures~ 8 3 All radioactive waste material packaged and destined for land disposal =sha11 conform to the requireuents of 10 CHL 20i311 as implemented by procedure HP-47 ~ If waste form classification exceeds Class 0 or packaging does not meet, the requirements of the waste form.class, the Health Physics Supervisor shall be notified'and shipment shall not be made}}