ML17340B024

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
Issue date:	04/06/1981
From:	Rodger W NUCLEAR SAFETY ASSOCIATES
To:
Shared Package
ML17340B023	List: ML17340B022 ML17340B024 ML17340B026 ML17340B027 ML17340B030 ML17340B032
References
ISSUANCES-SP, NUDOCS 8104220625
Download: ML17340B024 (30)

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

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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 ~