ML20030B827

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Weekly Info Rept for Wk Ending 810807
ML20030B827
Person / Time
Issue date: 08/13/1981
From: Rehm T
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-810807, NUDOCS 8108240308
Download: ML20030B827 (36)
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{{#Wiki_filter:.. 1 [qqust 13,1981 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING AUGUST 7,1981 A sun ary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report. Cont 7nts Enclosure Administration A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C Inspection a,nd Enforcement D Nuclear Regulatory Research E Executive Legal Director F* International Programs G 4 @ l in'/ State Programs H /g<D' ,g I L. Management and Program Analysis I AUG 16 O l Controller J* L;a....e Analysis and Evaluation of Operational Data K 48 9 gN. N l Small & Disadvantaged Business Utilization L* 4/ 3 Items Approved by the Commission M I

ehm, ssiM for Operations Office oT Ine Executive Director for Operations
  • No input this week.

Contact:

T. A. Rehm, EDO 49-27781 0010824030s g10813 ' PDR CONNS MRCC WEEKLYINFOREPT PDR

SUMMARY

OF WEEKLY INFORMATION REPORT Week Ending.. gust 7,1981 LaSalle Unit 1 Commonwealth Edison _ requested a construction permit extension for LaSalle Unit 1 from June 30, 1981 to April 30, 1982. The extension was formally authorized on August 3,1981. TMI Occupational Exposures Based on data collected for TMI Units 1 and 2 (1979 and 1981), the staff has concluded that (1) TMI occupation doses during 1979 (accident year) are comparable to those of other PWR sites, and (2) the difference in occupational exposure between TMI-2 and TMI-l is not significant. Reactor Sabotage Protection The staff is completing safeguards rules on three closely-related issues. These issues concern pat-down searches at power reactor protected area portals, personnel screening for persons granted unescorted protected and vital area access at. power reactors, and designation and protection of power reactor vital areas. Skagit Units 1 and 2 On July 31, 1981, Washington State signed two subagreements establishing procedures for cooperation on envircnmental reviews and joint hearings regarding Skagit Units 1 and 2, which will be relocated to the Hanford Federal Reservation near Hanford, Washington. ADP Long-Range Plan The staff distributed its final version of the ADP plan for FY 81-85. It will provide a baseline for more comprehensive planning this fall.

( OFFICE OF ADMINISTRATION Week Ending August 7,1981 ADMINISTRATION OF THE FREEDOM 0F INFORMATION '.CT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 359 11 Granted 253 2 Denied 45 7 Pending 61 2 ACTIONS THIS WEEK Received (An individual requesting Requests information.concerning his information about himself) Reactor Operator License written and (81-309) oral examinations. Philip C. Henry, Referral from the Department of Energy, Phillips, Hart & Mozley for tne names and addresses of purchasers (81-310) of thorotrast as well as the dates of distribution for the period 1950 through 1956. Jan Sullivan, Requests copies of all the licenses that Massachusetts Fair Share the Army Materials and Mechanics Research (81-311) Center (AMMRC) have been issued and all inspection reports on AMMRC. (An individual requesting Requests information concerning his information about himself) Reactor Operator License written (81-312) examination. Richard A. Udell, Requests eight categories of documents Cri tical Mass regarding steam generator problems. Energy Project (81-313) Mary Hargrove, Requests lists of all Oklahoma companies The Tulsa Tribune licensed to handle radioactive materials; (81-314) regulations governing the use of radioactive materials; all investigations relating to Oklahomans who have violated the licensing agreements; all companies in Oklahoma and nationally which have had their licenses revoked, and documents involving the investigation of an employee of Tulsa Gamma Ray, Inc. ENCLOSURE A

v 2 Received, Continued Frank B. Jewett, Jr.. Requests investigation reports on the Technical Audit Associates, Inc. flooding of the containment building at (81-315) Ir.dian Point, Unit 2, on March 7,1971, November 13, 1973, and July 2,1977. Peter C. Hearn, Requests all information relating to the l Vice President, moving of all or a portion of the NRC l MTEU Bethesda offices into building space' (81-316) in Northw;st Washington, DC. Michael G. Levi, Requests the location, function, cnd i D. C. Area Nuclear Map size of all facilities in the District of Project Columbia, Virginia, and Maryland. l (81-317) Granted Carroll L. Bryan, II, Esquire In response to a request for 12 categories Taylor & Ulin, P,S. of records pertaining to the Washington Public l (81-223) Power Supply System Nuclear Plant No. 2, made available 14 documents. Informed the requester additional documents subject to this request are already available at the PDR. Mark A. Brown, In response to a request for five categories Carlton, Fields, Ward, of information regarding the Crystal River Emmanuel, Smith and Plant and the Babcock and Wilcox Company, Cutler, P.A. made available 61 documents. (81-236) Richard A. Udell, In response to a request for.five categories l Critical Mass Energy Project of documents regarding the July 1 deadline I (81-255) for installation and operability of the 15 i alert notification systems for each operating nuclear plant and for each near term license plant, made available 43 documents. Informed the requester 20 additional documents subject to this request are already available at the PDR. I ENCLOSURE A e

3 Granted, Continued Peter Daltori, In response to a request for a listing Sierra Club Radioactive of Import and Export Licenses of radio-Waste Campaign active shipments for the year 1980, made (81-267) available a copy of the. list. K. E. Fischer, In response to a request for three categories University of California of infonnation concerning the suitability of (81-271) Palmyra Atoll for the storage of nuclear waste, informed the requester the NRC has no records subject to this request. James S. Oppenheim, In response to a request for a list of Business Publishers, Inc. individuals, corporations, and state (81-281 ) agencies involved with nuclear waste processing and fusion power research and demonstration, made available four documents. Marsha Walls, In response to a request for a mailing or Technical Insights, Inc. distribution list pe;-taining to recombinant (B1-285) DNA research, informed the requester the NRC does not sponsor DNA researen. Barbara A. Scott, In response to a request for a copy of Davic Polk & Wardwell

  1. N4 - mailing list entitled, Current Events -

(81-299) Power Reactors, during the period from January 1,1977 through December 31, 1978, made available a copy of the requested mailing list. Charles W. Elliott, In response to a request for a copy of the Thomas and Hair license Stage and Probabilistic Risk Assess-(81-302) ment required by letter by D. Eisenhut for the Linerick Nuclear Generating Station, Units 1 and 2, informed the requester these documents are already available at the LPDR in Pottstown, Pennsylvania. Denied _ (NRC employee) In response to a request for the names of all (81-272) candidates and their evaluation records for Vacancy Announcement 81-2112, denied portions of the Candidate Evaluation, Certification and Selection Record, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy. ENCLOSURE A

3, DIVISION OF CONTRACTS Week Ending August 8, 1981 PROPOSALS UNDER EVALUATION 1. RFP No. RS-NMS-81-026 Title - Benchmarking of Computer Codes and Licensing Assistance. Description - Services to benchmark computer codes for supporting regulations and for performing reviews of prc'osed nuclear waste management systems, evaluate the codes, end provide licensing analysis using these codes are

  • equired.

Pcriod of Performance - Five years Sponsor - Office of Nuclear Material Safety and Safeguards Status - Negotiations continue the week of August 3,1981. 2. RFP No. RS-tiMS-82-C26 Title " Environmental Assessments and Impact Statements For Low-Level Waste Disposal Facilities" Description - A Basic Ordering Agreement program will be established (multiple awards) under which NRC may obtain contractor services to assist in responding to Low-Level Waste Disposal Facility application from non-Agreement States and requests for technical assistance from Agreement States. Period of Perforrance - Jne year with an option to renew for a second year. Sponsor - NMSS Status - Proposals received were distributed to the Source Evaluation Panei members and advisors en July 30, 1981 for technical evaluation. RFP S ISSUED 1. RFP No. RS-NMS-82-031 Title " Assessment of Waste Retrieval Alternatives" Description - Identify and evaluate alternatives being considered tj the e0E for retrievability or recoverability of high level waste from geologic repositories as defined in existing conceptual designs. Period of Performance. - 2 Years Sponsor - NMSS Status - RFP issued July 31, 1981. Closing date for receipt of proposals is August 31, 1981. J E EllCLOSURE A -., + r- -~r, -,,

f 2-CONTRACTS CLOSED OUT (All Administrative action completed and final payment made) i l Contract No. Contractor-Close-Out-Date l NRC-03-78-126 Wyle Laboratories 7/30/81 i NRC-04-77-057 MIT 7/30/81 l NRC-19-80-473 Editorial Consultants, Inc. 8/05/81 l I l l l l' l l r INCLOSURE A

fr i e OFFICE OF NUCLEAR REACTOR REGULATION WEEK ENDING AUGUST 7, 1981 l L A SALLE COUNTY STATION, UNIT Nh.1 20,1961, 'he Commonwealth Edison Company requested a In a letter dated May t construction permit extension for La Salle County Station, Unit No. 1 from l June 30, 1,981 to April 30, 1982. On August 3,1981, the construction permit extension was formally autho,rized. l-l I ? EllCLOSURE B

NRC Till PROGRAM OFFICE WEEKLY STATUS REPORT 'I i Weak of August 2 - B,1981 i Plant Status Core Coolino Mode: Heat transfer from the reactor coolant system (RCS) ? loops to Reactor Building ambient, i Available Core Cooling Modes: Decay heat removal systems. Lon term cooling "B" (once through stea' generator-B m R IS Pressure Control Mode: Standby Pressure Control (SPC) System. f. B tckup Pressure Control Modes: Mini Decay Heat Removeil (MDHR) System. Decay Heat Removal (DHR) System. h( or Parameters (as of 0500, August 7,1981) (approximate values) Kt Average Inco:e Thennocouples: 119"F I Maximum Incore Thermocouple: 142*F V RCS Loop Tempera tures: s A B Hot leg 118'F 121.*F Cold Leg (1) 73*F 75'F .I (2) 75'F 75"F 1 RCS Pressure: 93 psig Reactor Building: Temperature: 74*F 4{. Water level: Elevation 290 S ft. (8.4 ft. from floor) via penetration 401 manometer

D Pressure:

-0.2 psig i concentration: 2.3 x 10-5 uCi/ml Kr-85 (Sample taken 7/30/dl) b lE Effluent and Environmental (Radiological) Information_ c l r[ 1. Liquid effluents from the 1NI. site released to the Susquehanna River i' after processing, were made within the regulatory limits and in l[ accordance with NRC requirements and City of Lancaster Agreement

p dated February 27, 1980.

E During the period July 31, 1981, through August 6,1981, the effluents -{ contained no detectable radioactivity at the discharge point although . g. individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity. Calculations indicate that less lI than 1 millionth (0.000001) of a curie of Cs-137 was discharged. This 'E represents less than 0.00001% of the permissable total liquid activity

F as specified in Technical Specifications for operational comercial P

reac tors. t } { ENCLOSURE B r P k i h g. _..

2 2. Airborn2 effluents from tha TMI site released to the environment, after procGssing, w;re made within the regulatory lir.its and in accordance with imC requirements. During the reporting period June 1-30, 1981, the licensee reported the following gaseous releases; f h Curies i s i Noble Gases 58.7 L Particulates 0.00000237 Tritium 3.8 [ The above rdleases represent a small fraction of the allowable [ regulatory limits. The noble gas (Kr-85) release for the month of p. Ju'ne, although well within limits and insignificant for environ-mental considerations, was higher than anticipated. A portion of [ the release can be att.rtbuted to Reactor Building purges, and the g licensee is currently examining the potential origin of the remainder.- g Preliminary indications are that the increase may ',e the result of sumer time temperatures affecting the lower sensitivity levels of 1 --- %e'vfhii. inut' Lor's. -Abborne effluent infermation will continua g to be provided on a montM y basis. F i 3. Environmental Protecti_on Agency (EPA) Environmental Data. The EPA announced on July 6 T981 that, due to a new shipping procedure for p! Kr-85 samples to the laboratory, the.results for the Kr-85 environ-mental monitoring stations around TMI will not always be available g on a weekly basis. The NRC till report these results as they (g become available. F g No radiation above normally occurring background levels was detected in any cf the samples collected from the EPA's air (. and gamma rate networks during the period from July 30, 1981, through August 5,1931. { k. NRC Environmental Data. Results from flRC monitoring of the environ-ment around the TMI site were as follows: g [, The following are the NRC air sample analytical results for the onsite continuous air sampler: y I-1 31 Cs-137 B Sample _ _ Period (uCi/cc), (uti/cc) ti HP-279 July 30,1981 - August 5,1981 <10.0 E-14 <10.0 E-14 r$ t .h i. i i ![ EfvCLOSURE B f h 1 3. -.. 3

s ' i 5 LicensPe Radioactive Material and_ Radwaste Shipments _. On Monday, August 3,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia. On Tuer. day, August 4,1981, one 6' x 6' EpICOR-I dewatered ~ t resin liner (liner P-16) from Unit I was shipped to Chem-Nuclear Systems Incorporated, Barnwell, South Carolina. r On Friday, August 7,1981, two Hittman steel liners containing a y Unit I solidified evaporator bottoms were shipped to U.S. Ecology. Richland, Washington. Major Activities l. Su_bmerged Dcmineralizer System _(SDS). Preenssing of the third batch hl ' Tapproximately30,000 gallons) of Reactor Coolant Bleed Tank (RCBT) water continued. As of 7:00 a.m., August 7,1981, approximately [ 34,000 gallons had been processed. Preliminary results indicated that the lodding on the first zeolite ion-exchange vessel as of August 7,1981 is 740 curies of Cs-137 and 3o0 curies of Sr-90. ? This loading represents greater than 99% removal of these radio-h. active materials from the process stream. h The licensee completed processing the third batch on August 9,1981. 3 l Prior to staging and processing reactor building sump water the licensee plans an outage period to incorporate minor system modifications.. Staging I and processing of reactor building sump water is expected to start the first part of September 1981. 6-f [ 2 Till Occupa_tional Exposures. Attachment i shows the data for Units 1 and 2 for 1979 - T981. The higher exposures for both units in 1979

  • relative to 1980 reflect both reactors being operational early in 1979, j'

the higher level of worker activity immediately after the March 28, 1979 accident, and the ef.ects of radioactive decay and subsequent ocse reduction. h i Attachment 2 provides a comparison of PWR average exposures for the years - 1979 and 1980 The two basic conclusions are (1) 1NI occupation doses during ' 1979 (accident year) are comparable to those of other PWR sites, and (2) the difference in occupational exposure between TMI-2 and TMI-1 is nct significant. E ~ Attachments 3A, 3B, and 3C present a breakdown of occupational exposure I for ths TMI station. These data indicate the number of personnci monitored [] ' for each indicated time period, and number of personnel in each exposure r range. As an example, attachment 3A irdicates that in 1979, 10,824 people [ were iaonitored at the TNI station, with no measured exposure for 6,869, and .g 249 received between 0.5 to 0.75 Rem exposure (for instance). The total 4 occupational exposure for the station was 1508 Rem in 1979. The 1979 exposure data directly related to the accident were evaluated in great depth by [ . the USNRC Special Inquiry Group, with the evaluation published in "Three i Mile Island, A Report to the Commissioners and to the public", by 4 . M. Rogovin, Director ( Attachments 4A, 48, and 4C). b 4 i 1 l i 1 I L t f [ ENCLOSURE B 1

4 F,eetino Attended On Thursday, August 6,1981, Lake Barrett met with a delegation of area mo'thers to discuss various issues related to TMI. Topics discussed included the safety of transportation of radioactive materials, NRC's investigation of Unit 1 operator licensee examination cheating, and Unit 2 funding. Tuture Meeting On Tuesday, September 1,1981, the Citizens Advisory Panel for the Decontamination of TMI Unit 2, will meet from 7:00 p.m. to 10:00 p.m. at

the Holiday Inn, 23 South Second Street in Harrisburg, to discuss current activities at TMI.

This cieeting will be open for public observation.- t W r i i k ) I p t E i ir E ^ 4 L t I 1{ i l f' ENCLOSURE B 4 t l k' li lb i i r b 5

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[ ll. r .s t j i t 1979 SUle'ARY P.EPORT [ TM1 STATION-UNITS I & II i CURRENT OCCUPATIONAL EXTERNA 1. RADIATION EXPOSURE t i j l7 l$ R eportperiod 1/01/79'- 1 2/31/79 y 1 ) i Pe -sonnel monitored - 10,824 ) I s i No measurable ?. exposure. 6,859 3 Rem. 1 o}sure less than 0.'l g s' 2,053 ,r, ..Ex; e l ~ 0.1 to 0225 715 L 0.25 to 0.5 521 1-g ,0.5 to 0.75 249 i I l0.75to1.0 153 0 1 'l.0 to 2.0 222 f k g !2.0 to 3.0 31 p-i t 3.0 to 4.0 6 (. 4.0 to 5.0 5. 'i i 6s' Greater than 5.0 0 i p, L a. i ,i / L r 8. l' I ~' .~- y 1 V l l i i t i Ycarif total for \\ [ Units I & II 1508 REM / ENCLOSURE B ' e / / t r i h ATTACHMENT 3A T ~ .r -m

1 r L, i. i'. sum ARY REPORT ,.,[ ) j TMI STATIO (-UNIT 5 I & II .- 7 CJPS.ENT OCCL'"ATIONAL EXTEmlAL RADIATION GPOSURr,,. .y. s. s Rep < rt period 01/01/80-12/31/80 j i 2 e L / Pcrst onel conitored 10,761 i [ No r.c Esurabia 8.433 r C.XpO3 t!T11 p l Rem s1,356 [ 90s ure 1ess than 04 g ..,q ._3 e -0 1 to 0.25 539 ..=j .a 0.25 to 0.5 304 '{ f 0.5 to 0.75 62 9.'.- P 1 O.75 to 1.0 35 {

.L T,.0 to 2.0 51 l-i k

2.0 to 3.0 1 [ l L. 3.0 to 4 0 t i f. l Greater than 3.0 0' i t i l Yearly total for n; Units 1 & 2 360 5 E q i L I l (^ i Ii 4 p t I f i I .L i y i '/ f = ENCLOSURE B I F .'ATTACHMEhT 3B i f I 3 . Q' ?

)

1..

.1 SUtG'ARY REPORT TM1 STA110:(-U:il151 & II i CUP.P.DIT OCCUPAT)O!iAL EXT LRf Al. RAD 1A110:i EXPO 5UR \\ i i i ..... q h , y.y: Repor".! p'eriod 01/01/,81-04/30/81 ? .:a i. .~ l 3920 hl manitored Personn rr ?O .,I o 1,

' No c.ee
;Urable 2717 exposu 1

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. 23

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ret hava any discernible c!!ect. The Ad Itoc Grc,up s* metry Task Group of the Pretidents Corr.m'ss on q i "h sed s*mhr con:losions."3 concluded, aher its review of the procedures and e rea data ressiding the cccups'ional cxpsu'es resu!bng 1 Jf. from the accidunt, that 'the avabbb data on occu-g .r e Occupational Exposure pational exposure at Three MSc ! stand must be h. e. l~, treated with caution. It may be in: cmp!ste.*17' We i q/- Met Ed reported three at:cident-related whole-agree with this conclusion. g d*M bod (exposurcs in excess of the NRC quarterly litr ! We find that the accident at TM-2 resu'!ed in '$p, of :: rem. These doses were 3.9,4.1, and 4.2 rem, several exposures in excess of regulatory limits to $'s ba# tion. two workers rece'ved overexposures to p! ant personnel in the first few days fo:iowing the i thei hands. The.se doses have been calculated by accident. We find further ihat the conective occu-D@. the NRC at about 50 rem to skin of the forearm of pational dose and the extent of overexposure is not. a one dorker and about 150 rem to the fingers of the large in relation to the radiation fields and contami-(tNr*. The worker who received 150 rem to his nation levels encountered during the accident, M, Angors is the same tridividual who received a a!though the actual co!!ec0ve occupational dose is jij-whcle-body exposure of 4.2 rern. (On August 27, not precisely known. N g. 1970,{ six workers received overexposures to the t' skirt and extrem!!ies. The doses, as measured by

  • p.'

'g. TlEs, were up to 50 rads to the sg and between

f. Health Effects of Low Level fonizing 40 and 150 rads to the extremities)

RadaUon. [M.r T% potential for severa, additional overexpo-surcs' existed during the first few days of the ac-The human hea!!h effects of ionizing red;ation cident. Extremely high radiation fiefds, in excess of may be clan as. @ ae somat.e ems, W Me'.. 1000 TVh, existed In the auxiliary building."3 More-developmental or teratogenic effects (3) late somat-W wei,innauthorized entries to the buUding were made b Ms, and W ges ekh 'id. in W!ation of station health physics procedures. Amte soma 0c eWcts,im&e varNs forms h N*"* RihNgh a person could have been severely diation cickness occurring shortly (a few days or r e' posed. there is no evidence that anyone was. weeks) after whofe-tady doses of about 100 rad or ovei x 'tMt total estimated cccupational collective. dose more. Tratogenic eUects imoh various kinds of 4 thro;gh June 30 was about 1000 person-rem.u4 developmental abnormai!bes foDow,ing stradation at h Tabe C-25 shows the number of Individuals moni-l~rs', forci and the co!!ective occupational dosas re-utero. Such effects have been ogserved in animals f !! wing doscs as bw as 5 rad and in humans Jhi. ceived for the period March through September foHowing doses exceeding 50 rad. There is no f.p ig7gg evidence associating much sm ter doses of rada- ' T. Tbe !!-26 shows the number of individuals who tion to developmental effects. recWed whofe-body coscs in excess of 100 mrem h radation opzures caused W the acM, ent during !! e period from March through September msun d,m, individual doses considerably sma:er, j'.O 1970.! The data In this tab!e were extracted from than those associated with acute and teratogenic' Met EdsTLD personnel dosimetry report. eMects. h most @ tant Ms of radahn y, N T1e co!!ective dose received by the 1596 indvi-man which may be caused by low level radiation are I duskreceiving doses in excess of 100 mrem is ap-those which may appear, or continue to appear, at + proumately 800 person-rem. These data show that e eUects) or." Na or her pro-

  1. #8"#

U 1 no indhidual has received a dose in excess of the d ye somat. in ina l'. a*onab!c annud Emit of 5000 mrem.w2 The aver-geny (gendc eMects). W used "in tNs rem h age dose rece}ved by theso 1596 individuals was levet* or *now dose

  • refers to doses below indvidual

~ 10 % of that Emit. ccupational dose standards of 5000 mrem per i I T ible E-27 contains the dose accumutation rate yea 4 for 11e seven individuals receMng more than 3000 mren'during that 7-month period. The tabte shows that most of the re!atively high individual exposure Late Somatic Effects-The most important late occured during the first month after the accident. somatic effect of low doses of radiation is the in-Ts cotective occupational dose is smaller than crease of incidence of cancer. Most human stuJies that received by the surrounding population. on populations exposed to radiation (e.g., atoric athcu'ghit ws: continue to rise during recovery bomb survivnrs in Hiroshima and Nagasaki, radum ope'r.t;ons. Moreover, the Health Physics and Do-dial painters). indicate that radiation-induced Efe ATTACH #.NT cb 401 y i ENCLOSURE B p i

r- -

l. ) [ ,j TAUL E 11 25. Occupational dor.e T/.;n ch 1 to Sistemkr 30.

  • G79 "8 i

Collective Dose ' Number of Dosimeters Distriouted (person.rcm) T/onth [ IAmich 1131 334 ? Apdl ' 4504 140 I' May 5282-350 1 l . June 2973 159, July 2500 (approx.) 63

  • /

e I ] August 25C0 (approx.). 63 September 2472 36 5 i TABLE II.20. Occupational doses In excess of 100 mrum March 1,1979 to Scpf ember 30,1979 Dose Range 100-- 259-501-751 - 1001-2001-3001-4001-More than (mrem) 250 500 750 1000 2000 3000 4000 5000 5000 7 L Number i of 648 465 213 Its 129 16 4 3 0 ? j Individuals 5 b TABLE !!-27. Dose accumulation rate for Individuals receiving more than 3000 mism from March t, t 1979 to September 30,1979 ra . Dose (mrom)

n lndiv.

Indiv. Indiv. In(cr. e T .indhr. Indiv. indiv. 'l

  • Period -

A 5 C D E F G, ,g i, ,' 03/01-03/31 4100 4120 1785 3575 2230 1785 2360 1 04/01-04/30 160 10 915 40 990 915 1335 3 l l* 05/01-OS/30 15 30 45 220 100 45 180

n j

j 07/01-00/30 30 15 395 70 345 395 210 j. _ _ _ =.. y , shortenino is largely due to increased cancer mor-dies also necessarily involved exposure to relativey

tafity."*

large doses. Cancers indire.ed by radiation are h-Radation-induced cancer is detectable only in a distinguishab!e from those occurfng from other ststistical sense. A particular case cannat be attri-causes. Radiogenic cancer thus can on?y be h-j buted to rad'ationss2 Human evidence for ra-ferted on the basis of an excess above the expect-

diogenic cancer comes from epidemiological studies ed naturalinc;dencet l conducted on relatively large popufation groups ex-Theoretical considerations suggest that at a.y

! posed to doses much larger than those experienced levc! of radatiort no matter how s,ma!!. some can$- , by the poputation in the vicinity of the Three Mile 1s-nogen'a poten:iaf exists. Thus far nearty a human " land Station. Numerous animal studios confirm the data rely on observations at high dose levc!s and

ct.fcino;enic proper 1ies of radiation, but those stu-high dose rates (do
cs generaDy greater than 50 i ).

ATTACHMENT 4C 4 02 s I E!1 CLOSURE B g' 3 i=

J 1 i l OFFICE OF NUCLEAR MATERIAL ~ SAFETY AND SAFEGUARDS Items of Interest Week Ending August 7, 1981 Reactor Sabotage Protection The staff is completing safeguards rules on three closely related issues. These issues concern pat-down searches at power reactor protected area portals, personnel screening for persons granted unescorted protected and vital area access at power reactors, and designation and protection of power reactor vital areas. A Commission paper is being developed to pro-l vide an overview of the interrelationships among these three rulemaking l actions. l Nerve Gas Detectors with Americium-241 Representatives of the U.S. Army met with NMSS/FC staff to discuss a nerv, gas detector which contains a relatively large Americium-241 source (230 microcuries). The Arnly plans to procure these detectors from nanufacturers licensed by NRC. Two applications have already been received by NRC for licenses to distribute the detectors to the Arnly as exempt products. Regu-latory alternatives were discussed regarding distribution of the detectors as exempt, generally licensed, or specifically licensed. In the event applications for exempt distribution are denied, it would be possible to meet the Army's need for these detectors by issuing a specific license to l the Arnly for use of the detectors. l i ROCKWELL INTERNATIONAL l l On August 4, 1981, staff members met with P.A. Scofield of Rockwell International to discuss possible approaches in establishing reportable l quantities for radionuclides covered by the Comprehensive Environmental l Response, Compensation and Liability Act of 1980 (Superfund). The dis-i cussion revolved around the reasonableness of alternative technical approaches. l ENCLOSURE C i

1 Meetings - Division of Waste Management 1. S;bject: Discussion of NRC Comments on'BNL Task 4 Draft Report Date/ Time: August 11 - 10:00 a.m. Location: Willste Building, Room 196 Attendees: M. J. Bell, F. R. Cook, E. A. Wick, WMHL; P. Soo, G. Bida, N. McIntyre, D. Schweitzer, S. Davis, BNL. 2.

Subject:

Bedded Salt Review Meeting Date/ Time: August 11 - 1:00-4:00 p.m. Location: Room 821, Willste Building At'tendees: WMHT staff 3.

Subject:

Discussion of Tailings Management Plan Date/ Time: August 11 Location: Willste Building Attendees; H. Pettengill, WMUR; Atlas Minerals representative 4.

Subject:

Modification of Licensing Due to Shutdown Operations Date/ Time: August 12 Location: Willste Building Attendees: H. Pettengill, WMUR; Western Nuclear Inc. representatives 5.

Subject:

Prelicensing Regulations Date/ Time: August 12 Location: Willste Building Attendees:

11. Pettengill, WMUR; J. Linehan, WMUR; Arizona Fublic Service representatives 6.

Subject:

BNL Project Ceview Meeting - NRC's Review of Task 1 Task j Report Date/ Time: August 18 - 10:00 a.m. l Location: Willste Building, Room 106 f Attendees: M. J. Bell, F. R. Cook, E. A. Wick, WMHL; P. Soo, G. Bida, R. Dayal or alternative key author, D. G. Schweitzer, M. S. Davis, BNL I i i 1 ENCLOSURE C i e m -e-. u-- g-e

b. Division of Safeguards - Planned Meetings 1.

Subject:

Mtg w/ Sr. Jose Maria Martin Oviedo of Spanish Nuclear Council to discuss physical protection regulations Date: August 10, 1981 - 9:30 a.m. Location: Willste - Rm. 872 Attendees: D. R. Chapell G. McCorkle or D. Kasun C. Gaskin C. Hillman 2.

Subject:

Meeting with Babcock and Wilcox Company to discuss Part 73 upgrade Date: August 20 and 21, 1981 Location: Lynchburg, VA J. Eanes (B&W)(B&W) i Attendees: i H. McClanahan l R. Cordani (B&W) l

0. Smith (SGPL)

G. Gundersen (SGML) 1 ABSENCES OF THE DIRECTOR OR DEPUTY DIRECTOR 1 Robert F. Burnett 3/10-14/81 Acting: Donald R. Chapell 1 1 4 1 1 4 I a 1 }. ENCLOSURE C 1 1

i i Meetings - Division of Fuel Cycle and Material Safety ^ L. -1.

Subject:

To discuss Joint Commission on Accreditation of Hospitals (JCAH) submissions of hospitals re misadmiristration and other regulatory matters. Date/ Time: August 11 - AM Location: Chicago, Illinois Attendees: Richard E. Cunningham (FC), Lidia Roche-Farmer (FC), Dr. Douglas Duncan (Associate Director, JCAH) 2.

Subject:

To discuss relationship of NCRP with NRC activities. Date/ Time: August 11 - PM Location: Argonne, Illinois Attendees: Richard E. Cunningham (FC), Mr. Sinclair (ANL) 3. S9bject: Meeting with NFS to discuss plant improvements. Dcte/ Tire: August 11 - 2:00 pm Location: . Region II Office Attendees: J. P. O'Reilly (Director, Region II), Region II Personnel, C. Taylor (Vice-President, NFS), NFS Personnel, i George Bidinger (FC) 4.

Subject:

Kerr-McGee, West Chicago Date/ Time: August i2 Location: Chicago, Illinois Attendees: Richard E. Cunningham (FC), Ed Shum (FC), Bill Crow (FC), Mr. Fonner (ELD), EPA, Region V, Region III, State Officials l 5.

Subject:

Meeting to discuss amendment application for plant expansion. Date/ Time: August 12 - 8:00 am Location: General Electric, Wilmington, North Carolina j Attendees: George Bidinger (FC), C. 7aughn (GE) 6.

Subject:

To discuss Fuel Cycle programs. Date/ Time: August 13 - AM Location: Glen Ellyn, Illinois Attendees: Mr. Keppler (Director, Region III), Region III Personnel, Richard E. Cunningham (FC) 7.

Subject:

Prehearing conference. Date/ Time: August 13 l Location: Chicago, Illiriois i Attendees: General Electric Personnel, Le Rouse (FC), Stu Treby (ELD), l M. Rothschild (ELD) ENCLOSURE C

p . 8.

Subject:

Summer 1981 National Meeting of the American Institute of Chemical Engineers. Date/ Time: August 17-19 Location: Detroit, Michigan Attendees: Bill Thompson 9.

Subject:

Containment System for Nuclear Spent Fuel and High-Level Waste Packaging. Date/ Time: August 19 - 9:00 am Location: Denver, Colorado Attendees: Chuck MacDonald (FC), ASME Committee Members ABSENCES OF DIRECTOR AND DEPUTY DIRECTOR Thomas F. Carter, Jr. - August 7 (Leave) Richard E. Cunningham - August 10-13 (Trip to Chicago) l l ENCLOSURE C

OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending August 7, 1981 1. The following Notification of Significant Enforcement Action was dispatched during the'past week: a. EN-81-25 Pharmatopes, Incorporated - A Notice of Violation and Proposed Imposition of a Civil Penalty in the amount of $5,000 was issued to subject licensee on August 6,1981, based on an alleged violation involving a radiation exposure to the right hand of an employee at their Washington 1 D.C. facility in excess of NRC limits. One other violation not related to the excessive exposure occurrence was also found. The nature and significance of that item was suchithat a civil penalty was not warranted. 2. Preliminary Notifications relating to the following actions w'ere dispatched during the week: a. PN0-I-81-35 Beaver Valley Power Station, Unit 1 - Boron Injection Tank (BIT) Bypass Valve Circuit Breaker was Found De-energized b. Pi40-III-81-66 Quad-Cities Station Unit 'l - Shutdown in Excess of 48 Hours c. PNC-III-81-67 Monticello Nuclear Generating Plant - Unplanned Liquid Release d. PNO-III-81-68 Callaway 1 - Crane Boom Collapse on Roof of ESW Pump House e. PN0-III-81-68A Callaway 1 - Crane Boom Collapse on Roof of ESW Pump House (Update) f. PNS-II-81-ll McGuire Nuclear Station, Unit 1 - Hoax Security Incicent g. PNS-V-81-08 San Onofre Neclear Generating Station - Bomb Threat 3. The following IE Infomation Notices were issued: a. IE Information Notice 81-23, " Fuel Assembly Damaged Due to Improper Positioning of Handling Equipment", was issued on August 4,1981 to all noclear power reactor facilities holding an operating license or construction pemit. '~1-.. ~ b. IE Infomation Notice 81-24, " Auxiliary Feed Pump Turbine Bearing Failures'?, was issued on August 5,1981 to all nuclear power reactor facilities holding an operating license or construction perr.it. ENCLOSURE D

i 4. Other Items t a. Activities of the Division of Emergency Preparedness: July 31, 1981 Director participated in a meeting with NRC's OMB budget examiner on the implement ation of the superfund legis16 tion to clarify the EPA and FEMA roles in responding to incidents involving radioactive releases and also discussed need for additional FEMA resources in the emergency prepared 1ess area. August 3, 1981 4 The first monthly report to Congress on emergency preparedness was delivered to the staff of the Subcommittee on Nuclear Regulation. The onsite c:.ergency preparedness appraisal at the Arkansas facility began on 8/3/81. August 5, 1981 4 Director, DEP, the Deputy EDO, the Chairman's technical assistant and representatives from FEMA met with a member of the Simpson Subcommittee staff to discuss the monthly report on emergency preparedness. l Director met with representatives from the Nuclear Safety Oversight Committee staff to discuss emergency preparedness appraisals. e e t ErlCl.0SURE D

i-OFFICE OF NUCLEAR REGULATORY RESEARCH IMPORTANT EVENTS FOR THE WEEK ENDING AUGUST 7,1981 Experimental Programs Branch 1. Semiscale Test NC-4, an investigation of reflux boiling, was successfully conducted on July 30, 1981. Visual observations were obtained in the steam generator plena and in the primary loop legs connected to the i steam generator. Data processing is underway. Planning for en additional test in the series, NC-1% has been initiated. This will provide supplemental information to fully establish natural convection behavior as a function of primary and secondary conditions. There is no change in the promised schedule. Test NC-5, with inert gas in the primary loop, is anticiptted on August 12, 1981. Reports covering behavior of the Westinghouse liquid level probe i for tests S-UT-6 and -7 were completed last week. Draft versions for tests S-UT-3 and -4 are done. I I 2. LOFT The LOFT +est L6-7/L9-2 was run successfully on July 31,1981. The first part of the test simulated the excessive steam loss that occurred at ANO-2 during a. turbine trip test. The second part of the test resulted in a continued cooldown resulting in a steam bubble in the reactor vessel upper plenum region. The test was designed to provide a basis tqr comparing the scaling between LOFT and the ANO-2 plant and also to provide data for assessment of computer code prediction capability. The test was successful in showing adequate simulation of the ANO-2 transient and in showing that natural circulation is an effective means of cooling down a reactor even with the presence of a steam bubble filling half the upper plenum region. The data have been obtained 'for comparing with code predictions as was indicated as beir.g needed following the St. Lucie cooldown transient. Further analysis of the data will continue. The Quick Look Report is expected to be completed in approximately one week. 3. ECC Bypass The data which resulted from the ECC Bypass program vill be maintained by Creare and Battelle Columbus Laboratories through,it FY 1982. This will be useful for comparisons with experiments at LOFT and CCTF. ENCLOSURE E

2 Analytical Models Branch 1. DehelopmentofTRAC-PF1wascompletedonscheduleatLANL. The main mission of this fast running advanced. code is the analysis.of consequences of SBLOCA scenarios in PWR!s. It can also be applied to a. variety of PWR transients that do not require modeling of the complete plant contr61 system of of the balance-of-plant. 2. Due to the air traffic controllers' strike the LANL presentation, to.the NRR staff, of the TRAC-PF1 capabilities has been postponed. A new date -is being arranged. 3. The versioc, of TRAC-BD2 containing models for reactor point kinetics feedback, bcron tracking (and its kinetics feedback), and for the subcooled void distribution in the reactor core is completed at INEL, With these additions the TRAC-BD2 code can be used for studies of various ATWS scenarios in BWR's, not requiring 3-D kinetics. 4. A meeting was held on August 3, 1981 with the Sandia staff to (a) organize theirworkscopeconcerningassessmentofRALOC-IIcode(forhydrogen distribution studies), using information from the forthcoming CSTF test series on H2 mixing, sponsored by EPRI; and (b) to explain our views and give directions regarding the FY 82 program on assessment of the RELAP-5 i i code. [ Severe Accident Assessment' Branch 1. Super Systems Code Verification at BNL Calculation of the 75% power and 75% power natural circulation tests on the FFTF reactor have.been completed. As with the previous SSC cases from 100% power and 100% flow, the simulations were carried out to 1800 seconds. For the two channel FFTF input deck used, the machine time re-quired was 460 seconds. As with the 15d% case, the SSC results, when compared to the experimental i data, are very encouraging. The predicted loop flow rates for both the primary and intermediate loops fall within the data spread. The predicted loop temperature responses are in good agreement with the data not only for the various maxima and minima achieved, but also from timing aspects as well. .e e I I ENCLOSURE :

. Publications to be issued in the Near Future

Title:

Guide for the Preparation of Applications for Use of Sealed Sources and Devices for Performing Industrial Radiography

== Description:== This guide provides assistance in the preparation of an application for an NRC license for possessi6n and use of sealed sources and devices for perfoming industrial radiography. Conta cl:' M. E. Wangler 443-5825 6 ENCLOSURE E

FORTHCOMING SPEAKING ENGAGEMENTS September 2, 1981 1981 IEEE Standards Workshop on Human Factors and Nuclear Safety t1yrtle Beach, South Carolina "NRC Regulations and Standards" - Karl R. Goller G S EllCLOSURE E

l ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING AUGUST 7. 1981 Implementation of U.S. - Australian Agreement for Cooperation IP, ELD, and NMSS represented NRC at a meeting at DOE on August 5 to discuss the implementing arrangements for the U.S.-Australian Agreement for Cooperation. The primary task to be accomplished is to establish a mechanism for tracking imports into the U.S. of Australian nuclear material under the agreement in order to assure that any subsequent re-exports receive appropriate Australian approval. Further interagency discussions will be held prior to meeting again with the Australian authorities. IAEA International Seminar on the Safety of Two-Loop PWRs, in Vienna, Austria, November 16-20, 1981 The IAEA is organizing an international seminar on the safety of two-loop PWRs to provide opportunity for the four developing countries with Westinghouse two-loop PWRs (Brazil, S. Korea, the Philippines, and Yugoslavia) to discuss, with each other and with experienced international personnel, safety issues related to these reactors and other PWRs. At the IAEA's request, the NRC has sent information about the meeting to U. S. PWR members, utility operators of two-loop PWRs, A-Es and other U.S. organizations such as INP0 and NSAC. IAEA would like the U.S. to be represented at the meeting by at least one person each from Westinghouse, INP0, NSAC, and the NRC, and two people from the U.S. utilities. The subject areas of greatest interest to the IAEA are TMI-related safety modifica-tions, unresolved PWR safety issues, and PWR operating experience. The IAEA technical secretary for the meeting suggested that the ideal NRC paper might be given by someone with broad management and field experience and might cover a wide range of topics, including some discussion of unresolved safety issues, and the status of the TMI action plan, with some added focus on the need for improved training of operators (including consideration of the special attention developing countries might give to maintaining natural circulation cooling and to other matters related to station blackout due to lightning strikes, grid / systems instability, etc.). Ron Hauber and Kevin Burke (X27788) may be contacted for further information. Swiss Visitor to TMI On Wednesday Dr. Konra. dasler, member of the Swiss Parliament, visited TMI accompanied by Robert Senseney, IP. ENCLOSURE G

o o O Foreign Reports Deleted from PDR copy.

    • Indicates the reports are in English ENCLOSURE G

) -. - r. OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING AUGUST 7, 1981 On July 31, 1981, Washington State signed two subagreements establishing procedures for cooperation on environmental reviews and joint hearings. regarding the Skagit Nuclear Power Plant Units 1 and 2 to be relocated to the Hanford Federri reservatinn near Hanford, Washington. NRC had previously signed the subagreement non July 28, 1981. R. J. Doda, Region IV State Agreements representative and Jim Montgomery, RSLO, Region IV, spoke on August 6, _1981, to a group-of~recently hired staff members in the Texas Department of Health. Mr. Doda spoke on " Background and Operational Aspects of the State Agreements Program." Jim Montgomery addressed the group on the role and function of the NRC. Texas has recently added_approximately 60 new employees to the radiation control program. d 4 1 ENCLOSURE H. y- -rc._m,-- y -- y --, 3,, i.

i. OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING AUGUST 7,1981 l. l Publications l ACP Long-Range Plan - Distributed final version of ADP plan for FY 81-85. It will provide a baseline for more compre-- hensive planning this fall. Summary Information Report - Issued draft of new publication i whose objective is to provide an overview of NRC's activi-i ties and major licensees' status. 1 t l I l i l l l l l ENCLOSURF I l r.

-i.. o 0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST. WEEK ENDING AUGUST 7, 1981 1. Sequence Coding and Search Procedure A meeting was held on August 4 and 5, 1981 with the Nuclear Safety Information Center to discuss the status of development and additional improvements in the AE0D Sequence Coding and Search Procedure (SCSP).- Development activities continue on schedule and it is still anticipated that a " trial use" period for other organizations can begin late this calendar year. 2. IAEA Meeting on Operational Experience IAEA has proposed a one week international meeting in Vienna in November 1981 to discuss operational experience with commercial reactors. AE0D has been specifically invited to participate in the meeting and to make a r. umber of presentations. Together with IP, discussions have been held with IAEA (R. Skjoeldebrand and M. Rosen) regaroing a suggested meeting agenda. At this time, it is inticipated that the meeting will focus on: (a) the 6 collection, evaluation, feedback, and data management of operational' data; and (b) recent operational events of possible generic interest. 4 1 Safety Concerns Associated with Pipe Breaks in the BWR Scram System AE00 reviewed and concurred (with one comment) on the staff SER. When the SER is issued, the staff will have defined the guidance for aLceptably resolving the plant-unique aspects of this issue. a t 4 4 ENCLOSURE K i 1 0 w m +m

=. V <r., s 1 ITEMS APPROVED BY THE C0 tit 11SSION - UEEK ENDIfiG AUGUST ~ 7,1981 'A. SECY-81-415 - PROPOSED LICENSE TO EXPORT DEUTERIUM OXIDE TO 22 COUNTRIES Memo SECY to Dircks, dtd 8/3/81. This is to advise you that the Commissioners have reviewed the subject liceTse.to Sigma Chemical Company. The Commission (with four Commissioners approving) has accepted your recommendation to export to 22 countries 5,000 kilograms of oeuterium oxide (D 0). In' tor.nection with this approval, Commissioner Bradford provided the following comment: "I would make the State Department's proposed quantity limitations explicit in the licenses." The Office of Internhtional Programs,. which was informed of this action by~ telephone on August 3,1981, has advised SECY that this condition will appear in the licenses. B. SECY-81-431 - APPROVAL OF A PROPOSED LICENSE TO EXPORT HIGH Et:RICHED URANIUM TO THE FEDERAL REPUBLIC 0F GERfiANY (LICEftSE NO. XSNM01482) ~ i Memo SECY to Dircks, dtd 8/5/81. i This is tu advise you that the Commissioners have reviewed the subject license to Transnuclear. Inc. The Commission (by a 4-0 vote) has accepted your reco,mmendation to exocrt to the Federal Republic of Germany 2.206 kilograms of uranium enriched to 93.3% U-235. The Office of International Programs was informed of this action by telephone on August 4,1981. C. SECY-81-410 - GEf1ERIC RULEMAKING FOR TRGTMENT OF WATER QUALITY MATTERS IN OL-STAGE LICEtlSE ACTIONS. tiemo SECfIh~Dircks, dtd 8/7/81. ~ l This is to advise you that the Commission (with four Commissioners i disapproving) has disapproved your recommendation that the staff be directed to prepare a policy paper. to specify NRC treatment of all matters regulated under the Clean Water Act not requiring a change to or i addition of rules. Commissioner Ahearne, while disapproving the paper, would have preferred providing guidance to the staff for a rewrite. The Office of.fluclear Reactor Regulation was informed of this action by 4 telephone on August 5, 1981. i l t EllCLOSURE M -. - - - - - -. -., -}}

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