ML19260D118

First Set of Interrogatories Directed to Mi Lewis in Restart Proceeding.Requests Basis for Alleged Necessity to Install Preheaters on Auxiliary Bldg Filters.Supporting Documentation & Certificate of Svc Encl

ML19260D118
Person / Time
Site:	Three Mile Island
Issue date:	01/23/1980
From:	Trowbridge G METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Lewis M AFFILIATION NOT ASSIGNED
References
NUDOCS 8002070441
Download: ML19260D118 (21)

Text

January 23, 1980 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROFJLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

LICENSEE'S FIRST SET OF INTERROGATORIES TO INTERVENOR MARVIN I. LEWIS These interrogatories are filed pursuant to 10 C.F.R.

S 2.740b, which requires that the interrogatories be answered separately and fully in writing and under oath or affirmation.

Licensee recognizes that you may not now be able to completely answer all interrogatories propounded below, since some areas are the subject of discovery by you to Licensee. Licensee there-fore requests that each of these interrogatories be answered within the time specified in S 2.740b to the extent that re-sponsive information is presently available to you. With re-scect to those interrogatories for which complete and responsive information is not now available to you, Licensee requests that revised answers be provided prior to the close of the discovery period established in the Licensing Board's December 18, 1979 First Special Prehearing Conference Order.

The following definitions apply to each of the inter-rogatories below: 1935 036 8002070 N h

A. " Document" means all writings and records of every type including, but not limited to memoranda, tapes, correspondence, reports, surveys, tabulations, charts, books, pamphlets, photographs, maps, bulletins, minutes, notes, diaries, logs, speeches, articles, transcripts and all other records, written, electrical, mechanical or otherwise.

B. " Identify" means:

(1) With respect to a natural person, name, present or last known home or business address, present or last known job title or position, and the dates of tenare in that position; (2) With respect to a document, the type of document (e.g., letter, record, list, memorandum, memorandum of telephone or face-to-face conversation, etc.), date of the document, title of the document, subject of the document, name of person who prepared the document, and name of person for whom the docu-ment was prepared or to whom it was delivered.

Interrogatories on the Lewis Contention 1-1. Explain with particularity the basis fc. your claim that it ir necessary to inctall preheaters on the filters in the TMI-l auxilic.ry building.

1-2. Identify and describe the nature of each and every design error which you contend exists in the TMI-1 filter cystem.

1935 037

1 3. With respect to each design error identified in ponse to Interrogatory 1-2 above, state with particularity what you con *.end ;aust be done to correct the design error.

1-4. With respect to each proposed action identified in response to Interrogatory 1-3 above, explain how it would improve on the systems presently installed at TMI-l for the control, hold-up and filtracion of radioactive gases, as de-scribed in Section III-D-2-a of the Final Environmental State-ment for TMI-l and TMI-2 (copy attached).

1-5. Do you contend that the safety evaluation per-formed by the NRC Staff with respect to the adequacy of the TMI-l gaseous radwaste systems, as described in the January 11, 1980 Status Report on the Evaluation of Licensee's Compliance with the NRC Order dated August 9, 1979, pages C5-1 through C5-14, is inadequate to resolve the concerns identified in your contention. If so:

(a) Describe in detail the inadequacies of the gaseous radwaste system safety evaluation performed by the NRC Staff, with special consideration given to the cost-benefit analysis made by the NRC Staff.

(b) For each inadequacy listed, set forth each and every fact and the source of each and every fact relating to or bearing upon the allegation.

(c) For each inadequacy listed, identify all documents, and the particular parts thereof, contain-ing any evidence or information relating to or bear-ing upon the allegation.

1935 038

1-6. Describe your understanding of the purpose (s) served by the filters in the TMI-1 auxiliary building.

1-7. Do you contend that the filters in the TMI-l auxiliary building should be designed to handle gasecus re-leases more severe than conditions associated with the design basis accidents for TMI-l? If so, describe each accident scenario which you contend the filters should be designed to handle.

Interrogatory No. 2 2-1. With respect to each individual whom you intend to call as a witness in this proceeding:

(a) Identify by name, address and affiliation each such individual; (b) State the educational and professional background of each such individual, including occupa-tion and institutional affiliations, publications and papers; (c) Describe the nature of the testimony which will be presented by each such individual, including an identification of all documents which the indi-vidual will rely upon in the testimony; (d) Identify by court, agency or other body, proceeding, date and subject matter all prior testi-1935 039

mory by each such individual.

Respectfully submitted, SHAW, PITTMAN, POTTS & TROWBRIDGE By: kj *

/bza/ t./

' f Gei(rge F. Trowbridg4 1800 M Street, N.W Washington, D.C. 20036 Tel: (202) 331-4100 Counsel for Licensee Dated: January 23, 1980 1935 040

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2. Radioactive Waste in the operation of nuclear power reactors, radioactive =aterial is produced by fission and by neutrou activation reactions of metals and caterial in the reactor coolant syste=. Small amounts of gaseous and liquid radio-active vastes enter the effluent streams, which are tenitored and processed within the Station to =inimize the radioactive nuclides that will ulti=ately be released to tta at=osphere and into the Susquehanna F.iver at low concen-trations under controlled conditions. The L1=itations of 10 CFR Part 20 and the "As Low As Practicable" requirements of 10 CFR Part 50 with respect to radioactive releases will be met during the operation of the Station at full power.

paragraphs, The are vaste treat =ent designed syste=s for the Station, described in the following to collect and process the gaseous, liquid , and soli'd vaste which =ay contain radioactive =acerials. These vaste handling and treat-ment syste=s are discussed in detail in the Final Safety Analysis Report for Unit 1 (March 2,1970), in the ?reli=inary Safety Analysis Report for Unit 2 (March 1969), and in the Applicant's Revised Environmental Report dated December 1971.

a. Gaseous Waste. During power operation of the facilities, radio-active materials released to the at=osphere in gaseous effluents include low concentrations of fission product noble gases (krypton and xenen), halogens (mostly iodines), tritium contained in water vapor and particulate material including both fission products nand activt . i corrosion products. The syste=s for the processing of radioactive gaseous :e and ventilation paths are shown sche =atically in Figures 9-11.

the primary coolantConcentrations of various solut es, such as hydrogen and boron, in are maintained at specified values, and the buildup of fission and activation products is limited by withdrawing coolant at a nor=al rate of 45 gpm (the letdown stream). A side stream from this coolant is. cooled, depressurized, and diverted to the makeup and purification system and, as necessary, to the boren management system or the liquid waste disposal system, Figure 12.

Normally, the vent valves on the makeup and purification system equipaent are closed and the system is operated at positive pressure.

By this procedure the inventories of noble gases in the coolant increase to steady-state values except in the case of long-lived krypton-85. Only the coolant that is diverted to the boron control system is normally degassed.

1935 041

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i III-16 g Gases stripped frc= the recycled reactor coelant together with cover gases are collected, compressed, and stored in pressurized tanks for radioactive decay. With the exception of long-lived krypton-85, the gases will decay to a small fraction of the original a=ount prior to being released. The gas is filtered through high efficiency particulate filters and charcoal adsorbers and released to the atmosphere through the acciliary building vent stack. i The holdup system was evaluated based on the Applicants' statement that a minicum holdup of 30 days will be used.

l Additional sources of radioactive gases which are not concentrated enough to per=it collection and storage include the auxiliary building exhaust, the turbine building exhaust, the reactor building contain=ent air, and the main condenser air ejectors, which re=ove radioactive gases '

which have collected in the condenser as a result of pri=ary to secondary syste= leakage. The air ejector exhaust frem the main condenser of Unit 1 is discharged through the turbine building exhaust without treat =ent. The ej ector exhaust from Unit 2 is routed through demisters to the ' auxiliary building filter train and released to the station vent.

l The auxiliary building is =aintain ad at a slightly negative l pressure with respect to ambient pressure. All the exhaust air is filtered through high efficiency particulate filters (EEPA) prior to being discharged through the auxiliary building vent stack. Areas within the auxiliary building which have possible contamination have the capability to be exhausted through charcoal adsorbers in addition to EE?l. filters. l The stems generators are once-through units with no blowdown and with full flow de=ineralizers on the condensate return. Turbine building ventilation is discharged to atmosphere without trea tment through roof-mounted exhaust f ans.

Calculations of expected normal discharges of noble gases and iodines are se==arired in Tables 4 and 5. The bases for these calcula- L tions are presented La Table 8. -

b. Licuid Wastes. All equipment relevant.to the liquid waste l processing system is duplicated in the two units except the miscellaneous waste evaporator which is located in Unit 1 and shared by Unit 2. A notable dif f erence between the two units is the method of condensate desineraliration.

Unit 1 uses Powdex; whereas, Unit 2 uses deep-bed desineralizers. Due to the constraints on wacte processing in the miscellaneous waste subsystem, we ass =med in our evaluation that 10% of the deep-bed regenerant solution and -:

100% of the Powdex sluice water will be released to the environ:nent without  :

tr ea tment . ,

In both units a make-up and purification system maintains the quality and boron concentration of the primary coolant. A stream is continuously " letdown," cooled, desineralired in a mixed bed ion exchanger, .

I935 046 -

3

Table 4 ANTICIPATED AtlHilAI. ItEI. EASE OF ItAD10 ACTIVE NUCl. IDES IN CASE 0llS EFFI.llEMT FROM TilREE Hil.E ISI.AtID UNIT 1 Discharge Ra'e t (C1/yr)

Cas Steam Auxiliary Containment Processing Generator llu11 ding System 1.cak 1.ca k Total Isotope Purge 1 1 2 Kr-83m - -

5 5 10 Kr-85m 665 10 10 705 Kr-85 20

- 2 3 5 Kr-87 -

9 9 18 y Kr-88 -

53 6 5 66 Xe-131m 2 10 10 20 Xe-133m 890 860 850 2740 Xe-133 140

- 15 15 30 Xe-135 -

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filtered, and fed to the cake-up tank from which it is returned to the g

reactor. When the boron rencentration is being' lowered, a " bleed" stream g

r-f rom the " letdown" stream is directed to the coolant taste system. This stream is processed through a demineralizer, filter and evaporator. The h

condensate from the evaporator passes through a mixed bed de=ineralize. , y to a storage tank from which it may be recycled or discharged. The

g concentrated boric acid (evaporator bottoms) is stored for re-use in g a subsequent core cycle or sent to the radioactive vaste dru=ing station  ;

y for off-site disposal.

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During the last portion of the core cycle, when the boron concentration is the lowest, the entire " letdown" stream is also passed  :

through a deborating de=inerali:er to eff ect reduction of boren content, rather than by use of a " bleed" strea=. ,

This = ode of operation does not produce a vaste stream directly; however, this deborating bed is regenera- g ted, and the neutrali:ed regenerants and rinses are . processed' through the -

=iscellaneous vaste system. No other de=inerali:ers processing radio- -

L active strea=s are regenerated except the =ain condensate de=ineralizers in J

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Unit 2, centioned above. Other vaste-water containing boric acid fro =

reactor shutdowns, startups, and refueling operations is also processed h

, HM through the coolant vaste disposal system equipment.

Wastes collected in the contain=ent and auxiliary building drains, lab and sampling drains, de=inerali:er resin and filter precoat sluice water, h%

deborating bed regenerants, and decontamination and other miscellaneous wastes are processed in the miscellaneous vaste system. These vastes are co-llec t ed , f ilt er ed , and evapora t ed . The condensate from this evaporator yQ is passed through a polishing de=ineralizer and then routed to recycle or M to hold-up for discharge. Bottoms from this evaporator are stored in the @

concentrated waste tank until they can be processed through the vaste y dru= ming station. dy Laundry vastes vill be collected, filtered, monitored, and s nor= ally routed with the sanitary vastes. The turbine building drains @h are monitorec. and discharged to the cooling tower effluent s tr eam. From an accu =ulative leak rate of 5 gpm f cm all systems in the turbine building .f 7 @

that contain secondary coolant we expect less than .05 C1/yr. -yd Controlled discharges will be made from the radvaste systems as into the cooling tower effluent stream. This flow is 36,000 gpm on an annual g

average basis f or the combined units. Unit 1 can discharge vaste at up to E 30 gpm while Unit 2 can achieve a maximum of 50 gpm. Activity monitors and E flow controllers vill maintain approximate activity levels. Discharges can- '% g not be made from both units simultaneously. No discharge vill be made unless the cooling tower af fluent flov is at least 5000 gpm. g Based on the assumptions noted above and shown on Table 8, the releases frce the primary sources for normal operation were calculated to R

be less than 5 C1/ year per unit. To compensate for treat =ent equipment 1

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i III-20 Table 6 ANTICIPATED ANNUAL RELEASE OF RADICACTIVE MATERIAL IN TFE LIQUID EFFLUENT FRCM Ti!REE MILE ISLAND UNIT 1 Nuclide Curies /vr Rb-86 0.00055 Sr-89 0.00044 Y-90 0.00005 Y-91 0.0099 Zr-95 0.00007 Nb-95 0.00007 Mo-99 0.037 .

Tc-9?s 0.037 l Ru-103 0.00005 i Rh-103s 0.00005 0.00005 i Sb-124 ,

Te-125m 0.00003  !

"e-127m 0.00032 Te-127 0.00035 Te-129m 0.0016 Te-129 0.0010 Te-131m 0.00074 Te-131 0.00014 Te-132 0.019 I-130 0.0013 l I-131 1.8 ,

I-13 2 0.020 l I - 13 3 0.21 I-135 0.025 Cs-134 0.21 Cs-136 0.083 Cs-137 0.17 Ba-137m 0.16 Ba-14 0 0.00048 La-140 0.00042 Ce-141 0.00007 Ce-144 0.00005 Pr-143 0.00007 .

Pr-144 0.00005 Nd-147 0.00002 '

Na-24 0.00007 P-32 0.00007 -:

0.0011 Cr-51 Fe-55 0.0010 Fe-59 0.0006 Co-58 0.0097 Co-60 0.0012 Ni-63 0.00009 1935 050 -

W-185 0.00005 ,

W-187 0.0005R Np-239 0.00035 c

TOIAL N 3.0 Tritium-1,000 C1/yr ' :. -

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III-21 Table 7 ANTICIPATED ANh".?AL RELEASE OF , LDI0 ACTIVE MATERIAL IN LIQUID EFFLUENTS FROM I'r2EE MILE ISLAND UNIT 2 Nuclide Ci/vr Nuclide C1/vr I

Rb-86 .0012 Pm-147 .000054 Sr-89 .0041 Na-24 )

.000089 Sr-90 .00012 -

P-32 .00048 Sr-91 .000018 Cr-51 .0088 Y-90  ;

.000072 Mn-54 .000036 Y-91 .0082 Fe-55

.011 Zr-95 .00072 Fe-59 .0054 Nb-95 .00080 Co-58 i

.095 Mc-99 .032 Co-60' .013 Tc-99m .030 Ni-63

.011  :

Ru-103 .00048 In-65 .000054 Ru-106 .00014 W-185 .00045 Rh-103= .00048 W-187 .00082 Rh-106 .00014 Np-239 Sb-124

.00075

.00036 Sb-125 -

.000036 TOTAL N 5.0 Te-125= .00034 i Te-127m .0036 Te-127 .0034 Tritiu= 1,000 C1/yr Te-129m .014 Te-129 .0088 Te-131= .0012 Te-131 .00021 Te-132 .050 I-130 .0013 I-131 2.7 I-132 .052 I-133 .20 1-135 .021 Cs-134 .54 Cs-136 .15 Cs-137 .41 Ba-137= .39 Ea-140 .0030 La-140 .0032 Ce-141 .00066 Ce-143 .00002 .

Ce-144 .00045 Pr-143 .00039 Pr-144 .00045 Nd-147 .00014 1935 051

I III-22 Table 8 ASSUMPTIONS USED IN DETERMINING RELEASES OF RADIOACTIVE EFTLUENTS AT THREE MILE ISLAND Unit 1 Unit 2 -

Reactor Power , MWt 2535 2772 0.8 0.8 Plant Capacity Factor Fuel with Def ective Cladding , " 0.25 0.2' ,

Leak of Prinary Coolant into Steam Generators, gpd 20 20 Leak of Pri=ary Coolant to the Auxiliary Building, gpd 40 40  ;

i 4 4 Frequency of Containment Purge, etnes/yr Waste Gas Holdup for Decay, days 30 30 2 2 Fold Shutdowns, times / year woolant Volumes Degassed and Processed During ,

i Cold Shutdowns and Nor:al Operations 5 5 Miscellaneous Waste Processed, gallons / year 600,000 600,000 l

i i935 052

n-a.- -=~-

?Wi~iu3 & ??%M M4%.; % M &-u W L u: w n =~ ~ ~ :n ~

- m n

III-23 ,

downtime and expected operational occurrences, the values shown in Tables 6 and 7 for the waste syste=s have been nor=alized to 3 curies per year for _

r Unit 1 and 5 curies per year for Unit 2. f t

n

.  : lid "c::::, Th; f;11:L ir.; :yp__ _: _; 1 2 -e- -ca - 11 ' c l

eated in Unit 1 (Unit 2 wastes that require solidification vill be trans-fe. ed to Unit 1):

1 (1) Compressible wastes - paper, rags, clothing, .ma charcoal filters (2) Incompressible wastes - metal pa ts from inside the reactor, wir es , cable , and spent filter cartridges.

(3) vaporator concentrates.

t (4) Sp t resins and used filter precoat. l I

All solid aste will be packaged and shipped to a licensed burial i ground in accordance vi h AEC and DOT regulations. Based on plants presently  ;

in operation, it is expec ed that approximately 300 to 600 drums of solid l waste vill be transported #f-site each year.

3. Chemical and Sanitarv 'as c es g The che=icals used in sig. ificant quantities at the Station are listed l in Table 9. 1 i

a. Demineralizer Receneration Solutions. Sulfuric acid and sodium hydroxide solutions are used f or regenn ting resins in the two-stage f eed water demineralizers used for both Uni:s and 2. These =aterials are disposed of on a batch basis; each batch, r a given unit, consists of 2,000 pounds of sulfuric acid and 1,300 poun of sodium hydroxide diluted in 70,000 gallons of water. The resulting sol tion of sodium sulfate, with a pH between 6 and 9, is released every three da s at a controlled rate over a 4-hour period (about 300 gpm flow rate) . The s te solution is diluted with the 36,000 sp= cooling water effluent of the ced-draf t cooling towers prior to discharge to the river. The amounts listed n Table 8 are the total quantities of acid and base used annurlly for the two nits at the Station.

The concentrations in the second column of the Table, he ever, occur in the 36,000 gpm cooling water effluent only during the batch d. charge f rom a single unit, since the two units discharge their batches at ifferent ti=es.

b. Condensate Polisher Receneration Solutions. The e densate polishers for Unit 1 are the wound element filter type precoated with powdered resin. The spent resin is washed out and discharged to t e sludge

..mo;_m.a 1.;m;c :;:hcr th r being rr:r-er- e> 'a--- -- -aga-av,**e 1935 053

January 23, 1980 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

CERTIFICATE OF SERVICE I hereby certify that copies of " Licensee's First Set of Interrogatories to Intervenor Marvin I. Lewid' were served upon those persons on the attached Service List by deposit in the United States mail, postage prepaid, this 23rd day of January, 1980.

Robert 4Eh Zahler Dated: January 23, 1980 1935 054

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

SERVICE LIST Ivan W. Smith, Esquire John A. Levin, Est;. lire Chair:ran Assistant Counsel Atomic Safety and Licensing Pennsylvania Public Utility Comm'n Board Panel Post Office Box 2265 U.S. Nuclear Pegulatory Ccmnission Harrisburg, Pennt,ylvania 17120 Washington, D.C. 20555 Karin W. Carter, Esquire Dr. Walter H. Jordan Assistant Attorney General Atomic Safety and Licensing 505 Executive House 30ard Panel Post Office Box 2357 881 West Outer Drive Harrisburg, Pennsylvania 17120 Oak Ridge, Tennessee 37830 John E. Minnich Dr. Linda W. Little Chair: nan, Dauphin County Board Atomic Safety and Licensing of Ccnmissioners Board Panel Dauphin C)unty Courthouse 5000 Hermitage Drive Front and Parket Streets Raleigh, North Carolina 27612 Harrisburg, Pennsyhenia 17101 Jartes R. Tourtellotte, Esg* Walter W. Cohen, Esquire Office of the Executive Legal Director Consumer Advocate C. S. Nuclear Regulatory Ccmnission Office of Consumer Advocate Washington, D.C. 20555 14th Flcor, Strawberry Square Harrisburg, Pennsylvania 17127 Docketing and Service Section Office of the Secretary U. S. Nuclear Pegulatory Ccmaission Washington, D.C. 20555 1935 055

6"ordan D. Cunningham, Esquire Karin P. Sheldon, Esquire Attorney for Nesberry Township Attorney for People Against Nuclear T.M.I. Steering Ca mittee Energy 2320 North Second Street Sheldon, Harrrr1 & Weiss Harrisb'1Ig, Pennsylvania 17130 1725 Eye Street, N.W., Suite 506 Washirston, D.C. 20006

'Iheodore A. Adler, Esquire Widoff Peager Selkowitz & Adler Robert Q. Pollard Post Office Box 1547 Chesapeake Energy Alliance I:arrisburg, Pennsylvania 17105 609 Montpelier Street Baltimore, Maryland 21218 Ellyn R. Weiss, Esquire Attorney for the Union of Concerned Chauncey Kepford Scientists Judith H. Johnsrud Sheldon, Harmon & Weiss Ernironmental Coalition on Nuclear 1725 Eye Strat, N.W., Suite 506 Power Washington, D.C. 20006 433 Orlando Avenue State College, Pennsylvania 16801 Steven C. Sholly 304 South Market Street Marvin I. Iewis Mechanicsburg, Pennsylvan2a 17055 6504 Bradford Terrace Philadelnhia, Pennsylvania 19149 Gail Bradford Holly S. Keck Marjorie M. Aamodt legislation Chairran R. D. 5 Anti-Nuclear Group Representing York Ccatesville, Pennsylvania 19320 245 West Philadelphia Street York, Pennsylvania 17404 1935 056