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{{#Wiki_filter:BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of)), FLORIDA POWER&LIGHT COMPANY))(Turkey Point Nucl'ear Generating
{{#Wiki_filter:BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of                     )   Docket Nos. 50-250 (SP)
)Units.3 and''))))Docket Nos.50-250 (SP)50-251 (SP)(Proposed Amendments to.Facility Operating License to Permit Steam Generator Repairs)AFFIDAVIT OF'ALTON A.RODGER ON CONTENTIONS 3 and 6 My name.is Walton A.Rodger.My address is 7815'English Way, Bethesda, Maryland 20034.A statement of my qualifications is attached hereto and made a part hereof.My testimony is directed to two contentions:
                                        )                 50-251 (SP)
Contention 3"During the course of the repairs.proposed by the Licensee, (a)the handling, processing, storing or discharging of primary coolant or (b)the discharging of laundry waste water i',s likely to result in the release of radioactive material to.unrestricted areas in quantities which will not be as low as is reasonably achievable within the meaning of 10 CFR Parts 20 and 50." Contention 6"The cumulative offsite radiation releases as a result of all activity at Turkey Point, during the proposed repairs, do not comply with 10 CFR Parts 20 and 50."
FLORIDA POWER   & LIGHT COMPANY     )
0 I have examined and am familiar wi.'th those parts of the Steam Generator Repair Report (SGRR),.the Safety Evaluation Report concerning Appendix I and the Final Environmental Statement which relates to these contentions., Concernin Contention 3 Section 5.,2.2..4'f the SGRR contains an analysis of the liquid releases which may be expected to result from the operations associated with.the steam generator repair.I have reviewed.these calculate.ons of releases, and the as-sumptions upon which they are based.I agree>ith the assumptions and find the data presented in Tables 5.2-4 and 5..2.-5 to be representative of concentrations which can be expected in reactor coolant and.laundry waste.water, respec-tively.Table 5.2'-6 of the SGRR gi;ves the estimated releases with the discharged liquid waste., I have independently reviewed'he values in Table 5.2;6 and f'ind them reasonable.
,
In the event that processed primary reactor coolant and laundry waste water are to be discharged, the discharge will be, into the canal system.Fishing is not permitted in the.canals..However, in order to conservatively estimate the maximum, ind'ividual dose, I assumed a poacher might eat both fish and shellfish taken from the canal system near the'ischarge point.I also assumed that the concentration of all isotopes in the canal system had reached their equilibrium values.These calculations were done using the methods outlined in NRC Regulatory Guide 1.109.The results are shown in Table 1 which, together with Tables 2-5, is attached to and made a part of this testimony.
                                        )   (Proposed Amendments  to (Turkey Point Nucl'ear Generating     )   .Facility Operating License Units. 3 and'')                     )   to Permit Steam Generator
~I Table 1 shows that the dose from these releases meets the requirements of Section II, paragraph A of Appendix I to Part 50.Section II, paragraph D of Appendix I requires that the applicant either (a)perform a cost-benefit analysis to show that population dose cannot be further reduced at a cost less.than$1000 per man-rem or (b)show that the total a/annual release is less than 5 curies.Table 5.2-6 of the SGRR shows that the release will amount to less than 5 curies.Therefore a cost-benefit analysis is not needed.The liquid releases from the steam generator repair are as.low as reasonably achievable within the meaning of 10 CFR Parts 20 and 50.Concernin Contention 6 To address this contention I have, for both liquid and.gaseous releases, calculated the maximum individual doses for the operation of one unit and also the doses associated with the steam generator repair.In estimating the doses associated.
                                        )  Repairs)
with a single opera-ting unit I used actual releases for the period July 1979 through June 1980.This period fairly represents releases which may be expected from the operating unit during repair of the other.These releases, both gaseous and liquid, are shown in Table 2.To estimate the doses due to all liquid discharges the liquid releases shown on Table 5.2-6 of SGRR~/'ther than tritium and dissolved noble gases.
                                        )
0 0 E, and Table 2 of this testimony were added together and are shown in Table 3.Then doses to the hypothetical poacher were calculated in the same manner as used in producing Table 1.The doses to the poacher from the combined liquid releases are shown in Table 4.Table 4 shows that, both.the operating unit and the steam generator repair activity meet.the requirements of Section II, paragraph A of Appendix I to Part, 50.Further the operating.
AFFIDAVIT OF'ALTON A. RODGER ON CONTENTIONS 3 and 6 My name. is Walton A. Rodger. My address   is 7815 'English Way, Bethesda,   Maryland   20034. A statement of my qualifications is attached hereto and made a part hereof.
unit will discharge less than 5 curies/year, as will the repair operation, so Section II, paragraph D of Appendix I to Part 50 is also met for liquid discharge.
My testimony is directed to two contentions:
Similarly for gaseous discharges I have calculated the P doses to maximum individuals for-actual releases from the 1979-80 period and for the estimated steam generator releases.=The gaseous releases from the repair operation were taken from Table 5.2-2 of the SGRR.The combined releases are also shown in Table 3.The resulting calculated gaseous doses are shown in Table 5.It can be seen that all doses meet Section II, paragraphs B and C of Appendix I and that the contributions from the steam generator repair activities are truly trivial.The requirement of Section II, paragraph D is met by the fact that releases cf I-131 per.unit are less than 1 curie/year.
Contention 3 "During the course of the repairs .proposed by the Licensee, (a) the handling, processing, storing or discharging of primary coolant or (b) the discharging of laundry waste water i',s likely to result in the release of radioactive material to. unrestricted areas in quantities which will not be as low as is reasonably achievable within the meaning of 10 CFR Parts 20 and 50."
Thus the cumulative releases at Turkey Point will indeed comply with 10 CFR Parts 20 and 50.It should 0 II be noted that the requirements of Section II, paragraphs A, B, and C of Appendix I apply to individual units.The only place cumulative doses come into play at all is in establishing the right to forego a cost-benefit analysis under Section II, paragraph D.Even so the cumulative effects of releases from one operating unit plus those associated with the steam generator repair will meet the S'ection II, paragraph A, B, and.C'imits for a single unit.Consequently I conclude that"the cumulative offsite radiation releases as a result of all activity at Turkey Point, during the proposed repairs, do comply with 10 CFR Parts 20 and, 50." cg Walton A.Rodger Subscribed and sworn to before me this 6th day of April, 1981.hot y Public My Commission expires: 8/31/85
Contention 6 "The cumulative   offsite radiation releases as a result of all activity at Turkey Point, during the proposed repairs, do not comply with 10 CFR Parts 20 and 50."


Table 1 Maximum Dose to Xndividual from Steam Generator Re ir Releases Age Group Max Organ Organ Dose,~/'Total Body Dose Adult Teen Child GX-LLX GX-LLX, Thyroid.1.3E-01 8.2E-.02 6.6E-02 4'.4E-02 3.0E-02 2.2E"02 Ik A page 1 of 3 Table 2 Turkey Point Units 3 and 4-Releases of Radioisoto s for the Period Jul 1, 1979-June 30, 1980 Xso tope Li;uid'eleases (Releases) 7/79-12/79 l/80-6/80 12-months Total curies curies curies Ag-110m Ba-140 Co-58 Co-60 Cr-51 Cs-134 Cs-136 Cs.-137's-138 F-18 Fe-59 I-131 I-132 I-133 I-134 I-135 La-140 Nn-54 Mo-99/Tc-99m.
0 I have examined and  am familiar wi.'th those  parts of the Steam Generator Repair Report (SGRR), .the Safety Evaluation Report concerning Appendix I and the Final Environmental Statement which relates to these contentions.,
'Na-24 Nb-95 Ru-103 Sb-l24.Sb-125 Sr-89 Sr-90 Te-132 Total Liquids 4.5E-,03 neg 8.8E-02.1..7E-Ol 9.4E-03 1.8E-02 4.9E-04 3.4E-02 neg neg 6.0E-04'.0E-02 7.9E-03 2.3E-02'eg neg 8.5E-04 2.2E-03 9.3E-04 3..'5E-03., 9.9E-04 3.1E-04 5.1E-03 2.4E-03 1.5E-03 7.3E-06 neg 4.1E-01 1.4E-03 neg 3.4E-02 4.,7E-02 1.4E-03 3.'.3E-02 neg 2.2E-02 neg neg 1.7E-04'.0E-03 5.8E-04 2.1E-03 neg.neg 2.2E-04 5.1E-04 1.2E-04 neg neg neg 1.2E-02 1.2E-02 5.7E-03 4.8E-05 S.OE-04 1.6E-01 5.4E-03-neg l.2E-'01 2.2E-01 , l.1E-02 3.1E-02 4.9E-04 5.6E-02 neg neg 7.7E-,04 4'-2E&2 8.5E-03 2.5E-02 neg'eg 1.1E-03 2.7E-03 1.1E-03 1.5E-03 9-9E-04 3.1E-04 1.7E-02 1.4E-02 7.2E-03 5.5E-05 S.OE-04 5.7E-01 II' Table 2 page 2 of 3 Turkey Point Units 3 and 4 Releases of Radioisoto s for the Period Jul 1, 1979Mune-30, 1980'sotope Gaseous Releases;(Releases) 7 79-12 79 1 80-6 80 12-.months Total curies curies cur ies Gases Ar-4.L Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Total Gases~lageos I-131 I-133 I-135 Br-82 Total Halogens 7.6E+Ol 1.0E-Ol 1.5E 00 6.2E-01 1.1E 00 3.6E 00 1.3E+04.1.0E+01 3.1E+01 9.8E-'02.neg, 1.3E+04 3.7E-02 3.1E-02 1.6E-02 1.1E-03 8.6E-02 3.4E+Ol 4'.,5E-01 1.1E 00 l.8E" 01 7.6E-01 2.0E-01 9.1E+03 4.2E 00 2.2E+Ol neg neg, 9.2E+03 1.7E-02 7.0E-03 neg 3.7E-04 2.5E-02 l.1E+02 5.5E-01 2.6E 00 8.0E-01 1.9E 00 3.8E 00 2.2E+04 1.4E+01 5.3E+01 9.8E-02 neg 2.2E+04 5.4E-02 3.8E-02.1.6E-02 1.5E-03 l.1E-Ol
Concernin    Contention  3 Section 5.,2.2..4'f the SGRR contains an analysis of the liquid releases which may be expected to result from the operations associated with. the steam generator repair. I have reviewed. these calculate.ons of releases, and the as-sumptions upon which they are based. I  agree > ith the assumptions and find the data presented in Tables 5.2-4 and 5..2.-5 to be representative of concentrations which can be expected in reactor coolant and. laundry waste .water, respec-tively. Table 5.2'-6 of the SGRR gi;ves the estimated releases with the discharged liquid waste., I have independently reviewed'he values in Table 5.2;6 and f'ind them reasonable.
In the event that processed primary reactor coolant and laundry waste water are to be discharged, the discharge will be, into the canal system. Fishing is not permitted in the.
canals.. However, in order to conservatively estimate the maximum, ind'ividual dose, I assumed a poacher might eat both fish and shellfish taken from the canal system near the
'ischarge point. I also assumed that the concentration of all isotopes in the canal system had reached their equilibrium values. These calculations were done using the methods outlined in NRC Regulatory Guide 1.109. The results are shown in Table 1 which, together with Tables 2-5, is attached to and made a part of this testimony.


Table 2 page 3 of 3 Turkey Point Units 3 and 4 Releases of Radioisoto s for the Period, Jul 1, 1979-June 30, 1980 Isotope Particulates (Releases) 7 79-12 79 1 80-6 80 curies 12-months Tota1 curies'g-,110m.Ba-140'e-141 Co-57 Co-58 Co-60 Cr-51 Cs-134's-136 Cs-137 Fe-59 I-131 La-140 Nn-54 Nb-95 Ru-103 Sb-124 Sr-89 Sr-90 Ir-95 Ce-144'Sb-125 Zn-65 Total Par ticulates 4.8E-05 2.8E-.05 2.6E-05'5.3E-05 2.0E-02 3.1E-03 2.1E-03 1.4E-04 6.9E-06 2.2E-04 1.8E-04 5.2E-05 2.0E-05 5.5E-04 3.9E-04 8.3E-05 2.3E-04 1.9E-05 l.2E-.06 1.7E-04 2.8E-02 3'.6E-05 1.,1E-04 5.5E-05 2.1E-02 1.0E-02 3.2E-03 2.0E-04 neg 3.2E-04 1.7E-04 4.1E-05 5.0E-05'.7E-04 3.3E-04 3.9E-04 1.6E-04 5.5E-05 1.1E-05 1.1E-04 7..3E-05 1.5E-05 1.5E-04 3.7E-02 4.8E-05 6.4E-05 1.4E-04 1.1E-04 4.1E-02 1.3E-02 5.3E-03 3.4E-04 6.9E-06, 5.4E-04 3.5E-04 9.3E-05 7:.OE-05 l.lE-03 7-2E-04 4.7E-04 3.'9E-04 7.4E-051.2E-05 2.8E-04 7.3E-05 l.5E-05 1.5E-04 6.5E-02 0
~I Table 1 shows  that the dose from these releases    meets the requirements of Section II, paragraph A of Appendix I to Part 50. Section II, paragraph D of Appendix I requires that the applicant either (a) perform a cost-benefit analysis to show that population dose cannot be further reduced at a cost less. than $ 1000 per man-rem or (b) show that the total a/
Table 3 page 1 of 2~lsoto Releases.from One Operating Unit and Steam Generator Re ir of the Other Releases from: (curies)One 0 tatin Unit>~SG Re it'otal Li uid Releases Ag-110m.Co-58 Co-60 Cr-51 Cs-134 Cs-136 Cs-137 Pe-59'-131 I-132 I-133 La.-140 Mn'-54.Mo-99/Tc-99m Na-.24 Ko-95 Ru-103 Sb-124 Sb-125 Sr-89 Sr-90 Te-132.Total Licpids 3.0E-03 6.0E-02 1.1E-01 5.5E3 1.6E-02'.5E-04 2.8E-02 3.9E-04 2.1E-02 4.3E-03, 1.3E-02 5.,5E-04 1.4E-03 5.5E-04 7.5E-04 5.0E-04 1.6E-04 8.5E-03 7..0E-03 3.6E-03 2.8E-05 4'.OE-04 2.9E-.01 1..7E-Ol 1.3E-01 3.,7E-04 3.0E-02 1.4E-01 1.7E-05 7.6E-02 1.8E-02 4.8E-05 5.5E-'3.3.0E-03 2.3E-01 2.4E-01 5:9E-03 4.6E-02 2.5E-04 1.7E-01 4.1E-04 9.7E-02 ,4.3E-03 1.3E-02 5.5E-04 1.9E-02'5.5E-Q4 7.5E-04 5.0E-04 1.6E-04 8.5E-03 7.0E-03 3.6E-.03 2.8E-05 4.0E-04 8.4E-Ol a One-half the, annual rel'eases from.Units 3 and 4 as shown on Table 2.
annual release is less than 5 curies.           Table 5.2-6 of the SGRR  shows  that the release will amount to less than 5 curies. Therefore a cost-benefit analysis is not needed.
Oi~~ll Table 3 page 2 of 2 Releases from One Operating.
The liquid releases from the steam generator repair are as. low as reasonably achievable within the meaning of 10 CFR Parts  20 and 50.
Unit and Steam Generator Re ir of the Other IsotooB Gaseous Releases One 0 ratin Releases from: (curies)Unit.~SG Re ir Total A-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m I-131 I-132 I-133 I-135 Br-82 Ag-110m Ba-140 Ce-141 Co-57 Co-58 Co-60 Cr-51 Cs-134 Cs-136 Cs-137 Fe-59 La-140 Nn-54 Nb-95 RQ-103 Sb-124 Sr-89 Sr-90 Zr-95 Ce-144/Pr-144 Sb-125 Zn-65 5.5E+Ol 2;8E-01 1.3E 00 4.0E-'1 1.0E 00 1.9E 00 1.1E+04 7.0E 00 2.7E+01 4.9E-02 2.7E-02 l.9E-02 8.OE-03 7.5E-04 2.4E-05 3.2E-05 7,.0E-05 5.5E-05 2.1E-02 6.5E-03 2.7E-03 1.7E-04 3.5E-06.2.7E-04 1.8E-04 3.5E-05, 5.5E-04 3-6E-04 2.4E-04 2.0E-04 3.7H-05 6.0E-06 1.4E-04 3.7E-05 7.5E-06 7.5E-05 9.1E-03 1.4E-03 4.0E-04 1.7E-02 1.3E-02 6.8E-04'.7E-04 1.7E-04 1.5E-03 2.5E-03.8.5E-04 1.4E-03 2.,7E-03'.5E+01 2'.8E-01 1.3E 00 4.0E-Ol 1.0E 00 1.9E 00 1.1E+04 7.0E 00 2-7E+Ol 4.9E-02.3.6E-02 1.4E-03 1.9E-02 8.0E-03'7.5E-04 2.4E-05 3 2E 05 4.7E-04 5.5E-05 3.8E-02 1.9E-'02 3.4E-03 1.7E-04 3.5E-06 2.7E-04 4.5E-04 2.1E-04 2.1E-03 2.8E-03 1.1E-03 2.0E-04 3.7E-05 6.0E-06 1.5E-03 2.7E-03 7.5E-06 7.5E-05 a Che-half the annual releases from Units 3 and 4 as shown on Table 0 II~q Table 4.Doses to Maximum Individual from Com'oined Li id Beleases Tyge of Dose Maximum Xndividual Dose, mrem/year from:.0 nation of One Unit~SG Re ait'Zotel.Adult-GX-LLX.-Total Body Teen-GX-LLX-Total Body Child-WX-LLI
Concernin    Contention  6 To address  this contention I  have, for both liquid and.
-Total Body 1.4E-Ol 1.9E-02 9.0E-02.1.5E-02 3.6E-02 1.3E-02 1.3E-01 ,4.4E-02 8.2E-02 3.0E-'2 3.1E-02 2.2E-02 2'.,7E-.01 6.1E-02 1.7E-01 4.5E-02 6.7E-02 3.5E-02 Ol I of Dose Table 5 Doses to.llaximum Individual from Combined Gaseous Releases.iMximum Individual Dose, mrem/ear, from: 0 nation One'nit~BG Be it Totai Air Dose-Site Boundary Beta Gamma Nearest Garden and Residence, 3.6 m NNN 2.2E-01'8.0E-02 2.2E-01 8.0E-02 Adult Teen Total Body Thyroid Total Body Thyroid'.0E-.03 1.3E-02 7.OE-'03 1.2E-02'5.7E-04 2.4E-03 6.0E-04 2.0E-03 7'.6E-03 1.5E-02 7'.6E-03 1.4E-02 Child.Infant Total Body, Thyroid.Total Body Thyroid 7.OE-.03 1.4E-02, 7..0E-03 8.0E-03 7.1E-04 7.7E"03: 2.8E-03 1.7E-02 4.9E-04'.5E-03 8.9E-04'8.9E-03 Staff Cow at 4.5 mi W Mult Total Body Thyroid 1.3E-04 2.9E-02 6.OE-05 9.5E-03 1.9E-04'.9E-02 Teen Total Body Thyroid 3.'.6E-04 4.2E-02 7.0E-05,.2.3E-04 1.4E-02 5.6E-02 Child Infant Total Body Thyroid Total Body Tnyroid 2.8E-04 8.5E-02 4.2E-04 2.0E-01 1.3E-04 2.8E-02 1.6E-04 6.6E-02 4.1E-04 1.1E-01 5.8E-0'4 2.7E-01
gaseous releases, calculated the maximum individual doses for the operation of one unit and also the doses associated with the steam generator repair.
In estimating the doses associated. with a single opera-ting unit I used actual releases for the period July 1979 through June 1980. This period fairly represents releases which may be expected from the operating unit during repair of the other. These releases, both gaseous and liquid, are shown in Table 2. To estimate the doses due to all liquid discharges the   liquid releases   shown on Table   5.2-6 of SGRR
~/'ther      than  tritium  and dissolved noble gases.


PROFESSIONAL QUALIFICATIONS AND EXPERIENCE OF DR.WALTON A.RODGER My name is Walton A.Rodger.I am President of the nuclear consulting f'irm Nuclear, Safety Associates, Inc.of Bethesda,, Maryland, and have.been associated; with the firm for.the past thirteen years.The four years, prior.to that I was Vice President of Nuclear Fuel'ervices, Inc., serving as.its'Technical Director and 1'ater as General Manager of its West Valley, plant.In the latter position I was responsi-ble for the construction, startup, and licensing of the worl'd's first privately owned nuclear fuel reprocessing plant.From 1960'.to 1962, I was a Partner in the nuclear consulting firm of McLain Rodger Associates.
0 0 E,
Before entering the consulting field, I spent 13.years at Argonne National'Laboratory, four at, Oak Ridge National Laboratory, and one at the Metallurgical Laboratory of the University of Chicago.At all three I was active in the development of al'1 of the various processes which have been considered for use in reprocessing of nuclear fuel.I also did a great deal of work in the field of radioactive waste management.
At Argonne I was Associate Director of the Chemical Engineering Division.My total experience in the nuclear field has covered 39 years.I was graduated in both Chemical and Metallurgical Engineering from the University of Michigan in 1939.I obtained


my Master's Degree in Chemical Engineering from the same institution in 1940..My Doctorate in Chemical Engineering was.awarded'y the Illinois Institute of Technology in 1956., I, am;the, author of sections of several nuclear handbooks and have published more than two dozen papers in the nuclear field, largely on reprocessing and waste disposal.I am, a.Fellow of'IChE, and in.1960 was Chairman of the Nuclear Engineering, Division of the Institute.
and Table  2 of this testimony  were added together and are shown  in Table 3. Then doses to the hypothetical poacher were calculated in the same manner as used in producing Table 1. The doses to the poacher from the combined liquid releases are shown in Table 4.
I am also a member of ANS and AIF., I am pas.t chairman of the ANSI Committee N.-'8 which is developing.
Table 4 shows that, both .the operating unit and the steam generator repair activity meet .the requirements of Section II, paragraph A of Appendix I to Part, 50. Further the operating. unit will discharge less than 5 curies/year, as will the repair operation, so Section II, paragraph D of Appendix I to Part 50 is also met for liquid discharge.
standards for the disposal of solid nuclear waste., In 1959, I served as Technical Consultant to the Joint Committee on Atomic Energy of the 86th Congress at the Hearings on Industrial Radioactive Waste Disposal.I served., as a principal witness for the Consolidated Utility Group in the As Low As Practicable Rule Making Hearing (RM-50-2).
Similarly for gaseous discharges I have calculated the P
In thi.s capacity I have done extensive:
doses to maximum individuals for -actual releases from the 1979-80 period and for the estimated steam generator releases.
cost-benefit studies on LWR radwaste systems.
= The gaseous releases from the repair operation were taken from Table 5.2-2 of the SGRR. The combined releases are also shown in Table 3.
4k I~}}
The resulting calculated gaseous doses are shown in Table 5. It can be seen that all doses meet Section II, paragraphs B and C of Appendix I and that the contributions from the steam generator repair activities are truly trivial.
The requirement of Section II, paragraph D is met by the fact that releases cf I-131 per .unit are less than 1 curie/year.
Thus the cumulative releases at Turkey Point will indeed comply with 10 CFR Parts 20 and 50. It should
 
0 II
 
be noted  that the requirements of Section II, paragraphs A, B, and C of Appendix I apply to individual units. The only place cumulative doses come into play at all is in establishing the right to forego a cost-benefit analysis under Section    II, paragraph D. Even so the cumulative effects of releases from one operating unit plus those associated with the steam generator repair      will meet  the S'ection  II, paragraph  A, B, and. C'imits for  a single unit.
Consequently  I conclude that "the cumulative    offsite radiation releases as a result of all activity at Turkey Point, during the proposed repairs, do comply with 10 CFR Parts  20 and, 50."
cg Walton A. Rodger Subscribed and sworn to before      me this 6th  day  of April,  1981.
hot y Public My  Commission  expires:  8/31/85
 
Table 1 Maximum Dose to Xndividual from Steam Generator Re  ir Releases Age Group        Max Organ
                                    ~/
Organ Dose,      'Total  Body Dose Adult              GX-LLX            1.3E-01                4'.4E-02 Teen              GX-LLX,          8. 2E-.02              3.0E-02 Child              Thyroid.          6.6E-02                2.2E"02
 
A Ik
 
page 1    of 3 Table 2 Turkey Point Units 3 and 4-Releases    of Radioisoto    s for the Period Jul 1, 1979-June 30, 1980 (Releases)
Xso tope                    7/79-12/79          l/80-6/80      12-months    Total curies                curies        curies Li;  uid'eleases Ag-110m                          4. 5E-,03          1.4E-03              5.4E      Ba-140                              neg                  neg                neg Co-58 Co-60 8.8E-02.
1..7E-Ol 3.4E-02 4.,7E-02
: l. 2E-'01 2.2E-01 Cr-51                            9.4E-03 1.8E-02 1.4E-03            , l. 1E-02 Cs-134                                                3.'. 3E-02            3. 1E-02 Cs-136                          4.9E-04                  neg              4.9E-04 Cs.-137's-138 3.4E-02              2.2E-02              5.6E-02 neg                  neg                neg F-18                                neg                  neg                neg Fe-59                            6.0E-04'.0E-02      1.7E-04'.0E-03 7.7E-,04 I-131                                                                      4'-2E&2 I-132                            7.9E-03              5.8E-04              8.5E-03 I-133                            2.3E-02              2.1E-03              2.5E-02 I-134                            'eg                      neg                neg I-135                                neg              . neg              'eg La-140                          8.5E-04              2.2E-04              1. 1E-03 Nn-54                            2.2E-03              5.1E-04              2.7E-03 Mo-99/Tc-99m.                    9.3E-04              1.2E-04              1.1E-03
    'Na-24                            3..'5E-03                neg              1.5E-03 Nb-95                        .,  9.9E-04                  neg              9-9E-04 Ru-103                          3.1E-04                  neg              3.1E-04 Sb-l24.                          5.1E-03              1.2E-02              1.7E-02 Sb-125                          2.4E-03              1.2E-02              1.4E-02 Sr-89                            1.5E-03              5.7E-03              7.2E-03 Sr-90                            7.3E-06              4.8E-05              5.5E-05 Te-132                              neg              S.OE-04              S.OE-04 Total Liquids                    4.1E-01              1.6E-01              5.7E-01
 
II' page 2  of 3 Table 2 Turkey Point Units 3 and 4 Releases of Radioisoto  s for the Period Jul 1, 1979Mune-30, 1980 (Releases) 7  79-12 79      1 80-6 80  12-. months    Total 'sotope curies          curies        cur ies Gaseous Releases; Gases Ar -4.L                    7.6E+Ol          3.4E+Ol        l. 1E+02 Kr-85                    1.0E-Ol          4'.,5E-01      5.5E-01 Kr-85m                    1.5E 00          1.1E 00        2.6E 00 Kr-87                    6.2E-01          l. 8E" 01      8.0E-01 Kr-88                    1.1E 00          7.6E-01        1.9E 00 Xe-131m                  3.6E 00          2.0E-01        3.8E 00 Xe-133                    1.3E+04.        9.1E+03        2.2E+04 Xe-133m                  1.0E+01          4.2E 00        1.4E+01 Xe-135                    3.1E+01          2.2E+Ol        5.3E+01 Xe-135m                  9. 8E-'02.          neg        9.8E-02 Xe-138                        neg,            neg,          neg Total  Gases              1.3E+04          9. 2E+03      2.2E+04
    ~lageos                                    1.7E-02        5.4E-02 I-131                      3.7E-02 I-133                      3. 1E-02        7.0E-03        3.8E-02.
I-135                      1. 6E-02            neg        1.6E-02 Br-82                    1. 1E-03        3.7E-04        1.5E-03 Total Halogens            8.6E-02        2.5E-02        l. 1E-Ol
 
page 3  of        3 Table 2 Turkey Point Units 3 and 4 Releases        of Radioisoto  s for the Period, Jul 1, 1979-June 30, 1980 (Releases)
Isotope                        7  79-12 79      1 80-6 80      12-months Tota1 curies                            curies Particulates
              .                  4.8E-05                            4.8E-05  'g-,110m 2.8E-. 05        3'.6E-05          6.4E-05 Ba-140'e-141 2.6E-05          1.,1E-04          1.4E-04 Co-57                            '5.3E-05          5.5E-05          1.1E-04 Co-58                            2.0E-02          2.1E-02          4.1E-02 Co-60                            3.1E-03          1.0E-02          1.3E-02 Cr-51                            2.1E-03          3.2E-03          5.3E-03 1.4E-04          2.0E-04          3.4E-04 Cs-134's-136 6.9E-06              neg          6.9E-06, Cs-137                            2.2E-04          3.2E-04          5.4E-04 Fe-59                            1.8E-04          1.7E-04          3.5E-04 I-131                            5.2E-05          4.1E-05          9.3E-05 La-140                            2.0E-05          5.0E-05'.7E-04 7:.OE-05 Nn-54                            5.5E-04                            l.lE-03 Nb-95                            3.9E-04          3.3E-04          7-2E-04 Ru-103                            8.3E-05          3.9E-04          4.7E-04 Sb-124                            2.3E-04          1.6E-04          3.'9E-04 Sr-89                            1.9E-05          5.5E-05          7.4E-05 Sr-90                            l. 2E-.06        1.1E-05          1.2E-05 2.8E-04 Ir-95                            1.7E-04          1.1E-04 7..3E-05          7.3E-05 Ce-144'Sb-125 1.5E-05          l. 5E-05 Zn-65                                            1.5E-04          1. 5E-04 Total Par ticulates                2. 8E-02        3.7E-02          6.5E-02
 
0 page 1  of  2 Table 3 Releases. from One Operating Unit and Steam Generator Re          ir  of the Other Releases    from:    (curies)
~lsoto                One 0    tatin Unit>              ~SG Re  it      'otal Li uid      Releases Ag-110m.              3.0E-03                                            3.0E-03 Co-58                  6.0E-02                          1..7E-Ol        2.3E-01 Co-60                  1.1E-01                          1.3E-01          2.4E-01 Cr-51                  5. 5E3                            3.,7E-04        5:9E-03 Cs-134                1.6E-02'.5E-04 3.0E-02          4.6E-02 Cs-136                                                                    2.5E-04 Cs-137                2.8E-02                          1.4E-01          1.7E-01 Pe-59'-131 3.9E-04                          1.7E-05          4.1E-04 2.1E-02                          7.6E-02          9.7E-02 I-132                  4.3E-03,                                          ,4.3E-03 I-133                  1.3E-02                                            1.3E-02 La.-140                5.,5E-04                                          5.5E-04 Mn'-54.                1.4E-03                          1.8E-02          1.9E-02 Mo-99/Tc-99m          5.5E-04                                          '5.5E-Q4 Na-.24                7.5E-04                                            7.5E-04 Ko-95                  5.0E-04                                            5.0E-04 Ru-103                1.6E-04                                            1.6E-04 Sb-124                8.5E-03                                            8.5E-03 Sb-125                7..0E-03                                          7.0E-03 Sr-89                  3.6E-03                          4.8E-05          3. 6E-.03 Sr-90                  2.8E-05                                            2.8E-05 Te-132.                4'.OE-04                                          4.0E-04 Total Licpids          2. 9E-.01                        5.5E-'3.        8.4E-Ol a    One-half the, annual rel'eases from. Units        3 and 4  as shown on Table 2.
 
ll Oi ~ ~
 
page 2  of  2 Table  3 Releases  from One Operating. Unit and Steam Generator Re      ir of the Other Releases  from:          (curies)
IsotooB            One 0    ratin  Unit.        ~SG Re          ir        Total Gaseous  Releases A-41                5.5E+Ol Kr-85                2;8E-01                                              2'.8E-01 Kr-85m              1.3E 00                                              1.3E 00 Kr-87                4.0E-'1                                              4.0E-Ol Kr-88                1.0E 00                                              1.0E 00 Xe-131m              1.9E 00                                              1.9E 00 Xe-133              1.1E+04                                              1.1E+04 Xe-133m              7.0E 00                                              7.0E 00 Xe-135              2.7E+01                                              2-7E+Ol Xe-135m              4.9E-02                                              4.9E-02.
I-131                2.7E-02                      9. 1E-03                3. 6E-02 I-132                                            1. 4E-03                1. 4E-03 I-133                l. 9E-02                                            1.9E-02 8.0E-03 I-135                8. OE-03 Br-82                7.5E-04                                            '7.5E-04 Ag-110m              2.4E-05                                              2.4E-05 Ba-140              3.2E-05                                              3 2E 05 Ce-141              7,.0E-05                    4.0E-04                4.7E-04 Co-57                5.5E-05                                              5.5E-05 Co-58                2.1E-02                      1.7E-02                3.8E-02 Co-60                6.5E-03                      2.,7E-03'.5E+01 1.3E-02                1. 9E-'02 Cr-51                2.7E-03                      6.8E-04'.
3.4E-03 Cs-134              1.7E-04                                              1. 7E-04 Cs-136              3.5E-06.                                              3.5E-06 Cs-137              2.7E-04                                              2.7E-04 Fe-59                1.8E-04                                7E-04          4.5E-04 La-140              3.5E-05,                    1.7E-04                  2.1E-04 Nn-54                5.5E-04                      1.5E-03                2.1E-03 Nb-95                3-6E-04                      2.5E-03 .              2.8E-03 RQ-103                2.4E-04                      8.5E-04                1.1E-03 Sb-124              2.0E-04                                              2.0E-04 Sr-89                3.7H-05                                              3.7E-05 Sr-90                6.0E-06                                              6.0E-06 Zr-95                1.4E-04                      1.4E-03                1.5E-03 Ce-144/Pr-144        3.7E-05                                              2.7E-03 Sb-125                7.5E-06                                              7.5E-06 Zn-65                7.5E-05                                              7.5E-05 a  Che-half the annual releases from Units      3 and 4 as shown on            Table
 
II
    ~q 0
 
Table  4
                  .Doses  to  Maximum  Individual from Com'oined  Li id    Beleases Tyge of Dose              Maximum  Xndividual Dose, mrem/year from:.
0  nation of  One Unit        ~SG Re ait  'Zotel.
Adult GX-LLX.                1.4E-Ol                  1.3E-01  2'.,7E-.01 Total Body            1.9E-02                ,4.4E-02  6. 1E-02 Teen GX-LLX                  9.0E-02.                8.2E-02  1. 7E-01 Total Body              1.5E-02                  3.0E-'2  4. 5E-02 Child-WX-LLI                  3.6E-02                  3. 1E-02  6.7E-02 Total Body            1.3E-02                  2. 2E-02  3.5E-02
 
Ol I Table    5 Doses to.llaximum Individual from Combined Gaseous Releases.
iMximum    Individual Dose, mrem/ ear, from:
of Dose                    0  nation One'nit        ~BG  Be  it      Totai Air Dose Site  Boundary    Beta              2. 2E-01                        2. 2E-01 Gamma            '8.0E-02                        8.0E-02 Nearest Garden and Residence, 3.6 m NNN Adult          Total  Body            '.0E-.03            '5.7E-04      7'. 6E-03 Thyroid                  1. 3E-02            2.4E-03      1. 5E-02 Teen          Total  Body                7. OE-'03          6.0E-04      7'.6E-03 Thyroid                  1.2E-02            2.0E-03      1.4E-02 Child.        Total Body,              7. OE-.03          7.1E-04      7.7E"03:
Thyroid.                  1. 4E-02,          2.8E-03      1.7E-02 Infant        Total  Body              7..0E-03            4.9E-04'.5E-03 Thyroid                    8.0E-03            8.9E-04'    8.9E-03 Staff  Cow at 4.5 mi W Mult          Total  Body              1.3E-04            6. OE-05    1. 9E-04 Thyroid                  2.9E-02            9.5E-03    '.9E-02 Teen          Total  Body              3.'.6E-04          7.0E-05, . 2.3E-04 Thyroid                  4.2E-02            1.4E-02      5.6E-02 Child          Total  Body              2.8E-04            1.3E-04      4.1E-04 Thyroid                  8.5E-02            2.8E-02      1.1E-01 Infant        Total  Body              4.2E-04            1.6E-04      5. 8E-0'4 Tnyroid                    2.0E-01            6.6E-02      2.7E-01
 
PROFESSIONAL QUALIFICATIONS AND EXPERIENCE OF DR. WALTON A. RODGER My name  is  Walton A. Rodger. I am President of the nuclear consulting f'irm Nuclear, Safety Associates, Inc. of Bethesda,, Maryland, and have. been associated; with the firm for. the past thirteen years. The four years, prior. to that I was Vice President of Nuclear Fuel'ervices, Inc., serving as.its 'Technical Director and 1'ater as General Manager of its West Valley,plant. In the latter position I was responsi-ble for the construction, startup, and licensing of the worl'd's first privately owned nuclear fuel reprocessing plant.
From 1960'. to 1962, I was a Partner in the nuclear consulting firm of McLain Rodger Associates. Before entering the consulting    field, I spent 13. years at Argonne National
'Laboratory, four at,  Oak Ridge National Laboratory, and one at the Metallurgical Laboratory of the University of Chicago.
At all three I was active in the development of al'1 of the various processes which have been considered for use in reprocessing of nuclear fuel. I also did a great deal of work  in the field of radioactive waste management. At Argonne I was Associate Director of the Chemical Engineering Division. My total experience in the nuclear field has covered        39 years.
I was graduated in both Chemical and Metallurgical Engineering from the University of Michigan in 1939.      I  obtained
 
my Master's Degree in Chemical Engineering from the same institution in 1940.. My Doctorate in Chemical Engineering was. awarded'y the Illinois Institute of Technology in 1956.,
I, am; the, author of sections of several nuclear handbooks and have published more than two dozen papers in the nuclear field, largely on reprocessing and waste disposal. I am, a. Fellow of'IChE, and in. 1960 was Chairman of the Nuclear Engineering, Division of the Institute. I am also a member of ANS and AIF., I am pas.t chairman of the ANSI Committee N.-'8 which is developing. standards for the disposal of solid nuclear waste., In 1959, I served as Technical Consultant to the Joint Committee on Atomic Energy of the 86th Congress at the Hearings on Industrial Radioactive Waste Disposal.
I served., as a principal witness for the Consolidated Utility Group in the As Low As Practicable Rule Making Hearing (RM-50-2).
In thi.s capacity I have done extensive: cost-benefit studies on LWR   radwaste systems.
 
4k I ~}}

Revision as of 10:55, 22 October 2019

Affidavit in Support of Summary Disposition of Contentions 3 & 6 Re Cumulative Offsite Radiation Dose & Discharge of Laundry Waste & Coolant Water.Releases Comply w/10CFR20 & 10CFR50
ML17340B024
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 04/06/1981
From: Rodger W
NUCLEAR SAFETY ASSOCIATES
To:
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ML17340B023 List:
References
ISSUANCES-SP, NUDOCS 8104220625
Download: ML17340B024 (30)
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Text

BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of ) Docket Nos. 50-250 (SP)

) 50-251 (SP)

FLORIDA POWER & LIGHT COMPANY )

,

) (Proposed Amendments to (Turkey Point Nucl'ear Generating ) .Facility Operating License Units. 3 and) ) to Permit Steam Generator

) Repairs)

)

AFFIDAVIT OF'ALTON A. RODGER ON CONTENTIONS 3 and 6 My name. is Walton A. Rodger. My address is 7815 'English Way, Bethesda, Maryland 20034. A statement of my qualifications is attached hereto and made a part hereof.

My testimony is directed to two contentions:

Contention 3 "During the course of the repairs .proposed by the Licensee, (a) the handling, processing, storing or discharging of primary coolant or (b) the discharging of laundry waste water i',s likely to result in the release of radioactive material to. unrestricted areas in quantities which will not be as low as is reasonably achievable within the meaning of 10 CFR Parts 20 and 50."

Contention 6 "The cumulative offsite radiation releases as a result of all activity at Turkey Point, during the proposed repairs, do not comply with 10 CFR Parts 20 and 50."

0 I have examined and am familiar wi.'th those parts of the Steam Generator Repair Report (SGRR), .the Safety Evaluation Report concerning Appendix I and the Final Environmental Statement which relates to these contentions.,

Concernin Contention 3 Section 5.,2.2..4'f the SGRR contains an analysis of the liquid releases which may be expected to result from the operations associated with. the steam generator repair. I have reviewed. these calculate.ons of releases, and the as-sumptions upon which they are based. I agree > ith the assumptions and find the data presented in Tables 5.2-4 and 5..2.-5 to be representative of concentrations which can be expected in reactor coolant and. laundry waste .water, respec-tively. Table 5.2'-6 of the SGRR gi;ves the estimated releases with the discharged liquid waste., I have independently reviewed'he values in Table 5.2;6 and f'ind them reasonable.

In the event that processed primary reactor coolant and laundry waste water are to be discharged, the discharge will be, into the canal system. Fishing is not permitted in the.

canals.. However, in order to conservatively estimate the maximum, ind'ividual dose, I assumed a poacher might eat both fish and shellfish taken from the canal system near the

'ischarge point. I also assumed that the concentration of all isotopes in the canal system had reached their equilibrium values. These calculations were done using the methods outlined in NRC Regulatory Guide 1.109. The results are shown in Table 1 which, together with Tables 2-5, is attached to and made a part of this testimony.

~I Table 1 shows that the dose from these releases meets the requirements of Section II, paragraph A of Appendix I to Part 50.Section II, paragraph D of Appendix I requires that the applicant either (a) perform a cost-benefit analysis to show that population dose cannot be further reduced at a cost less. than $ 1000 per man-rem or (b) show that the total a/

annual release is less than 5 curies. Table 5.2-6 of the SGRR shows that the release will amount to less than 5 curies. Therefore a cost-benefit analysis is not needed.

The liquid releases from the steam generator repair are as. low as reasonably achievable within the meaning of 10 CFR Parts 20 and 50.

Concernin Contention 6 To address this contention I have, for both liquid and.

gaseous releases, calculated the maximum individual doses for the operation of one unit and also the doses associated with the steam generator repair.

In estimating the doses associated. with a single opera-ting unit I used actual releases for the period July 1979 through June 1980. This period fairly represents releases which may be expected from the operating unit during repair of the other. These releases, both gaseous and liquid, are shown in Table 2. To estimate the doses due to all liquid discharges the liquid releases shown on Table 5.2-6 of SGRR

~/'ther than tritium and dissolved noble gases.

0 0 E,

and Table 2 of this testimony were added together and are shown in Table 3. Then doses to the hypothetical poacher were calculated in the same manner as used in producing Table 1. The doses to the poacher from the combined liquid releases are shown in Table 4.

Table 4 shows that, both .the operating unit and the steam generator repair activity meet .the requirements of Section II, paragraph A of Appendix I to Part, 50. Further the operating. unit will discharge less than 5 curies/year, as will the repair operation, so Section II, paragraph D of Appendix I to Part 50 is also met for liquid discharge.

Similarly for gaseous discharges I have calculated the P

doses to maximum individuals for -actual releases from the 1979-80 period and for the estimated steam generator releases.

= The gaseous releases from the repair operation were taken from Table 5.2-2 of the SGRR. The combined releases are also shown in Table 3.

The resulting calculated gaseous doses are shown in Table 5. It can be seen that all doses meet Section II, paragraphs B and C of Appendix I and that the contributions from the steam generator repair activities are truly trivial.

The requirement of Section II, paragraph D is met by the fact that releases cf I-131 per .unit are less than 1 curie/year.

Thus the cumulative releases at Turkey Point will indeed comply with 10 CFR Parts 20 and 50. It should

0 II

be noted that the requirements of Section II, paragraphs A, B, and C of Appendix I apply to individual units. The only place cumulative doses come into play at all is in establishing the right to forego a cost-benefit analysis under Section II, paragraph D. Even so the cumulative effects of releases from one operating unit plus those associated with the steam generator repair will meet the S'ection II, paragraph A, B, and. C'imits for a single unit.

Consequently I conclude that "the cumulative offsite radiation releases as a result of all activity at Turkey Point, during the proposed repairs, do comply with 10 CFR Parts 20 and, 50."

cg Walton A. Rodger Subscribed and sworn to before me this 6th day of April, 1981.

hot y Public My Commission expires: 8/31/85

Table 1 Maximum Dose to Xndividual from Steam Generator Re ir Releases Age Group Max Organ

~/

Organ Dose, 'Total Body Dose Adult GX-LLX 1.3E-01 4'.4E-02 Teen GX-LLX, 8. 2E-.02 3.0E-02 Child Thyroid. 6.6E-02 2.2E"02

A Ik

page 1 of 3 Table 2 Turkey Point Units 3 and 4-Releases of Radioisoto s for the Period Jul 1, 1979-June 30, 1980 (Releases)

Xso tope 7/79-12/79 l/80-6/80 12-months Total curies curies curies Li; uid'eleases Ag-110m 4. 5E-,03 1.4E-03 5.4E Ba-140 neg neg neg Co-58 Co-60 8.8E-02.

1..7E-Ol 3.4E-02 4.,7E-02

l. 2E-'01 2.2E-01 Cr-51 9.4E-03 1.8E-02 1.4E-03 , l. 1E-02 Cs-134 3.'. 3E-02 3. 1E-02 Cs-136 4.9E-04 neg 4.9E-04 Cs.-137's-138 3.4E-02 2.2E-02 5.6E-02 neg neg neg F-18 neg neg neg Fe-59 6.0E-04'.0E-02 1.7E-04'.0E-03 7.7E-,04 I-131 4'-2E&2 I-132 7.9E-03 5.8E-04 8.5E-03 I-133 2.3E-02 2.1E-03 2.5E-02 I-134 'eg neg neg I-135 neg . neg 'eg La-140 8.5E-04 2.2E-04 1. 1E-03 Nn-54 2.2E-03 5.1E-04 2.7E-03 Mo-99/Tc-99m. 9.3E-04 1.2E-04 1.1E-03

'Na-24 3..'5E-03 neg 1.5E-03 Nb-95 ., 9.9E-04 neg 9-9E-04 Ru-103 3.1E-04 neg 3.1E-04 Sb-l24. 5.1E-03 1.2E-02 1.7E-02 Sb-125 2.4E-03 1.2E-02 1.4E-02 Sr-89 1.5E-03 5.7E-03 7.2E-03 Sr-90 7.3E-06 4.8E-05 5.5E-05 Te-132 neg S.OE-04 S.OE-04 Total Liquids 4.1E-01 1.6E-01 5.7E-01

II' page 2 of 3 Table 2 Turkey Point Units 3 and 4 Releases of Radioisoto s for the Period Jul 1, 1979Mune-30, 1980 (Releases) 7 79-12 79 1 80-6 80 12-. months Total 'sotope curies curies cur ies Gaseous Releases; Gases Ar -4.L 7.6E+Ol 3.4E+Ol l. 1E+02 Kr-85 1.0E-Ol 4'.,5E-01 5.5E-01 Kr-85m 1.5E 00 1.1E 00 2.6E 00 Kr-87 6.2E-01 l. 8E" 01 8.0E-01 Kr-88 1.1E 00 7.6E-01 1.9E 00 Xe-131m 3.6E 00 2.0E-01 3.8E 00 Xe-133 1.3E+04. 9.1E+03 2.2E+04 Xe-133m 1.0E+01 4.2E 00 1.4E+01 Xe-135 3.1E+01 2.2E+Ol 5.3E+01 Xe-135m 9. 8E-'02. neg 9.8E-02 Xe-138 neg, neg, neg Total Gases 1.3E+04 9. 2E+03 2.2E+04

~lageos 1.7E-02 5.4E-02 I-131 3.7E-02 I-133 3. 1E-02 7.0E-03 3.8E-02.

I-135 1. 6E-02 neg 1.6E-02 Br-82 1. 1E-03 3.7E-04 1.5E-03 Total Halogens 8.6E-02 2.5E-02 l. 1E-Ol

page 3 of 3 Table 2 Turkey Point Units 3 and 4 Releases of Radioisoto s for the Period, Jul 1, 1979-June 30, 1980 (Releases)

Isotope 7 79-12 79 1 80-6 80 12-months Tota1 curies curies Particulates

. 4.8E-05 4.8E-05 'g-,110m 2.8E-. 05 3'.6E-05 6.4E-05 Ba-140'e-141 2.6E-05 1.,1E-04 1.4E-04 Co-57 '5.3E-05 5.5E-05 1.1E-04 Co-58 2.0E-02 2.1E-02 4.1E-02 Co-60 3.1E-03 1.0E-02 1.3E-02 Cr-51 2.1E-03 3.2E-03 5.3E-03 1.4E-04 2.0E-04 3.4E-04 Cs-134's-136 6.9E-06 neg 6.9E-06, Cs-137 2.2E-04 3.2E-04 5.4E-04 Fe-59 1.8E-04 1.7E-04 3.5E-04 I-131 5.2E-05 4.1E-05 9.3E-05 La-140 2.0E-05 5.0E-05'.7E-04 7:.OE-05 Nn-54 5.5E-04 l.lE-03 Nb-95 3.9E-04 3.3E-04 7-2E-04 Ru-103 8.3E-05 3.9E-04 4.7E-04 Sb-124 2.3E-04 1.6E-04 3.'9E-04 Sr-89 1.9E-05 5.5E-05 7.4E-05 Sr-90 l. 2E-.06 1.1E-05 1.2E-05 2.8E-04 Ir-95 1.7E-04 1.1E-04 7..3E-05 7.3E-05 Ce-144'Sb-125 1.5E-05 l. 5E-05 Zn-65 1.5E-04 1. 5E-04 Total Par ticulates 2. 8E-02 3.7E-02 6.5E-02

0 page 1 of 2 Table 3 Releases. from One Operating Unit and Steam Generator Re ir of the Other Releases from: (curies)

~lsoto One 0 tatin Unit> ~SG Re it 'otal Li uid Releases Ag-110m. 3.0E-03 3.0E-03 Co-58 6.0E-02 1..7E-Ol 2.3E-01 Co-60 1.1E-01 1.3E-01 2.4E-01 Cr-51 5. 5E3 3.,7E-04 5:9E-03 Cs-134 1.6E-02'.5E-04 3.0E-02 4.6E-02 Cs-136 2.5E-04 Cs-137 2.8E-02 1.4E-01 1.7E-01 Pe-59'-131 3.9E-04 1.7E-05 4.1E-04 2.1E-02 7.6E-02 9.7E-02 I-132 4.3E-03, ,4.3E-03 I-133 1.3E-02 1.3E-02 La.-140 5.,5E-04 5.5E-04 Mn'-54. 1.4E-03 1.8E-02 1.9E-02 Mo-99/Tc-99m 5.5E-04 '5.5E-Q4 Na-.24 7.5E-04 7.5E-04 Ko-95 5.0E-04 5.0E-04 Ru-103 1.6E-04 1.6E-04 Sb-124 8.5E-03 8.5E-03 Sb-125 7..0E-03 7.0E-03 Sr-89 3.6E-03 4.8E-05 3. 6E-.03 Sr-90 2.8E-05 2.8E-05 Te-132. 4'.OE-04 4.0E-04 Total Licpids 2. 9E-.01 5.5E-'3. 8.4E-Ol a One-half the, annual rel'eases from. Units 3 and 4 as shown on Table 2.

ll Oi ~ ~

page 2 of 2 Table 3 Releases from One Operating. Unit and Steam Generator Re ir of the Other Releases from: (curies)

IsotooB One 0 ratin Unit. ~SG Re ir Total Gaseous Releases A-41 5.5E+Ol Kr-85 2;8E-01 2'.8E-01 Kr-85m 1.3E 00 1.3E 00 Kr-87 4.0E-'1 4.0E-Ol Kr-88 1.0E 00 1.0E 00 Xe-131m 1.9E 00 1.9E 00 Xe-133 1.1E+04 1.1E+04 Xe-133m 7.0E 00 7.0E 00 Xe-135 2.7E+01 2-7E+Ol Xe-135m 4.9E-02 4.9E-02.

I-131 2.7E-02 9. 1E-03 3. 6E-02 I-132 1. 4E-03 1. 4E-03 I-133 l. 9E-02 1.9E-02 8.0E-03 I-135 8. OE-03 Br-82 7.5E-04 '7.5E-04 Ag-110m 2.4E-05 2.4E-05 Ba-140 3.2E-05 3 2E 05 Ce-141 7,.0E-05 4.0E-04 4.7E-04 Co-57 5.5E-05 5.5E-05 Co-58 2.1E-02 1.7E-02 3.8E-02 Co-60 6.5E-03 2.,7E-03'.5E+01 1.3E-02 1. 9E-'02 Cr-51 2.7E-03 6.8E-04'.

3.4E-03 Cs-134 1.7E-04 1. 7E-04 Cs-136 3.5E-06. 3.5E-06 Cs-137 2.7E-04 2.7E-04 Fe-59 1.8E-04 7E-04 4.5E-04 La-140 3.5E-05, 1.7E-04 2.1E-04 Nn-54 5.5E-04 1.5E-03 2.1E-03 Nb-95 3-6E-04 2.5E-03 . 2.8E-03 RQ-103 2.4E-04 8.5E-04 1.1E-03 Sb-124 2.0E-04 2.0E-04 Sr-89 3.7H-05 3.7E-05 Sr-90 6.0E-06 6.0E-06 Zr-95 1.4E-04 1.4E-03 1.5E-03 Ce-144/Pr-144 3.7E-05 2.7E-03 Sb-125 7.5E-06 7.5E-06 Zn-65 7.5E-05 7.5E-05 a Che-half the annual releases from Units 3 and 4 as shown on Table

II

~q 0

Table 4

.Doses to Maximum Individual from Com'oined Li id Beleases Tyge of Dose Maximum Xndividual Dose, mrem/year from:.

0 nation of One Unit ~SG Re ait 'Zotel.

Adult GX-LLX. 1.4E-Ol 1.3E-01 2'.,7E-.01 Total Body 1.9E-02 ,4.4E-02 6. 1E-02 Teen GX-LLX 9.0E-02. 8.2E-02 1. 7E-01 Total Body 1.5E-02 3.0E-'2 4. 5E-02 Child-WX-LLI 3.6E-02 3. 1E-02 6.7E-02 Total Body 1.3E-02 2. 2E-02 3.5E-02

Ol I Table 5 Doses to.llaximum Individual from Combined Gaseous Releases.

iMximum Individual Dose, mrem/ ear, from:

of Dose 0 nation One'nit ~BG Be it Totai Air Dose Site Boundary Beta 2. 2E-01 2. 2E-01 Gamma '8.0E-02 8.0E-02 Nearest Garden and Residence, 3.6 m NNN Adult Total Body '.0E-.03 '5.7E-04 7'. 6E-03 Thyroid 1. 3E-02 2.4E-03 1. 5E-02 Teen Total Body 7. OE-'03 6.0E-04 7'.6E-03 Thyroid 1.2E-02 2.0E-03 1.4E-02 Child. Total Body, 7. OE-.03 7.1E-04 7.7E"03:

Thyroid. 1. 4E-02, 2.8E-03 1.7E-02 Infant Total Body 7..0E-03 4.9E-04'.5E-03 Thyroid 8.0E-03 8.9E-04' 8.9E-03 Staff Cow at 4.5 mi W Mult Total Body 1.3E-04 6. OE-05 1. 9E-04 Thyroid 2.9E-02 9.5E-03 '.9E-02 Teen Total Body 3.'.6E-04 7.0E-05, . 2.3E-04 Thyroid 4.2E-02 1.4E-02 5.6E-02 Child Total Body 2.8E-04 1.3E-04 4.1E-04 Thyroid 8.5E-02 2.8E-02 1.1E-01 Infant Total Body 4.2E-04 1.6E-04 5. 8E-0'4 Tnyroid 2.0E-01 6.6E-02 2.7E-01

PROFESSIONAL QUALIFICATIONS AND EXPERIENCE OF DR. WALTON A. RODGER My name is Walton A. Rodger. I am President of the nuclear consulting f'irm Nuclear, Safety Associates, Inc. of Bethesda,, Maryland, and have. been associated; with the firm for. the past thirteen years. The four years, prior. to that I was Vice President of Nuclear Fuel'ervices, Inc., serving as.its 'Technical Director and 1'ater as General Manager of its West Valley,plant. In the latter position I was responsi-ble for the construction, startup, and licensing of the worl'd's first privately owned nuclear fuel reprocessing plant.

From 1960'. to 1962, I was a Partner in the nuclear consulting firm of McLain Rodger Associates. Before entering the consulting field, I spent 13. years at Argonne National

'Laboratory, four at, Oak Ridge National Laboratory, and one at the Metallurgical Laboratory of the University of Chicago.

At all three I was active in the development of al'1 of the various processes which have been considered for use in reprocessing of nuclear fuel. I also did a great deal of work in the field of radioactive waste management. At Argonne I was Associate Director of the Chemical Engineering Division. My total experience in the nuclear field has covered 39 years.

I was graduated in both Chemical and Metallurgical Engineering from the University of Michigan in 1939. I obtained

my Master's Degree in Chemical Engineering from the same institution in 1940.. My Doctorate in Chemical Engineering was. awarded'y the Illinois Institute of Technology in 1956.,

I, am; the, author of sections of several nuclear handbooks and have published more than two dozen papers in the nuclear field, largely on reprocessing and waste disposal. I am, a. Fellow of'IChE, and in. 1960 was Chairman of the Nuclear Engineering, Division of the Institute. I am also a member of ANS and AIF., I am pas.t chairman of the ANSI Committee N.-'8 which is developing. standards for the disposal of solid nuclear waste., In 1959, I served as Technical Consultant to the Joint Committee on Atomic Energy of the 86th Congress at the Hearings on Industrial Radioactive Waste Disposal.

I served., as a principal witness for the Consolidated Utility Group in the As Low As Practicable Rule Making Hearing (RM-50-2).

In thi.s capacity I have done extensive: cost-benefit studies on LWR radwaste systems.

4k I ~

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