ML20058N374

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Weekly Info Rept for Wk Ending 810717
ML20058N374
Person / Time
Issue date: 07/22/1981
From: Rehm T
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
Shared Package
ML20058M131 List:
References
FOIA-92-436 SECY-81-443, WIR-810717, NUDOCS 9310140217
Download: ML20058N374 (27)
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{{#Wiki_filter:- - - 3 M UNITED STATES NUCLEAR REGULATORY COMMISSION d WASHINGTON, D. C. 20555 S ' " ~ * ' "" Juh 22,1981 INFORMATION REPORT For: The Comissioners e From: T. A. Rehm, Assistant for Operations, Office of the EDO g!r Subiect: WEEKLY INFORMATION REPORT - WEEK ENDING JULY 17, 1981 45 A sumary of key events is included as a convenience to those Commissioners ~ who may prefer a condensed version of this report. Contents Enclosure Administration A Nuclear Reactor Regulation B i Nuclear Material Safety and Safeguards C Inspection and Enforcement D Nuclear Regulatory Research E Executive Legal Director F International Programs G State Programs H* Management and Program Analysis I Controller J* Analysis and Evaluation of Operational Data K* Small & Disadvantaged Business Utilization L* Items Approved by the Commission M l A. J- , Assistant for Operations Office of the Executive Director for Operations

  • No input this week.

DISTRIBUTION: ~, Commissioners Commission Staff Offices 9

Contact:

ACRS Q; T. A. Rehm, EDO Secretariat j 49-27781 C 9310140217 930218 PDR FOIA GILINSK92-436 PDR,

I Pae o L T i !% E % Dl8I SU!! MARY OF WEEKLY INFORMATION REPORT Week Ending July 21, 1981 Oconee Unit 1 Following the removal of the Oconee Unit 1 Reactor Pressure Vessel internals, in preparation for the 10-year ISI, several loose parts were visually detected (attachment bolts and nuts for the thermal shields). Duke Power Co. will inform other B&W owners of this possible generic problem. Brunswick Steam Electric Plant, Unit 1 A lubricating oil system failure has caused significant turbine generator bearing damage, resulting in plant shutdown (about two months for repairs). GE-Morris Operation The staff issued its Safety Evaluation Report on the proposed renewal of the fuel storage operation. A orehearing conference has been scheduled by the ASLB for August 6, 1981. l l Draft IAEA Safety Guide SG-9, " Site Survey for Nuclear Power Plants" l l Member State coments are being tran::mitted to the IAEA on the draft I safety guide, SG-59. The staff is recomending that SG-9 be approved for IAEA publication and is forwarding several technical coments concerning corrections and omissions. US/ Australian Bilateral Acreement NRC staff met with representatives of the Australian government DOE and State to discuss Administrative Arrangements for implementing the US/ Australian Bilateral Agreement. The Administrative Arrangements will outline the type and frequency of reports that will be submitted between the U.S. and Australia dealing with accounting for nuclear material of Australian origin. l t l

h OFFICE OF ADMINISTRATION Week Ending July 17, 1981 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 312 11 Granted 225 2 Denied 41 7 Pending 46 2 ~ ACTIONS THIS WEEK Received Robert Alexander, Requests a copy of 11 listed documents. Mockingbird Alliance (81-262) Robert Matisoff, Requests, on behalf of United Association, documents O'Donoghue & 0'Donoghue which relate to the function or purpose which the (81-263) box beams are designed to serve at the Browns Ferry nuclear power plant. Jay E. Silberg, Requests all records relating to the requirement in Shaw, Pittman, 10 CFR 73.55(d)(2) that all hand-carried packages Potts & Trowbridge be searcneo for certain specified devices; all (81-264) records relating to the requirement in 10 CFR 73.70(d) that nuclear power reactor licensees maintain a log indicating the time of exit of all individuals granted access to a normally unoccupied vital area and all records relating to the requirement in Sections I.C and E of Appendix B to 10 CFR Part 73 for an annual physical fitness denonstration for certain personnel and that the physical fitness denonstration be held wi, thin 30 days after a medical examination. Sarah Gorin Jones, Requests 54 categories of documents regarding Wyoming Powder River Basin Mineral Corporation's Irigaray Project. Resource Council (81-265) (An individual requesting Requests information on herself in the NRC. information about herself) (81-266) CONTACT: J. M. Felton 492-7211 ENCLOSURE A i

'h 1 g Received, Cont'd Peter Dalton, Requests a listing of import and export licenses ) Sierra Club Radioactive of radioactive shipments for 1980. i Waste Campaign (81-267) (NRC employee) Requests information on him from Personnel, DIA (81-268) and any charges made against him. 4 j Glenn B. Humphress Requests documents which describe the frequency I (81-269) of use of the TERA system, relative perfomance of the system pertinent to user needs, plans for future development, cost / benefit analyses and ] user surveys. ) Lawrence Coe Lanpher, Requests actual measurements made of radiation Hill, Christopher and levels in plant systems, structures or components j Phillips, P.C. after completion of a low power test program; (81-270) documents which describe, analyze, or predict 3 the radiation levels which would exist after completion of a low power test program and 4 written materials which discuss possible worker i exposures to radiation in conducting maintenance on or effecting modifications to plant systems after completion of a low power test program. Jilian Mincer, APPEAL TO THE ED0 for a lack of response to a request American Friends for documents which indicate spent fuel routes Service Comittee approved by the NRC since publication of draft j (81-A-10-81-241) NUPIG-0725 issued in September,1980. I Robert L. Cohen APPEAL TO THE COMMISSION for a copy of the Louis (81-A-11-81-36) Harris and Associates Survey. Granted i. Eugene Rosolie. In response to a request for seven categories of Coalition for documents relating to Washington Public Power Safe Power Supply System, made available five documents. (81-199) Informed the requester additional documents subject i to this request are already available at the PDR l and the LPDRs in Washington. 1 Harold J. Gabriel, In response to a request for a copy of the original Norton & Christensen contract and any amendments among the owners of 1 (81-244) the Perry Nuclear Power Plants and Gilbert Associates and Kaiser Engineers, infomed the requester the NRC has no documents subject to this request. l J ENCLOSURE A

3 i Granted, Cont'd 1 F. Ronald Laupheimer, In response to a request for all records relating Pacific Gas and to FOIA requests made to the NRC referring to l Electric Company Diablo Canyon Nuclear Power Plants, Units 1 and 2, (81-249) informed the requester of the FOIA requests already available at the PDR. McNeill Watkins, II, In response to a request for all public coments Debevoise & Liberman received by the NRC on Regulatory Guide 1.120 (81-252) following its publication in June 1976, the ACRS meeting in May 1977, and publication of Revision 1 in November 1977, informed the requester all the coments are already available at the PDR. Sherri L. Knuth, In response to a request for records of health Atomic Workers Health and safety inspections from 1979 to 1981 for & Safety Project Westinghouse Nuclear Fuel Division; Columbia, SC; (81-256) Home Transport Company and Tri-State Motor i Transport, Inc. Barnwell, SC: worker exposure records for above plants and records of health and safety complaints made by workers at these plants, made available four inspection reports completed since 1979 for the Westinghouse Electric Corporation. Made available a copy of the worker exposure information submitted by the Westinghouse Nuclear Fuel Division for 1979 and 1980. Infonned the requester the NRC does not have any records of health and safety complaints made by workers at Westinghouse. Also informed the requester the Home Transport Company and the Tri-State Motor Transport, Inc., Barnwell, S.C. are not NRC licensee shippers subject to inspection by the NRC. The U.S. Department of Transportation and the S.C. Department of Transportation have jurisdiction over their activities at Barnwell, S.C. Denied l Sanford L. Hartman, In response to an appeal to the Comission for 15 Debevoise & Liberman documents which were denied pertaining to the (81-A-8-81-97) Comission's deliberations preceding the issuance I of CLI-80-21, continued to deny these documents containing advice, opinions and recomendations. ENCLOSURE A f

hk i. DIVISION OF CONTRACTS Week Ending July 18, 1981 CONTRACTS CLOSED OUT (All administrative action completed and final payment made) Contract No. Contractor Close-Out Date NRC-04-78-240 ENSCO, Inc. 7/14/81 NRC-02-77-172 Decisions & Designs. Inc. 7/9/81 i l NRC-02-80-052 Southern States Energy Board 7/13/81 l l NRC-02-77-016 Science Applications, Inc. 7/13/61 l l NRC-19-78-472 Mr. Sol Lindenbaum 7/15/81 NRC-18-78-461 Ames Color Corporation File 7/15/81 NRC-13-78-438 Damans & Associates 7/16/81 ENCLOSURE A t

.. ~. -.-... _ -.- ll a i t i. I I j -l l 1 ) i 1 i i DIVISION OF RULES AND RECORDS ) I 0FFICE OF ADMINIS1 RATION i 4 i The Executive Director for Operations has issued final minor l amendments to Parts 21 and 73 changing the telephone number l of the NRC Region IV office identified in these regulations. i 1 Because the amendments were minor and of a nonpolicy nature, l f notice of proposed rulemaking and public procedure thereon i e i were unnecessary and good cause existed to make the amendments i effective on July 14, 1981, the date of publication in the l, j Federal Register. 1 -l i I i 1 'f 9 3 l ENCLOSURE A i f

Division of Technical Infonnation and Document Control Week Ending July 14, 1981 Translations The following translations were completed by the Div'sion of Technical Information and Document Control in the period June 4 to July 14. Copies of these translations will be available in the Library on microfiche. German NRC Translation 863 KTA 1201, Safety-Technology Regulations of the KTA Requirements Made of the Operating Manual. Kerntechnischer Ausschuss (KTA), October 1979. 18 pages. Requested by: HRR. NRC Translation 864 KfK2915. EUR6402d, The Foundation of Boolean Algebra with Restricted Variables. Nuclear Research Center, Karlsruhe Institute for Reactor Develop-L. Caldarola. ment. February 1980. 58 pages. Requested by: NRR. NRC Translation 889 GRS Kurzinformation 1981 C:ll, Recommendations of the Reactor Safety Comission on its 161st Meeting of 17 December,1980. Gesellschaft fur Reacktorsicherheit. (GRS) MbH. Glockengasse 2, 5000 Koln. April 1981. 40 pages. Requested by: ACRS French NRC Translation 8C7 SN 18: Bulletin on the Safety of Nuclear Installations. Ministry of Industry, Paris, France. November-December 1980. 15 pages. Requested by: IP Ital i an__ NRC Translation 868 DISP (79)7, Italian Site Map (Art. 23, Law Dated August 1975, No. 393) - Report, The National Comittee for Nuclear Energy Central Office for Nuclear Safety and j Health Protection. Rome, Italy. September 1979. 17 pages. Requested by: IP. NRC Translation 888 DISP (77)2, Qualifications and Criteria for Possible Site Selection to Build a Nuclear Power Plant-July 1977. National Committee for Nuclear Energy (CNEN) Rome Italy. July 1977. 33 pages. Requested by: ACRS. Spanish NRC Translation 876 DSN/055/81, Class I. Response to the Questionaire Submitted by the NRS in its Telex Pertaining to the Operating Personnel of Nuclear Power Plants. Pilar Villajos. Nuclear Safety Department, Licensing Division. Spain. March 1981. 15 pages. Requested by: IP. NRC Translation 882 Nuclear Practical and Oral Examination for the Applicant for an Operator's License. Energy Board. Spain. Publication date not available. 10 pages. Requested by: IP ENCLOSURE A .~.,...,,.. ~~~...

?Y l Translations 2 i c i NRC Translation 883A Law 15/1980, of 22 April, on the Creation of the Nuclear Security Council. Don Carlos I, King of Spain in Boletin Oficial del Estado (Official State Bulle-tin) 100:8650, p. 8967. Requested by: IP. NRC Translation 883B Circular Number 689 of the Directorate-General of Customs on the Detemination of the Density of Magnesium Oxide. Ministry of the Treasury. Spain. Boletin Oficial del Estado (Official State Bulletin) 255:18906. October 24, 1972. 2 pages. Requested j by: IP. i NRC Translation 883C . Decree 2889/1972, of 21 July, Which Approved of the Regulations on Nuclear and Radio-active Installations. Ministry of Industry, Spain. Boletin Official del Estado (Official State Bulletin) 255:18906. 25 pages. Requested by: IP. Japanese NRC Translation J80 Comencement of Comercial Operations for the Genkai Nuclear Power Station Unit 2 (Kyushu Electric Co.). Agency of Natural Resources and Energy. Japan. March 30,1981. 2 pages. Requested by: IP. NRC Translation 881 Earthquake Resistance of Cathode Ray Tube-Type Nuclear Reactor Room Display Equipment. Agency of Natural Resources and Energy. Japan. March 2,1981. 2 pages. Requested by: IP. i DOCUMENTS PROCESSED BY TIDC Number of NUREG reports printed and/or distributed by the Policy and Publications Management Branch, TIDC for the month of June. Number processed in June Type of Report Draft Environmental Statement 1 Final Environmental Statement 3 Safety Evaluation Report 6 l Environmental Standard Review Plan 0 l NRCI's 0 Staff Report 30 Contractor Report 60 1 Brochures 1 T TOTAL 'This antry celeted from the PDR copy A listing of these NUREG reports is contained in " Regulatory and Technical Reports Compilation" (NUREG-0304), issued quarterly and available from TIDC. ..,. ~.....

l i I i t DIVISION OF SECURITY l Week Ending July 10, 1981 1 j US/NRC-FRG/BMI Agreement i l i On July 6,1981, Chairman Palladino and Dr. Gerhart Baum, Minister of the l i Interior, Federal Republic of Germany, signed the first NRC-BMI agreement to ] permit the exchange of classified information between the NRC and a foreign j government, t 1 0 i ) i S ENCLOSURE A I

4 OFFICE OF NUCLEAR REACTOR REGULATION ~ WEEK ENDING JULY 18, 1981 Oconee Nuclear Station, Unit 1 Following the removal of the Oconee Unit 1 Reactor Pressure Vessel internals on July 15, 1981 in preparation for the 10 year ISI 'several loose parts were visually detected. Preliminary investigations suggest that these loose parts are attachment bolts and nuts for the thermal shields. It is not yet known if all the bolts are accounted for or if other parts ray be involved. Duke r Power Company indicates that they mill inform other B&W owners of this possible generic problent l r t ? Brunswick Steem Electric Plant, Unit 1 . A lubricating oil system failure at Brunswick Unit 1 has caused significant turbine generator bearing damage, resulting in plant shutdown. The l licensee anticipates a two month forced outage to effect repairs. j MEETING NOTIFICATION 1. There will be an NRR meeting with PWR Owners Group on July 17, 1981 i from 9:00 a.m. to 11:00 a.m. in Room P-422 to discuss PWR Owners appeal for elimination of NRC requirement for qualification of PORY block valves. 2. There will be an NRR meeting with Westinghouse on July 27, 1981 from { 1:00 p.m. to 4:00 p.m. in Rcom P-118. Westinghouse representatives will make a presentation of the advanced PWR systems development ~ i under way at their company. l l i ENCLOSURE B 1

. n. $ E9 y! MRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT m :n Week of July 12 - 18, 1981 [@ i 3 ',]. Plant Status l Core Cooling Mode: Heat transfer from the reactor conf ant system (RCS)' ? l loops to Rasctor Building ambient, ~. y,@ i C--<,- cooling *8* (once through steam generator-8} tare Decay heat.removaT systems. Lone N.. Avatlable Core Cooling Modes: '['%w'j j .. de RCS Pres'sure Control Mode: Standby Pressure Control (SPC) System."";, ... J..J. l s u d. Backup Pressure Control hodes: MiniDecayHeatRemoveT(MDHR)Sysder. w . 6;U Decay Heat Removal (DNR) Systeen, ..: 6 Major Paramatars (as of 0600, July 16,1981) (approximate values)

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4 Average Incore Therencouples
120*F Maximum Incore Thermocouple: 144*F

. t. :e. ... w .;. g, l RCS. Loop Temperatures: A 8 Q, Hot Lag 119'F 122*F ..m. 1) 73*F 75*F '..T Cold Leg ((2) 1 74*F 74*F i RCS Pressure: 97 psig My ~ o Reactor Building: Temperature: 75'F ' .'ii Water level: Elevation 290.9 ft. (8.4 ft. from floor) . [.. via penetration 401 manometer g' j Pressure: -0.3 ps15 j Concentration: 9.3 x 10-5 uC1/m1 Kr-85 (Sample taken 7.wfN' 7/9/81 ) '.V g s. i Effluent an Environmental (Radt61ocical) Information .I.

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~ l ..,Q l 1. Liquid effluents from the WI site released to the. Susquehann'a River ' f;g;0 after processing, were made vi+' N the regulatory limits and in, JA,f. e accordance with NRC require x:;ts a i City of Lancaster Agreement ~ dated February 27. 1980. .mti During the period JuTy T0, ..3., through July 16,198T, the affluents contained no detectable radioactivity at the dise arse oeint and .= n 1 inatv1cual artiuent sources which originated within Onit 2 contained 1 no detectable radioactivity. 'Q d i .. ~ ' 1

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-t- .m es i a.p.y 2 l 2. Environmental Protection Agency (EPA) Environsenta1 Data. The EPA 988)R l j announced on July 6,1981 that, due to a new shipping procedure for -,g Kr-85 samples to the laboratory, the results for the.Kr.85 environ-E. l 4 mental monitoring stations around TNI will not always, be available { on a weekly basis. The NRC will report these results as they ;. - ;M i - *8tm?

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e h.ca= available. .1..wa, i r No radiation above nomally occurring background levels was mye ) detected in any of the samples collected from the EPA's air 'M l l and garmaa rate networks during the period from July 2,1981, .q4 through July 16, 1981. fiff ...w 3. NRC EnvironmentaT Data. Results from NRC monitoring of the environ-

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sent arouno the TMI site were as follows: 1 ag's s. .. w e The following are 'the NRC air Iample analytical results, for $f ~ ~ 4 the onsite continuous air sampler:- 25

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Cs 137 i Sample Period fuCi/cc) *-{uC1/cc) t.!,g 4 wasjli,,;,pl Hp,276 July 8,1981 - July 15,1981 'd.5 E-14 d.5 E-14 ~ 4 Licensee Radioactive ~.Matierial and. Radwaste Shipments.. . J,., .~ .. >e.- On Monday,, July 13,1981, a 40 ml Unit 2 reactor coolant ;.: - .T pg 4 sample was sent to Babcock and Wilcox (58W), Lynchburg,. ' ?

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Virginia. g, i On Tuesday, July 14,1981, a Unit 1 one liter Waste Eva'porator i I Condensate Storage Tank (WECST) composite sample was, sent to.'?. 3 i Teledyne Isotopes, Westwood, New Jersey. -.. c

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.~.. y.. On Tuesday, July I4,1981, a Unit i solidified precoat was. shipped to Chan-Nuclear Systems Incorporated, Barnwellit.i"-. ;. f. ~ U. South Carol-ina. 3-) '.' r,. - ~ i Ma.ior Activities; [ 1. Sutmerged Demineralizer Syster (SDS1 Processing of the firsth .3 r baten (approximately 50,000 galloas? of Reactor Coolant Bleed Tank M 1 (RCBT) water continued. As of 7:00 e.s., July 17, 1981, approximately r 32,300 gallons had been processed. The licensee expects to complete 9.$ l the processing cf this first batch during the week of July 19, 1981. Preliminary results indicated that casium 137 and strontium 90 I loadings os the zeolite-filled processing vessala, as of My 16,.1981, S[j; are: 180 curies Cs-137 and 84 curies.$r-90. The loadings am.. ? primarily on the number one vessel in the filter line-up, and . "S, represent greater than 99% removal of these radioactive materials from the process stream.

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i 1 I i . ~, 3 r.e.:c. i 'I ~ ' ',.,5 2. Containment Entry. The thirteenth reactor building containment entry is schedul.ed for July 23, 1981. The activittas planned p-during this entry include: ,;;j;.'

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at Maintenance of the closed circuit TV system, f m. ~.- Removal of crystalline and water sannies. ~ 4;/:j- ~ ..w. I f' Removal of core fTooding tank transducers.' f. Photographs of parts of the reactor fiuf d inake-up systas, l .v-Resurveying the north side of the reactor vesseT head and the~ i deep end of the refueling pool, Obtaining a 100 mi sample of water from the neutron shield ~? l X.. e. - tank. and Installation of a continuous air monitor and an area radiation -). monitor. 4 1 I i i ...., =. f - i,c i l ~ ":s t.r. .p .s... ..f.c ~,~.t,, .t: ;e

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~ 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending July 17, 1981 US/ Australian Bilateral Agreement On July 14-15, staff members met with representatives of the Australian government DOE and State to discuss Administrative Arrangements for implementing The Australians tabled a 15-page the US/ Australian Bilateral Agreement. l draft of the Administrative Arrangements for Implementing the US/ Australian This paper is being reviewed and problems are being Bilateral Agreement. The Administrative Arrangements will outline the type and frequency l resolved. i of reports that will be submitted between the U.S. and Australia, dealing with accounting for nuclear material of Australian origin. GE-Morris Operation The staff's safety evaluation report on the proposed license renewal of the GE-Morris Spent Fuel Storage Operation was issued on July 13, 1981, based on requirements of 10 CFR Part 72. An EIA on the proposed renewal-was issued earlier. A pre-hearing conference has been scheduled by the ASLB for August 6, 1981. Edlow International Company On July 15, 1981, representatives of the Fuel Cycle Division met with J. Edlow and B. Podhurst of Edlow International Company to discuss the needed content of a license application for storage of anriched uranium hexafluoride. Edlow International Company is planning to store enriched uranium hexafluoride at the site in East St. Louis which is already licensed under Part 40 for storage of natural uranium hexafluoride and uranium oxide. Kerr-McGee - West Chicago Site l A meeting was held with Kerr-McGee representatives on July 10, 1981 to discuss . if an environmental impact appraisal rather than an environmental impact l statement would be appropriate to support license renewal action for the West Chicago site. No conclusion was reached except that a second reeting on this subject will be needed after the staff has discussed the question with ELD. l i ENCLOSURE C j f .~

PLANNED MEETINGS - DIVISION OF SAFEGUARDS 1.

Subject:

United Nuclear Corporation to review Part 73 upgrade commitments Date: July 20-22,1981 Location: Montville, Connecticut Attendees: T. Collopy, R. Gustoafson, UNC B. Floyd, C. Emeigh (SGPL & SGML) E. Woltner, Reg. I 2.

Subject:

Implementation of the US/IAEA Agreement Date: July 20-22, 1981 Location: Oak Ridge, Tennessee Attendees: G. Sparks (SGMD) Representatives of NRC, DOE and Union Carbide l ABSENCES OF DIRECTOR'OR DEPUTY ~ DIRECTOR July 20 & 21: Robert F. Burnett ACTING: Don Kasun, SGPL Donald R. Chapell J i 1 ENCLOSURE C f

l Meetines - Division of Fuel Cycle and Material Safety 1.

Subject:

Congresswoman Schneider requested a briefing on the status of the decomissioning of the United Nuclear Facility at Wood River Junction, Rhode Island. Date/ Time: July 15 - 2:00 pm Location: Ms. Schneider's office Attendees: Ed Fay (OCA), Bill Cmw (FC), Congresswoman Schneider 2.

Subject:

To discuss if an environmental impact appraisal rather than an environmental impact statement would be appropriate to support license renewal action for the West Chicago site of Kerr-McGee. Date/ Time: July 16 - 2:00 pm Location: 9th floor conference room Attendees: R. E. Cunningham (FC), Bill Crow (FC), Bill Nixon (FC), l J. L. Rainey (President, Kerr-McGee Chemical Corp.) J. Charnoff ( Attorney) 3.

Subject:

Use of FSV-1 Cask for Poison Rods. Date/ Time: July 16 - 1:00 pm Location: Room 546, Willste Attendees: Richard Odegaarden (FC), Doug Murphy ( ANEFCO) 4

Subject:

Cobalt-60 problem at Neutmn Pmducts, Inc. (Technical Assistance to the State of Maryland) Date/ Time: July El l Location: Dickerson, MD Attendees: Ralph Wilde (FC), Jim Ashley (SP), Jim Berger (0RAU), Dick Brisson (State of MD), T. F. Carter (FC) 5.

Subject:

To discuss the disposition of waste at the United Nuclear Site, Wood River Junction, Rhode Island. Date/ Time: July 23 - 1:00 pm Location: Providence, Rhode Island Attendees: Bill Crow (FC), Representative fmm IE, Malcolm Grant and Dante Ionato (State of Rhode Island) 6.

Subject:

To discuss license renewal application for l Combustion Engineering. l Date/ Time: July 22 & 23 Location: 5th floor conference room (7/22), 8th floor conference room (7/23) Attendees: N. Ketzlach (FC), A. L. Soong (FC), J. Roth (IE, R:I), G. Bakevich, G. Johnstone and F. Pianki (Combustion Engineering) Absences of Director or Deputy Director Thomas F. Carter, Jr. - July 23 (afternoon) and July 24 ENCLOSURE C 3 t

Meetings - Division of Waste Management 1.

Subject:

Waste Management Program and Future Directions t Date/ Time: July 21 - 1:00 Location: Willste Building Attendees: R. D. Smith (WMLL), M. Dunklenan (WMLL). D. Jacobs (Evaluation Research Corporation) 2.

Subject:

Contract Meeting with Golder Associates Date/ Time: July 23 - all day Location: Willste Building i Attendees: Golder Associates; L. Hartung (nNHT), J. Greeves (WMHT), l P. Edgeworth (TACB) h l 1 i ENCI(Milor r I

t l-0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest i Week Ending July 17, 1981 i i 1 1. The following Preliminary Notifications were dispatched during the week: l i a. PNO-I-81-77 Limerick Generating Station, Unit 2 - Cooling Tower Problems i f b. PNO-I-81-78 Yankee Rowe - Radiation Exposure to Worker 2 c. PNO-I-81-79 Union Carbide Corporation, Medical Products Division - South Carolina Suspends Licensee Shipments of Radioactive Waste for Burial ~ l i l d. PNO-I-81-80 Beaver Valley Power Station, Unit 1 - Unscheduled Shutdown j to Repair Failed Pressurizer Relief Tank (PRT) Rupture Disk e. PNO-II-81-50 Surry Unit 1 - Auxiliary Feedwater Leak and Safety Injection f l 1 j f. PNO-II-81-51 McGuire Unit 1 - Reactor Coolant System Leak J g. PNO-III-81-63 Palisades - Ten Day Shutdown to Replace Reactor Coolant Piamp 1 Shaft Seal and Five CRDM Seals l i h. PNO-IV-81-17 Houston Lighting and Power Company, South Texas'. Project;' Units ' 1 & 2 - Update-Expansion of Previously Authorized ASME !felding-l

i. PNO-IV-81-18 Wolf Creek Generating Station - Injury of Perso'nnel Due to i

Explosion of Water Tank

j. PNO-IV-81-19 Arkansas Nuclear One, Unit 1 - Reactor Shutdown Due to Unidenti-fied Primary System Leakage Exceeding One Gallon Per Minute l

k. PNO-V-81-39 San Onofre Nuclear Generating Station, Unit No.1 - SONGS-1 Fire { in Diesel Generator No.1 Room 1. PNO-V-81-40 San Onofre Nuclear Generating Station Unit Nos. 2 and 3 - Steam Generator Feedwater Ring Collapsed During Testing j d ] Constructic i Worker Suffered Fatal Heart Attack { ] m. PNO-V-81-41 San Onofre Nuclear Generating Station, Unit Nos. 2 and 3 - j i n. PNO-TMI-81-15 Three Mile Island, Unit 2 - Initial Operation of the Submerged Demineralizer System (SDS) 2, The following IE Infonnation Notice was issued: a. IE Information Notice 81-20 " Test Failures of Electrical Penetration Assemblies", was issued on July 13, 1981, to all nuclear power reactor facilities holding an operating license or construction pennit. 4 I ENCLOSURE D ) i I!

0FFfCE OF NUCLEAR REGULATORY RESEARCH IMPORTANT EVENTS FOR THE WEEK ENDING JULY 17, 1981 A. Fue1~ Behavior Branch 1. NRU The second in reactor NRU LOCA heatup and clad ballooning test, MT-2, is scheduled for July 20-26. This test series uses a 32-rod cluster of full-length commercial enrichment fuel rods. A slow clad heatup rate and a rod fill gas pressure of 3 MPa (approximately 450 psi) were selected to compare the high a, high distortion clad behavior of nuclear heated rods with that of the MRBT electrically heated rods. The test assembly is in place at CRNL and pretest checkouts are on schedule. B. Experimental Procrams Branch 1. Semiscale The second test of the Natural Convection (NC) series was conducted on ,' July 0, 1981. This was an extensive experirent (it ended at approximately midnight) covering single phase, two-phase and reflux conditions. Fifty-two complete data sets, covering steady state and transition conditions, were obtained. The next test, S-NC-3 and portions of S-NC-5, is anticipated in two weeks. Preparation for the August Semiscale-LOFT Analysts Workshop and for the Semiscale Review Group Meeting have been initiated. A broad attendance representation is anticipated at the workshop, including vendors, PWR owners groups, national laboratories, utilities and individual organizations. 2. FLECHT SEASET During the test of the last 21 rod blocked bundle test, Westinghouse discovered a ralfuctioned turbine reter. A new meter has been installed and calibrated and testing has resumed. Because of this malfunction, there will be a one-week schedule delay, but no additional cost is expected. 3. Advanced Two-Phase Flow Instrumentation for Reactor Safety ORNL began to analyse the data from the Westinghouse dp reactor liquid level detector test at Semiscale. It is planned that the result will be issued 30 days after receiving the data via a letter report for each test. A final topical report will be issued at the end of the test series. 4. 2D/3D In an effort to improve the predictability and limits of the cost of the 2D/3D program, RES is proposing to the Gerrans and Japanese consideration of various cost-control measures such as the elimination of the Japanese Slab Core III test, reduction of Upper Plenum Test Facility (UPTF) test The scope and the reduction of NRC instruments and TRAC calculations. program managers, one from each country, will discuss these reasures in September and submit their recommendation to the Steering Committee, which will meet in December 1981, for a final decision. ENCLOSURE E I

2 The Germans have proposed holding a neeting to discuss the change of the UPTF fuel bundle design for 16 x 16 to 18 x 18 type. The new design will be closer to the new Westinghouse design of 17 x 17. However, the design change at this late stage will incur additional cost because of instrument redesign and additional tests and calculations. RES does not have additional funding to support this effort. Therefore, RES will present at a meeting later this month, the reasons why the design change cannot be accommodated at this time. 5. BHDT at ORNL The Blowdown Heat Transfer Program at Oak Ridge National Laboratory has completed the Experimental Data Report for the first THTF transient film boiling test. Additional steady state and transient film boiling and bundle uncovery data will be made available within the next two months. r C. Office of the Director 1. Member State Comments on Draft IAEA Safety Guide SG-S9, " Site Survey for Nuclear Power Plants" By letter dated July 10, 1981 from Joseph D. Lafleur, Jr. to Mr. Thoras R. Gabbert of the Department of State, Member State comments are being transmitted to the IAEA on draft safety guide, SG-59. We are recommending that SG-S9 be approved for IAEA publication and are also forwarding several technical comments concerning corrections and omissions. SG-59 contains general guidance on the first stage of the siting process for nuclear power plants - the site survey. The guide presents the organization and procedures for a site survey. The most common safety related site characteristics generally used in the site survey decision process are identified. The guide describes information to be collected for these safety related site characteristics and presents criteria for rejection of an area or a site. In the annexes to the guide, methodologies for site surveys, examples of detailed prosedures for some site characteristics, and the more important non-safety related site characteristics are identified. The description and methodology for conducting the site survey are consistent with current U.S. practice. Furtner, the general guidance provided in the document does not conflict with the U.S. review policy. l l l ENCLOSURE E I i

i i - i i j } Publications to be Issued in the Near Future 3

Title:

Safety Related Concrete Structures for Nuclear Power Plants (Other Than Concrete Reactor Vessel and Containment)(Reg. Guide 1.142, Rev.1) 1 Expected Issuance Date: September 1981 1

== Description:== The guide endorses ACI Standard 349(1976) with its 1979 supplement, with additions and exceptions. l

Contact:

H. Ashar 1 443-5860 j l l Publications Issued During the Week of July 13-17, 1981 Reg. Guide 1.136, Rev. 2 - Materials, Construction, and Testing of Concrete Containments (Articles CC-1000 -2000, and -4000 through -6000 of the " Code for Concrete Reactor Vessels and Containments") Withdrawal of Certain Regulatory Guides The following six regulatory guides are being withdrawn: ) Reg. Guide 1.10 - Mechanical (Cadweld) Splices in Reinforcing Bars of Category 1 Concrete Structures, Rev.1. January 1973 Reg. Guide 1.15 - Testing of Reinforcing Bars for Category I Concrete j Structures, Rev.1, December 1972 Reg. Guide 1.18 - Structural Acceptance Test for Concrete Primary Reactor Containments, Rev.1. December 1972 Reg. Guide 1.19 - Nondestructive Examination of Primary Containment Liner Welds, Rev.1, August 1972 Reg. Guide 1.55 - Concrete Placement in Category I Structures, June 1973 Reg. Guide 1.103 - Post-tensioned Prestressing Systems for Concrete Reactor Vessels and Containments, Rev.1, October 1976 The regulatory positions of the above guides are now considered to be covered i by one or more of the following national standards: ACI 359 (ASME Section III, Division 2), endorsed by Reg. Guide 1.136; ACI 349 endorsed by Reg. Guide 1.142; and ANSI N45.2.5 endorsed by Reg. Guide 1.94. euernessor e

OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING JULY 17, 1981 Palisades Nuclear Power Facility On July 14, 1981, the presiding Administrative Law Judge in this civil penalty proceeding issued a Memorandum and Order in which he 1) approved the settlement agreement between NRC and the licensee, which reduced the civil penalty to be levied from $450,000 to $225,000, and 2) terminated the proceeding. Diablo Canyon Nuclear Plant, Units 1 and 2 On July 17, 1981, the presiding ASLB issued a Partial Initial Decision in i which it authorized the Director, NRR, to issue a license permitting fuel load and low power testing up to five percent of rated power. Salem Nuclear Generating Station, Unit 1 On July 17, 1981, the Appeal Board issued a Decision (ALAB-650) in this i proceeding involving an application for spent fuel pool expansion. The Appeal Board affirmed the ASLB decision authorizing the amendment of the license to permit the spent fuel pool expansion. o ENCLOSURE F I

l i i i

  • i ITEMS OF INTEREST OFFICE OF INitRNAT10NAL PROGRAMS WEEK ENDING JULY 17, 1981 i

i Foreign Visits to NRC On Wednesday and Thursday Dr. Oscar Jimenez Reynaldo, one of the five counsellors recently appointed to the new Nuclear Safety Council (the new NRC in Spain), met with Chairman Paladino to discuss the Systematic Evaluation Program and other i nuclear matters. Dr. Reynaldo also met with Victor Stello, Director, IE, H. Denton, NRR Director, R. B. Minogue, Director, RES, J. D. Lafleur, Deputy Director, IP and W. Russell, NRR. 'i e e ,i i 1 ) i J l I ENCLOSURE G 9

4 i i ) 4 Foreign Reports l The following foreign reports were received at IP during July 13 -17. (For further infomation contact Eva Szent-Ivany, IP X27788) IP.) 1 From Canada: j AEC - Annual Report 1980-81** - Three Dimensional Kinetics Benchmark Problem in a j Heavy Water Reactor ** i j From Italy: y j Monitoring Procedures and Techniques Around Linear Accelerators ] Analytical Method for the Detemination of Plutonium-239 in i Tissue and Bone Samples of Mice J Hazards Evaluation and Radioprotection Relation Pertinent to the Activity of the Radiotoxicology Group of the Health Physics Laboratory of CNEN Tadiation Damage on DNA Molecules Radiation Protection l From Japan: l Annual Program of Safety Research on Nuclear Power Plants and Related Facilities (1981-1985) Summary Report of Incidents of Nuclear Power Plants in Japan (FY 1980) Annual Report of Operating Administration of Nuclear Power Plants (FY 1979 and FY 1980) NSC Monthly Report (Vol.4, No.1,1981) From Switzerland: Three Reports About Incidents at the Swiss Power Plants:** Beznau - July 2,1981 Gosgen - July 2,1981 i Muhleberg, June 22, 1980 From the U.K.: The Assessment of Weldnents in SA 533B Class 1 Steel Plate ** Crack Propagation Toughness of Structural Steels at Temperatures Above the Brittle-Ductile Transition Temperature ** Deleted from PDR copy.

    • Indicates the reports are in English.

ENCLOSURE G I

OFFICE OF MANAGEMENT R'O PROGRAM ANALYSIS Items of Interest WEEK ENDING JULY 17, 1981 NRC Shutdown Plan Completed draft of plan on how to close NRC in the event Congress does not appropriate funds for operation. Plan is in response to an OMB request and will circulate to Offices for comments. Expected completion, August 31. Backgrounders on Congressren for Chairman With the Regions and other Offices, prepared background papers for l Chairman's meetings with Senators Johnston, Cranston, Hatfield, and Representative Corcoran. I ENCLOSURE I l ~l i 4

1 ITEMS APPROVED BY THE COMMISSION - WEEK ENDING JULY 17, 1981 A. SECY-81-385 - APPROVAL OF PROPOSED LICENSE AND AMENDMENTS TO EXPORT LOW-ENRICHED URANIUM TO SPAIN (LICENSE N05. XSNM0844, XSNM01045, AND XSNM01645). Memo SECY to Dircks, dtd 7/15/81. This is to advise you that the Commission (with three Commissioners approving) has reviewed the subject' license amendments to Westinghouse Electric Corporation and General Electric Company. The Co= mission (with three Commissioners approving) has accepted your recommendation to amend the subject licenses to export to Spain an additional 2,774 kilograms of uranium, enriched to 3.2% U-235, in the form of fuel assemblies. i Commissioner Ahearne was not available to participate in this action. B. SECY-81-402 - PROPOSED LICENSE TO EXPORT NATURAL URANIUM TO THE REPUBLIC i 0F KOREA (XUO8520). Memo SECY to Dircks, dtd 7/17/81. This is to advise you that the Commissioners have reviewed the subject license to Edlow International Company. The Commission (with all Commissioners approving) has accepted your recommendation to export to the Republic of Korea 10,176 kilograms of natural uranium, in the form of U-308. In connection with his approval, Commissioner Bradford provided the following comment: "I would like to know when in the conversion process safeguards apply to this material." The Office of International Programs was informed of this action by telephone on July 16, 1981. It is requested that you provide a response to Commissioner Bradford's request to the Office of the Secretary by c.o.b. July 31, 1981. ENCLOSURE M i}}

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