ML19253A511

From kanterella
Jump to navigation Jump to search
Submits TMI Daily Rept Re Reactor & Plant Status,Radwaste & Health Physics & Environ Measurements
ML19253A511
Person / Time
Site: Crane Constellation icon.png
Issue date: 05/16/1979
From: Vollmer R
Office of Nuclear Reactor Regulation
To: Stello V
Office of Nuclear Reactor Regulation
References
NUDOCS 7909100185
Download: ML19253A511 (28)
v • d • e


Text

{{#Wiki_filter:' + 3 t >Jt Ra cq*/ 4 UNITEO STATES + o -gV 4 * *4 NUCLEAR REGULATORY COMMISSION 'g _v j, j WASHINGTON, O. C. 20s55 % %@%j n /j = g, 2,4 j, May 16, 1979 M EMO RANCUM FOR: Victor Stello ] e CROM: Richard H. Vollmer I SU3 JECT: TMI DAILY REPORT f A. Roactor and Plant Status 1. A meeting was held with invited state and local of#icials at the Hershey Convention Center to discus 5 eleases of liquid waste from TMl to the Susquehanna. Main inte est was centered around the highly contaminated water on the reactor building Floor and the prirary systen. The opening statement and list of NRC representatives is attached. o110 wing this eeting a press con T cerence was held in Middletaan with esseatially the same focus. 2. Te chn i ca l Progress Meeting - see Attachment #or agenda and notes. 3. Syste-Para eters and : ore Map - systen solid until late -orning when bubble draan to permit pressure reduction to coen JH-V2 (see bel ow). Prima ry l eakage s t i t i opp-oximately gpu at 600 psi. cre -ap is atta: bed.

h. *tast night, OH-V6 was opened to obtain acnta!c ent water :: vel reading.

Level was 290.7',,iost :overing t e gasket on the h limit switch cover on JH-V2. Motor drive connections are also inside this cover. Megger readings on motor indicate no

hange # rom previous readings and limit switch appears C.A.

Intend to ocen OH-V2 as soon as possiale to preclude future inability to do so. Subble drawn this orning and 7C: pressure at 602 psig at 2:00 c.n. Pet-Ed investigating ways to sa'elv accelerate coolfavn i' recessary to per-it cariv JP-V2 cpening without popping JW-RI. CTSG "I' closed l oop portion vill be #1us5e3 toda', cnd ce eady #7e operational testing to-orrow.

  • As of 5: 00 p..,.

today, information was recei"ed which puts level measurerent in doubt. All aspects are oe;ng rec"ecked and wi!! be reported to orrow. ( ) 7 9 09100 /9F 300RORGiul P:

' lictor Stello = 3. Environ ental Mea s u r-e n t s 1. ido radiation level above background was detected by 30E aerial surveys. fio reports were received from other Federal agencies. j 2. tJRC ground survey data showed all beta-gamma levels at .32 mr/hr. 3 Ai r samples at locations around the site ranged from 1.3 x 10-12 to 7.5 x 10-I2 4 Three milk samples showed readings less than 10.h picocuries per liter. 5. One soil sample on 5/lk/73 along Rt. Ehl showed 1.2 x 10 - I '] micro curies per gram of I-131 and 2.16 x 10-/,icro curies per gram of O -137-s 6 Release data is attacFed. I ^ 'c8 :;n / R fc a r d H. '/o l !-e r Attachment; cc: J. Eisenhut G. Smith, IE R. Vollmer D. Crutchfield

3. Grimes G.

Chioman J. Collins G. Lainas 0"3 l-L, P00RDIGNAL

OPENING STATEMENT 3Y R. H. VOLLMER AT MEETING WITH INVITE] STATE AND LOCAL CFFICI ALS AT HERSHEY CCNVENTION CENTER, MAY 16, 1979, 11:23 A.M. 4 Good Morning - it's my pleasure to welcome you, on behalf o' the Nuclear Regulatory Commission, to discuss releases of water from the Three Mile Island facility to the Susquehanna River. At a y meeting with Governor Thornburgh on Monday, the Covernor suggested that this meeting be arranged to answer your questions concerning j releases to the Susquehanna and the cleanup and disposition of the highly contanirated water that exists primaril y in the reactor e building and the reactor coolant system. le appreciate the concerns expressed by many o# you regarding the cl:anup and disposition of contaminated water f rom Three Mile 1s!and. We hooe to reassure you, as a result of today's discussions and answers to your questions, that there are sa#eguards and controis which will prevent any irpact from the cleanup process, on you and the people you represent. I an not planning on a detailed discussion at this tire - rather - after a few brief comments on what we discussed with Governor Thornburgh, I would like to open the meeting tn your questions. First, from the releases that have occurred between March 21 and the nresent, our analysis shows that the levels of radioactivits in the Susquehanna a re indistinguishable fran the existing back-ground levels at puolic water supply intakes 'ro, the river. This has been con #irmed by independent downstream measurements made by NRC, EPA, and the Connonweal th of Pennsylvania. Put more simply, the liquid releases from the plant, which have been primarily from creaccident Unit I water and secondly # rom water contarinated by the accident, have not added measurably to radiation levels down-stream in the Susquehanna. N av, concerning the water that has been highly contaminated by the accident, none of this has been crocessed or discharged and none will be orocessed or discharged until the NRC has performed a detailed review and analysis of Metropolitan Edison's processing plans, nethods, equip ent, and procedures and we have full assurance that these operations will not have an irpact on Jownstrea co munities. The results of our review and analysis of the c!eanup process will be made available to the public. The NRC intends to continue its -onitoring activities, and other governmenta! agencies.vili be involved as well, to assure that radicact ive levels in the Susquehanna remain at essentially ' ackground quanti ties. Althougn the plant c "as undergone a serious accicent, we will require that the conditions for elease to the river will re-ain the sa e as 'or normal operation. 4e expect that the cleanuo process can and will be done with this nojective. P00R ORGN a =

Now I would like to respond to your questions - and to be sure that we can respond in all your areas of interest - I have with me today - Mr. 3rian Crines - whose responsibilities include environmental evaluation of operating reactors, e Mr. John Collins - whose responsibilities include evaluation of systems for the treatrent and cleanup o# contaninatec ef fluents, Mr. Frank Congel - whose responsibilities include eval ua t ion o f radiation dose # rom drinking water, fish consumption and so #crt", Jr. labert Scres - who is responsible #or onitoring and valuation af environ ental sa ples, and Mr. Tho-as Il sasser .sho many of you already knav and is responsiale # 3r contacts with state and ~unicipal o#'icials. -:llowing th:s question and answer session, Mr. "er an J i e c'.cro, P esident of GP'J !,as ceen asked to ake a state ent corcerning t'e co pany's ? an #cr cleanup and disposit!an of contarinate; l 2ater. le can only respond to those questiers chi:h deci 's i P t'e O resp:nsibi'ities, ou-review o# the cl ea.;p a -t i. ties, and

, trois that aill Se in pla;e #or the eletnup process.

P00R OR8Et o m. =

f. "' *g, UNITED STATES f ; n,

,i NUCLEAR REGULATORY COMMISSION

.\\
- e OFFICE OF PUBLIC AFFAIRS, REGION I

%'.... j' 631 Park Avenue, King of Prussia, Pa.19406 t May 16, 1979 7 e I NRC STAFF REPRESENTATIVES THREE MILE ISLAND BRIEFING HERSHEY MOTOR LODGE Richard H. Vollmer - Assistant Director for Systems & Projects, Division of Operating Reactors and NRC Staff Director for Th ree Mi le Island Operation Brian K. Grimes - Assistant D::ector for Engineering & P roj ect s, Division of Coerating Reactors John T. Collins - Chief, Effluent Treatment Systems Branch, Division of Site Safety and Environmental Analysis Frank Congel - Section Leader, R4diological Assessment, Division _ of_ Si te Safety and Envi ronmental Analysis 2 Robert J. Bores - Radiation Scecialist, Environmental and Special Projects Section, Of fice of Inspection and Enforcement, Region I Thomas C. Elsasser - State Laison Officer, NRC Region I t Karl Abraham Public Af fairs Of ficer NRC, Region i h {i /

'Y 5/\\6/79 2~P ~ k_ 3 4 i 0 7 ( 9 lo 11 i> 13 it n' 4 ~ R ic X ~ ~ s X f X 2u R X i7o c X ~-' X e CT o X . W X 1 X4-m... X X 99 X' 22' X 171 X ~ ~~ ~ E ~. F R X R no X X I75 N ~ R X 231 X i87 X is4 X 4 R X-238 H 09 X X X m R X R X X ia+ X X X I" W X e 173 R X tr3 X X W X t W X 17 5 ~ s isr X X a+ X aoo d . X t91 X X no R X, X o X n1 X X R N P 04 X X q R [63 11 8 230RBEIM'E gj ~ I, LOCATION OF FUEL ASSEMBLIES CONTAINING -{. { }J BURHABLE PO!SOH RODS THREE MILE ISLAND NUCLEAR STATION UNIT 2 '[ N f l 'O ~ d FIGURE 43 2 ~ - c r *-

5/16/79 TECHNICAL WORKING GROUP 1300 5/16/79 t. 1. Agenda, 1300, 5/16/79 Technical Working Group 2. Radioactive Releases and RCS Profile 3. Top Priorities List 4. Action Items from 1300, 5/15/79, Technical Working Group 5. Task Lists S '/ [bi

5/16/79 AGENDA TECHNICAL WORKING CROUP 1300 5/16/79 1. Radioactive Releases ? e a. 748, 219, Auxiliary Suilding Fans b. Vent Header and Drain Trunk c. Dorae Radiation Monitor d. Measurement of Radiation Level Inside Containment 2. Plant Status a. RCS Profile b. Plant Operations Schedule Bypass Valve Adjustment Toward 64" Bleed Tanks 'A' and 'B' Sample Results - Boron Concentration Cycle DHV-6B -- Result fM eMws DHV-2 Operation t:* >t , 6+v%sM sa Lee w f" 6 DHP 'A' Test 9 1 Replacement 'B' train FHB charcoal filters g 7 + p, 3. Analvsis Swg a. Reevaluation of existing rec...mendation to draw a bubble vs solid operation b. Procedure ior verification of Solid PZR during solid operations at 300 psi c. Reduction to 300 psig - increase in loss f pressu e protection? )/* l>wW 4 _Qanscruction Status Estimated Completion a. Tank Farn 5/19 b. OTSG 'B' Long Tera Cooling 5/18 c. EPICOR (CAP-GUN II) 5/18 d. RCS Pressure / Volume Control Turnover 5/25 for testing e. Auxiliary Diesel Generator Auto Start 5/17 -a f. Alternate Decay Heat Removal System tie-ins 6/1 ( ,f il, J f

  • % < *-v % *Y Q

te.* t s h M g [][Qw&c :.L RS- =

5/10/79 TOP PRIORITIES Development of plan for management of radioactivity in A-1 Auxiliary tad Containment Buildings. 1; Identify and isolate sourc..s of iodine leakage. A-1 e Cocplete tank farm in Unit 2 spent fuel pool. A-1 Completion of EPICOR (CAP-GUN II) System A-2 Development of plan f or '.reatment of Auxi.liary Building B-1 liquid :.aste Complete "B" OTSC cooling and modification (Long-term) C-1 Development of alternace system for pressure / volume C-1 control system. Complete external valve pit for ADHR System. C-2 CATECORY A Control (i.e., containment) of radioactivity in Auxiliary and Containment Buildings B Recovery of Auxiliary Building to near normal operations C Place the plant in a cold condition suitable for depressurization uith long-term pressure / volume control ( ~ ') '. ~ C 1 )' ) e

5/16/79 ACTION ITEMS TECHNICAL WORKING GROUP 1300 5/15/79 Item Action 40 1. Confirm the presence of K in RB gas sample. If present, Hetrick determine its source. ~ 2. Obtain due date from Mt. Lakes for proposed method to deter-Wilson mine R3 activity levels by direct measu:cment by 1300, 5/16/79. 3. Present summary description of radioactive liquid waste process-Rusche ing plans to the 5/22/79 Technical Working Group Meeting. 4. Re-evaluate present reco==endation to draw a bubble vs. staying Wilson / solid in RCS operational mode. Document reco=nendation by Herbein/ meno prior to 1300 on 5/16/79. B&W 5. Maintain RCS in solid operation mode until further guidance is Herbeta provided by Technical Working Group. 6. Initiate reduction of SG 'A' turbine bypass valve position Herbein toward 64% at 3% per hour. 7. Evaluate if there is a downside/ loss of pressure protection Wilson increase at 300 psi vs. 500 psi. 8. Insure that adequate verification of continued solid operation Wilson is placed in the current procedure for solid RCS operation. 9. Evaluate the implications of processing the contents of SG Rusche/ 'B' through the Long-term Cooling System with emphasis on NRC/ the impact on nacural circulation, radiological and operational Herbein/ implications. Wilson / B&W/- Herbein to coordinate. 10. Proceed with RB sump level determination (Cycle DHV-6). Herbein 11. Obtain next RCS sample on 5/13/79. Hetrick ( 1. l}'t

Page 1 of 2 1300 5/16/79 PLANT OPERATION ST-AFF Expected Task Task Description Priority Canaletion Status Coord. 1. Obtain RCS sample (Primary C-1 None Hetrick letdown). schedu.ed. 3 2. Obtain MEC approval (Tie-in C-1 Need ECM's Kunder/ } approval only). 79 R2, 180 R0, Faulkner / 272 Rl. Seelinger. 3. SSRW pump, "C" repair. C-1 Co=p. by 5/20. 4. Decay Heat System. C-1 Cycle DHV-6 Cycled 5/15. Toole after hydro. 5. Remove water from "B" Fuel Fool. B-1 Kunder 6. Isolate Unit !/1 and !!2 samplo Need new sample Limroth/ stations. sink. McGoey 7. Training on Diesel. In progress. Troffer/ Kunder/ Toole 8. Training on Decay Heat. C-1 In progress. Westinghouse Troffer/ will provide Kunder/ training plan. Toole 9. Sample AB/FH3 charcoal beds. B-1 A3 "A" & "B" Kunder/ 3/19. Hetrick FHB "A" 5/23. 10. Grey diesel. C-1 5/17 Both complete Toole except for White diesel. 5/17 auto start 5/17 Toole 11. Move filters out of Aux. Bldg. B-1 In progress. 12. Repair DW-P-4A. Working 4A. 60% cocplete. 13. Repair SW-P-13. Need -.s Regn. No. Shovlin s* 201-1720 i 14. CO-P-1B repair. In progress. Shovlin 15. Install self-cooling on Toole/ condensate pump 1A. Gunn ( OJ s

Page 2 of 2 1300 5/16/79 PLANT OPERATION STAFF Expected Task Task Description Priority Comoletion Status Coord. 16. Rebuild breaker for Cap-Gun. ' Breaker r ?- Shovlin built, to be installed. 17. M.aintain turbine su=p empty. Until comple-Kunder/ i tion of "B" Frederick OT.SG Flush. s m

1300 5/16/79 PLANT MODIFICATIONS Expected Task Task Description Priority Concletion Status Coord. WG-1 Install AB/FHB Filter System. A-1 Comp 19te by System opera-Shubert 5/15. tional 5/10; complete 5/15. WG-2 Decon. water in AB using EPICOR A-1 Turn over Lacy / ~. (L-1) ion exchange process. 5/19. Fricke IIG-6 Install storage vessels in Fuel A-1 Turn over Gibson (L-2) Fool "A". by 5/19 WG-ll Water Chemistry Lab for use A-1 System com-Tolle/ with CAP-CLN (WG-2). plete by 5/17 Pao WG-12 Ventilation filtration system A-1 Turn over Shubert for decay heat pits. 5/26. TS-13 Install elec. heaters on Aux. A-2 On hold. Shubert Bldg. intake ducts. TS-3C Develop complete package for C-1 Turn over Jordan / long-term cooling OTSG "B". 5/17. Lanza TS-6B RCS pressure control syster. C-1 Schedule Estimated com-Miller / being . pletion 5/ 25. Lilly revised. TS-11 Aux. diesel generators. C-1 Testing Complete Gagliardo except for auto start 3/17. TS-14 Shielding for decay heat pump. C-2 Turn over Lieberman 5/23. NOTE: Plant Modification Preliminary Schedule for Uestinghouse ADHR System indicates 6/21/79 completion date. t 6 s e

1300 5/16/79 WESTINCHOUSE Expected Task Task Descriotion Priority Comoletion Status Coord. W (II.3) ~ B&R (TS-15) ADHR Installation: 6/l* I Qualify wall penetration C-1 No status and grout mockup Assemble ADER skid C-1 Cocplete In progresa by 5/25 Assemble CCW skid C-1 Complete In progress by 5/25 Fit up elec. trailer C-1 Complete In progress by 5/20 Install Panel /MCC's in C-1 Start 5/21 central trailer Co=plete 5/25 Install penetration C-1 Start 5/20 isolation box Complete 5/22 Core bore 12 holes in C-1 Prep. 5/20 Not started west wall Set-up 5/12 Bore 5/23-5/26 Install, pe/ cable penetration C-1 3/2S Not started Install 8" suction pipe C-1 Start 6/5 Not started Complete 6/7 Install 6" pipe ("A" train) C-1 Start 5/24 Not started Complete 5/29 Install 6" pipe ("3" train) C-1 Start 5/29 Not started Complete 6/4

  • Plant Modifications Schedule indicatc, 6/21/79 complete date.

Except for this 6/1 date, all dates in the Expected Ccmpletion column t J-are from B&R acheduling. U U

1300 5/16/79 TECHNICAL SUPPORT - Expected Task Task Description Priority Conoletion Status Coord. LS.2 Tech. Sp ec. and Surveillance 1 ? Active: NRC L. W. Hardit and Bases Changes to those interactions left deletions, additions. under negotla-tion. LS.3 Initial Reporting of Event. 1 5/15 to NRC. Active. R. A. Lenge TM.23 Reactor Coolant Systes 1 5/23 Active. Cobean P/V Control. TM.30 Determine what 30P loads 1 Continuing Draft criteria Capodanno/ need backup electrical power. docu=ent issued Langenbach 4/24. TM.35 Long-tern plant instrumentation 1 On hold. Criteria docu. Capodanno/ requirements (criteria). being revised. Langenbach AA 61. Update SAR. 1 ? Draft received. B&W AA 66. D. How to caintain primary 1 ? Active. GPUSC/MPR boron conc. AA 69. Define all plant mods needed 1 ? Croneberger for long-tern operations. AA 80. Analytical and Tech. Planning 1 ? Continuing. J. A. Danie Support for updated procedures (EP-32, etc.). AA 83. Identify critical valves and 1 ? Active. Prelin,R. Long instruments which may be list available. dsmaged by high sump levels. AA 84. Identify flow paths from the 1 B&R investi-Active. containment su=p. gating. AA 87. Solid Pressurizer Analysis. 1 ? Active. J. Moore AA 96. Boron concentration in RB sump 1 ? Active. J. Moore 4/30 through 5/16. TM.37 Installation of cartridge-type 1 EC1 issued. Revising desigt.Capodanno/ Desineralizer for clean-up of Langenbach S.C. "B" secondary side. AA 1. Letdown Plow Analysis 1 Continuing. Active. Met-Ed Control Roc (continuing curve development). AA 71. Deternine requirements to 1 ? ? perform sa ple analysis locally. (- ) / u

Page 1 of 7 1300 5/16/79 UASTE MA::A21ENT GROUP Expected Task Task Dascription Priority Comalerion Status Coord. I L-1 Design, installation, and B-1 5/19

a. Design - 97%

Snider / operation of EPICOR for

b. Construction-Garman/

Unit 2. 50% McCutche?

c. Licensing -

nWeller/ < NRC con-0 Collins I currence

d. Operation -

est. 5 / I.4. Piping installa-tion slipping schedule to 5/19 comp. date. L-2 Design, installation, and E-1 3/1 75% comp. Rein = ann / operation of energency sur8e piping in FHB. Snider / tanks (tank fara) in Unit 2 cueller/ ..A" Fuel Pool. }0% comp. welds & Collins In u, E p r; e, F3 pipe. Prefab. pipe ready for installation -~ in AB. "B" train pour planned for S/7; "A" train pour complete. 75A concrete slabs placed atop fuel pool. L-10 Pursue activities on processing A-1 In progress. Carnan/ Unit 1, cater throu3h CAP-CUN to Ueller both provide su port to insure available freeboard for Unit 2 and to develop resin formula-tions for Unit 2 *;ater. L-l!, Evaluate.2ste gas vent header A-1

lorhing per McConnell leakage problems and recom:'end J.

Seelinger's Arthur / fixes depending on results. .zaste gas plan

  • Bland af 4/17/79.

' RC contae t i U ?00R DlGK1

Page 2 of 7 1300 5 / 16 / 7 9 UASTE t4AMACDIENT GRCUP Expected Task Task Descrintion PrioritS Cercletion Status Coord. L-36 Investigate the effects which C-1 In progress. McCoey/ the operations associated Ross/ with reactor plant long-tern

  • Collins cooldown vill have on discharge to the vaste sys tems.

Related to L-6. L-42 Development recommendations and C-1 McGoey/' procedure for draining and Ross/ disposition of RCBT water to

  • Collins support plant needs to ca..e up with degassed demin. uater.

L-44 Evaluate systen designs with Et Report being Kraft / Technical functions and U to prepared; nUeller assess possible interference delayed by problems from standpoint of higher priority locatians, operations, tasks. taintenance, etc. L-47 Resolfe sample lab requirem2nts E-1 Meeting held Kraft versus capabilities to 5/1/79; support EPICCR I and II opera-resolution tions. .in progress. C-1 Install AB/FHO off-gas filter A-1 Phases I, II, Montgone systen to back-up plant system. and III dasign Itschner complete. ^ Collins Systen descrip-tion and start-up procedures are complete. Four (4) fans are operable, 3 or 4 are run-ning. .;C contact 'l i t i ?001 ORGN 1

Page 3 of 7 1300 5/16/79 WASTE MANAGEMENT GROUP. Expected Task Task Description Priority Comnletion Status Coord. G-5 Chatrgc aut AB/FHB HVAC vent A-1 "A" & "B" train s McConnell/ fi'.ter train charcoal bed. of the A3 fil-Edwards / ters and "A"

  • Weller S

train of FHB I. e filters removed and replaced, units back in 2 service. FH_B "B" train in change-out scheduled for 5/17. Deluge systems secured on all renewed filter trains. Spent filter tray removal to storage com-pleted. G-31 Determine air flow paths in A-1 Operating matri> Nawaz/ AB/FH3. developed and Itschner/ available. Robison/

  • Weller G-32 Determine that there are no A-1 Examination of Nawaz/

unidentified air flow paths. plant status /

Itschner, configuration Robisoni underway.
  • Barrett First cust.

review complete

  • NRC contact

'l t.

Page 4 of 7 U OO 5/16/79 UASTE mat!AGEME.'T GROUP. Expected Task Tcsk Descriotion Priority Cor.71c t io n Status _Ccord. C-3S Develop plan for ventilation B-1 Meed identified Itschner system operation based on fau/ to set up a

  • Stoddari filter train status and on plan.

Control / t, door openings and other plant advise on local operation evaluations. and systaa ven-tilation practice., G-40 Criteria for and control tasks A-1 20 " Red Devil" 4 Collins resulting in the evolution of type local contaminates that could poison filtration charcoal filters. systens on order to contro: uelding fumes. L-3 Deteraination of leakage paths 2 Plan t s taf f Kraft / and flow rates in Unit 2 Aux. following. Arthur / Bldg. and FHB and repair

  • Cualina of leaks uhere possible.

Plant has leakage ID and Status Board in Unit 2 Control Room. Pursue Plant activities associated uith this. L-12 High level solid vaste disposal E-2 In progress. Pastor / investigation. Eduards/

  • Weller/
  • Collins L-26 Perforn assessment of the value A-2 Price proposal Kraft /

and need for a closed circuit being assessed Lutz/ TV Monitor to provide remote versus decon.

  • Stoddart indicator of raduaste panel schedule of data.

Aux. Bldg. L-27 Develop sacpling plan to assess E-2 Identified 4 Passelli AB unste for trancuranic samples, agreed Williams content. Insure that Met-Ed on 3. Agreement,

  • Collins Ops. coordinate sample require-reached on using cents with OR':L to insure previously taken satisfactory analysis results.

samples from sump and bleed tanks; add i tio nal saraples to be taken. P00R BRBM ,,.C contact

Page 5 of 7 1300 5/16/79 WASTE MANAGEMENT GROUP Expected Task = Task Descriotion Prioriev Cc oletion Status Coord. L-29 Investigate reported uater B-2 Uater fros Uilliams collection in the "B" fuel poal Unit 2 const.

  • Barrett obtain samples and make plans Sample needed.

for disposition. Also investi-gate the preoperational i condition of the fuel pool from a leakage standpoint. L-33 Develop a plan for tying in the B-2 System cri'teria Reinmann tank farm to EPICOR 2. sent to B&R on Snider / 5/1/79. AUeller/

  • Collins L-35 Investigate the need for a B-2 Alternate McConnel design and construction task to design Unit 1 Williams erect a barrier betueen the side to be
  • Barrett Unit 1 and Unit 2 Fuel Handling subcitted Eldg. to enable Unit 1 opera-4/27/79, tions with Unit 2 in processing
Iode.

L-37 Develop a plan for renoving all B-2 Requires com-McConnel radioactive gases from the pletion of L-14 SCollins systems in the A3 and FHO. G-7 Ccndenset vacuun pu=p discharge A-2 Filter opera-Robison/ filter system. tional. Inves-Montgome. tigating opera-

  • Collins ting criteria.

Will evaluate DF. G-30 Reactor Purge System Charcoal A-2 R3 purge filter McConnel: Filter Sample. Scheduled week sample all ready 0 Collins of 5/20 for analysis. s_ 3 C-33 Desensitize AB and FHB Filter A-2 Preliminary Sieg/

danitors, investigation -
  • S toddar t desensitization infe;31 hic.

', ?.C contac t ?00fl DRGNAL ~ I 1

Page 6 of 7 1300 5/16/79 UASTE MANACEIENT CROUP E::pected Task Task Descriotion Priority Cenolecion Status Coord. G-39 Develop and assess back-up gas B-2 B&R has devel-McConne: filtration scheme to cross-oped a concept.

  • Lee connect the Auxiliary Euilding Second esticate filters to the RB purge filters-scheduled shows 14 day +

schedule. Heisman Co. has developed draw-ings.

Exposure, schedule cost appears too high.

Con-tingency plan is to open roughing filter manway if emer-gency ventila-tion of Auxiliary Building is needed. Standard proce-McConnell G-41 Develop filter m.anagement E-2 dures to sample strategy-charcoal systems in review. G-42 Develop a progran to assess E-2 Four-part McConne and nonitor I releasa sources, approach: McGoey/ bbntgoce

1. B&R to com-3g1:

plete revie" Cline / of release pelitti candidates. Vollegu

2. Pursue a tracer progran to find leak.
3. Pursue an air moni-toring pro-gram with SAI/EPRI to plot I levels.
4. Revieu local ventilation P0DP{ 0
q j"[,

I conditions to verify flow distri-butions. i L; coatict t L a e

Page 7 o' 7 1300 5/16/79 UASTE MANAGDIENT GROUP-Enpected Task Tash Description Priority Comaletion Status Coord. L-11 Investigate / develop process for B-3 Proposal to be Snider / eliminating Unit 2 uater in received from

  • Ueller RCST's.

Process planning for chem-nuclear 5 Units 1 and 2. Design (con-3/4/79. ceptually) a vaste processing e system for Unit 2 High Level Liquid Uastes. 2 L-16 Lou-level waste (paper, rags, B-3 In progress; Edward rood, etc.) disposal. second com-

  • Welleri pactor ordered.
  • Collins L-17 Cevelop CAP-GUN 3 Systca.

B-3 Initial plannin, Snider / only. Detail

  • Ueller, design ECollins scheduled to start 4/25/79.

L-20 Obtain a level measurement and B-3 ficasure=ent Ross/ a sacple of uater from the RB using Heise

  • Cualin sump and basement.

gage being explored. L-22 Develop a plan for long-tern B-3 Open/ cleanup to provide access to

  • Collins Auxiliary Bldg. for restoration activities.

L-30 Deve. lop plan for radiation B-3 Open/ survey in Auxiliary and Fuel

  • Stoddar Handling Bldg.

G-15 Energency RB Gas Purge Cleanup A-3 On hold; no Open/ System. plan to

  • Collins implement-G-29 FU3 Air:l oc'...

B-3 Airlock Inac ti'. unnecessary at

  • Barrett this time.

SP.C contact P00RORSN?1 ~ i

RELEASES 0900 (5/14/79', 1100 (5/15/79) 1100 (5/16/79) -9 748 3.7 x 10 6.1 x 10-9 3.4 x 10~ -10 0 219 5.4 x 10-10 1.12 x 10-11 1.4 x 10 -10 Inlet 2.2 x 10-9 2.4 x 10~9 3.72 x 10 Train #1* 1.8 x 10-12 Not Running 2.71 x 10' -13 Train #2* 5.3 x 10-12 1.72 x 10-11 <1.79 x 10 Train #3* 1.1 x 10-11 9.65 x 10-12 6.9 x 10 ~ -12 -12 Train #4* 8.2 x 10-12 9.65 x 10 3.37 x 10 REACTOR COOLANT SYSTEM PROFILE PLANT STATUS 0900 (5/14/79) 1100_.3/15/79) 1100 (5/16/79) A B A B A B Th 163.5 169.8 167.5 168.5 166.9 168.3 Tc 156.3 99.2 155.8 99.1 155.9 99.1 45T 12.2 70.6 11.7 69.4 11.0 69.2 Tsta 154.4 123.2 153.0 121.6 153.2 122.4 PZR LEVEL Cal. Solid Solid Solid DWI LT-3 Not Reading Correctly R.C. Press. 646 614 - 446 t/./ 5 S/G Level 413" 93% 415" 96% ',AeP 95% Turb. B/P 84: Closed 34% Closed 69% Closed I.C.T. High 307.1 303.4 303.9 Avg. Not Available 191.8 Not Available M.U. Temp. 128 124 127 t i

d iN Y r lls 2 ) 9 d 4 N m e 4 1 4 3'e s Q ^ ~ c n W d as7 s N M N N O .t O \\ W t 3 4 itt t ~ o h N C = O C C q J C L A s d C G s s s N i 3 O k a b w& 9 -i o 6 N' N s ( w \\ d l G s N + s ~ s i N N s v v J \\ \\ \\ b 'L Y e o s d' O 4 NS s g , O4 ~ N 3 3u. Y u$ 0 r__ a C3 5 h N N N k k c=3 N b G C R e o O \\r m/ u o ? s c y . ' _ u o N o o w s -c e <n e g s a ~ o s y, r m u o o o o O o o C o C o o - o o o o o o o o O 3 9 [ o a o o e e o e o e o o a o o o a o o e r' 4,, n x m = nd x m, m ~r u~ m n x m C -e m m a c c. Q% m m o o o o e o o c o

f I d C I = 1 o 0 \\J i V 2 b N 2 ~ Q \\$ Y "1 's 4 y A 4,) '1 O \\ O H o s },o . O = a C y J o s S .( f m T s, s nd O d' S (f d e o. c ~ d i i g P k w 6 r T d $7 2 4 11 e ~+ 0 N 4 ) g,l ,y'** o ^ .) pg.L. d as : $ ;s g ~. 0 m as 3, s O L f' y \\r: s 1.* ors a..m l N o C 2 E s, m W M m 4.s L n ( rna Y e.r. T T ba w) qig Q q u. w swa u m. d M o x L. b o-g y I %~ o u \\ n' wi ~ c c .e d w q N E s-e 2 Qt 0 b C f5 + o h, c s 'I S ( ( ) [ / S C } Q ~ l ee$ M e k o o c o o o o o o o ? 0 .C o o a o o o c c o o o o o o o o o o o o o o o o o o o o o e O o 4 <w N e e o e m o en c m s m e c e m m o o m m m a o o c o o o o o c m e

k d 5 k d m\\ m 4 f. t s n s 3 = 5 t u e s s b Q 3 4 2 6 1 i 4 No L, - a i s i t 1 i / N 5 I I C m s s e ~ w ~ $d e J N G 2 k 0 C D 9 n C D 3 l 0 t O 3$ Q sa Y 9 E 5 Jz 2 3 c) S d& 3 3 u. y ) 5 L e J 2 N W D N h N k N N N b c-{ c3 = o o o a W G b b b \\r o q B Q G ) o%h d s o o w e s i s e r c-e o-e o e ~ n s a w s M M N 2 e3 .s q o o g ~ ~ 94*k 8 8 8 8 8 e 8 8 8 8 8 8 8 8 8 M 8 8 8 8 8 E 8 8 $w 5 8 8 8 8 8 8 8 8 S : 2 = 0 R R Z: =

( p d E v AdJ a 2 6 0 H t3 3 S -(f a m ar A )-4 5iig2 _a QJO -.m 2 C 3 0 WI$ ct or -1 x 5 %y b 4 9 4 a s m M b,5 x 11., i a u C N d 4 m N N l4 \\ \\ s' 2 hO M ^ D 3 s a ) l3 n'A D e s 3 s r m -g e A s# 8 8 s es s e s s ~ a s s 8 8 s s a s s s s s s 8 s a s s a a s s s a s a s e na = = n i

f i i R g e N 4 (u n. i s g p w e o \\J c r ,e. M' N S M w w

4. -

w i tg L Q m t 0 6 Y N 0 5 4 3 e4 d E d ? 7 4 s t R h 4 0 n P 3 N t h, O 3 t n a G o-9 E 5 h t V S 2 to m M z f 2 i E s G c-x o b c 1 S 4 d 14 m 4 m e n a 3 s i a J w c 9 i { %'1 N b ,9 ~" ~ g 2 .7 \\ .m. g D o ~ -- Jj <w ( ~ C d=m o c c O CJ33 0 t { g 3 3 i ^I N g ~ r a a ~ C T d C) b. O Q N 0-c)g I b G s! m a Yl 5 e x x o 4 0 2 4 d E! 2 4 t t t e o a s a s y a a, t A s% I k I d N 4 i o s D e Q y o l8 s s ~ c oH E N \\ l M l 3 o d s o t a o 4 A, M 3 s ? m o m: u m n Q gg g g g g g g g g g g g g g g g Sb g g g g g g g g su s a a 8 s a a a s a 2 2 r e! e a = = as}}

Retrieved from "https://kanterella.com/w/index.php?title=ML19253A511&oldid=4884988"