ML20247G744

Weekly Info Rept for Wk Ending 890721

ML20247G744
Person / Time
Issue date:	07/25/1989
From:	Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
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WIR-890721, NUDOCS 8907280171
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'. July 25,.1989 For: The Commissioners From: James L. Blaha, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING JULY 21, 1989 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report. Contents' Enclosure Nuclear Reactor Regulation' .A Nuclear Material Safety and Safeguards .B Nuclear Regulatory Research C Analysis and Evaluation of Operational Data D Governmental &.Public Affairs E General Counsel F* . Administration G Information Resources Management H Controller I 4 Personnel J Small & Disadvantaged Business Utilization & Civil Rights K* Enforcement 'L Consolidation M* Regional Offices N Executive Director for Operations 0* Items Addressed by the Commission P Meeting Notices Q Proprietary or Other Sensitive Information (Not for R externaldistribution)

• No. input this week.

8907280171 890725 J s L. Blaha, Assistant for Operations NhKL TR t PDC fice of the Executive Director _for Operations

Contact:

O I %pf/ ] / James.L. Blaha, OEDO 492-1703' 9 \\ \\

t .c HIGHLIGHTS OF WEEKLY INFORMATION REPORT 1 WEEK ENDING JULY 21, 1989 l NRC Bulletin No. 89 02. " Stress Corrosion Cracking of High-Hardness Type 410 55 Internal Preloaded Bolting in Anchor Darling Ecdel 5350W Swing Chec( Valves or Valves of similar Design." will be issued on July 19. 1989. Sumary: This bulletin is prompted by events at Diablo Canyon, D.C. Cook and FitzPatrick where ASTM A193-B6 Type 410 stainless steel bolts were found to have cracked by stress corrosion cracking (SCC). The bulletin requests licensees to conduct a record review for Anchor Darling model S350W swing check valves or similar valves with internal preloaded bolting made of the above material. Disassembly and inspection of the subject valves are requested, if appropriate. Internal preloaded bolting susceptible to SCC requested to be replaced. Unusual Occurrence at Radiation Sterilizers. Inc. (RSI) Irradiator, Decatur. Georgia l 1 An unusual occurrence happened at the RSI irradiator in Decatur, Georgia, July 12, 1989. The cask used to transport Waste Encapsulation Storage Facility (WESF) capsules was being lifted from the pool when a brake malfunction occurred with the lifting crane. The main brake failed but a hand brake stopped the descent shortly after the cask re-entered the pool. DOE reported that there was no equipment damage, no personnel or equipment contamination, no airborne radioactivity, and no personnel injury resulting from this occurrence. To prevent recurrences, brake inspections will be performed daily before crane operations and will be documented and the results will be reviewed by the site quality assurance supervisor. Crane and cask handling operatiuns resumed July 17, 1989 following inspection and testing according to OSHA requirements. IAEA Transportation Safety Meeting RES staff participated as part of the U.S. delegation to an IAEA transportation safety meeting during the week of July 10, 1989. Participants developed recommendations for all 124 issues submitted by Member States on whether and how to modify IAEA Safety Series No. 6 " Regulations for the Safe Transport of Radioactive Material." Representatives from 18 Member States and 2 inter-national organizations participated in the meeting, including representatives from Czechoslovakia, the German Democratic Republic, Hungary, Poland, and the Union of Soviet Socialist Republics. l Meeting with Thermedics. Incorporated On July 18, 1989, SGTR staff met with a representative of Thermedics, Inc. to l discuss explosives detection technology under development by Thermedics for both the Federal Aviation Administration and the Department of State. This technology has the potential for detectirg plastic explosives. Thermedics is beginning production of a portable explosives detection unit using this technology, and has under development a portal-type unit. These units may have potential application at those nuclear sites that are required by NRC to perform explosives searches. I

s Office of Nuclear Reactor Regulation Items of Interest Week Ending July 21, 1989 ~ l NUMARC Staff Making Last-Minute Revisions to Industry Fitness-for-Duty Data Collection Form Tom Tipton of NUMARC (Nuclear fianagement and Resources OnJuly)19,1989, Council briefed NRR staff on last-minute revisions to their industry data j collection form covering fitness-for-duty program results. NUMARC intends to send the revised version to the DEDO (J. M. Taylor) within the week. It will supersede the version receivea from NUMARC on June 30, 1989. NRC Bulletin No. 89-02, " Stress Corrosion Cracking of High-rfardness Type 410 SS Internal Preloaded Bolting in Anchor Darling Model 5350W Swing Check Valves or Valves of Similar Design," will be issued on July 19, 1989. Summary: This bulletin is prompted by events at Diablo Canyon, D.C. Cook and FitzPatrick where ASTM A193-B5 Type 410 stainless steel bolts were found to have cracked by stress corrosion cracking (SCC). The bulletin requests licensees to conduct a record review for Anchor Darling model S350W swing check valves or similar valves with internal preloaded bolting trade of the above material. Disassembly and inspection of the subject valves are requested, if appropriate. Internal preloaded bolting susceptible to SCC requested to be replaced. Meeting With DOE on LLNL and'EPRI Seistaic Hazard Estimates At the request of DOE, NRR staff met with Jim Knight and other DOE staff on July 20, 1989, to discuss the use of LLNL and EPRI probabilistic seismic hazard curves. DOE is using these methodologies to generate seismic hazard curves at a number of their facilities, including the Savannah River Site, in different parts of the eastern United States. Topics discussed included the prcblems associated with the use of the mean vs the median, the large uncertainties and the use of both methodologies to arrive at robust conclusions. Specific approaches to seismic hazard and seismic risk (including the display of information) being considered by the NRC staff in NUREG-1150, IPEEE and the resolution of the Charleston Earthquake issue were also discussed. We were informed that Oak Ridge Laboratories has a contract with Risk Engineering to compare the EPRI and LLNL hazard estimates for that site. He requested a copy of that comparison when it becomes available. i i i

i m o Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending July 21, 1989 SAFEGUARDS Domestic NRC/ Federal Bureau of It.vestigation (FBI) Memorandum of Understanding (MOU) On July 19, 1989, NitSS and FBI representatives met to discuss the revised NRC/ FBI Memorandum of Understanding (MOU), and agreed to begin the concurrence q process within each agency. NMSS was advised that review and concurrence by j the FBI's legal office could require three months. j Neeting with Thermedics, Incorporated On July 18, 1989, SGTR staff met with a representative of Thermedics, Inc. to discuss explosives detection technology under development by Thermedics for both the Federal Aviation Administration and the Department of State. This technology has the potential for detectino plastic explosives. Thermedics is beginning production of a portable explosives detection unit using this technology, and has under development a portal-type unit. These units may have potential application at those nuclear sites that are required by NRC to perform explosives searches. Transportation Meeting on Shipment of Cesium Chloride Capsules On July 10, 1989, Transportation Branch staff met with Department of Energy (DOE) subcontractors to discuss the shipment of cesium (Cs-137) chloride czpsules from F.adiation Sterilizers Inc. facilities. Since it cannot be verified that the ccpsules qualify as "special form", they will be shipped in a specially-designed sealed canister placed within the Model 1500 shipping cask. An amendment to request shipment of the cesium chloride capsules in canisters, is expected in August 1989. Meeting on Combined Transport Shipoino Cask Transportation Branch staff met with the Department of OnJuly(13,)1989,and Nuclear Assurance Corporation (NAC) to discuss the NAC l Energy DOE Combined Transport Cask (CTC). The CTC is being designed under DOE contract i as a 100-ton rail / barge cask for shipments under the Nuclear Waste Policy Act. j It has a capacity of 52 boiling water reactor or 26 pressurized water reactor fuel assemblies. The meeting focused on the design of the cask lid and fuel basket. The cask lid, secured by 15 hydraulically controlled wedges which are part of the lid, will te tested using a full scale model. An application is expected in June 1991.. l l l l [ l JULY 21, 1989 ENCLOSURE B l l

4' -2. 'c. Meeting on Babcock & Wilcox BR-100 Shipping Cask 18, 1989, Transportation Branch staff met with the Department of On July (DOE) and Babcock & Wilcox (B&W) to discus the BR-100 shipping cask. Er, qy -The JR-100 is being designed under DOE contract as a 100 ton rail / barge cask for' shipments under the Nuclear Waste Policy Act. 'It has a capacity of 52 boiling water reactor fuel assemblies or 21 pressurized water reactor. Major issues discussed were the design and performance of the borated concrete neutron / thermal shield, the use of ceramic metallic plates for criticality control, and the design and performance of impact limiters. B&W also discussed plans for a testing program to provide data for material properties of cask components. An application is expected in March 1991. Plutonium Air Transport On July 14, 1989, the interim report entitled " Draft Criteria for Package Drop and Aircraft Crash Test," was provided to the Power Reactor and Nuclear Fuel DevelopmentCor) oration (PNC)ofJapaninaccordancewiththeagreementbetween NRC and PNC. T1e interim report describes the technical criteria for testing plutonium air transport packages to satisfy Public Law 100-203. HIGH-LEVEL WASTE MANAGEMENT Nevada Nuclear Waste Storage Investigation Audit Postponed .The U. S. Department of Energy (D0E) Yucca Mountain Project Office has postponed the quality assurance (QA) audit of Sandia National Laboratories (SNL) scheduled for July 19, 1989. SNL is responsible for repository systems development; data management; conceptual design of the repository; and system performance assessment. A recent QA surveillance revealed that some procedures for the activities to be -audited were missing and that the procedures in place had not'been properly implemented. DOE has not announced a new date for the audit. Quality Assurance Meeting with DOE On July 11, 1969, representatives of the U. S. Nuclear Regulatory Commission (NRC), the U. S. Department of Energy (DOE), and the State of Nevade held the bi-monthly quality assurance (QA) meeting. Discussion at the meeting focused on: 1) DOE'sscheduleupdatesforaudits;2)resultsofsurveillancesperformed by the Yucca Mountain Project Office; 3) NRC observations of the Lawrence Livermore National Laboratory (LLNL) audit; 4) DOE's assessment of the. status of open items remaining from the July 7, 1988 DOE /NRC QA meeting, and 5) HRC staff review comments on the QA program plans of the U. S. Geologic Survey (USGS),LLNLandSandiaNationalLaboratory(SNL). No major issues were identified. Suggested topics for future meetings included discussion of problematic areas, qualification of existing data, and issues related to prototype borehole. JULY 21, 1989 ENCLOSURE B

O - INDUSTRIAL AND MEDICAL NUCLEAR SAFETY Fuel Cycle Safety Site Visit to Virginia Power's_ Dry Spent Fuel Storage Installation Surry Site ) On July 13, 1989, members of the Fuel Cycle Safety Branch visited the Surry Power Station to observe transfer of a nodular cast iron CASTOR V dry spent i fuel storage cask from the Surry station fuel building to the storage area j on the site. The cask transfer and emplacement on the concrete pad proceeded smoothly, with no problems encountered. This is the eighth CASTOR V cask emplaced. Virginia Power expects to load and transfer four more CASTOR V 1 casks this fall. Materials Safety Generic Exemption for Well Loggers On July 17, 1989, the Director, Office of Nuclear Material Safety (and Safeguards, signed a generic exemption that affects well loggers i.e., those licensed pursuant to 10 CFR Part 39). The exemption allows licensees to use sealed sources for well logging that meet either the prototype testing criteria that are described in 10 CFR 39.41(a)(3) and are based on a 1977 national standard or alternative criteria that are described in the generic exemption and are based on a 1968 national standard. The generic exemption has been forwarded for publication in the Federal Register. The staff plans to mail well. logging licensees a copy of the Federal Register notice together with an explanatory letter and a list showing 7 he various sealed sources authorized on well logging licenses and their suitability for continued use. The Agreement States will be notified of this action end, where appropriate, asked to consider providing similar exemptions to their licensees. I I JULY 21, 1989 ENCLOSURE B

Office of Nuclear Regulatory Research Iterns of Interest Week Ending July 21, 1989 Prevention of Damage to Reactor Cores Rig of Safety Assessment (ROSA)-IV The Rig of Safety Assessment (ROSA)-IV held its 10th coordination meeting between the NRC and the Japan Atomic Energy Research Institute (JAERI) on June 26-28, 1989, at Tokai, Japan. The ROSA-IV is a cooperative prc, gram between NRC and JAERI. It enables the NRC to obtain experimental data to benchmarkthermal-hydraulicbest-estimate (BE) codes. These BE codes are used to aid in resolving licensing and safety issues related to Pressurized Water Reactor (PWR) plants with U-tube steam generators. The meeting was attended by representatives from JAERI, NRC, Idaho National Engineering Laboratory (INEL), and Los Alamos National Laboratory (LANL). The meeting commenced with a review of the status of the ROSA-IV program. TheLargeScaleTestFacility(LSTF)wasrefurbishedwithanewcore,and shakedown of the facility was completed in December 1988. Next, JAERI presented LSTF experiments on depressurization of PWR primary (using pressurizer power operated relief valve) and secondary systems (opening of secondary atmosphe-ic relief valve) which addressed the effectiveness of proposed accident management measures. JAERI presented future test plans for LSTF and TPTF. Future LSTF test categories identified were: SBLOCA transients, tests to assist in accident identification and management, and severe accident related tests. As urged by NRC/INEL during the last coordination meeting in December 1988, ROSA-IV will include tests for LSTF to address accident management measures as well as noncondensible gas and venting. The meeting was adjourned after a general discussion among the participants on future experiments planned for LSTF and TPTF. The next ROSA-IV coordination meeting will be held in November 1989, in Idaho Falls, Idaho. Resolving Safety Issues and Developing Regulations USI A-40, Seismic Design Criteria On July 13, 1989, the full ACRS Committee considered the final resolution of USI A-40, Seismic Design Criteria. (The staff had met with the appropriate ACRS Subcommittee on Extreme Extertial Phenomenon on June 22,1989.) The proposed resolution had been published for public comment in Jure 1988. The public comment received, including responses to specific questions on soil-structures interactions that were included in the Federal Register Notice, were used to revise the final resolution package. The final resolution will consist of revision to SRP Sections 2.5.2, 3.7.1, 3.7.2, and 3.7.3.- The ACRS has written a letter to the Commission endorsing the final resolution of { USI A-40 proposed by the staff. j JULY 21, 1989 ENCLOSURE C C--- _ - _ -- - )

9 2 IAEA Transportation Safety Meeting RES staff participated as part of the U.S. delegation to an IAEA transportation safety meeting during the week of July 10, 1989. Participants developed recommendations for all 124 issues submitted by Member States on whether and how to modify IAEA Safety Series No. 6 " Regulations for the Safe Transport of Radioactive Material." Representatives from 18 Member States and 2 inter-1 national organizations participated in the meeting, including representatives from Czechoslovakia, the German Democratic Republic, Hungary, Poland, and the i Union of Soviet Socialist Republics. Metric Conversion The Omnibus Trade and Competitiveness Act of 1988 required, among other things, that by the end of FY 1992 each Federal Agency must convert to the metric system in its business-related activities. A comittee was formed in March 1989 charged with responsibility to review NRC activities for possible conversion to the metric system, develop a proposed implementation plan and schedule of activities to be converted, advise on the responsibility for implementation, and consider periodic review of the metric conversion. The work of this comittee has been completed, and a final report delivered to the Director of RES for review. The report findings indicate that the offices of NRR, NMSS, AE0D, and RES are most affected by any form of metric conversion and that imediate conversion of all NRC activities in the near future is impractical. Instead, under the options discussed in the report, some gradual form of conversion seems preferable. The committee proposed that several actions be taken prior to development of final recommendations to be submitted to the Comission. These include: 1. Organizing a public workshop to solicit the coments of those outside NRC; 2. Submitting the comittee's report to the Regional Administrators for review, since there were no representatives from the regions on the Metrication Committee; 3. Organizing a meeting between DOE and NRC to discuss the Committee's findings as they affect high-level waste and advanced reactor activities; 4. Initiating an updating of the 1986 CIRRPC report on metric radiation units; and 5. Through GPA, arranging the for review of the committee's report by the Agreement States.

Contact:

2. Rosztoczy 492-3760 JULY 21, 1989 ENCLOSURE C

( - ?* - w: 3 p. o.7 OTHER ITEMS 1 Recently Issued Public6tioqs Reg. Guide 3.64, Calculation of Radon Flux Attenuation by Earthen Uranium Mill Tailings Covers, June 1989..

Contact:

G.Birchard(301)492-3864 Draft Div. 7 Reg. Guide, Fracture Toughness Criteria for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of Four Inches (0.1 m), Task DG-7001. Comments requested by September 22, 1989.

Contact:

W. E. Campbell, Jr. (301) 492-3806. l l, 1 i i l ~ JULY 21, 1989 ENCLOSURE C

4 Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending July 21, 1989 Division of Operationa Assessment The Incident Investigation Team training course is scheduled to begin July 25. Commissioner Curtiss will give the opening presentation on that date. 3 part of the preparation process for the Diagnostic Evaluation at Arkansas h;; clear One, the site visit by DEIIB and regional staff was completed on July 19-20. The first presentation of the recently revised Diagnostic and Therapeutic Nuclear Medicine Course (H-304) (formerly titled Medical Uses of Byproduct Material) was held July 10-14 in San Antonio, Texas. Presented by the University of Texas Health Sciences Center at San Antonio, the course topics included familiarization with facilities, equipment and instrumentation, a review of applicable codes and regulatory guides, clinical procedures, patient handling, training of personnel, quality assurance programs, misadministration, transportation and emergency procedures. The course also included hands-on experience for the students and a discussion of a typical medical facility inspection by NRC personnel. In addition to the contractor, NRC personnel from AE00, NMSS, and Region I provided instruction during the course. An Eddy Current Testing Course (E-307) was held July 10-14 in Niantic, Connecticut. The class was presented by Hellier Associates and Cramer and Lindell Engineers through a TTC task order. Attendees included personnel from Regions I and V, NRR, RES, and Canada. The course reviewed eddy current methodology, applicable codes and standards., eddy current applications and analysis tools and included laboratory demonstrations and hands-on student exercises. The Region I Materials and Processes Section Chief 'provided a review of the history of steam generator designs and problems and one of the students from RES provided the class with information on the findings of the Surry steam generator study. The first Cold Chemistry Course (H-106) was held at the TCC July 17-21. 1 Attendees included personnel from Regicns I, II, III and IV, NRR, and the Brookhaven National Laboratory. The course was conductea by Quantum Technology, Inc. Course topics included regulatory and operational bases for plant chemistry, procedures, required analyses, analytical methods, and chemistry techniques. The course also included an in-class, hands-on demonstration of a ion chromatography system and a field trip to the TVA Power Operations Training Center Chemistry Laboratory for demonstrations of analyses end equiptent. Division of Safety Programs On July 19, 1989 the NRC staff met with NURMARC and INP0 to discuss the staff's ) current activities to develop maintenance performance indicators. This meeting was in response to the Commission's direction (memorandum S. Chilk to V. Stello, COMLZ-65-21, June 26,1989, Item 4) regarding the proposed maintenance rulemaking. The staff is proceeding with development activities on an expedited schedule and JULY 21, 1989 ENCLOSURE D

this meeting was a first step in obtaining industry participation in the develop-i ment of a set of indicators to monitor the effects of ir.dustry's maintenance program improvements.- Preliminary Notifications The following Preliminary Notifications were issued during the past week, PHS-I-89-13, Peach Bottom Atomic Power Station (Units 2 and 3), Trespasser a. Arrested. b. PNO-I-89-54A,SyncorCorporation(DocketNo. 030-15125), Update on the June 28, 1989, Reported Loss of Radiopharmaceutical Vehicle. I c. PNO-I-89-58, Long Island Lighting Company (Shoreham Nuclear Power Station), Shoreham Defueling. d. PNO-I-89-59,BostonEdisonCompany(PilgrimNuclearPowerSthtion), Reactor Trip. PN0-II-89-54, Medical Delivery Services, Inc. (A General Licensee), Decayed e. TC-99M Generators Stolen. f. PNO-II-89-54A, Medical Delivery Services, Inc. (A General Licensee), Decayed TC-99M Generators Stolen - An update to PNO-II-89-54 issued on July 17, 1989. 9 PNO-II-89-55, Hidden Hollow Construction Co. (An Agreement State Licensee), Stolen Troxler Moisture Density Gauge. h. PNO-II-89-56, Keith Senars, Practicing Attorney (An Agreement State Licensee), Stolen Troxler Moisture Density Gauge. 1. PNO-III-89-45, D. Cohen & Sons Scrap tietal (Non-Licensee), Contaminated Ductwork at Scrapyard. I j. PH0-III-89-47, Commonwealth Edison Co. (Braidwood Units I & 2), Lighting l Causes Reactor Shutdown. k. PHO-IV-89-47, University of Nebraska (Nebraska Agreement State License). Explosion During a Chem Lab Experiment Involving a Corpound Tagged with l Carbon-14. ~ 1. PNO-IV-89-48, Houston Lighting & Power Company (South Texas Project, l l Unit 2), Shutdown Greater Than 48 Hours Because of kain Transformer Problem. PNO-V-89-43, Arizona Nuclear Power Project (Docket llos. 50-528, 50-529, m. and 50-530), Low Level Radioactivity Found in Cooling Tower Sludge. JULY 21, 1989 ENCLOSURE D w

~ Office of Governmental and Public Affairs Items of Interest Week Ending July 21, 1989 INTERNATIONAL PROGRAMS: Departure of French Nuclear Attache On Tuesday, Daniel Chavardez, Nuclear Attache of the Embassy of France, visited Chairman Carr, V. Stello and H. Denton to say farewell prior to his return to France. Mr. Chavardez will assume new duties as Director of International De alopment for Framatome. He was accompanied on his visit by his replacement, Bertrand de Galassus. Mr. de Galassus is coming from the French Atomic Energy Comission where his most recent position was Deputy Director of the International Affairs office. International Visitors On Tuesday (JAERI)yojiro Fuketa, Vice President, Japan Atomic Energy Research Dr. To Institute , accompanied by Mr. Hiromi Terada, JAERI's Washington representative, met with Chairman Carr, Commissioner Curti:s, E. Beckford, and Dr. Ross to discuss Japan's nuclear energy program. On Wednesday Dr. Michael L'Annunziata, Head of the Fellowships and Training Section of the Department of Technical Cooperation at the International Atomic Energy Agency, met with GPA and GPA/IP staff persons to inform them about the IAEA fellowship program end to discuss NRC's role in it. U.S./ Australia / Canada / nonproliferation Meetings From July 17 through July 20, t'he U.S., Australia and Canada held a series of trilateral and bilateral discussions at the State Department on nuclear nonproliferation issues. The meetings were led by Ambassador Kennedy. Exports / Import During the week ending July 21, 1989, three applications for export licenses were received from Mitsui & Company, Mitsubishi International Corporation, and Edlow International Company. Several licenses for export were issued to Edlow International Company, General Atomics, Imaging & Sensing Technology (2), MitsubishiInternationalCorporation(3). STATE, LOCAL AND INDIAN TRIBE PROGRAMS Unusual Occurrence at Radiation Sterilizers, Inc. (RSI) Irradiator, Decatur, Georgia An unusual occurrence happened at the RSI irradiator in Decatur, Georgia, July 12, 1989. The cask used to transport Waste Encapsulation Storage Facility (WESF) capsules was being lifted from the pool when a brake malfunction occurred with the lifting crane. The main brake failed but a hand brake stopped the descent shortly after the cask re-entered the pool. DOE l l 1 JULY 21, 1989 ENCLOSURE E ] l

l 1 2 4,. reported that there was no equipment damage, no personnel or equipment contamination, no airborne radioactivity, and no personnel injury resulting 1 from'this occurrence. To prevent recurrences, brake inspections will be i performed daily before crane operations and will be documented and the results will be reviewed by the site quality assurance supervisor. Crane and cask handling operations resumed July 17, 1989 following inspection and testing according to OSHA requirements. Radiation Sterilizers. Inc. (RSI) Monthly Meeting R. L. Woodruff, Region II State Agreements Officer, attended an RSI Capsule and Site Recovery Information monthly meeting on July 18, 1989 at the WESF facility in Richland, Washington. The meeting covered various regulatory items, including the recent crane incident in Decatur, Georgia. I Meeting with Ohio Officials Roland Lickus, Region III State Liaison Officer, met with James Williams, Chief of Staff of-the Ohio Disaster Services Agency and State Liaison Officer, and inembers of his staff on July 19, 1989 in Worthington, Ohio. The purpose of the meeting (was to begin discussions on an umbrella memorandum ofMOU) with understanding the States..This MOU is intended to provide a basis for subsequent detailed subagreements between the NRC and Ohio. Northeast LLW Compact Financial Assurance Workshop The Northeast Interstate Low-Level Radioactive Waste Commission sponsored a workshop on July 19, 1989 in Stanford, Connecticut, to provide an overview of financial assurance requirements and to discuss traditional and alternative insurance. Highlights of the discussion included'the announcement by American Nuclear Insurers (ANI) to resume coverage of third party damage claims resulting from new low-level radioactive waste disposal facilities after January 1990 and the clarification that non-nuclear fuel c/cle radioactive material would be covered by conventional insurance because it is not captured under the nuclear exclusion exemption. Neutran Products. Inc. Administrative Hearing John McGrath, Region I State Agreements Officer, John White and Ron Nimitz, Region I, testified at an administrative hearing on Neutron Products, Inc. which was held on July 20-21, 1989 in Baltimore, Maryland. The hearing was requested by the licensee as a result of a license amendment issued by the State of Maryland which temporarily suspended operation; at Neutron Products in Dickerson, Maryland. 1 i l l JULY 21, 1989 ENCLOSURE E

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l. \\ Office of Administration Items of. Interest i l Week Ending July 21, 1989 Credit Checks Division of Security on-line computer capability to access nation-wide credit information through Trans Union Credit Reporting Serv'ces has been implemented and is fully operational. Credit checks will now be conducted as part of the 145b process. 4 NRC Acquisition Regulations The'NRC Acquisition Regulations have been submitted in draft to OMB for comment. Significant FOIA Requests Received by the NRC for 5-Day Period July 14 - 20, 1989 Request for 24 categories of records regarding the shutdown of the Seabrook nuclear power plant on June 22, 1989, or the cessation or suspension of low power operation. (Matthew Brock, The Commonwealth of Massachusetts, F01A-89-309) Request for all records on the content of the June 23, 1989 telephone conversation between Edward Brown of the iicensee and Thomas Martin of the NRC regarding the Seabrook nuclear power plant. (Michael Mokrzycki, Associated Press,F01A-89-313) Request for records en contents of communications on June 22-23, 1989, between Region I and utility officials. (Michael Mokrzycki, Associated Press, F01A-89-314) Request for copies of three recoros identified in enclosure 3 to the minutes of CRGR meeting No.157 held February 8,1989. (Darlene Calandra of Bishop, Cook, Purcell & Reynolds, F01A-89-317) Recuest for a copy of the report entitled, " Quarterly Report on Status of Contaminated Sites." (Robert Burgin, Nuclear Energy Services, F01A-89-320) I l JULY 21, 1989 ENCLOSURE G

3 i Office of Information Resources Management l Items of Interest Week Ending July 21, 1989 1. Federal Register Notices and Comments Tracking System The Federal Register Notices and Comments Tracking System is in production, j A formal user's guice is being prepared by the Office of Information ResourcesManagement(IRM). In the meantime, the users have been provided with materials to enable them to use the system. 2. Agency Training System Several training sessions were held for the Agency Training System (ATS) on July 17-20, 1989. An additional $5,000 will be added to the Mathtech, Inc, contract, ar.d the period of performance is being extended through August 16, 1989. This will enabic Mathtech to provide orientation for Applied Management Systems, the maintenance contractor scheduled to take over the system. l 3. OMB Negotiations Gain LER Form Approval The Office of Management and Budget (OMB) approved the extension of the informatiur, collection requirements contained in the NRC Form 366, LicenseeEventReport(LER). However, OMB questioned one element of the I 1 form pertainine to the requirement to submit an LER at the time of a ncr, routine shutdown of e r.uclear power plant. The 5,000 hours of burden associated with this submittal was denied. Conversations between IRM and the OMB Desk Officer have resulted in OMB restoring the 5,000 hours of burden and agreeing that the LER submittal is required. 4. Files Maintenance and Records Disposition Workshops The fourth of five planned Files Maintenance and Records Disposition Workshops was conducted at NRC cn July 19-20, 1989 by the Washington 1 National Records Center staff. The workshop was attended by 22 records liaison officers, file custodians, and secretaries. The final wor kshop will be conducted on August 23-24, 1989. I i l l JULY 21, 1989 ENCLOSURE H

w;.< ) Office of the Controller Items of Interest Week Ending July 21, 1989 1.- FY 1990 Appropriations Bill On Thursday, July 20, 1989, the Senate Appropriations Subcommittee on Energy and Water Development met to markup the FY 1990 Appropriations Bill (H.R. 2696) passed by, the House of Representatives. The Subcommittee made no changes to H.R. 2696 that affect NRC. Thus, NRC's FY 1990 budget request of $475 million continues to be reduced by $30 million. The full Appropriations Conmiittee is expected to meetL next week. 2. Relocation Allowances for Separating SES'ers 'GSA issued an interim regulation on July 14, 1989, implementing legis-lation authorizing limited relocation allowances for a "last move home" for career SES'ers who are separated on or after September 22, 1988, for purposes of retirement, and who have been reassigned geographically in the' interest of the Government within the 5-year period immediately preceding retirement. Appropriate revision to Manual Chapter 1501 will be made. 3. Shoreham Part 171 Exemption Request .i I A response' to long Island Lighting Company's request for exemption of Shoreham Nuclear Power Plant from Part 171 fees has been forwarded to the l ED0 for signature. l l l JULY 21,,1989 ENCLOSURE I

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• 1 Office of Personnel Items of Interest Week Ending July 21, 1989 The ITS Training Laboratory moved to the third floor of the Woodmont Building to be a part.of NRC space. Classes at the new site begin July 24, 1989. The Laboratory has a new mail stop,.W-306; phone numbers remain unchanged.

" Arrivals The following employees reported this week:- LorenDonate11,ProjectManager(PFT),NRR Jose-Cortez,Sr.Res.ProgramCoordinator(PFT),RES Departures None l l .I l' l L l-l ' JULY 21, 1989-ENCLOSURE J

I { ) Office of Enforcement Items of Interest I Week Ending July 21, 1989 Significant Enforcement Action A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $500 was issued on July 19, 1989 to Bucks Diagnostic Center, Levittown, j Pennsylvania. The action was based on nine violations that, in aggregate, were considered to represent a lack of proper management atteation to license responsibilities. The violations were identified by NRC approximately six months after operations began. (EN 89-69) A Notice of Viol 6 tion and Proposed Imposition of Civil Penalty in the amount of $75,000 was issued on July 20, 1989 to Illinois Power Company (Clinton). u The action was based on the failure to take adequate corrective actions for environmental qualification deficiencies for which an earlier civil penalty was assessed (EA 88-90) and for additional environmental qualification deficiencies subsequently discovered. The escalation and mitigation facters of the Enforcement Policy were considered and 50% mitigatien for the licensee's identification of the deficiencies und corrective action was found to be appropriate for the civil penalty for the corrective action problem. (EN89-70) Civil Penalty Paid s Power Authority of New York (Indian Point 3) paid the civil penalty in the amount of $25,000. The action was based on the actual entry into the Protected Area of an individual who had been terminated for cause three days earlier. (EA89-075) l l I JULY 21, 1989 ENCLOSURE L

~ Region I Items of. Interest Week Ending July.21,1989 -1.. MEETINGS HELD BETWEEN NRC AND FEMA On Wednesday, July-19, 1989, Dr. Malcolm R. Knapp, Director, Division of Radiation Safety and Safeguards, and Dr. Ronald R. Bellamy, Chief,

Facilities Radiological Safety and Safeguards Branch, met with Mr. Philip McIntyre, Acting Director, FEM, Region II at the FEMA-Regional Office in New York City. On 1hursday, July 20, 1989, Dr. Bellamy and Mr. William Lazarus, Chief, Emergency Preparedness Section, met with the Chairmen of the Regional Assistance Committees for FEMA I, II, and III in-New York City.. Both discussions will cover the evaluation of recent emergency preparedness exercises for power reactors in NRC Region I.

1 2. ' LOSS OF'RADI0 PHARMACEUTICAL VEHICLE WITH SUBSE00ENT LOSS OF RADI0 ACTIVELY. LABELED MATERIAL On June 28, 1989, Syncor, Inc., reported that a radiopharmaceutical delivery vehicle and its. driver were missing. The driver later was found and claimed to be assaulted and robbed. At the time of this report, no radioactive material appeared to be missing. On July 16, the Philadelphia Firo Department reported that a box with radioisotopes was found hit by a car on a city street. Radiation surveys by the Fire Department found no - measurable radioactivity. A Regional Senior Health Physicist responded to the scene, but arrived after the recovery. The material was recovered by Syncor, determined not to be radioactive,:and found to be a return-shipment of unused diagnostic unit doses of thallium-201 and technetium-99M from the missing vehicle. The vehicle has not yet been found. 3. MILLSTONE-The inspection team looking into allegations raised by 180 technicians at Millstone had an exit meeting with the licensee at 10:00 a.m. on Friday, July 21. The team will meet in the Region I office next week to review the inspection findings to date und further inspections at the site may be conducted the week of August 1. 4. PILGRIM _ An INFO Team is on site for the second and final week of their evaluation. I Dr. T. Murley visited the site on Monday July 17, 1989 to meet with the residents and tour the plant. Mr. S4 Collins, Deputy Director, Division of Rt. actor Projects, Region I accompanied Dr. Murley. The NRC restart staff is presently in extended shift coverage and will continue to monitor the licensee's performance. JULY 21, 1989 ENCLOSURE N i

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CALVERT CLIFFS UNITS 1 AND 2 Commissioner Rogers toured the Calvert Cliff s facility on 7/18/89. Mr. William Russell, Regional Administrator, accompanied the ~ Commissioner on the tour. 6. HADDAM NECK The Deputy Regional Administrator toured and iret with senior site representatives at Haddam Neck on July 18, 1989. The purpo;e of the visit was to review site familiarity, observe housekeeping and professionalism, hold discussions with the NRC resident staff, and seek I feedback from licensee management. 7. NINE MILE POINT UNIT 1 On July 18, 1989, Region I issued Inspection Report No. 50-220/89-16, which discussed the results of a special team's review of additional technical and fitness for duty allegations raised by Mr. D. Ellison in 1988. i JULY 21, 1989 ENCLOSURE N

~ Region II Items of Interest Week Ending July 21, 1989 1. Management Meeting Held Regarding Turkey Point On July 17, 1989, Region II and Headquarters renagement toured Florida Power and Light Corporate Headquarters at Juno Beach and met with cor-porate management to review selected corporate nuclear facility support functions. 2. St. Lucie SALP Meeting On July 18, 1989, Region II presented the St. Lucie SALP. Region II and Headquarters management toured the facility. 3. FPL Management Meeting On July 19, 1989, a management meeting between NRC and FPL was held at the Turkey Point site and concluded with a site tour. On July 14,1989, INP0 notified FPL management thnt based on their recent assessment, Turkey Point will be given a rating of Level 4. INPO had previously rated Turkey Point at a Level 3. Unit 4 was brought off line on July 17, 1989, due to low flow in the ICW system. They went to Mode 4 and began repairs. The repairs were com-pleted and they declared the system operable at 7:00 p.m. on July 20, 1989, and entered Mode 3 at 3:00 a m. on July 21, 1989. They plan to be critical sometime this afternoon and be on the grid late evening or early morning July 22. Turkey Point Unit 3 continues to operate at 100 percent. 4 Enforcement Conference With Duke Power Company I On July 20, representatives of the Duke Power Company were in the Region II Office to attend an Enforcement Conference regarding the inoperability of the reactor vessel level instrumentation system at thcir Catawba facility. 5. North Anna Power Station On July 20, 1989, Commissior,er Rogers visited VEPC0's North Anna facility for site familiarization. 6. RSI Facility Cask Drop During GE600 cask handling operations on 7/12/89, a cable brake malfunc-tion occurred allowing the suspended cask to drop nineteen (19) feet into the irradiator pool. The cask dropped to a depth of five (5) feet below the surface of the pool before an operator arrested the drop by use of a C JULY 21, 1989 ENCLOSURE N

f .? 2 manual brake. There was no damage to facility equipment, no. injuries, and no equipment or personnel contamination. No source racks were below the rask.- Corrective action includes a' daily check of the cable, a_djustment ' of the cable as necessary, 150 percent load test daily, and documentation'- of'both. The corrective action was approved by both the crane manufac-turer and Westinghouse representatives. 7. Stolen Moisture Density Gauces l Troxler moisture density gauges, each containing Cesium and Americium /- Beryillium sources, were stolen from job sites in Grant County, Kentucky and Dade County, Florida, on July 16, 1989, and July 18, 1989, respec-tively. In both cases, the appropriate State agencies and law enforcemtu j organizations investigated these incidents, and press releases were issued. To date, neither of the gauges have been recovered. ) 8. Minor Transportation. Incident-On July 15, 1989,'a carton containing Chromium-51 was inadvertently l crushed by a Federal Express (An Agreement State Licensee) forklift operator on company-leased property at the airport in Memphis, Tennessee, resulting in some minor contamination of the asphalt. A consultant was brought in to clean up and recover from this incident. The State per-formed a confirmatory survey cn July 17, 1989. 9. _V_irginia Electric and Power Company (VEPCO) Management Meeting On July 20, 1989, a management meeting was held to dit, cuss Surry's Unit 2 status and proposed reduction in the scope of Operational Readiness Assurance Program. Additionally, the licensee discussed the technical aspects of a proposed modification to increase service water flow to the control room chillers. D_ecayed Tc-99m Generators Stolen 10. e Florida, an Agreement State, notified the Region II Office that a vehicle owned by Medical Delivery Services, Inc., Miami, Florida was broken into on Sunday night, July 16, 1989, and two each Molybdemun-99/ Technetium-99 generators were taken from the vehicle, along with the shipping papers and a briefcase. The used generators had been decayed to approximately 0.09. curies and 0.01 curies, respectively. The incident is under investi-gation by local policy, and the Florida Radiation Control Program. i i l i 1 I i l 1 JULY 21, 1989 ENCLOSURE N i }

l n. -- i i 'e.r. Region III i Items of Interest Week Ending July 21, 1989

1. -

Zion Nuclear Power Station ] u On July 21, 1989, the Regional Administrator and the Director, Division (, of Reactor Projects met with the NRC resident staff at the Zion site to discuss NRC policy and Region III expectations. i 2. Regicn III Management Retreat 'The Regional Administrator met on July 20, 1989 with senior Region III staff. The management retreat was a full day meeting held in the vincinity_of the Region-III office. 3. Palisades Nuclear Generating Station On July 19, 1989, the licensee determined, during a containment pressure transmitter calibration test, that a one-quarter inch test valve in a one-half inch line for containment penetration No. 48 was leaking slightly. -This test valve is the nearest valve to the containment penetration and is not a designated containment isolation valve; the isolation valves are located downstream in series with the test valve. Corrective action to repair the valve revealed that in addition to the valve leaking, the line between the test valve and the downstream inboard isolation valve was never tested with regard to withstanding containment designpressure(55 psi). Additionally, there are three cther lines which extend-though penetration 48 with a similar configuration _and four other lines in another penetration that also have not been tested. Generic Letter 8709 allows a 24 hour period to test the lines before the. Limiting Condition for Operation (LCO) takes effect. Due to the number of untested lines, Technical Specification 3.0.3 was determined to be the most applicable in this case, providing a one hour LCO. As corrective action, the licensee wrote a procedure to test the untested lines. However, the-testing of these lines will exceed the the 24 hour grace period plus the one hour LCO. To prevent an unnecess6ry plant shutdown, and to allow continued testing, the licensee requested enforcement discretion from RIII. On July 20, 1989 at approximately 2:00 p. m., the licensee was granted verbal enforcement discretion for a period of 12 hours, with a written report to follow within 24 hours. At the time of the granting of enforcement discretion, 5 of the 8 lines had been tested satisfactorily. 4. Braidwood Nuclear Power Station. Units 1 and 2 On July 18, 1989, Units 1 and 2 were both automatically shut down due to lightning strikes on each unit, six minutes apart, resulting in the loss of power to the rod control systems. The subsequent negative flux trip signals tripped both units. The power supplies were reset and the plants restarted. JULY.21, 1989 ENCLOSURE N

N' d' L H 1 u / a. l l 5. St. Joseph's Hospital On July 18, 1989, the Regional Administrator and other members of the L regional staff held an enforcement confererice with St. Joseph's~ management staff to discuss numerous violations and concerns found during a recent l inspection of the licensee's nuclear medicine and radiation therapy prograra. 6. Perry Nuclear Power Plant L The Director, Division of Reactor Projects and his staff met with Cleveland Electric Illuminating Company cor) orate ranagement to discuss recent plant performance. The meeting was 1 eld at the Perry site on July 17, 1989. 7. D. Cohen and Sons Scrap Hetal On July 14-17, 1989, Region III and State of Ohio staff responded to a report of a truckload of scrap metal being contaminated with radioactive material. The contaminated metal was detected via a radiation monitor in a junk yard in Pennsylvania and, subsequently, transported back to its origin, D. Cohen and Sons in Cleveland, Ohio. The contamination is from stainless steel ductwork containing removable accelerator-produced radionuclides under the State of Ohio authority. Staff at the Perry ^ Nuclear Power Station assisted Region III in deterinining the type of radionuclides in the contamination. Regicn III continues to assist the State of Ohio. I -l i i i JULY 21, 1989 ENCLOSURE N l i

s ,s. [, 1 Region IV Items of Interest Week Ending July 21, 1989 1. South Tex g Project, Unit 2 L L On Jet 9 89, South Texas Project, Unit 2 (STP-2), tripped from IG actor power after a failure of one of the two STP-2 main tr.n. uised a transformer lockout and subsequent reactor trip. See is w8, dated July 14, 1989. STP-2 has the capability to operate a. A percent of rated electrical output (approximately 625 megawatts electric) with the undamaged main transformer. Houston Lighting & Power Company (HL&P) completed its recovery efforts earlier this morning. An "A" phase fault to ground was identified as the cause of the transformer failure. STP-2 is in Mode 1 (4 percent reactor power) while HL&P continues its investigation. A Region IV electrical specialist will be cnsite today to inspect the faulted transformer. South Texas Project, Unit 2 (STP-2) is currently operating at approximately 65 percent reactor power because of the failure of one of its two main transformers on July 13, 1989. The undamaged transformer is limited to 20,000 amps. Houston Lighting & Power Company (HL&P) is arranging to replace the damaged transformer, manufactured by McGraw-Edison, with a compatible transformer manufactured by Westinghouse. The replacement transformer was intended for a City of San Antonio fossil fuel plant and is scheduled for delivery from Westinghouse in September 1989. In the interim HL&P plans to move one of the two South Texas Project, Unit 1 (STP-1), main transformers to STP-2 after STP-1, which is currently operating at 100 percent reactor power, shuts down for a 55-day refueling outage on August 4,1989. HL&P estimates 1 week for the move. The damaged STP-2 transformer will be returned to the i manufacturer for refurbishing and return to the South Texas Project site as a spare sometime in the first quarter of 1990. South Texas Project, Unit 1 (STP-1), was unaffected by the STP-2 main i transformer failure and continues to operate at 100 percent reactor power. STP-1 is scheduled to begin a 55-day refueling outage on August 4, 1989. i i 2. Louisiana Power & Light Company Waterford 3 was returned to power operation on July 17, 1989, following a l manual reactor trip on July 15, 1989. The manual reactor trip was i i initiated because of problems with control of Steam Generator No. I water level. The level control problem occurred when the main feedwater regulating valves went closed from an unknown cause. Subsequent investigation by the licensee revealed a failed card in a feedwater regulating valve controller which caused the initial closure of the i feedwater regulating valves. The failed card was replaced and other routine maintenance items were completed prior to unit restart on July 17, 1989. JULY 21, 1989 ENCLOSURE N

h4,T . [. 3. Sequoyah Fuels Corporation The NRC staff recently. completed a team operational safety assessment at Sequoyah Fuels Corporation's (SFC) Gore, Oklahoma' uranium conversion facility. The assessment was performed the week of July 10-14, 1989. The team included re)resentatives from RIV, Headquarters, and the Occupational Safety and Healti Administration. The assessment included a review of management organization and controls in light of the recent transfer of control of STC from Kerr McGee to General Atomics. The assessment team concluded that the new organizational structure at the site reflects a commitment to safe operation of the Gore facility. Minor recommendations for. improvement in areas of operational safety will be included in the . forthcoming team assessment report. l l t-1 JULY 21, 1989 ENCLOSURE N

.. ~ e- [ ,g a b.}s - Region V Items of Interest Week Ending July 21, 1989 1. Palo Verde Nuclear Generating Station Unit 2 On Friday, July 14, the licensee informed the Senior Resident Inspector that small amounts of radioactivity had been found in the sludge of the i Unit 1 cooling towers. Levels'59 to 1250 times less than the water.- concentrations allowed for unrestricted release were identified. Subse-quently, the licensee identified similar concentrations in the. cooling tower sludge at Unit 3., Samples showed no detectable contamination in Unit 2 cooling tower sludge. ) L 1 The licensee has previously removed cooli.ng tower sludge to a state-licensed sanitary landfill on licensee-controlled property, outside the protected area..The licensee is working to resolve the regulatory issues involved with the Arizona Department of Environmental Quality, which licenses the landfill; the Arizona Radiation Regulatory Agency, which would have to license any low-level radioactive waste disposal site in l Arizona outside~the plant protected area; and Region V. ~2. Medical Licensees Conference On July 19, 1989, Region V completed a two day conference for medical licensees. Hugh Thompson and John B. Martin began the conference with presentations on the NRC medical regulatory programs. The conference, held in Oakland, California, was attended by approximately 100 physicians, physicists and. technologists. NRC and licensee speakers addressed many topics including quality assurance, misadministration, decommissioning, radiation safety management and NRC enforcement policy. 3. U. S. Testing Company On ' July. 20,1989, Region V staff conducted an enforcement conference with the United States Testing Company. Apparent violations related to indus-trial radiographic activities at a field job site were discussed in detail. JULY 21, 1989 ENCLOSURE N j

ITEMS ADDRESSED BY THE COMMISSION - Week Ending July 21, 1989 1 A. STAFF REQUIREMENTS - BRIEFING ON POLICY STATEMENT ON RULES FOR EXEMPTION FROM REGULATORY CONTROL, 1:30 P.M., TUESDAY, JULY ll, 1989, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) - SECY to Memorandum for the Record dated 7/18/89 The Commission was briefed by the staff on a proposed policy state. ment on public use of radioactive materials whose activity is sufficiently low that it does not warrant expenditure of Commission resources for stringent control. There were no requirements placed on the staff at this meeting. B. STAFF REQUIREMENTS - BRIEFING ON STAFF COMMENTS ON DOE SITE CHARACTERI-ZATION PLAN FOR YUCCA MOUN H TN, 10:00 A.M., TUESDAY, JULY 11, 1989, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVI.LLE MARYLAND (OPEN TO PUBLIC ATTENDANCE) - SECY to H. Thompson, DEDR,and D. Moeller, C/ACNW dated 7/21/89_ The Commission was briefed by the staff and the Chairman of the Advisory Committee on Nuclear Waste (ACNW) on staff's review of I the Department of Energy's Site Characterization Plan for the nation's high level nuclear waste repository at Yucca Mountain, Nevada. The Commission: 1. Commended the staff for the thoroughness of the review in light of tight time schedules. 2. Supported staff's high priority rulemaking activities en substantially complete containment, performance assess-ment, and disturbed zone, which are scheduled for completion in 1992. 3. Shared staff's concern that DOE's schedular objectives and substantial schedule slippage in the front-end work of the site characterization program may be affecting the integration of necessary technical information gathering activities and may potentially affect DOE's projected 1995 application and 2003 operation dates for the repository. 4. Encouraged staff's continued effort to concentrate its comments to DOE on the important issues. 5. Endorsed staff's efforts to encourage DOE to give highest priority early in the site characterization process to those investigations which may lead to identification of potentially disqualifying conditions. 6. Encouraged the staff to continue its frequent dialogue with DOE, states, and Indian tribes to ensure fruitful, timely and constructive progress. JULY 21, 1989 ENCLOSURE P

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7. Requested that the ACNW letter of July.3, 1989, "ACNW Review.of NRC Comments on DOE Site Characterization Plan," be clarified to show in which way, if any, the gommittee's comments differ from those of the staff. The staff informed the Commission that'it intends to submit an information paper discussing the background and application of performance assessment in demonstrating compliance with the EPA high level waste standard. l i JULY 21, 1989 ENCLOSURE P

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