ML20245K478

Weekly Info Rept for Wk Ending 890623

ML20245K478
Person / Time
Issue date:	06/29/1989
From:	Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
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WIR-890623, NUDOCS 8907050139
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S ForPDR 4

June 29, 1989 For: The Commissioners From: ' James L. Blaha, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 23, 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 Haterial Shfety 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 Personnel J Small & Disadvantaged Business Utilization & Civil Rights K*

Enforcement- L Consolidation H Regional Offices N Executive Director for Operations 0*

Items Addressed by the Comission P Meeting Notices Q Proprietary or Other Sensitive Information (Not for R externaldistribution)

• No input this week.

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$ f0$$kk $0h29 J mes L. Blaha, Assistant for Operations WEEKLYINFDREPT PNU 'fice of the Executive Director for Operations

-Contact: q James L. Blaha, OEDO

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HlGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING JUNE 23, 1989 Millstone Unit 3 i

On June 21, 1989, with the plant in a refueling outage, a fire ignited and l burned for approximately 13 minutes inside containment. At the time that the firestarted,thereactorvesselheadwasinstalledandtensioned(Mode 5),

and the refueling cavity seal ring was being lifted. The fire occurred in a a temporary fan that had been installed to cool the polar crane resistor bank on j the crane bridge. No damage to the resistor bank or crane appears to have 6 occurred. The fire interrupted the seal ring lift in such a way as to suspend the seal ring over the reactor vessel head approximately 35 feet above the refueling cavity floor. With power removed from the polar crane, the brakes are set and the use of a triple suspension system makes a load drop a remote threat. It is expected that the plant safety cosmittees will approve the restoration of power to the crane on June 21 to allow completion of the seal 3 lift ring.

Limerick Unit 2 Limerick, Unit 2 was granted a fuel loading and arecriticality testing operating license on Thursday, June 22, 1989. T1e license authorizes fuel ,

loading and certain Startup Tests that can be performed within the "no i i

criticality" restriction. The licensee expects to begin fuel loading on friday, June 23, 1989; the current schedule calls for a need for the low power I license during the period July 74 and August 1,1989. )

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Turkey Point Drug Testing Extensive drug screening effort was initiated on June 16, 1989 in response to the FBI arrest of one (non-nuclear) Turkey Point employee for drug l distribution. The testing started with management, supervisors, and licensed individuals and working through to contractors. As of 6:00 p.m.

June 22, 1989, the licensee had tested 915 employees, and had received 456 test results from the preliminary tests. While no confirmed results have been " positive," the initial onsite screen has caused 7 samples to be referred to the offsite laboratory for confirmatory testing. One mid-level supervisor has refused the test and has been suspended. Miami, Florida, and local media coverage has been extensive and is expected over the weekend. FBI investigation is continuing. The State of Florida Attorney General has also shown interest in criminal investigation.

AsofthemorningofJune23,UnitNo.3wasinMode3(restarting)and Unit No. 4 was at 50 percent power. Region II is maintaining very close >

cognizance of FBI and licensee efforts.

PHASE I 0F AECB LEUKEMIA STUDY The first phase of an independent study of the occurrence of leukemia in children near Canadian nuclear facilities has been conducted on behalf of the Atomic Energy Control Board (AECB). The study concludes that no large '

increases in leukemia were present near the Canadian nuclear facilities that were investigated, and no similarities exist with the nine-fold excess of childhood leukemia observed in the vicinity of a nuclear facility involved in fuel reprocessing at Sellafield in the U.K. Due to the statistical uncertainties resulting from the small number of cases identified in Canada, the AECB has decided to extend the study to a wider age range in order to -

increase the number of children involved (from ages up to 4 years to ages up to 14 years) and to improve the precision of the fin 61 results. Phase II of the stud [skuld be completed ,in March 1990.

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i Office of Nuclear Reactor Regulation Items of Interest Week Ending June 23, 1989 Brunswick Unit 2 On June' 17,1989, Unit 2 was operating at 100% power when a ground fault i alarm on the startup transformer (SAT) was received in control room. The j plant operator initiated a gradual power decrease. While an I&C technician was trouble shooting the cause of the alarm, a second electrical short occurred'and.  !

caused the loss of the SAT. Both recirculation pumps tripped and the reactor l was manually scrammed at 72' percent power per procedure. All four diesel generators (EDGs) were started and the two assigned to Unit 2 were loaded. An Unusual Event (UE) was declared when the SAT was lost. The UE was terminated after the offsite power was restored to the Unit Auxiliary Transformer (UAT) at 0620 on 6/18/89.

The other source of power to Unit 2 through the (UAT) was also lost when the l main generator tripped. Unit 2 has no generator output breakers and power l backfeed through the UAT was not pcssible without removing the main generator 1 disconnect links. Power could not be restored to the emergency buses from )

offsite for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, resulting in prolonged challenges to the EDGs.  ;

On June 19, 1989, while Unit 2 was in Hot Shutdown, the licensee prepared to line up the train B RHR. system to promote recirculation in the reactor. A gasket on the inlet service water side of the RHR heat exchanger burst and. i flooded the RHR room with 2 feet of water. With one RHR loop out of service, 1 the licensee started to place the Unit in Cold Shutdown as required by Technical Specifications. Region II and NRR are following closely this event.

i River Bend Station, Unit 1 )

On June 15, 1989, the River Bend plant was preparing.for_startup following a ,

refueling and maintenance outage. Before reaching criticality, it was  !

discovered that the valve providing cooling water to-seals.of the control rods  ;

was shut. Upon investigation, the licensee also found that a number of lock l wires on other valves were not properly installed although the other valves were in the correct position. The licensee has determined that the procedures  !

used in recent maintenance and testing required verification that the wires  ;

were installed but the sign-off of verification was lacking.- The licensee.

believes the missin9 wires to be the result of failure to follow procedures.

To assure the plant is ready for startup, the licensee has initiated a 100% l

! field walkdown of all valves needed for safe operation. There are about 2,000 l valves in the walkdown.

River Bend Station achieved criticality at 3:26 a.m., June 19, 1989 following completion of the second refueling outage. During the outage, which began on i March 15, 1989,-the licensee located'and removed loose parts from two segments of feedwater sparger, performed augmented inspection of the service water system to determine the extend of corrosion and repaired piping and components JUNE 23, 1989 ENCLO!URE A'

8 as necessary, upgraded the instrument air system, and performed planned  !

inservice inspection and inservice testing. The generator is expected to be J synchronized to the grid after the completion of the installation and testino  !

of two replacement preferred station transformers. The work on the transformers j is' expected to be completed by June 21, 1989.

Millstone Unit 3 On June 21, 1989, with the plant in a refueling outage, a fire ignited and  !

burned for approximately 13 minutes-inside containment. At the time that the l fire started, the reactor vessel head was installed and tensioned (Mode 5),  !

and the refueling cavity seal ring was being lifted. The fire occurred in a 1 temporary fan that had been installed to cool the polar crane resistor bank on i the crane bridge. No damage to the resistor bank or crane appears to have ')'

occurred. The fire interrupted the seal ring lift in such a way as to suspend the seal ring over the reactor vessel head approximately 35 feet above the refueling cavity floor. With power removed from the polar crane, the brakes are set and the use of a triple suspension system makes a load drop a remote '

threat. .It is expected that the plant safety comittees will approve the restoration of power to the crane on June 21.to allow completion of the seal-lift ring.

Generic Consnunications On Monday, June 12, 1989, NRR began implementation of a computerized system to both distribute the text of NRC generic communications (information notices, ,

bulletins, and generic letters) electronically upon issuance and to allow access to the text of previously issued NRC generic communications (the text of NRC generic communications issued since January 1,1988 is currently available). Since this system utilizes an existing NRC mainframe computer (the Data General MV8000), it is readily available for NRC use. NRR hopes to expand the capabilities of this system to include on-line access to the  ;

Generic Communications Index and the Proposed Generic' Communications Tracking i System, as well as making available the text of NRC generic communications  ;

issued prior to 1988.  !

NRR has also initiated a trial program to allow approximately 12 selected industry representatives access to this system. Upon completion of this trial i program, NRR will review the program results and determine the feasibility of allowing additional non-NRC participants access to this system.

ISTGenericLetter89-04 Meetings (EMEB)

A five member team from NRR conducted four one-day meetings with all licensees centered around In-Service Testing (IST) in general and the new Generic Letter 89-04 in particular. At these meetings, which were held in Philadelphia, Atlanta, Chicago, and San Francisco, Regional management made opening state-  !

ments followed by more detailed presentations from NRR. All questions were-answered to the extent possible with more complete responses to be provided in the meeting minutes under preparation. The meeting minutes will be forwarded to all licensees and attendees. The meetings at Chicago and San Francisco were transcribed to facilitate the preparation of minutes. In general, the meetings-went very well with many attendees indicating agreement with the NRC's GL and JUNE 23, 1989 ENCLOSURE A

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e the new direction being taken. The meetings were particularly useful in clarifying the applicability of the Generic Letter to various plants and the manner in which tc follow its provisions. Problems with the Generic Letter's schedule were noted; however, with some licensees stating that a 6-month period is not sufficient to complete program and procedure reviews. It seemed that licensees who had made a strong and timely resource commitment to the implementation of the Generic Letter were able to meet the required schedule more readily; whereas those who had not were having the most difficulty.

Several licensees said that they could not start with the implementation phase until the NRC held the meetings to clarify the GL. The NRR staff will provide a sumary of these and other comments in the meeting minutes. In addition, general guidance will be given concerning the information licensees will have to supply to the respective Project Mar. agers if relief from the schedule is i desired.

Comanche Peak Auxiliary Feedwater System Check Valve Leakage (EMEB) l The Augmented Inspection Team (AIT) formed on May 15, 1989, to investigate the i prcbable causes and circumstances of failure of the check valves in the j Auxiliary Feedwater System at Comanche Peak, Unit 1, during hot functional I testing, completed its finding on June 9, 1989. As a result of the check ,

valve failures, hot (557 F) secondary water from the steam generator intruded l into the Auxiliary Feedwater System damaging some pipe hangers. The failure of the 3 and 4 inch Borg-Warner check valves was due to a misaligrsent of the disc and the seat. The approved Borg-Warner operations and maintenance manual for the 3 inch and 4 inch valves had omitted a significant step in the assembly technique of the valves which resulted in their failure. The AIT has reviewed and approved the applicant's plans to corrective action verification and reassembly of all the affected valves in both the units. The team also identified several precursor events duririg which inoperable check valves were 1 identified. If the applicant had aggressively pursued the investigation of 1 those failures instead of assigning normal work request priority, the events of April 25 and May 5 could have been averted.

NRR fleeting with GA0 NRR Vendor Inspection staff met with a GA0 representative on June 21, 1989.  !

The meeting was requested by GA0 as part of their continuing review of NRC's Vendor Inspection Branch and NRC's handling of vendor issues involving counterfeit or fraudulently marketed vendor products. Staff responded to GA0 questions and comments concerning NRC/VIB activities in the following areas:

(1) vendor inspection, (2) Part 21 reporting requirements, (3) NRC issuance of Information Notices Bulletins,andGenericLettersonvendorissues,(4) allegation review, (5) coordination with other Federal Agencies on vendor issues,(6)briefingtoNRCmanagementonvendoractivities,(7) coordination with 01, (8) basis safety-related for NRC equipment, insp(ection and of venders,

10) VIB interface (9) dedic6

/ coordination tion with theprograms for regional offices, i

JUNE 23, 1989 ENCLOSURE A

4 Limerick Unit 2 Limerick, Unit 2 was granted a fuel loading and precriticality testing operating license on Thursday, June 22, 1989. The license authorizes fuel loading and certain Startup Tests that can be performed within the "no criticality" restriction. The licensee expects to begin fuel loading on Friday, June 23, 1989; the current schedule calls for a need for the low power license during the period July 24 and August 1, 1989.

JUNE 23, 1989 ENCLOSURE A

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j Office of Nuclear Naterial Safety and Safeguards-Items of Interest Week Ending June 23,198S I

SAFEGUARDS' International Meeting with French Security Personnel 1989 NRC staff from the Offices of Nuclear Material Safety and i On June 16,(NMSS), Nuclear. Regulatory Research (RES), and International Sateguards .

Programs (IP) met with five physical protection experts from France. The purpose of the meeting was to exchange information regarding physical protection requirements and measures utilized in the U.S. and France.

Safcguards at Large Scale Reprocessing Plants (LASCAR) ,

e During June 19-23, 1989 NMSS staff participate as a member of the U.S. team at .J the second plenary meeting on LASCAR which was held in the United Kingdoun The i I

LASCAR group also includes representatives from Japan, France . United Kingdom, West Germany, EURATOM and the International Atomic Energy Agency (IAEA). This l '

group is working to identify the technical considerations that are expected to impact and influence the IAEA's capabilities to achieve safeguards goals at large scale reprocessing' plants.

Physical Inventory and Verification at Babcock & Wilcox (B&W)

On June 19-23,.1989 NMSS staff observed the physic 61 inventory at the B&W low enriched uranium fuel f abrication facility in Lynchburg, Va., as well as the International Atomic Energy Agency (IAEA) verification activities. B&W was selected by the IAEA for inspections starting this year as provided through the US/IAEA Agreement. The IAEA verification involved item count, non-destructive enalysis (NDA) measurements and sample taking for independent analysis. in the IAEA's analytical laboratory in Seibersdorf, Austria. 1 Transportation International Symposium on the Packaging and Transportation of Radioactive Material [PATRAM)

On June n-16, 1909, Transportation Branch staff httended the 9th PATRAM syrposium in Washington, DC. The syniposium was attended by over 600 persens  ;

representing 17 countries and provided the opportunity for the international ,

consonity to meet and exchange ideas and experience cn the transportation of  :

~ radioactive material. The next PATRAM symposium is slated to be held in Japan 1 l in 1992.  !

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-2 INDUSTRIAL AND MEDICAL NUCLEAR SAFETY Fuel Cycle Safety Fuel Cycle Facilities Forum Members of the Office of Nuclear Material Safety and Safeguards (NHSS) and the Office of Nuclear Regulatory Research (RES) attended a meeting at which representatives of the fuel Cycle Facilities Forum explained the industry group's purpose and activities. David Culberson of Babcock and Wilcox, who is Chairman of the Forum, led the briefing. The Fuel Cycle Facilities Forum is a consortium of representatives of domestic uranium / plutonium processors which was established last year to provide a forum for addressing generic decontamination and decommissioning issues primarily at facilities currently or formerly used for fuel processing activities. The initial issue of concern to the Forum is the disposition of large volumes of soil contaminated with small amounts of radioactive material. Mr. Culberson indicated that the Forum is considering a petition for rulemaking on disposal of uranium and thorium in soil which, if adopted, would supplant the Fuel Cycle Safety Branch's technical position on the subject.

HIGH-LEVEL WASTE MANAGEMENT DOE QA Plans and Procedures During the week of June 19, 1989, the Division of High-Level Waste Management (HLWM) completed and forwarded to the U. S. Department of Energy (DDE), the results of its review on the Quality Assurance Program Plans (QAPPs) for the Lawrence Livermore National Laboratory and U. S. Geological Survey. The QAPPs provide a description of applicable quality assurance requirements and controls for related activities of the respective DOE support contractors. Based on its review, the HLWM staff found that, with resolution of a few minor comments, the plans meet the requirements of 10 CFR Part 50, Appendix B.

JUNE 23, 1989 _ ENCLOSURE B

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Office of Huclear Regulatory Research Items of Interest l Week Ending June 23, 1989 j I

1 Containment Performance and Protection from Radiation Preliminary Dose Data for LWRs for 1988 l 1

The RES staff, with cantractor assistance, has completed a preliminary analysis of the annual occupational radiation cose data submitted by light water reactor licensees for CY 1988. The analysis indicates that 1 i

the average collective dose per reactor continued its five-year decline.

The 1988 value of 400 person-rems is the lowest in 15 years. The average measurable dose per. worker has also declined, but appears to be leveling j off at 0.4 rem. The average number of workers per reactor has also decreased 1 during the last few years and was found to be about 1,000 in 1988. This information is based on data submitted by 102 LWP.s as required by 10 CFR 20.407.

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JUNE 23, 1989 ENCLOSURE C

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4 Office for' Analysis and Evaluation of Operational Data <

Items of Interest )

Week Ending June 23, 1989

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Division of Safety Programs Dr. Giuseppe Verri, Head of the Information System ~ Division, ENEA-0ISP, Rome, )

Italy, will meet with the Division of Safety Programs staff on Tuesday, June 27, -t to discuss the organization of general computerized information systems-at HRC l and the applications and use of database management systems.

On. June 13, 1989', AEOD issued the Engineering Evaluation Report E905, " Electrical Bus Bar Failures," recommending that an NRC'Information Notice be sent to all licensees. The report concerned failures of electrical bus bars in medium. voltage buses that have resulted in bus bar electrical: faults and fires,. electrical power system undervoitage conditions, plant transients, and reactor trips. These failures occurred at the Palo Verde. Kewaunee, Millstone, and Sequoyah units.

Failure of the bus bars was attributed to cracking of the "Noryl" bus bar insulation combined with.the presence of moisture or debris in the bus bar housings, which jointly provided undesired tracking paths for electrical faults.

Division of Operational Assessment On June 21, Commissioner Carr and the Headquarters and Region II response teams participated in a full-scale emergency exercise for Crystal River Unit.3 and represent 6tives of the State of Florida'and local counties. On June 22, Region Il continued its participation in an ingesticn. pathway and reentry-recovery extension of.the exercise. In general, the exercise objeetives were met with excellent coordination demonstrated among the various participants. A memorandum identifying rajor lessons learned will be issued in about 4 weeks.-

Preliminary Notifications The following Preliminary Notifications were issued during the past week.

a. PNS-I-89-09, Boston Edison Company (Pilgrim Nuclear Station), Attempted Intrusion Into Protected Area. .

b. PNS-I-89-10, Consolidated Edison Company (Indian Point Nuclear Generating Statfor Unit 2), Security Threat.

c. PNO-II-89-47A, Florida Power Corporation (Crystal River, Unit 3), Crystal' River Alert Update.

d. PNO-II-89-48, Carolina Power & Light Company (Brunswick Unit 2), Brunswick.

Unusual Event - Loss of Offsite Power.

e. PN0-III-89-38, Abbott-Northwestern-Hospital (LicenseNo. 22-04588-01),

Diagnostic Misadministration with Radiation Dose in Therapeutic Range.

f. PNO-III-89-39, Northern State Power. Company (Monticello), Reactor Scram.

JUNE 23,.1989 ENCLOSURE D

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g. PNO-IV-89-38,Fanstell, Incorporated (DocketNo. 40-07580), Offsite Release of Source Material.

h. PNO-IV-89-38A,Fanstell, Incorporated (DocketNo. 40-07580), Offsite ReleaseofSourceMaterial(Update).

i. PNS-V-89-05, Portland General Electric Company (Trojan Nuclear Plant),

Drug Investigation,

j. PNO-V-89-35, Sacramento Municipal Utility District (Rancho Seco Unit 1),

Rancho Seco Organizational Changes,

k. Pt:0-V-89-36, Sacramento Municipal Utility District (Rancho Seco Unit 1),

SHUD Board Votes to Allow Bids for Takeover of Rancho Seco.

JUNE 23, 1989 ENCLOSURE D

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Office of Government and Public Affairs Items of Interest Week Ending June 23, 1989 l

4 INTERNATIONAL PROGRAMS: J USNRC/ CANADIAN AECB EXCHANGE ARRANGEMENT On June 21, Chairman Zech and Atomic Energy Control Board (AECB) President, Rene J. A. Levesque signed the first formal URC/AECB information exchange and cooperation arrangement at a ceremony at the Canadian Embassy in Washington D.C. Among the witnesses to the event were Canadian Ambassador to the U.S.

Derek Burney ond Commissioners Rogers and Curtiss. ,

PHASE I 0F AECB LEUKEMIA STUDY The first phase of an independent study of the occurrence of leukemia in )

children near Canadian nuclear facilities has been conducted on behalf of the i' Atomic Energy Control Board (AECS). The study concludes that no large increases in leukemia were present near the Canadian nuclear facilities thi.t were investigated, and no similarities exist with the nine-fold excess of -

childhood leukemia observed in the vicinity of a nuclear facility invohed in fuel reprocessing at Sellafield in the U.K. Due to the st:tistical l uncertainties resulting from the small number of cases identified in Canada, '

the AECB has decided to extend the study to a wider age range in order to increase the number of children involved (from ages up to 4 years to ages up to 14 years) and to improve the precision of the fin 61 results. Phase II of the study should be completed in March 1990. Copies of Phese I of the study are available from GPA/IP, W. Upshaw, X20330.

1 S0VIET ACTIVITIES FOR WEEK OF 6/19/89 To prepare the two NRC officiels to serve as visiting inspectors at a Soviet plant for seven weeks and their alternates, IP arranged a series of briefings j and discussions. The material presented covered: the objectives the <

inspectors are expected to fulfill (J. Taylor, H. Denton); the design of the type of plant to be visited (A. Thadani, S. Ebneter); Soviet society (M.

Launer, interpreter); Soviet medical practices (A. Weinstock, M.D.); and administrative matters.

The US team is scheduled to depart for Moscow on July 7 and to return on 4 August 27. The Soviet team hopes to arrive in the U.S. on July 21. j Export / Imports i

During the week ending June 23, 1989, an application for export license was i received from Energy Fuels Nuclear, Inc. (XU08680) for the export of 300,000 l kilograms of natural uranium for conversion in Canada, enrichment at URENCO  ;

and/or EURODIF and possible return to the U.S.  ;

Licenses for export / import were issued to Edlow International Company and l Transnuclear, Inc. j l

JUNE 23, 1989 ENCLOSURE E 1 i

g EATE,LOCALANDIEDIANTRIBEPROGRAMS Inspection Procedures Course i Joel Lubenau, SLITP, Richard Woodruff, Regicn II State Agreements Officer, and Jack Hornor, Region V State Agreements Officer, conducted an Inspection 'f Procedures training course at the National Emergency Training Center on June 19-23, 1989 in Ermitsburg, Maryland. The course covered a range of materisis inspections including broad licenses, industrial sources and devices, industrial radiography and well logging and medical ~1icenses. The class consisted of 23 State inspectors, one from the Department of Navy and one frori the NRC.

Heeting with New Jersey Deputy State tfaison Officer  !

ThomasT.Partin,DeputyAdministratorofRegionI,CurtisLowgili,Proje:t -

Section Chief, and Marie Hiller, Region I State Liaison Officer, met with Gerald !!icholls, Deputy Director, Division of Environmental Quality, ano members of his principal staff in Princeton, New Jersey, on June E0, 1989. 3 State and NRC activities at Oyster Creek were discussed including State review of licensee's design basis reconstitution efforts, sal.P report trends, low-level waste, mixed waste issues and licensee performance. New Jersey expressed their concerns for a tinely resolution of the Gereral License Program Evaluation, for a final exemption from regulatory control policy and coordinated KPC and EPA criteria for clean-up of formerly utilized contaminated siten l

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Office of Administration Items of Interest Week Ending June 23, 1989 Implementation of New "L" Reinvestigation Program As a result of the GA0 recommendations on the personnel security program, the Division of Security has implemented the new "L" reinvestigation program.

Initial me.moranda have been issued to several offices.

Water Testing at OUFN The Division of Contracts and Property Management ccmpleted water testing for lead levels of all new water fountains on June 21. Verbal results are to be furnished by the Public Health Service within seven days.

Fcderal Women's Program Achievement Award ,

Edward L. Halman, Director, Division of Contracts and Property Management has been selected as a recipient of the 1989 Federal Women's Program Achievement r Award. The award is in recognition of Mr. Halman's significant contributions toward improving the status of women within the agency. The Federal Women's Interagency Board and the Office of Personnel Management will present the award J[.

at a luncheon on June 29 at Fort McNair.

Significant F0IA Recuests Received by the NRC for 5-Day Period June 16 - Jur.e 22,1989 l

l Request the present forofa allegations list of 01A/0IG completed against investigations management for the p(eriod at each region. Virginia1080 to Lowe, '

The Liberty Consulting Group, F01A-89-2ES)

Request for copies of all records not already in the PDR concerning the former Lindsey Light Company site in k'est Chicago, Illinois. (Bruce deGrazia of Burditt, Bowles & Radzius, Chartered, F01A-89-266)

( Request for copies of all preliminary recommendations of the NRC staff to the Commission regarding the staff's list of " problem plants". (ColleenAmoruso, l STS Incorporated, FOIA-89-268)

Request for records related to reactors operated at Texas A&M University, Texas Engineering Experiment Station, and the University of Texas. (GinaAmeci, Myerson8Kuhn,F01A-89-270)

Request for copies of all records which form the basis for a specific statement on severe accident risks in NRC's May 23, 1989 letter to the licensee about the Limerick nuclear power plant. (Charles Elliott of Poswistilo, Elliott &

Elliott,FOIA-89-271)

Request for a copy of an agreement permitting the United Nuclear Corporation to discharge low-level radioactive waste into the local sewage system. (Robert Fromer, LEAF, F01A-89-272) l JUNE 23, 1989 ENCLOSURE G

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Request for copies of records related to the sale and other activities of the Sequoyah Fuels Corporation, Gore, Oklahoma. (Jessie Deerinwater, Native An.ricans for a Clean Environment, F01A-89-273) 1 Request for ccpies of contract flRC-33-89-132 on ADP systems development and  !

maintenance and re16ted records. (Christopher Speer, Computech, F01A-89-274) i I

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1 JUNE 23, 1989 ENCLOSURE G

Office of Information Resources Management Items of Interest i Week Ending June 23, 1989 j

1. Workload Information and Scheduling Program (WISP) i A test of Cooperative Processing wes successful. Data was successfully )

passed back and forth between two application programs (one residing on a j PC and the other in SINET). Cooperative processing will be incorporated into the SINET/ WISP Prototype beginning this week.

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2. NRC Annual Report (NUREG-1145, Vol. 5)

John Orban, designer of the cover of the NRC Annual Report, inspected cover proofs at the printer's site on June 13. The Annual Report was issued this week and many favorable comments have been received on its Cover.

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1 JUNE 23, 1989 ENCLOSURE H !

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Office of the Controller Items of Interest Week Ending June 23, 1989 NRC FY 1990 Appropriations On Tuesday, June 20, 1989, the House Appropriations Colmittee reported out the FY 1990 Energy and Water Develonent Appropriation Bill (H.R. 2696). H.R. 2696 would reduce the NRC's FY 1990 audget request of $475 million by $30 million.

It is our understanding that H.R. 2656 will be brought up for a vote by the House of Represelitatives during the week of June 26, 1989. A letter is being drafted for the Chairinan to request the Senate Appropriations Connittee to restore the $30 millfor. reduction.

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JUNE 23, 1989 ENCLOSURE I

Office of Personnel Items of Interest Week Ending June 23, 1989 During the week, OP sponsored the follcwing training courses:

- " Clear Writing for Senior Managers," June 19-23, 1989.

- " Editing and Reviewing," June 19-21, 1989.

- " Acquisition for Project Officers," June 19-22, 1989.

- " Acquisition for Supervisors and Managers of Project Officers,"

June 23, 1989.

Arrivals The following employees reported this week:

Stewart Hagruder, Quality Assurance Enginecr (PTT), NRR Catherine Holzle, Attorney (PFT), 000 Departures hone j

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j JUNE 23, 1989 ENCLOSURE J

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Office of Enforcement Items of Interest Week Ending June 23, 1989 Civil Penalties Paid i

Cornish Wireline Service, Inc., Chanute, Kansas paid the civil penalty in the l amount of $500. The action was based on the finding that the licensee willfully J f6iled to provide personnel dosimetry to well-logging operators for a nineteen month period February 1987 to September 1988. (EA89-15)

Virginia Electric and Power Company (Surry) paid the civil penalty in the amount 1 of $500,000. The action was based on a riajor breakdown in the control of licensed activities, including the self-identification of deficiencies, ,

cor. duct of appropriate evaluations, and institution of prompt and adequate j corrective actions. (EA88-296) 1 I

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JUNE 23, 1989 ENCLOSURE L

Office of Consolidation Items of Interest Week Ending June 23, 1989 4

Approval for Second Building June 22, the Maryland National Capital Park and Planning l On Thursday [MHCPPC) voted unanirnously to adopt a final version of the Commission i conditions for approval of the second building. The differer.ces between the i developer and the MHCPPC over the conditions stipulated in the April 13th j approval have been resolved.

The developer may now apply for a building permit, execute various agreements  ;

required by the Montgomery County Planning Board, and post the required  ;

letter of credit guaranteeing part of the traffic mitigation program. I As a condition of the approval, the developer has agreed to build a 200-ur.it residential building on the site ccocurrently with the construction of the second building for the NRC.

Commencement of excavation is anticipated around November 1, 1989 following all necessary County end State reviews of site plan changes, road improvement j agreements, traffic mitigation agreements ar.d program commencement, financial 1 arrange:Lents, filing of record plats and the review and approval of  !

construction plans by the Montgomery County Department of Environmental i Protection.  !

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Region I Items of Interest Week Ending June 23, 1989

1. Safety Light Corporation, et al The staff has completed its review of the site characterization plan submitted by Safety Light, et al in response to the March 16, 1989 Order regarding the Bloomsburg, Penndsy vania site. A number of apparent failures to comply with specifications of the Order were identified. An additional requirement of the Order, to erect barriers to preclude access to contaminated areas of the site, and to properly post these areas, was to be implemented by June 15, 1989. An inspection on June 16 revealed that, while efforts to enclose the contaminated areas of the site were underway, the required barriers and posting had not been completed. An enforcement conference has been scheduled with the Presidents of Safe V Light Corporation and USR Industries for July 6, 1989, in the Region I office.

2. Limerick Generating Station Unit 2 The Mechanical Stress Improvement Process (MSIP) was employed on sixteen reactor vessel nozzle / safe end welds at Limerick Unit 2, and ultrasonic examinations of the welds were performed pre and post MSIP. All ten N2 nozzles (14" diameter)exhibitedsi with the exception of two nozzlesN2B (gnificant and H2D)ultrasonic appeared indications to originate atwhich, the I.D. surface and extend approximately 40% through the wall. The licensee implemented an evaluation program including metallurgical evalua-tion and ultrasonic, liquid penetrant, visual and radiographic examination of mockups which closely resembled the Limerick N2 nozzles. The mockups were subjected to the MSIP followed by the evaluation and NDE techniques.

Ultrasonic indications were detected similar to those found in the Limerick nozzles in terms of size and location. Metallurgical samples containing the UT reflectors were compared to pre-MSIP specimens. The samples showed no discernible evidence of defects, or metallurgical anomalies to which the ultrasonic indications could be attributed.

Additionally, no PT, VT or RT indications were observed. On June 22, 1989, the licensee will demonstrate to the NRC the ultrasonic condition of the questionable welds and its capability of performing a meaningful volumetric inservice inspection of those welds.

3. Seabrook Since initial criticality on June 13, 1989, the licensee has conducted low power physics testing without any significant problems. The last test (natural circulation) will be completed on June 22, 1989, after which the plant will be placed in Mode 3. Main turbine torsional testing will continue through the weekend and the plant placed in Mode 5 early next week.

1 JUNE 23, 1989 ENCLOSURE N

Region II Items of Interest Week Ending June 23, 1989 i

1. VEPCO Presents Performance Assessment of North Anna On June 19, representatives from VEPC0 were in the Region II Office to  !

present their assessment results of performbi.ce at their North Anna Nuclear Station.

2. Full Scale Emergency Preparadna:3 txercise at Crystal River Crystal River Unit 3 conducted a full-scale emergency exercise June 21-22, 1989, with full participation of NRC Base Team, Site Team, and a Head-quarters' Response Team. Headquarters' participation included a 4 'l executive team response led by Commissioner Carr. The overall exc. ise was judged successful with good transitioning observed between the Region II Base Team, Headquarters, and Site Team. Licensee performance was also adequate with one exercise weakness identified by the NRC inspection team in the area of untimely offsite notification for the General Emergency declaration.

3. US/ USSR Inspector Exchange Program On June 23, the Regional Administrator was in Headquarters to participate in a meeting regarding the US/ USSR Inspector Exchange Program.

4. Turkey Point Drug Testing 1

Extensive drug screening effort was initiated on June 16, 1989 in response I to the FBI arrest of one (non-nuclear) Turkey Point employee for drug distribution. The testing started with management, supervisors, and licensed individuals and working through to contractors. As of 6:00 p.m.

June 22, 1989, the licensee had tested 915 employees, and had received 456 test results from the preliminary tests. While no confirmed results have been " positive," the initial onsite screen has caused 7 samples to be referred to the offsite laboratory for confirmatory testing. One mid-level supervisor has refused the test and has been suspended. Miami, Florida, and local media coverage has been extensive and is expected over the weekend. FBI investigation is continuing. The State of Florida Attorney General has also shown interest in criminal investigation.

As of the morning of June 23, Unit No. 3 was in Mode 3 (restarting) and Unit No. 4 was at 50 percent power. Region 11 is maintaining very close cognizance of FBI and licensee efforts.

5. Brunswick Unit 2 Loss of Offsite Power On June 17, 1989, the licensee declared an Unusual Event after Unit 2 was mar.ually scrammed following a loss of offsite power. The loss of offsite power occurred due to a phase fault on the Startup Auxiliary Transformer JUNE 23, 1989 ENCLOSURE N

2 (SAT). Power was restored via backfeeding through the_ Unit Auxiliary Transformer (UAT). The emergency diesel generators provided power during the 61 hours7.060185e-4 days <br />0.0169 hours <br />1.008598e-4 weeks <br />2.32105e-5 months <br /> required to restore offsite power through the UAT. Repairs to the SAT were completed and it was subsequently returned to service. j The licensee is reviewing their procedure for backfeeding offsite power  ;

via the UAT, and thus far has identified several areas for improvement.

6. Oconee Nuclear Power Station 1

i A meeting was held in Headquarters on June 22, 1989, with Duke Power Company (DPC) representatives regarding Oconee electrical distribution system problems. DPC reviewed the system description, history of LERs, and the design reviews that are scheduled and in progress. Based en DPC's presentation, the NRC will oversee the design reviews; in addition, an 3 on-site technical meeting between the NRC and DPC to assure certain areas, such as support systens, are being reviewed. A meeting will be held in October to provide results of these design reviews. Moreover, DPC is making arrangements to present their Design Basis Documentation Program (similar to the Regional presentation on'May 25th) at NRR.

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Region III Items of Interest Week Ending June 23, 1989

1. Commonwealth Edison Company (CECO)

On June 23, 1989, CECO will present to Region III the strategy and focus I of its new engineering organization. Region III will present their experiences and observations regarding CECO's performance in the engi-neering/ design area. Mr. Cordell Reed of Commonwealth Edison Company, A.

Bert Davis and H. J. Miller of Region III and their supporting engineering staffs will participate in this meeting. This meeting will take place in the new CECO engineering office in Downers Grove, Illir.ois.

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2. Region III Engineering Counterpart Meeting I On June 21-23, 1989, Region III is hosting a counterpart meeting to discuss NRC computer programs for evaluating licensoe containment integrated leak rate test (CILRT) performance, proposed 10 CFR Part 50, Appendix J rulemaking, and inspection interpretations regarding CILRT's with representatives from NRR, RES, and the other regions.

3. Braidwood Nuclear Power Station Mr. Stephen P. Sands, Licensing Project Manager, NRR and James Belanger, l Plant Protection Analyst, Division of Reactor Inspection and Safeguards  ;

will be accompanying six French representatives on June 22, 1989, to the l Braidwood Station for a management meeting to discuss plant physical i protection and security philosophy.

4 University of Missouri The Regional Administrator and the Director, Division of Reactor Projects toured the University of Missouri Research Reactor (MURR) and met with MURR management and staff June 20, 1989 to discuss the findings from a '

recent Region III team inspection of the reactor.

5. Clinton Nuclear Power Station On Friday, June 16, 1989, the Region III Administrator and members of the Regional and NRR staffs met with Illinois Power Company (IP) management at the Clinton site for a plant tour, a management meeting and to discuss the restart provision of Confirmatory Action Letter CAL-RIII-80 ^16 regarding the recirculation (RR) pump seal failure event of Ju 1, 1989.

The licensee presented the results of the investigations and proposed corrective actions. Although no conclusive root cause of the seal failures was determined, the licensee believed installation error was the most probable cause. Discussions of actions related to the motor operated feed pump feed regulating valve (FRV) problems and the drywell chiller trip were also presented. The FRV problems were expected to be reduced by moving the control circuitry junction box from the valve operator to a stationary location on the wall so it will be less susceptible to JUNE 23, 1989 ENCLOSURE N

5. Clinton Nuclear Power Station (continued) vibration. IP is also pursuing long term solutions to historical problems with this FRV. Root cause of the drywell chiller trip is believed to be due to the momentary decrease in service water pressure at the chiller inlet due to the increased heat load caused by the event. This pressure fluctuation coincident with a high setpoint on the low pressure trip is believed to have caused the trip. To prevent recurrence, IP lowered the trip setpoint and installed a pulsation dampener in the pressure sensor line to darpen out the initial pressure decrease spike. Because no conclusive root cause of the RR pump seal failures could be determined, IP committed to perform increased monitoring of several parameters on the RR pumps during the startup and to keep the NRC informed of any anomalies.

At the end of the meeting, based on the IP proposed actions, the Region III Administrator authorized startup of the Clinton plant. Subsequently, E on June 19, 1989, the Clinton reactor was taken critical at 8:56 a.m., E l but was summarily shut back down due to discovery of two room temperature l instruments which were out of calibration and uncertainty as to how extensive that problem was. The plant was brought critical again at 10:14 p.m. on June 19. However, during plant heatup, it was discovered that upper seal staging pressure in the "B" RR pump was not tracking which was found to be due to a shut instrument isolation valve. This deficient condition alcng with the failure of IP management to properly communicate the commitments from the management meeting on June 16 to the operating shift personnel, and the resultcnt failure by the shift to honor these commitments, resulted in a call from the Deputy Regional Administrator (DRA) to the Senior Vice President of IP and a hold on Clinton's startup. Following licensee actions to prevent recurrence, the DRA released IP to continue Clinton's startup. As of 7:00 a.m.,

June 22, 1989, Clinton had completed the startup through 50% power with the seals on both RR pumps performing satisfactorily in both slow and fast speed, and the FRV and the drywell chiller performing satisfactorily as well.

6. Clinton Nuclear Power Station On Wednesday, June 14, 1989, Region III conducted two enforcement con-ferences with Illinois Power on Environmental Qualification issues and on an 01 issue wherein an egloyee was alleged to have instructed subordinates to deviate from precedures.

1 JUNE 23, 1989 ENCLOSURE N

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Region IV Items of Interest Week Ending June 23, 1989 l

1. South Texas Project Houston Lighting & Power Company declared South Texas Project, Unit 2 1

(STP-2), in commercial operation at 12:01 a.m., on June 20, 1989. STP-2 was licensed for full power operation on March 28, 1989, and completed '

startup testing last week. South Texas Project, Unit 1, began commercial operation on Atsust 25, 1988.

2. Arkansas Nuclear One Mr. Gene Campbell, Vice President for Nuclear Operations of Arkansas Power j

& Light Company, announced on June 19, 1989, the personnel selections for i the Arkansas Nuclear One (ANO), Units 1 and 2, plant manager positions.  !

Mr. James Vanderprift has been selected as the ANO, Unit 1, Plant Manager. !

Previously, Mr. /andergrift was the ANO Operations Manager. Mr. Robert  !

Fenech has beer, selected as the ANO, Unit 2, Plant Manager. Previously, )

Mr. Fenech carved as the Operations Superintendent at Palisades. In  ;

addition to these personnel selections, several other management selections in the ANO organization were announced. l,

3. South Texas Project A group of French security experts visited the South Texas Project near Bay City, Texas, June 20, 1989, as part of a special agreement between the NRC and the French Ministry of Industry and Research regarding the exchange of security information. Houston Lighting and Power Company '

is providing the 1-day tour of the South Texas Project to the French security experts and their NRC Headquarters escorts in response to an NRC request.

4 State Visit On June 22, 1989, the Deputy Regional Administrator and Regional State Liaison Officer met with the Radiation Control Division's State Liaison Office Director in Denver, Colorado, to discuss State and NRC programs.

5. Wolf Creek Generating Station The Regional Administrator, other members of the Region IV staff, and NRR personnel met with Wolf Creek Nuclear Operating Corporation personnel at Wolf Creek Generating Station near Burlington, Kansas, on June 23,1!89, to present the utility's most recent SALP report.

JUNE 23, 1989 ENCLOSURE N

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.. 1 Region V Iteras of Interest Week Ending June 23, 1989

1. Sacramento Municipal Utility District-(SMUD)

The Sacramento Municipal Utility District Board voted on June 20,'1989,.

by a 3-2 vote, to allow ten days for qualified private bidders to submit  ;

proposals to takeover Rancho Seco. . Any proposal that might be accepted )

by the SMUD board may require further utility district voter approval.

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l JUNE 23, 1989 ENCLOSURE N'

ITEMS ADDRESSED BY THE COMMISSION - Week Ending June 23, 1989 A.. STAFF REQUIREMENTS - PERIODIC BRIEFING ON OPERATING REACTORS AND FUEL' FACILITIES, 2:00 P.M., THURSDAY, JUNE 1, 1989, COMMISSIONERS' CONFERENCE L ROOM, ONE-WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) - SECY to V. Stello, Jr., EDO and Harold R. Denton, D/GPA dated 6/19/89-The Commission was briefed by the staff on the conclusions of .

the recent biannual senior management meeting to review.the i performance of NRC licensees. 1 The Commission expressed disappointment in the long term operating performance of Florida Power _and Light Company's Turkey Point. nuclear power plants. The Commission _ requested: l

.the staff;to convey to the licensee that the commission expects j near term improvements in the operation of the Turkey Point ]

plants.

The staff committed to submit to the Commission a paper on-

a. International OSART inspections of nuclear power plants.

The paper..should address the goals of the OSART' inspection, how those goals are accomplished, and- )

recommend constructive-suggestions, if appropriate, which a may prove useful.to IAEA. The report should also address l the OSART inspection of Calvert Cliffs and provide the )

introspective lessons learned from the Calvert Cliffs j experience.

b. Economic incentive arrangements for nuclear power plants.

This analysis.should. include the following:

1) an update of NUREG-1256;

2) a plant-by-plant description'of the types of incentive-based programs that are in place or under consideration;

3) an assessment of the potential financial impact of such arrangements on individual utilities, including

- - .an assessment of whether such arrangements pose potential health and safety concerns; and

4) a discussion of the options available to the Commission to take action in response to such arrangements, where such arrangements pose potential health and safety concerns.

Subsequent to the meeting, on June 6, 1989, a referendum was-passed which directed the Sacramento Municipal Utility District to no longer operate the Rancho Seco Nuclear Power Plant. The-staff should keep the Commission advised on the licensee's future plans for Rancho Seco.

JUNE 23, 1989 ENCLOSURE P

l B. STAFF REQUIREMENTS - BRIEFING ON PROPOSED RULE ON BASIC QUALITY ASSURANCE IN RADIATION THERAPY, 2:00 P.M., TUESDAY, JUNE 13, 1989, COMMISSIONERS' )

CONFERENCE ROOM, ONE WHITE FLINT tl0RTH, ROCKVILLE, MARYLAND (OPEN TO j PUBLIC ATTENDANCE) - SECY to V. Stello,-Jr., EDO dated 6/23/89 i The Commission was briefed by the staff on proposed amendments to 10 CFR Part 35 to require a basic quality assurancelprogram and to modify the reporting and recordkeeping requirements for medical users of radioisotopes.

Chairman Zech emphasized the fact that while the Commission i recognizes that diagnostic errors in the medical use of 1 radioisotopes are low, the' Commission, nevertheless, believes that there exists room for improvements to further reduce errors in the medical use of radioisotopes.

Commissioner Carr recommended that the staff consider:

a. Retaining the term " misadministration" in the enforcement program, consistent with the graduated level of enforcement action related to the seriousness of the violation.

b. Placing more emphasis on inspection and less on the review of programmatic issues in the continuing regulatory program for assessing the effectiveness of licensees' medical quality assurance programs.

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